boric acid concentration reduction technical bases
TRANSCRIPT
BORIC ACID CONCENTRATION REDUCTION
TECHNICAL BASES
AND
OPERATIONAL ANALYSIS
PREPARED FOR
FLORIDA POWER & LIGHT COMPANY
TURKEY POINT NUCLEAR UNITS 3 AND 4
NOVEMBER 1990
Cem leted B :
ngineer
Reviewed B : W
A roved B :
ngineer
anage
Date l/ z6
Date I( (~',t 'fO.
ABB COMBUSTION ENGINEERING NUCLEAR POWER
MECHANICAL PRODUCTS AND SERVICES iWindsor, Connecticut
9iOi3i0092 eiOi24PDR *DOCK 05000250P PDR
Report No. 849963-MPS-5MISC-003 REV 0 Title Page
.C7
Section
1.0 INTRODUCTION
TABLE OF CONTENTS
Title ~Pa e No.
2.0
3.0
4.0
5.0
1. 1 PURPOSE AND OBJECTIVES1.2 BACKGROUND1.3 BASIS OF BORIC ACID CONCENTRATION REDUCTION
PERFORMANCE RE UIREMENTS
2.1 DESIGN BASIS PERFORMANCE REQUIREMENTS:SAFETY-RELATED
2. 2 DESIGN BASIS PERFORMANCE REQUIREMENTS:QUALITY-RELATED
2.3 SAFETY ANALYSIS REQUIREMENTS
2.4 10CFR50 APPENDIX R REQUIREMENTS
2.4. 1 Safe Shutdown2.4.2 Cold Shutdown
ANALYSIS SCENARIOS
3.1 LICENSING BASIS SCENARIOS
3. 1. 1 Operating Modes 1, 2, 3, and 4
3. 1.2 Operating Modes 5 and 63. 1.3 Operating Modes 1, 2, 3, and 4:
Peak Xenon
3.2 OPERATIONS ANALYSES
METHOD OF ANALYSIS AND ASSUMPTIONS
4. 1 ANALYSIS METHODOLOGY
4. 2 PHYSICS ANALYSIS ASSUMPTIONS
4.3 SYSTEM ANALYSIS ASSUMPTIONS
4.4 ADDITIONAL ASSUMPTIONS, MODE 5 COOLDOWN
DESIGN BASIS ANALYSES
5.1 REQUIRED RCS BORON CONCENTRATION
5.2 COOLDOWN FROH HOT STANDBY, EQUILIBRIUMXENON, EOC
1-11-11-2
2-1
2-1
2-7
2-102-11
2-112-12
3-1
3-1
3-13-33-5
3-6
4-1
4-14-24-94-14
5-1
5-15-10
5.2.15.2.25.2.35.2.4
PurposeAnalysesResultsRWST Boration Requirements,Modes 1, 2, 3, and 4
5-105-105-135-15
Report No. 849963-HPS-5HISC-003 REV 0 Page
Section
6.0
TABLE OF CONTENTS (continued)
Title5.3 COOLDOWN FROM COLD SHUTDOWN TO REFUELING
TEMPERATURE, MODE 5
5.3.1 Purpose5.3.2 Analyses
5.3.2. 1 Mode 5 Cooldown with BoricAcid Tank
5.3.2.2 Mode 5 Cooldown with RWST
5.3.3 Results
OPERATIONS ANALYSES
6.1 BLENDED MAKEUP OPERATIONS6.2 FEED AND BLEED OPERATIONS6.3 COOLDOWN TO REFUELING - MODE 66.4 COOLDOWN TO COLD SHUTDOWN - MODE 56. 5 BATCHING OPERATIONS6.6 RESPONSE TO EMERGENCY SITUATIONS
Pacae No.
5-29
5-295-29
5-31
5-32
5-34
6-1
6-46-66-96-126-136-15
6.6.16.6.26.6.36.6.46.6.5
Accident ResponseShutdown Margin RecoveryEmergency BorationFast Cooldown TransientsTechnical Specification ActionStatements
6-166-166-166-186-20
7.0
8.0
9.0
10.0
6.7 IMPACT OF RCS LEAKAGE6.8 LONG TERM COOLING AND CONTAINMENT SUMP pH
TECHNICAL SPECIFICATION CHANGES
7.1 RECOMMENDED CHANGES7.2 NO SIGNIFICANT HAZARDS EVALUATION
~5AFF Y EVALUA ioNf
8. 1 RECOMMENDED UFSAR CHANGES
8.2 NO UNREVIEWED SAFETY QUESTIONSDETERMINATION
OPERATING PROCEDURE GUIDELINES
REFERENCES
6-226-23
7-1
7-17-13
8-1
8-18-6
9-1
10-1
Report No. 849963-MPS-5MISC-003 REV 0 Page
Section
APPENDIX 1
APPENDIX 2
APPENDIX 3
APPENDIX 4
TABLE OF CONTENTS (continued)
Title
DERIVATION OF THE REACTOR COOLANT SYSTEM
FEED AND BLEED EQUATION
A PROOF THAT FINAL SYSTEM CONCENTRATION
IS INDEPENDENT OF SYSTEM VOLUME
METHODOLOGY FOR CALCULATING DISSOLVED BORIC
ACID PER GALLON OF WATER
METHODOLOGY FOR CALCULATING THE CONVERSION
FACTOR BETWEEN WEIGHT PERCENT BORIC ACIDAND PPM BORON
~Pa e No.
Al-1
A2-1
A3-1
A4-1
APPENDIX 5 BOUNDING PHYSICS DATA INPUTS
APPENDIX 6 PROPOSED MARKED-UP TECHNICAL SPECIFICATIONS
APPENDIX 7 PROPOSED MARKED-UP SAFETY ANALYSIS REPORT
A5-1
A6-1
A7-1
APPENDIX 8 FUTURE FUEL CYCLE REVIEW FOR COMPARISON OF
BOUNDING PHYSICS PARAMETERS
A8-1
APPENDIX 9 ANALYSIS OF PEAK XENON SCENARIO
APPENDIX 10 COMPUTER CODE CERTIFICATE AND INPUT
A9-1
A10-1
Report No. 849963-MPS-5MISC-003 REV 0 Page iii
INTRODUCTION
PURPOSE AND OBJECTIVES
The purpose of this project, as proposed by Reference 10.7 and
authorized by Reference 10.8, is to perform the necessary
engineering work and to generate the necessary license amendment
documents that would allow Florida Power & Light (FPL) to "reduce the
boron concentration required to be maintained in the concentrated
boric acid tanks at the Turkey Point Nuclear Units 3 and 4 to a
concentration of 3.0 to 3.5 weight percent boric acid. At the new
boric acid concentrations the need to heat the boric acid tanks and
the need to heat trace the boric acid makeup system piping and
valves would no longer be required since the ambient temperatures
that normally exist in the plant's auxiliary building are sufficientto prevent boric acid precipitation.
1.2 BACKGROUND
The General Design Criteria contained in the Code of Federal
Regulations specifies that concentrated sources of borated water ar'
to be available for charging into the Reactor Coolant System (RCS)
of pressurized water reactor (PWR) plants as needed for reactivitycontrol. Although these borated sources are required to be
available, the concentration of the solutions contained in them isdetermined by the designers. The basis for determining the boric
acid concentration is the ability to safely control reactivity at
any time during core life. Boric acid is used to offset slow
reactivity changes caused by normal changes in reactor power level,or to establish hot shutdown, cold shutdown or refueling conditions.
In the original plant design process for PWRs, two sources of
borated water are typically provided, each having different boron
concentrations. A refueling water storage tank is available which
has a specified minimum concentration of 1950 ppm. In addition to
Report No. 849963-HPS-5HISC-003 REV 0 Page 1-1
the refueling water storage tank three concentrated boric acid tanks
are available. Each boric acid tank has a specified minimum levelof 3,080 gallons with a specified concentration of 20,000 to 22,500
ppm boric acid. In order to keep the boric acid in solution atthese high boron concentrations, extensive heating networks are
required. These heating networks maintain the temperature of the
tanks and associated pipes, pumps, and valves at greater than 145'F
in order to prevent boric acid precipitation.
The requirement to maintain a highly concentrated boric acid
solution in the boric acid tanks can place an undue burden on plantmaintenance and operational personnel. Significant problems can be
encountered in keeping the boric acid makeup system operable as
required in the plant technical specifications. These problems
include heat tracing failures, plugging problems due to crystallineboric acid deposits, and various corrosion problems such as seal
failures, fitting leaks, and valve failures. In addition, the
presence of crystalline boric acid deposits on the exterior of
piping, valves, etc. can present a cleanliness problem. One
solution to these problems would be to reduce the concentration
requirements in the boric acid tanks by a factor of three or more
below the present value. This reduction is justifiable based on the
analyses presented in this report which demonstrate the ability to
safely control reactivity throughout core life. At low enough
concentration levels the system would no longer need to be heated
since boric acid would remain in solution at temperatures below the
normally anticipated ambient temperatures in the auxiliary building.Additionally, problems with corrosion and cleanliness associated
with concentrated boric acid could be greatly improved.
1.3 BASIS OF BORIC ACID CONCENTRATION REDUCTION
The boric acid tank level and boron concentration minimum values
specified in the current Turkey Point Technical Specifications are
Report No. 849963-MPS-5HISC-003 REV 0 Page 1-2
based on the ability to borate the RCS to the required cold shutdown
boron concentration by utilizing avialable pressurizer volume or
through a feed and bleed process. The current method is to borate
the RCS to the boron concentration required to provide the requiredshutdown margin of IX ak/k at 200'F prior to commencing the plantcooldown. The boration subsystem is then required to providesufficient boric acid to first achieve this shutdown margin and,
second, to provide blended makeup to compensate for the contractionof the coolant throughout the cooldown. Since boron concentration
typically has to be increased by 700 to 800 ppm prior to commencing
cooldown, highly concentrated boric acid solutions are required toachieve this in a reasonable period of time with limited storage
volume capability.
The required boron concentration in the boric acid tanks can be
reduced with a simple change in the methodology of accomplishing
plant boration and cooldown. This report analyzes a number of plantcooldown scenarios where boration is accomplished concurrently withcooldown as part of the normal inventory makeup required as a resultof coolant contraction during the cooldown. By identifying the
exact RCS boron concentration required to maintain proper shutdown
margin at each temperature during a plant cooldown and applying the
makeup capacity limitations of the system, the exact volume of boricacid required from the boric acid tank can be identified. By
eliminating the boric acid loss associated with the feed and bleed
process and by utilizing boric acid available from the refuelingwater storage tank (in addition to the boric acid tank), the
concentration of boric acid required for the boric acid tanks can be
reduced. Effectively, the concentration required for the boric acid
tanks to perform a cooldown to cold shutdown conditions can be
decreased to the range of 3.0 to 3.5 weight percent where heat
tracing af the boric acid system is no longer required.
Figure 1-1 is a plot showing the solubility of boric acid in water
for temperatures ranging from 32'F to 160'F. (Data for Figure l-l
Report No. 849963-NPS-5HISC-003 REV 0 Page 1-3
were obtained from Reference 10.9 and are reprinted in Table 1-1.)Note that the solubility of boric acid at 32'F is 2.52 weight
percent and at 50'F is 3.49 weight percent. At or below a
concentration of 3.5 weight percent boric acid, the ambient
temperature that normally exists in the auxiliary building will be
sufficient to prevent precipitation within the boric acid makeup
system.
This report presents the technical justification for reduction ofthe boric acid concentrations required to be maintained in the boricacid tanks which will then support the elimination of all boric acid
system heat tracing. Section 2.0 presents the results of a detailedreview of the Turkey Point boration design basis. Section 3.0
presents the analysis scenarios that were chosen to demonstrate the
capability of the boration system to comply with these design basis
requirements with reduced boric acid concentration. Sections 4.0,5.0, and 6.0 present the results of the analyses completed for the
scenarios identified in Section 3.0. Sections 7.0 and 8.0 identifythe necessary changes to Turkey Point licensing documentation, while
Section 9.0 identifies general changes that will be required forTurkey Point operating procedures.
Report No. 849963-MPS-5HISC-003 REV 0 Page 1-4
Table 1-1
Boric Acid Solubility in Water'(1)
Temperature
('F)H3B03
(Wt.X)
32.0
41.0
50.0
59.0
68.0
77.0
86.0
95.0
104.0
113.0
122.0
131.0
140.0
149.0
158.0
167.0
176.0
2.52
2.98
3.49
4.08
4.72
5.46
6.23
7.12
8.089.12
10.27
11.55
12.97
14.42
15.75
17.91
19.10
Solubility from Technical Data Sheet IC-11, US Borax 8 ChemicalCorporation, 3-83-J.W. These data have been empirically derived andare supported by WCAP-1570 "Literature Values for SelectedChemical/Physical Properties of Aqueous Boric Acid Solutions".
Report No. 849963-MPS-5MISC-003 REV 0 Page 1-5
Figure 1-1 Boric Acid Solubility in Water
(We+%)I I
H I
0>0
9—I
8 —;
7 —.
6 —,
5 —'-
.~
I
(
1—'
I1
I
TIII(IIItae(DW(F(
Report No. 849963-MPS-5MISC-003 REV 0 Page 1-6
PERFORMANCE REQUIREMENTS
To technically justify a significant reduction in the concentrationof boric acid in the boration subsystem of the Chemical and Volume
Control System (CVCS), a careful review of the boration design and
licensing basis of the CVCS is required. It is necessary that thespecific design basis and licensing performance requirements be
clearly identified and understood to ensure that one or more
analyses can be completed that will demonstrate these requirementscontinue to be met.
References 10. 1 through 10.6 were reviewed to identify allperformance requirements/limitations related to RCS boration and
core reactivity control that should be factored into the boric acidconcentration reduction analyses. This section identifies the
system design basis performance requirements and the expected impact
of a reduction in the concentration of stored boric acid. The need
for analyses to demonstrate compliance with these system
requirements is assessed and appropriate reference made to the
specific analysis scenarios outlined in Section 3. The intent isnot necessarily to conduct a specific analysis for each system
requirement but, instead, to identify the minimum number of limitinganalysis scenarios, the results of which will bound all establishedboration requirements.
2.1 DESIGN BASIS PERFORMANCE REQUIREMENTS: SAFETY-RELATED
This section addresses each of the safety-related design basis
performance requirements presented in Section 3. 1 of Reference 10. 1.
All requirements are addressed regardless of any impact created by a
reduction in boric acid concentration. For ease of cross reference,
these requirements are presented in the same order as they appear in
the design basis document with the same last two digits of the
section numbers used in this evaluation (i.e., Section 2.1.2 here
corresponds to Section 3. 1.2 of Reference 10. 1).
Report No. 849963-HPS-5HISC-003 REV 0 Page 2-1
2.1.1 The CVCS charging line and the individual Reactor Coolant Pump (RCP)
seal injection lines (one for each RCP) are required to satisfycontainment boundary isolation requirements.
~im act: None
~Anal sis: Not Applicable.
2.1.2 The CVCS shall be capable of making and holding the core subcriticalfrom any hot operating condition including those resulting from
power changes. Clarifications of Section 2. 1.3 (Reference 10. 1)
state that the boration system is required to be capable of shuttingdown the reactor from a hot full power condition (with no controlrod insertion) and adding sufficient boric acid subsequent to the
shutdown to compensate for the eventual decay of all xenon, thereby
maintaining the required shutdown margin.
~lm act: References 10.1, 10.2 and lb.3 state that the required
boration can be accomplished in less than 16 minutes and that, in
less than 16 additional minutes, RCS boron can be increased
sufficiently to fully account for the decay of xenon, thereby
maintaining the required shutdown margin. (A total of 155 minutes
would be required if the source of water were the refueling water
storage tank instead of the boric acid tanks.) This is recognized
to be a statement of system capability and does not represent a
licensing requirement. A reduction in boric acid tank boron
concentration will only increase the amount of time it will take and
will not impact the system's ability to accomplish this task.
Analysis: Although an exponential relationship exists; the time to
borate to the hot shutdown, xenon free condition is roughly
inversely proportional to the boric 'acid concentration of the water
source (at low initial concentrations and assuming one source with
constant concentration and addition rate). Reduction in boron
concentration by a factor of 3 to 4, therefore, is expected to
Report No. 849963-MPS-5MISC-003 REV 0 Page 2-2
increase the completion time by a factor on the order of 3 to 4.
Previous reactivity analyses have analyzed this capability with
boron concentrations from 4.0 to 3.0 weight percent boric acid
resulting in times to shutdown of 30 to 40 minutes, respectively.In any case, the shutdown capability of 155 minutes using the
refueling water storage tank remains as the upper limit on time to
achieve boration. Volume of boric acid is not considered a
limitation in this instance since a stated design basis variation in
the boration lineup is to use the refueling water storage tank as a
sole source. The volume requirement in this instance is bounded by
that required by post LOCA emergency core cooling. See Section
6.6.3.
2.1.3 The CVCS boration system is required to be capable of maintaining
shutdown margin during a 100'F/hr cooldown initiated from a hot zero
power subcritical condition, with the RCS borated sufficiently for a
cold shutdown (= or < 200'F), xenon free condition and the most
reactive control rod stuck in the fully withdrawn position.
~lm act: A reduction in boron concentration of the water used to
provide boration and makeup under these conditions will effectivelyrequire that a greater volume be added to the RCS for reactivitycontrol. Additionally, greater boric acid flow rates to the blender
will be required to provide blended makeup that will maintain the
RCS boron concentration established prior to initiating the
cooldown. The required boric acid flow rates for fast cooldowns
will be available via the normal flow path with the proposed
modification of flow control valve FCV-113A discussed in Section 6. 1
or via the emergency boration flow path using one or both transfer
pumps.
~Anal sis: See Section 6.6.4.
2.1.4 The CVCS charging system must be capable of satisfying the technical
specification requirements to be in various stages of hot or cold
Report No. 849963-MPS-5MISC-003 REV 0 Page 2-3
shutdown during varying time periods. Accordingly, the CVCS must:
1) meet the RCS boration requirements such that the shutdown boron
concentration can be achieved prior to (and maintained during) plantcooldown; 2) satisfy RCS fluid inventory control requirements
during cooldown by making up for shrinkage of the reactor coolant
with blended makeup water of the correct boron concentration. The
clarification of Section 3. 1.4 (Reference 10. 1) states that the
limiting requirement in this respect is to achieve cold shutdown
(1% z k/k shutdown, 200'F) in 30 hours from a hot zero power
condition, including allowances for RCP seal leakage and
identified/unidentified RCS leakage.
~lm act: An exception to this design basis statement is that the
methodology presented in this report involves boration in
conjunction with the cooldown to minimize the boron loss that would
occur during the feed and bleed process suggested (i.e., boration
prior to cooldown). Such an approach is used in the licensing
analysis of Section 5.0 to establish the minimum technical
specification volume/concentration requirements for the boric acid
tanks.
~Anal sis: See Sections 5.0 and 6.0.
2.1.5 The CVCS charging system must be capable of satisfying safe shutdown
fire protection criteria imposed as a result of 10CFR50, Appendix R.
Boration to the cold shutdown boron concentration and cooldown to
350'F must be achieved within 19 hours with suction from the
refueling water storage tank. Cold shutdown is to be achieved
during the ensuing period from 19 to 72 hours. Accordingly, the
CVCS must: 1) meet the RCS boration requirements such that the
shutdown boron concentration can be achieved prior to (and
maintained during) plant cooldown; 2) satisfy RCS fluid inventory
control requirements during cooldown by making up for shrinkage of
reactor coolant with blended makeup water of the correct boron
Report No. 849963-HPS-5MISC-003 REV 0 Page 2-4
concentration. The 19-hour time requirement is based on condensate
storage tank capacity as the water source for auxiliary feedwater.RCP seal leakage and identified/unidentified RCS leakage are
assumed.
~Im act: An exception to this design basis statement is that the
methodology presented in this report involves boration inconjunction with the cooldown to minimize the boron loss that would
occur during the feed and bleed process suggested (i.e., borationprior to cooldown). Such an approach is used in the licensinganalysis of Section 5.0 to establish the minimum technicalspecification volume/concentration requirements for the boric acid
tanks. The 19 and 72 hour limitations are not considered limitingfrom the perspective of boric acid tank inventory since the
refueling water storage tank is the stated source for reactivity and
inventory control.
A~nal sis: See Sections 5.0 and 6.0.
2.1.6 The CVCS boration system is required to insert negative reactivityat a rate that is sufficient to compensate for the maximum xenon
burnout rate which occurs during a return to power at a peak xenon
condition following a short period at hot standby.
~im act: A reduction in the boron concentration in the boric acid
tanks will require greater boric acid flow rates to add the same
amount of boron in a given period of time. The preferred method ofreactivity control in these circumstances is to provide a mixture ofconcentrated boric acid from the boric acid tank and pure makeup
water from the primary water system. Water from these sources would
be mixed in the blender at an established ratio to provide boric
acid at the desired concentration.
If the current range of reactivity control is to be maintained using
the boric acid blender as the preferred boration flow path (as
opposed to the emergency boration flow path), an increase in the
Report No. 849963-HPS-5MISC-003 REV 0 Page 2-5
flow rate of boric acid will be required. This will be necessary tobe able to provide the same amount of boron to the blender in a
given period of time using the reduced boric acid tank boron
concentrations as compared to the existing concentrations. FPL
already plans to replace the valve trim for Flow Control Valve
FCV-113A to increase the achievable boric acid flow rates into the
blender and, hence, satisfy this requirement.
~Anal sis: No additional analyses are necessary since previous
analyses have shown it is possible to meet this requirement withboron concentrations in the range of 3.0 to 4.0 weight percent.
2.1.7 The CVCS boration system is required to insert negative reactivityat a rate that is sufficient to compensate for decay of xenon.
~im act: A reduction in the boron concentration of the boric acid
tanks will require greater boric acid flow rates to add the same
amount of boron in a given period of time. Greater boric acid flowrates to the boric acid blender will be achievable with modificationof FCV-113A as discussed in Section 2. 1.6 above.
'Anal sis: See Section 5.0.
2. 1.8 The CVCS boration system is required to be available post-LOCA foruse in controlling recirculation fluid pH.
~lm act: None
A~nal sis: Not Applicable.
Report No. 849963-MPS-5HISC-003 REV 0 Page 2-6
DESIGN BASIS PERFORMANCE REQUIREMENTS: EQUALITY-RELATED
This section addresses each of the quality-related (important to
safety) design basis performance requirements presented in Section
3.2 of Reference 10. 1. All requirements are addressed regardless ofany impact created by a reduction in boric acid concentration. For
ease of cross reference, these requirements are presented in the
same order as they appear in the design basis document with the same
last two digits of the section numbers used in this evaluation
(i.e., Section 2.2.2 here corresponds to Section 3.2.2 ofReference 10. 1).
2.2.1 One charging pump is required to deliver a charging line flow of 45
gpm and a total RCP seal injection flow of 24 gpm to three RCPs fora total pump flow of 69 gpm with a normal RCS pressure of 2235 psig.
~lm act: None
~Anal sis: Not Applicable.
2 '.2 The CVCS must provide adequate letdown and charging flow forpurification, cleanup and degassing operations.
~lm act: None
~Anal sis: Not Applicable.
2.2.3 The CVCS is required to provide seal water injection flow, nominally
8 gpm, to each RCP No. 1 seal. The temperature of the seal
injection water is required to be 130'F or lower. It is required
that suspended solid particles larger than 5 microns be removed from
the injection stream.
~lm act: None
Report No. 849963-MPS-5MISC-003 REV 0 Page 2-7
~Anal sis: Not Applicable.
2.2.4 The CVCS is required to provide a means for cooling the RCP lower
bearing under low RCS pressure conditions when all of the RCP No. 1
seal injection may flow directly into the RCS through the labyrinthseals instead of upward past the lower bearing.
~im act: None
A~nal sis: Not Applicable.
2.2.5 The CVCS is required to makeup for shrinkage during a 100'F/hr
cooldown of the RCS from hot zero power (mode 3, 547'F) to 350'F.
This is considered to be an original design basis function of the
CVCS.
~Im act: This criterion is independent of boron concentration.Since the charging system capacity is not being altered, the abilityof the system to provide sufficient makeup capacity under these
conditions is not impacted. Boration requirements are specified in
Section 2. 1.3 of this evaluation.
~Anal sis: See Section 6.6.4.
2.2.6 In modes 1 through 4, the CVCS is required to ensure that sufficientboric acid is available to bring each unit to cold shutdown with the
required shutdown margin from a hot zero power peak xenon condition
(mode 3, 547 F). It should be noted that the clarification ofSection 3.2.6 (Reference 10. 1) recognizes the refueling water
storage tank as an alternate source of water to satisfy this design
basis requirement (i.e., 70,000 gallons feed and bleed at 1950 ppm
boron).
~lm act: A reduction in the boron concentration of the boric acid
tanks will effectively decrease the rate of RCS boration by
Report No. 849963-UPS-5MISC-003 REV 0 Page 2-8
decreasing the amount of boron in every gallon charged to the RCS.
An additional consequence will be the corresponding increase in the
makeup volume required to add the total amount of boron required tocompensate for xenon decay and moderator cooldown. Boration inconjunction with the cooldown, however, will significantly reduce
the amount of boron lost during the traditional feed and bleed by
taking advantage of the contraction of the RCS. The effectivecooldown rate utilized in Section 5.0 is selected conservatively low
to allow for significant xenon decay during the cooldown scenario.
The methodology presented in this report and approved by the NRC on
previous plants did not assume boration starting at the
post-shutdown xenon peak as stated in this design criterion. A more
conservative approach was taken that assumed xenon had returned toits full power equilibrium level prior to initiation of the
cooldown. In this manner, the negative reactivity inserted by the
buildup of xenon after shutdown was not credited. The end of cycle
was chosen since it presented the worst case xenon and moderator
temperature reactivity effects to be compensated for through
boration. This approach has been reviewed in detail and fullyapproved by the NRC. To conservatively account for this design
basis requirement, however, a peak xenon transient is presented in
Appendix 9.
A~nal sis: See Section 5.0 and Appendix 9.
2.2.7 In modes 5 and 6, the CVCS is required to ensure that sufficientboric acid is available to compensate for coolant contraction and
the reactivity added due to moderator temperature effects in
proceeding from mode 5 at 200'F to ambient conditions.
~Im act: A reduction in the boron concentration of the boric acid
tanks will effectively increase the volume of boric acid and time
required to accomplish this task.
Report No. 849963-HPS-5HISC-003 REV 0 Page 2-9
Since this final phase of the RCS cooldown goes beyond the
requirement to achieve cold shutdown, the volume of boric acid
required to achieve this can be batched and added to the boric acid
tank(s) after cold shutdown is achieved. This volume does not need
to be considered in the boric acid tank volume requirement for modes
1, 2, 3, and 4. In accordance with the Hode 5 and 6 boric acid
inventory requirement bases in the technical specifications, a
cooldown to 140 F is the licensing basis for the tanks.
A~nal sis: See Section 5.3.
2.3 SAFETY ANALYSIS REOUIREHENTS
A reduction in the concentration of boric acid in the boric acid
tanks and elimination of the heat tracing associated with the
bor ation subsystems will require several changes to the Turkey Point
Technical Specifications as described in Section 7.0. Accordingly,
Reference 10.3 was reviewed in detail to ensure the bases behind
these technical speci,fications were understood and addressed.
A principal concern when reducing the available boric acid
concentration is the possible impact on the accident analyses of
Chapter 14 of the Final Safety Analysis Report (FSAR). A careful
review of this chapter has shown that the Turkey Point accident
analyses do not rely on any injection of concentrated boric acid.
The only boron injection credited is the relatively low
concentration from the refueling water storage tank. The boron
injection tank boron concentration, as well, has been reduced to a
level corresponding to the refueling water storage tank
concentration. The accident analyses of Chapter 14, therefore, are
not impacted by a reduction in the boron concentration of the boric
acid tanks.
Several sections of the FSAR, however, describe the boration
capabilities and procedures in terms of the high boron concentration
Report No. 849963-HPS-5HISC-003 REV 0 Page 2-10
that is currently available for reactivity control. Changes tothese sections are recommended through markups of the appropriatepages provided as Appendix 7. The principal areas of change are inChapter 1 (brief descriptions of boration capability), Chapter 3
(more detailed descriptions of boration reactivity controlmeasures/capabilities), and Chapter 9 (CVCS system description and
required functions).
2.4 10CFR50 APPENDIX R REQUIREMENTS
Reference 10.5 provides a detailed assessment of the capabilities ofthe plant to achieve and maintain both hot and cold shutdown
conditions. Safe shutdown is defined as hot subcritical conditionsas a minimum (T>540'F), with the capability to proceed to cold
shutdown should conditions warrant. Hot shutdown (per technical
specification mode definition) is specifically defined as the
initiation of Residual Heat Removal (RHR) system operation (350 F).
Although the capability exists to bring the plant to cold shutdown
conditions, the preferred approach appears to be to keep the plantat hot zero power (T>540'F) for as long as practically possible
(while the fire and any resulting damage are dealt with). The plant
would be brought to cold shutdown if, and only if, a plant
configuration resulted that required such action (e.g., a technical
specification limiting condition of operation not satisfied).
2.4.1 Safe Shutdown
The Turkey Point reactivity control system consists of two
independent reactivity control subsystems: 1) rod cluster control
assemblies (RCCAs), and 2) boric acid injection via the charging
system (CVCS). It is clear from the discussions of References 10.3
and 10.5, however, that the RCCAs alone are capable of achieving and
maintaining subcritical conditions during long term hot conditions.
The principal reasons for the boric acid injection capability are:
1) to provide a backup to this capability, and 2) to assure adequate
Report No. 849963-HPS-5MISC-003 REV 0 Page 2-11
reactivity control during the subsequent cooldown from the hot plantconditions. RCS makeup may or may not be required while maintainingthe plant in a hot condition depending upon RCS leakage and the
length of time. Adequate makeup capability exists, however, toaccount for normal leakage under these conditions for a reasonable
period of time. Given the limited volume available in the boricacid tanks, however, provisions should be made to preserve theconcentrated boric acid for the design basis cooldown scenario by
providing RCS makeup during long term hot plant conditions from therefueling water storage tank.
2.4.2 Cold Shutdown
If the plant is forced to go to a cold shutdown condition,reactivity control via boric acid injection will be required. This
will be necessary to compensate for the positive reactivity insertedby the reduction in core moderator temperature. In this manner,
adequate shutdown margin will be maintained preventing an
inadvertent return to criticality.
Boron addition and RCS makeup for contraction are possible using one
of three charging pumps and one of two independent sources of a
boric acid solution. The preferred source of boric acid is the
three (shared) boric acid tanks containing a solution of reduced
concentration boric acid via one of four shared boric acid transferpumps. The backup source of boric acid is the charging pump directgravity feed line from the refueling water storage tank containing a
lower concentration of boric acid. Additional provisions exist toalign either unit's refueling water storage tank to the suction ofeither unit's charging pumps.
4
The current methodology for conducting a plant cooldown is toinitiate a feed and bleed process to bring the RCS boron
Report No. 849963-MPS-5MISC-003 REV 0 Page 2-12
concentration to a level corresponding to the required shutdown
margin for a cold xenon free core. Once this has been accomplished,
the plant is cooled down with makeup for plant volume contractionprovided with a combination of makeup water and boric acid blended
to the new RCS concentration. This will effectively maintain a
constant RCS boron concentration throughout the cooldown process.
Such a feed and bleed process requires that a bleed path be
available. Turkey Point Units 3 and 4 have several design featuresthat assure the availability of RCS letdown under a variety ofconditions. The following potential letdown paths are described in
the Turkey Point FSAR (Reference 10.3):
(1) letdown via the non-regenerative heat exchanger (normal path);
(2) letdown directly to the VCT or holdup tanks bypassing the non-
regenerative heat exchanger (in the event of a loss ofcomponent cooling water —requires temperature to be maintained
<120'F) in conjunction with balanced letdown and charging flow
through the regenerative heat exchanger;
(3) letdown to the pressurizer relief tank via the letdown linesafety valve (achieved by isolating the letdown line outside ofcontainment);
(4) letdown via the RCP seal water return line to the VCT (normal)
or drain tank/pressurizer relief tank (emergency).
A revised approach for conducting a plant cooldown without letdown
consists of borating the plant in conjunction with the cooldown. In
this manner, no feed and bleed would be necessary since all the
boric acid injection would occur during the makeup provided to
compensate for contraction of the reactor coolant. Such an approach
allows a significant reduction in the concentration of boric acid
maintained in the boric acid tanks and the elimination of boration
Report No. 849963-MPS-5MISC-003 REV 0 Page 2-13
subsystem heat tracing. The use of letdown, however, will be
evaluated in the Operations Analyses of Section 6.0.
Implementation of a boric acid concentration reduction will impact
the Turkey Point Appendix R commitments since the use of the
methodology presented in this report will require a change from
boration prior to plant cooldown to ~durin plant cooldown.
Additionally, reduced boric acid concentrations will invalidate the
times to achieve the required boron concentration presented in
Reference 10.5 (which appear to be applicable to Fuel Cycle No. 8).All other aspects of the post-fire shutdown to hot standby
conditions and subsequent cooldown to cold shutdown conditions willremain the same. The 19 and 72 hour limitations are not considered
limiting from the perspective of boric acid tank inventory since the
refuelikng water storage tank is the stated source for reactivityand inventory control.
Report No. 849963-HPS-5HISC-003 REV 0 Page 2-14
ANALYSIS SCENARIOS
This section outlines the three basic scenarios proposed fordetailed analysis of the Turkey Point Units 3 and 4 borationcapabilities. These scenarios have been picked based on a carefulreview of the CVCS design and licensing basis for the currentbor ation capability as outlined in Section 2.0 of this evaluation.Specifically, the first two scenarios of Section 3. 1 are the ones
that have been approved by the NRC and used successfully for eightC-E designed plants. The basic scenario has been updated toinclude the plant specific data obtained from Turkey Point design
documents. The third scenario of Section 3. 1 is included toaddress the CVCS design basis requirement to support cold shutdown
from a peak xenon condition. Section 3.2 describes thenon-licensing analyses performed to evaluate the impact of reduced
boric acid concentration on normal plant activities.
3.1 LICENSING BASIS ANALYSES
3.1.1 Operating Nodes 1, 2., 3, and 4: Equilibrium Xenon
The cooldown methodology proposed herein has been developed toallow a significant reduction in the boric acid concentration thatis required to be maintained in the boric acid tanks while
operating in Nodes 1, 2, 3, and 4. The proposed cooldown
methodology differs from the current methodology employed at
Turkey Point in that boration of the reactor coolant system isperformed concurrently with cooldown as opposed to borating priorto initiating plant cooldown. This approach can be justified ifit can be demonstrated through conservative analyses that proper
shutdown margin can be maintained when concentrated boron is added
as part of normal system makeup during the cooldown process. To
accomplish this, the exact boron concentration required to be
present in the RCS must be known at any temperature during the
cooldown process. In addition, in order to ensure applicability
Report No. 849962-UPS-5HISC-003 REV 0 Page 3-1
for an entire cycle, a cooldown scenario must be developed which
is conservative in that it places the greatest burden on an
operator's ability to control reactivity (i.e., this scenario must
define the boration requirements for the most limiting time incore cycle). The limiting scenario is as follows:
(1) Conservative core physics parameters are used to determine
the required boron concentration and the required boric acid
tank volumes to be added during plant cooldown. End of cycle
(EOC) initial boron concentration is assumed to be zero. EOC
moderator cooldown effects normalized to the most negative
technical specification Hoderator Temperature Coefficient(HTC) limit are used to maximize the reactivity insertionrate during the plant cooldown. EOC Inverse Boron Worth
( IBW) data are used in combination with the EOC reactivityinsertion rates, since this yields results that are more
limiting than the combination of specific HTC and IBW values
at any fuel cycle exposure prior to EOC. These assumptions
ensure that the required boron concentration and the boric
acid tank minimum volume requirements conservatively bound
all plant cooldowns during corelife.'2)
The most reactive rod is stuck in the full out position.
(3) Prior to time zero, the plant is operating at 100X power with
100X equilibrium xenon and with zero RCS leakage. Assuming
zero RCS leakage conservatively limits the boron addition to
that which is added to the RCS to make up for contraction
during the cooldown. Additionally, slow cooldown rates willfurther reduce the boron addition by limiting the rate ofreactor coolant concentration change.
(4) At time zero, the plant is shutdown and held at hot zero
power (547 F) conditions for 23.5 hours. The xenon peak
after shutdown will have decayed back to the 100X power
Report No. 849962-HPS-5HISC-003 REV 0 Page 3-2
equilibrium xenon level by this time. Further xenon decay
will add positive reactivity to the core during the
subsequent plant cooldown. No credit is taken for the negativereactivity effects of the peak xenon concentration followingthe reactor shutdown.
(5) At 23.5 hours, offsite power is lost and the plant goes intonatural circulation. The non-safety grade letdown is lost.During the natural circulation the RCS average temperature
rises 25'F due to decay heat in the core. The initialtemperature at the start of the cooldown is 572'F.
(6) Approximately 0.5 hours later, at 24 hours, the operatorscommence a cooldown to cold shutdown.
The scenario outlined above is used to generate the borationrequirements for Modes 1, 2, 3, and 4. It produces a situationwhere positive reactivity will be added to the RCS simultaneously
from two sources at the time that a plant cooldown from hot
standby is commenced. These two reactivity sources result from a
temperature effect due to an overall negative isothermal
temperature coefficient of reactivity, and a poison effect as the
xenon-135 level in the core starts to decay below its 100X power
equilibrium value. This scenario, therefore, represents the
greatest challenge to an operator's ability to borate the RCS and
maintain the required technical specification shutdown margin
while cooling the plant from hot standby to cold shutdown
conditions.
3. 1.2 Operating Modes 5 and 6
The methodology developed for Modes 5 and 6 is similar to the
method proposed for Modes 1, 2, 3 and 4 in that boration of the
RCS is performed concurrently with cooldown. Concentrated boric
acid is added as part of normal system makeup during the cooldown
Report No. 849962-HPS-SHISC-003 REV 0 Page 3-3
process. To accomplish this, the exact boron concentrationrequired to be present in the RCS must be known at any temperatureduring the cooldown process. The following scenario was developed
to identify the most limiting cooldown transient for Modes 5 and 6.
(1) EOC conditions with the initial RCS boron concentrationnecessary to provide shutdown margins of 1000 pcm (IX ak/k)at 200'F and xenon free. EOC moderator cooldown effects are
used to maximize the reactivity change during the plantcooldown. EOC IBW data are used in combination with EOC
reactivity insertion rates normalized to the most negativetechnical specification HTC limit since this yields resultsthat are more limiting than the combination of actual HTC and
actual IBW values at all periods through the fuel cycle priorto EOC.
(2) The most reactive rod is stuck in the full out position.
(3) There is zero RCS leakage.
(4) RCS feed and bleed can be used to increase boron .
concentration (for the case where the refueling water storage
tank is the source).
(5) RCS makeup is supplied either from the refueling water
storage tank alone or from the boric acid tank.
(6) The most limiting scenario for boration in Mode 5 requiresthat a 1000 pcm (IX sk/k) shutdown margin be maintained
during the cooldown from 200'F to 135'F. The boration
requirements for Mode 6 only address maintaining a previouslyestablished shutdown margin.
Report No. 849962-HPS-5HISC-003 REV 0 Page 3-4
The scenario outlined above was used to determine the borationrequirements for Hodes 5 and 6. It produces a situation where
positive reactivity will be added to the RCS due to the overallnegative isothermal temperature coefficient of reactivity; Since
the core is already assumed to be xenon free there is no
contribution to core reactivity due to xenon decay.
3. 1.3 Operating Hodes 1,2,3, and 4: Peak Xenon
The basic elements of this analysis scenario consist of the
following:
(1) the cooldown transient is initiated eight hours followinga reactor trip from extended full power operation(corresponding to the peak xenon condition instead of the
full power equilibrium xenon concentration) and,
(2) the subsequent cooldown boration must compensate for the
decay of the entire xenon inventory from its peak value
(instead of its full power equilibrium value).
This scenario presents a worst case near the end of the cycle when
sufficient RCS boron concentration (>0 ppm) is available to allow
RCS boron concentration to be diluted by the operator tocompensate for the post-shutdown xenon buildup in anticipation ofa rapid return to power. Starting a design basis cooldown to cold
shutdown from the peak xenon condition under these conditions willeffectively increase the amount of boron required to be charged to
the RCS to compensate for the decay of the xenon peak.
Specifically, the boration required to maintain shutdown margin
will be completed from the boric acid tank and refueling water
storage tank in conjunction with the plant cooldown such that the
volume of boric acid charged into the plant will make up forcooldown contraction. The proposed scenario for this analysis isdiscussed further in Appendix 9.
Report No. 849962-HPS-5HISC-003 REV 0 Page 3-5
OPERATIONS ANALYSES
A series of analyses are presented in Section 6.0 in order todemonstrate the general impact of a reduction in boric acid tankboron concentration on a variety of plant operations. The
specific areas that will be addressed will include operatorresponse to emergency situations, typical plant feed and bleed
operations, typical plant blended makeup operations, plantshutdown to refueling, and plant shutdown to cold shutdown. It is a
difficult and unnecessary task to evaluate each of these five areas
and consider all possible combinations of plant conditions.Instead, initial plant parameters and analyses assumptions will be
selected in a conservative manner to give worst case responses. As
a consequence, the results (i.e., the volumes and finalconcentrations that are obtained) should be bounding for any event
or any set of initial plant conditions.
Report No. 849962-HPS-5MISC-003 REV 0 Page 3-6
0
METHOD OF ANALYSIS AND ASSUMPTIONS
4.1 ANALYSIS METHODOLOGY
The basis for the proposed methodology for reduction in the boricacid concentrations required to be maintained in the boric acid
tanks is a more efficient use of available boric acid sources. The
current cooldown methodology in use at Turkey Point accomplishes RCS
boration to the required cold shutdown concentrations before the
cooldown begins by utilizing available volume in the pressurizer orthrough a feed and bleed process. Plant cooldown is initiated withmakeup for contraction provided from the reactor makeup water
system. This makeup water is blended with boric acid from the boricacid tank to the new RCS concentration. In this manner, RCS
concentration is held constant during the cooldown process.
A proposed cooldown methodology is analyzed that will cover a worst
case cooldown scenario without letdown (Section 3. 1. 1). This
methodology makes two simple changes to the current approach:
(1) Borate the RCS in conjunction with plant cooldown by using a
concentrated boric acid solution as makeup for coolant
contraction.
(2) Utilize the refueling water storage tank as an additionalsource of boric acid makeup.
The basis for the minimum volume specified for the boric acid tank
will be such that injection of the boric acid tank contents in the
early phase of the cooldown will raise the RCS boron concentration
to a sufficient level such that subsequent makeup from the lower
concentration refueling water storage tank will maintain adequate
shutdown margin throughout the completion of the cooldown. (See
Section 5.0.)
Report No. 849963-HPS-5HISC-003 REV 0 Page 4-1
Justification for this approach is accomplished in two steps. The
first step is to calculate the actual RCS boron concentrationrequirements during each temperature increment of a plant cooldown
that will ensure maintenance of adequate shutdown margin. The next
step is to model a plant cooldown and to identify the expected boron
delivery to the RCS as makeup for coolant contraction is provided
from the boric acid tank and refueling water storage tank. As longas boron delivered to the RCS is always greater than the boron
required, shutdown margin is assured. Selection of conservativephysics and plant system parameters and the conservative modeling ofboron injection ensure that a bounding analysis is presented thatwill cover those cooldown reactivity control scenarios reasonably
expected to occur.
4.2 PHYSICS ANALYSIS ASSUHPTIONS
This section describes the assumptions utilized in the calculationof the required RCS boron concentration during the cooldown. The
basic approach of balancing core reactivity effects with boron
addition has been devised to conservatively bound the reactivityeffects of the design basis cooldown scenarios described in Section
3. 1. 1 and 3. 1.2. This is intended to ensure that these analyses
conservatively bound any similar cooldown which may occur any time
during the fuel cycle.
The following presents an item-by-item discussion of the specificcore reactivity effects that have been accounted for in the physics
analysis. Appendix 5 presents the physics data provided by FPL as
input to this analysis. Table 4-1 summarizes the important physics
parameters utilized in this analysis and compares them to similarvalues used for a typical plant that has implemented this change.
Where applicable, all uncertainties and cycle to cycle variances
have been applied in a conservative manner to maximize the
reactivity control requirements. Appendix 8 provides a checklist ofthese key physics parameters to allow cycle to cycle confirmation
that these prarameters remain bounding for future cycles.
Report No. 849963-HPS-5HISC-003 REV 0 Page 4-2
1. Time in cycle
Positive reactivity is added to the core as the moderator
temperature is lowered during plant cooldown. The reactivityeffects associated with this cooldown vary over core life so itis important to analyze the most restrictive case. The EOC (orend of life) case was selected for the following reasons:
a. Moderator Tem erature Coefficient
The MTC indicates the expected change in core reactivitywith a change in moderator temperature. A negative HTC
indicates that a positive reactivity effect will resultfrom a decrease in core temperature. The HTC varieswidely over core life with the most negative value
occurring at EOC. A value of -3.5 x 10 ak/k/'Fcorresponds to the most negative technical specificationlimit per Specification 3. 1. 1.3 of Reference 10.6 and was
used for this analysis.
b. Re uired Shutdown Har in
The shutdown margin requirements for Turkey Point are
specified in Figure 3. 1-1 of Reference 10.6, and, likeMTC, varies with core life as a function of fueldepletion, RCS boron concentration and RCS average
temperature.
A sufficient shutdown margin ensures that: 1) the reactor
can be made subcritical from all operating conditions, 2)
the reactivity transients associated with postulated
accident conditions are controllable within acceptable
limits, and 3) the reactor will be maintained sufficientlysubcritical to preclude inadvertent criticality in the
shutdown condition.
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The most restrictive condition, again, occurs at EOC withRCS average temperature at no load operating temperature
and is associated with a postulated steam line break
accident and resulting uncontrolled RCS cooldown. This
results in a shutdown margin of 1.77X ak/k fortemperatures above 200'F (corresponding to an RCS boron
concentration of 0 ppm) and 1.0X ak/k for temperatures
below 200'F. The reduction in margin requirements at200'F is due to the fact that the reactivity transientsresulting from inadvertent RCS cooldown or dilution are
minimal. Hence, 1X ak/k is adequate protection at these
lower temperatures.
c. Boron Concentration
Hany of the physics parameters used for this analysis vary
with boron concentration. In particular, the smaller
boron concentration associated with EOC gives the most
negative HTC over cycle life. Consequently, an EOC boron
concentration of 0 ppm is selected as the most limitingfrom a core physics perspective.
d. Inverse Boron Worth
IBW data were extracted from the physics data of Appendix
5. EOC IBW data were used in combination with EOC
reactivity insertion rates normalized to the most negative
technical specification HTC limit since it was known that
this yields results that are more limiting than the
combination of actual HTC and actual IBW values at allperiods through the fuel cycle prior to EOC. The specific
IBW values utilized for the EOC analyses are presented in
Table 4-2.
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2. Scram Worth
A conservative scram worth was used in the physics analysis.Specifically, the available scram worth was computed utilizingthe hot zero power scram worth for all rods in, minus the worstrod stuck full out. From this value the rod bank insertionlimit worths were subtracted to obtain a net available scram
worth. An uncertainty of 10X was subtracted from the availablescram worth for added conservatism. This scram worth isfurther reduced by subtracting an EOC reactivity value
associated with the Full Power Defect.
3. Determination of Excess Scram Worth
Excess scram worth was determined by comparing the availablescram worth at zero power (Item 2 above) to the requiredtechnical specification shutdown margin presented in Item lbabove.
It was determined that there is a 0.697X sk/k excess scram
worth available for temperatures above 200'F and an excess
scram worth of 1.468X ak/k for temperatures below 200'F.
4. Core Reactivity Effects
A reactivity calculation has been performed to account for the
addition of positive reactivity due to both the decay of xenon
and the cooldown of the moderator and fuel. Uncertainties were
applied to all reactivity effects as indicated in Table 4-1.
Table 4-1 summarizes the uncertainties used in this calculationand compares them to the values used for the calculation of a
previous unit .
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a. Xenon Reactivit Effects
As shown in the data presented in Appendix 5, the xenon
worth peaks at its most negative reactivity worth around
eight hours after the reactor is shutdown. Xenon decay
reduces the negative reactivity of the xenon back to itsfull power steady state operating value at approximately
24 hours after shutdown. At times after 24 hours, the
plant must be borated to compensate for the positivereactivity addition provided by further reductions inxenon concentration. As an added conservatism, the
reactivity calculation does not credit the extra negative
reactivity inserted by the xenon peak that occurs aftershutdown. Instead, the plant is assumed to remain at hot
standby for 24 hours to allow xenon to return to the 100/o
steady state value so that further xenon decay will add
net positive reactivity simultaneously with the moderator
cooldown effects. The data presented in Appendix 5 was
used to determine the positive reactivity inserted intothe core for times after 24 hours at discrete time
intervals. Note that a slow cooldown rate will prolong
the time required to reach Mode 5 where the shutdown
margin drops to IX sk/k and, therefore, would require a
larger boron concentration to counteract xenon decay
during the cooldown. A 10 F/hr cooldown rate has been
utilized in this calculation. It should be noted thatthis method accounts for xenon decay for a full 61 hours
from its full power equilibrium level. This is a much
longer time frame than is expected to actually achieve
cold shutdown.
The analysis of Appendix 9, however, considers the impact
of borating from a peak xenon condition as discussed in
Section 3. 1.3.
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b. Reactor Cooldown Effects
The effect of the reactor cooldown was calculated by
determining the fuel temperature and moderator temperaturereactivity effects for each incremental temperaturedecrease. Data from Appendix 5 were utilized to determine
these effects. It should be noted that these reactivityeffects are independent of time and solely dependent on
the change in temperature of the core.
5. Effective Cooldown Rate
As discussed above, positive reactivity is added simultaneouslyfrom two sources at the time that the plant cooldown from hot
standby is commenced. The component resulting from an overallnegative isothermal temperature coefficient of reactivity isindependent of time, but is directly dependent upon the net
change in moderator temperature. In contrast, the component
that results from the decay of xenon below its full power
equilibrium value is independent of temperature, but directlydependent upon time. The reactivity contribution from the
moderator cooldown is fixed given the fixed temperature
endpoints (e.g., 572'F to 200'F). The reactivity contributionfrom xenon decay, however, will vary depending upon the time
interval required to achieve the cooldown (i.e., the effectivecooldown rate). As a result, a slower cooldown rate willrequire more boron to be added to the RCS than a fast cooldown
rate for a given temperature decrease. This is because the
cooldown will take a longer period of time allowing more
positive reactivity to be added to the core from the decay ofxenon.
Additionally, since the boration is being accomplished through
makeup for coolant contraction, the addition rate of boron iscontrolled by the rate of coolant contraction. Slower cooldown
Report No. 849963-MPS-5HISC-003 REV 0 Page 4-7
rates will result in slower makeup rates which, in turn, resultin slower boron addition rates. Superimposing this effect over
the temperature independent xenon decay will assure that the
most limiting reactivity control scenario is analyzed.
The effective cooldown rate, therefore, is an important inputparameter for these analyses. A lower limit of 10'F/hr was
selected as the limiting case based on the considerations ofTable 4-3.
6. Core Temperature Endpoints
a. Startin Tem erature
The normal hot zero power RCS temperature corresponds to547'F. For the purpose of the analyses presented in
Section 5.0 it is assumed that the cooldown initiates from
a temperature 25 F higher to conservatively model the
expected thermal hydraulic response to a natural
circulation condition. This temperature increase also
corresponds with natural circulation tests completed at
plants of similar size. The cooldown startingtemperature, therefore, will be assumed to be 572'F.
b. Endin Tem erature
The ending temperature for the cooldown from Hot Standby
to Cold Shutdown is chosen to coincide with the 200'F
transition from Mode 4 to Mode 5. At this temperature,
the shutdown margin requirement is decreased to 1.0X nk/k
and the boration source and flow path requirements are
relaxed.
The additional cooldown while in Mode 5 is analyzed
separately since the boration requirements while in thismode are independent of the Mode I, 2, 3, 4 boration
Report No. 849963-MPS-5MISC-003 REV 0 Page 4-8
requirements (source and flow path). The Bases section ofReference 10.6 indicates that the Mode 5 borationrequirement in terms of volume and boron concentration isbased on performing a Mode 5 cooldown to 140'F. For the
purpose of these analyses with reduced boric acid concen-
tration, the endpoint temperature is assumed to be 135'F
to conservatively maximize the core reactivity effects.
Appendix 8 provides a checklist of the key physics parameters thatcan be used to evaluate subsequent fuel cycle data to ensure the
data utilized in these analyses remain bounding.
4.3 SYSTEM ANALYSIS ASSUMPTIONS
Table 4-4 presents a list of the specific parameters utilized in the
analysis of boron delivery during the design basis cooldown
described in Section 3.0. A comparison is made to the St. Lucie
Unit 2 data so that differences in the analyses input and output can
be identified. The basic approach in conducting the cooldown
analysis is identical to that used for all previous CE units. A few
minor changes have been made to make the analysis more conservative.
The following paragraphs describe the specific analysis assumptions
in greater detail.
1. System Volumes
a. RCS Volume
The total coolant volume is listed in Reference 10.3 as
9343 ft . Subtracting the total pressurizer volume leaves
8015 ft for the RCS alone. The pressurizer water volume
is listed as 808 ft for 100X power and 520 ft for OX3 3
power. As a conservatism, the 100X power pressurizer
volume will be utilized in the analyses of Section 5.0.
This will provide a higher total system mass to dilute the
Report No. 849963-MPS-5MISC-003 REV 0 Page 4-9
boric acid added during the plant cooldown. The OX power
pressurizer volume will be used in the analyses of Section
6.0, however, since this represents the expected volume
following a shutdown. Note that a basic assumption
throughout the analyses of Section 5 and 6 is that the
operators charge to the plant to maintain pressurizerlevel throughout the cooldown transient.
b. Residual Heat Removal S stem Volume
The RHR system is brought into service below 465 psia and
below 350'F. As shown by Appendix 2, the volume of the
RHR system will not impact the final boron concentrationwhen its concentration is assumed to be equal to the RCS
boron concentration.
Also, because it is connected to the RCS after the C-E
methodology has shifted the RCS makeup to the refuelingwater storage tank, the RHR volume will not factor intothe boric acid tank minimum volume requirements. However,
in order to identify the specific refueling water storage
tank volume requirements for each case analyzed the RHR
volume must be included in the calculations for coolant
contraction. To place a conservative upper bound on these
volumes an RHR volume equal to the RCS volume (8015 ft )3
is assumed in the Section 5.0 analyses. The operations
analyses of Section 6.0, however, assume a closer, yet
still conservatively high, volume of 2000 ft .3
2. Residual Heat Removal System Boron Concentration
For the conservative analyses of Section 5.0, the RHR system isassumed to be at the low concentration equal to the RCS
concentration at the time it is lined up to the RCS. In thismanner, the system model does not credit boron addition from
this system.
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3. Hakeup Source Temperatures
Appendix 3 presents the derivation of the mass of boric acidthat is added to the RCS with every gallon of water charged tothe system as makeup for coolant contraction. Although thereis a very slight variation in boron delivery with temperature,the effect of source temperature on the required volume is more
significant. This makes the higher temperature the limitingcase, because it is makeup water density that converts the RCS
shrinkage mass into a makeup volume requirement. A highertemperature requires a greater volume to provide the same mass.
A temperature of 120'F was selected because it is above the
technical specification limit of 100'F for the refueling water
storage tank and provides for the possibility of high ambient
temperatures in the vicinity of the boric acid tank.
RCS Leakage
Zero RCS leakage is assumed throughout the analyses of Section
5.0. This is 'a conservative assumption because it limits the
available boron addition to the RCS to that which is provided
by makeup for coolant contraction alone. The effect of RCS
leakage on top of the cooldown analyses presented in Section
5.0 would be a feed and bleed in conjunction with the makeup
for contraction resulting in a net increase in the boric acid
added to the system. Even though boric acid is being lost, the
concentration of the makeup water is always higher than thatwhich is lost assuming the boric acid tank or refueling water
storage tank is the source of. makeup. With RCS leakage, the
contents of the boric acid tank will be added to the RCS sooner
causing the transition to the refueling water storage tank
sooner. The refueling water storage tank would continue tomake up for leakage and coolant contraction with an effectivelyhigher boron addition rate. The net result is that the finalboron concentration in the RCS will be significantly higher
than that which is indicated by the results of Section 5.0.
Report No. 849963-HPS-5HISC-003 REV 0 Page 4-11
RCS leakage, however, will impact the total volume used from
the refueling water storage tank throughout the cooldown. The
refueling water storage tank volumes indicated in the tables ofSection 5.0 are based on zero RCS leakage and should be
adjusted accordingly. Technical specification limit leakage of11 gpm over a 24 hour hold and a 37 hour cooldown equates to a
maximum expected leakage volume of approximately 42,000
gallons. When added to the contraction makeup volumes, the
refueling water storage tank volumes required to support plantcooldown are well within the volume limit of 320,000 gallonsfor Modes 1 through 4 (supporting emergency core coolingrequirements) and need not be accounted for separately.
5. Letdown
Letdown is assumed not to be available for this analysis. The
basis for this is that attempted boration is more difficultwithout it. The availablility of letdown would provide the
opportunity to control reactivity changes (xenon and cooldown)
through one or more feed and bleed operations. However, the
use of letdown at 45 gpm and 60 gpm is evaluated in the Section
6.0 operations analyses to evaluate system boration capabilityvia a feed and bleed process.
6. Boron Mixing in the RCS
Throughout the plant cooldowns analyzed in Section 5.0, a
constant pressurizer level is always assumed (i.e., plant
operators charge to the RCS only as necessary to makeup forcoolant contraction). Under these conditions, the drivingforce for the mixing of fluid between the RCS and the
pressurizer is relatively small. As a conservatism, however,
complete and instantaneous mixing is assumed between all makeup
fluid added to the RCS through the loop charging nozzles and
the pressurizer. Further, a pressure reduction is performed
during the plant cooldown process as indicated in Section 5.0.
Report No. 849963-MPS-5MISC-003 REV 0 Page 4-12
This pressure reduction is necessary since the shutdown coolingsystem is a low pressure system and is normally aligned at orbelow an RCS pressure of 465 psia. Typically, such
depressurizations are performed using the auxiliary pressurizerspray system under conditions where the RCPs are not running.As an added conservatism, any boron added to the pressurizervia the spray system is assumed to stay in the pressurizer and
not be available for mixing with the fluid in the remainder ofthe RCS. In the analyses of Section 6.0, however, the boron
added to the plant to account for pressurizer mass shrinkage
during the depressurization from 2250 psia to 465 psia iscredited since plant procedures call for regular pressurizersprays to equalize boron concentration between the RCS and the
pressurizer.
7. RHR Pressure
In accordance with Reference 10. 10, RCS pressure will be
controlled in the range of 375 to 400 psig. A pressure of 350
psia was chosen for the RCS pressure while on RHR cooldown toconservatively bound the allowable range. Lowering the
pressurizer pressure has the effect of causing more pressurizershrinkage mass that dilutes the RCS when no credit is taken forthe bor ation of this shrinkage mass make up.
8. Final RCS Pressure
As one final dilution step, the RCS is assumed to be
depressurized to atmosheric pressure in preparation forrefueling.
9. Final Boron Concentration
Final boron concentration is arbitrarily selected as 50 ppm
over the highest value for the 200'F shutdown margin
requirement. This provides ample margin to support possible
physics parameter changes in future cycles.
Repor t No. 849963-MPS-5MISC-00$ REV 0 Page 4-13
ADDITIONAL ASSUMPTIONS, MODE 5 COOLDOMN
I
The following additional assumptions are applicable to the cooldown
analysis for Mode 5 (i.e., cooldown from 200'F to 135'F). The
assumptions of Section 4.3 remain applicable, as well
1. Pressurizer Volume
The OX power pressurizer level is assumed for this phase of the
cooldown analysis since it is a more realistic representation
of the plant operations.
2. Initial RCS Boron Concentration
The analyses of Section 5.0 indicate a final boron
concentration in excess of the required boron concentration at
the completion of the cooldown to 200 F. However, the initialconcentration is assumed to be equal to the 200'F xenon free
boron requirement. This will assess the ability of the
boration system to recover and maintain a degree of margin
above the absolute minimum.
For the case where the refueling water storage tank is utilizedfor cooldown makeup, a feed and bleed is necessary at the startof the cooldown to ensure shutdown margin is maintained. The
amount of boron added to the system during this feed and bleed
was calculated to bring the final RCS boron concentration
exactly to the 135'F shutdown margin requirement.
Report No. 849963-MPS-5MISC-003 REV 0 Page 4-14
Table 4-1
Boric Acid Concentration Reduction AnalysisComparison of Physics Parameters
Parameter
Core Power (100X)
Shutdown Margin T>200'F
Shutdown Margin T<200'F
RCS Average Temperature (OX Power)
RCS Cooldown Starting Temperature
Moderator Temperature Coefficient
TypicalC-E Unit
2560 HWt
5.0X ak/k
3.5X ak/k
532 F
557'F (1)
-2.7E(-4)Gk/k/'F
Moderator Data Uncertainty (Bias)
Doppler Data Uncertainty (Bias)
IBW Data Uncertainty (Bias)
Effective Cooldown Rate
10X (OX)
15X (15X)
10.9X (-3.1X)
12.5 F/hr
Scram Worth Data Uncertainty (Bias) 13X (-9X)
Turkey PointUnits 3 and 4
2200 HWt
1.77X nk/k
1.0X ak/k
547'F
572'F (1)
-3.5E(-4)ak/k/ F
10X (OX)
10X (OX)
20X (OX)
10.9X (OX)
10'F/hr
Start of Cooldown (time afterShutdown)
Excess Scram Worth (T>200'F)
Excess Scram Worth (T<200'F)
26 hrs
0.08X ak/k
1.58X nk/k
24 hrs (2)
0.697X b,k/k
1.468X nk/k
(1) Based on 25'F heat up from hot zero power condition uponinitiation of natural circulation.
(2) The analysis of Appendix 9 starts from the peak xenon condition at 8
hours after a full power shutdown.
Report No. 849963-MPS-5HISC-003 REV 0 Page 4-15
Table 4-2
Inverse Boron Morth
Tem erature 'F IBM
572.0
552.0
532.0
512.0
492.0
472.0
452.0
432.0
412.0
392.0
372.0
352.0
332.0
312.0
292.0
272.0
252.0
232.0
212.0
202.0
200.0
98.65
95.88
93.44
91.26
89.33
87.61
86.06
84.66
83.39
82.21
81.12
80.08
79.10
78.16
77.24
76.34
75.46
74.60
73.76
73.34
73.26
Report No. 849963-MPS-5HISC-003 REV 0 Page 4-16
Table 4-3
Derivation of Limiting Cooldown Rate (*)(Modes 1, 2, 3, and 4)
Action
1. Plant Shutdown to Hot Standby
2. Initial Hold at Hot Standby
3. Plant Cooldown 572'F to approx. 350'F
4. Hold for upper Head Cooling
5. Plant Cooldown from approx. 350'F to 200'F
6. Additional Conservatism
TlmB Total
13
22
28
37
7. Effective Cooldown Rate: (372'F)/(37 hr) 10'F/hr
(1) Per NRC Branch Technical Position (BTP) RSB 5-1
(2) Cooldown rate limited to 25'F/hr per Reference 10. 10 (normally limited to
6 hours by technical specification ACTION statements)
(3) Per Reference 10. 10
(4) Allows for actual plant cooldown rates during Steps 3 and 4 as low as
15'F/hr
(*) This represents a conservative estimate of the time required to complete
a cooldown to COLD SHUTDOWN to maximize xenon decay reactivity effects.
Report No. 849963-MPS-5MISC-003 REV 0 Page 4-17
Table 4-4
Boric Acid Concentration Reduction AnalysisComparison of System Analysis Parameters
Parameter
RCS Volume
Pressurizer Water Volume (100X Power)
Pressurizer Water Volume (OX Power)
RCS Normal Operating Pressure
RCS Hinimum Operating Pressure
RCS Cooldown Starting Pressure
RCS Cooldown Final Pressure (Mode 5)
RCS Average Temperature (100X Power)
RCS Average Temperature (OX Power)
Post-Shutdown RCS Temperature Increase
RCS Cooldown Starting Temperature
RCS Cooldown Final 'Temperature (Mode 2 to 5)
RCS Cooldown Final Temperature (Modes 5 and 6)
Effective Cooldown Rate
Shutdown Cooling System Entry Pressure
Shutdown Cooling System Entry Temperature
RWST Minimum Volume (Modes 1-4)
RWST Minimum Boron Concentration
RWST Temperature (Assumed)
Boric Acid Tank Temperature (Assumed)
RCS Leakage (Assumed)
Letdown UtilizedInitial RCS Boron Concentration
Pressurizer Condition
TypicalC-E Unit
9398 ft600 ft450 ft2250
2200
2200 psia275 psia572 F
532'F
25 F
557'F
200 F
135'F
12.5'F/hr275 psi a
325'F
417,100 gal1720 ppm
50 F
70'F
0 gpm
No
0 ppm
Saturated
Turkey PointUnits 3 and 4
8015 ft (1)808.0 ft (2)520.0 ft2250
2200
2250 psia14.7 psia574.2'F547'F
25'F
572'F
200'F
135'F
. 10'F/hr350 psia350'F
320,000 gal
1950 ppm
120'F
120'F
0 gpm
No
0 ppm
Saturated
(1) Loop and vessel volumes only(2) Pressurizer water volume only (the total capacity of the loops, vessel,
and pressurizer is listed as 9343.
Report No. 849963-MPS-SHISC-003 REV 0 Page 4-18
. 5.0 DESIGN BASIS ANALYSES
This section presents the results of the analyses completed for thescenarios outlined in Sections 3. 1. 1 and 3. 1.2. These specificscenarios were chosen on the basis that they represent the most
limiting reactivity control conditions during a design basis
cooldown of the plant. Section 5. 1 presents the actual RCS boron
concentration requirements that conservatively maintain the requiredshutdown margin at discrete temperature increments. Section 5.2
discusses the conservative analysis of the cooldown from the hot
standby condition to cold shutdown. Section 5.3 completes the
cooldown analysis by presenting the conservative cooldown from cold
shutdown conditions to refueling temperatures.
5.1 RE(UIRED RCS BORON CONCENTRATION
Using the physics data of Appendix 5 and the assumptions of Section
4.2, a detailed reactivity balance calculation was completed. The
output of this calculation is a specified minimum boron
concentration change that must occur in the core (i.e., in the RCS)
to maintain the specified shutdown margin. This reactivity balance
specifically takes into account the positive reactivity addition ofxenon decay below its initial full power equilibrium concentration
and positive reactivity addition of moderator cooldown. With the
uncertainties of Section 4.2 conservatively applied, shutdown margin
will be assured if the RCS boron concentration is maintained above
the levels indicated in Tables 5. 1-1 through 5. 1-6 for each
temperature step. The data in these tables are presented in
Figure 5.1-1.
As can be seen from the tables and Figure 5. 1-1, the slower cooldown
rates have higher boron concentration requirements. This is because
in the time to get to 200'F, more xenon will have decayed, adding a
greater amount of reactivity that must be compensated for.
Report No. 849963-MPS-5MISC-003 REV 0 Page 5-1
It should also be noted that three different boron concentrationrequirements are specified for the 200'F temperature endpoint. The
E
first corresponds to the endpoint of the cooldown and corresponds toa shutdown margin of 1.77X sk/k. At 200'F, however, the shutdown
margin requirement drops to 1.0X ak/k, effectively requiring less
boron to be in the system. The third entry corresponds to the
boron concentration required to maintain a 1.0X ak/k shutdown margin
at 200 F with all xenon decayed away (xenon free). Xenon requires
approximately 150 hours after shutdown to effectively decay away tothis level. It should be noted that all of the tables indicate the
same xenon free required boron concentration at 200'F.
The results of the peak xenon calculation are presented in Appendix
9. Since the Appendix 9 final concentration for 200 degrees at a
10'F/hr cooldown rate is the higher value, the acceptance criteriafor the cooldown evaluations will be a final concentration 50 ppm
higher than the identified limit of 840 ppm boron.
Report No. 849963-HPS-5MISC-003 REV 0 Page 5-2
Table 5.1-1
Required Boron Concentration vs. Temperature
Equilibrium Xenon, EOC, 10'F/hr Cooldown Rate
Tem erature 'F Re ui red Boron m
572.0
552.0
532.0
512.0
492.0
472.0
452.0
432.0
412.0
392.0
372.0
352.0
332.0
312.0
292.0
272.0
252.0
232.0
212.0
202.0
200.0 (1.77X ak/k)200.0 (1.0X nk/k)200.0 (Xenon Free)
-180.81
-63.90
48.22
147.89
233.39
307.02
370.73
426.15
474.64
517.38
555.32
589.29
619.98
647.95
673.68
697.57
719.94
741.05
761.12
770.81
772.73
710.17
730.70
Report No. 849963-MPS-5MISC-003 REV 0 Page 5-3
Table 5. 1-2
Required Boron Concentration vs. Temperature
Equilibrium Xenon, EOC, 25'F/hr Cooldown Rate
Tem erature 'F Re uired Boron m
572.0
522.0
472.0
422.0
372.0
322.0
272.0
222.0
200. 0 (1. 77X nk/k)200.0 (1.0X nk/k)200.0 (Xenon Free)
-180.81
61.05
243.12
373.13
471.12
549.62
616.31
675.63
700.05
637.49
730.70
I
Report No. 849963-HPS-5HISC-003 REV 0 Page 5-4
Table 5.1-3
Required Boron Concentration vs. Temperature
Equilibrium Xenon, EOC, 50'F/hr Cooldown Rate
Tem erature 'F Re uired Boron m
572
522
472
422
372
322
272
222
200.0 (1.77X ak/k)200.0 (1.0X ak/k)200.0 (Xenon Free)
-180.81
47.11
218.02
339.06
429.91
502.89
565.54
622.11
645.68
583.12
730.70
Report No. 849963-HPS-5MISC-003 REV 0 Page 5-5
Table 5.1-4
l
Required Boron Concentration vs. Temperature
Equilibrium Xenon, EOC, 90'F/hr Cooldown Rate
Tem erature 'F Re uired Boron m
572
482
392
302
212
200.0 (1.77K ak/k)200.0 (1.0X nk/k)200.0 (Xenon Free)
-180.81
177.91
377.29
503.38
602.42
614.50
551.94
730.70
Report No. 849963-HPS-5MISC-003 REV 0 Page 5-6
Table 5.1-5
Required Boron Concentration vs. Temperature
Equilibrium Xenon, EOC, 100 F/hr Cooldown Rate
Tem erature 'F Re uired Boron m
572
472
372
272
200.0 (1.77X b,k/k)
200.0 (1.0X nk/k)200.0 (Xenon Free)
-180.81
204.79
406.67
534.57
610.44
547.88
730.70
Report No. 849963-HPS-5HISC-003 REV 0 Page 5-7
Table 5.1-6
Required Boron Concentration vs. Temperature
Mode 5 Cooldown to Refueling
Tem erature 'F Re uired Boron m
200 (Xenon Free)
180
160
140
135
730.70
746.83
762.95
779.08
783.11
Report No. 849963-MPS-5MISC-003 REV 0 Page 5-8
Figure S.l—l Required Boron Concentration
00
ED
l
C/lI
.j
-200
0 10 'F/'hrTemperature t Des, F )
+ 50 'Ff'hr 0 100 'F/hr
5.2 COOLDOWN FROH HOT STANDBY, EgUILIBRIUH XENON, EOC,
5.2.1 Purpose
The purpose of this analysis is to model a plant cooldown from hot
standby to cold shutdown to determine the actual expected boron
delivery to the RCS. The criterion for this analysis is that a
shutdown margin of 1.77X hk/k must be maintained throughout the
cooldown process down to a temperature of 200'F. (At 200'F and
below, the shutdown margin requirement is reduced to I.OX zk/k.)Haintenance of these shutdown margins will be assured as long as
the actual boron delivered with the makeup provided for coolant
contraction maintains RCS boron concentration above the required
boron concentration of Tables 5. 1-1 through 5. 1-5 of Section 5 and
Appendix 9.
5.2.2 Analyses
The assumptions and initial conditions for this analysis are
discussed in Section 4.0 and are summarized in Table 5.2-1. Since
the boron delivery to the RCS is limited to the makeup. that is
provided to compensate for coolant contraction, the expected
coolant contraction must be determined for discrete temperature
changes. A known boron content of the makeup water leads to an
accounting of the accumulated boron at each temperature increment
which, in turn, leads to a determination of the boron concentration.
The calculations are performed in the following manner.
To begin, boron concentration in terms of weight fraction is
defined as follows:
(boron concentration) = mass of boron in system
where, if complete mixing is assumed between the RCS and the
pressurizer, the total system mass is the sum of the boron
mass in the system, the RCS water mass, and the pressurizer water
Report No. 849963-HPS-5HISC-003 REV 0 Page 5-10
mass. Mass of boron in the system will be determined by identifyingthe boron added with each temperature increment.
Therefore, the initial total system mass of 393,572. 1 ibm in Tables
5.2-2 through 5.2-4 was calculated as follows:
(Total System Mass). - (Boron Mass). + (RCS Water Mass). + (PZR
Water Mass),.
or
08015 ft3
1)0.022042 ft /ibm
808 ft(2)
0.02698 ft /lb01
The total system mass is then corrected for each temperature
increment by accounting for both water and boron addition as makeup
is provided for the contraction of the reactor coolant. The amount
of coolant contraction (or shrinkage) with each temperature
increment is found by comparing the specific volume at the startingtemperature (v.) of each increment to the specific volume at the
1
final temperature (vf) of each increment.
The following represents a summary of the calculations for each
temperature increment of the plant cooldown:
Initial Temperature
Final Temperature
Initial Specific Volume v.i
Final Specific Volume = v (4)f
(1)(2)(3)
(4)
SpecificSpecificObtainedpressureObtainedpressure
volume of compressed water at 572 degrees and 2250 psia.volume of saturated water at 2250 psia.from Reference 10. 11 for compressed liquid at givenand T.from preference 10. 11 for compressed liquid at givenand Tf
Report No. 849963-HPS-5HISC-003 REV 0 Page 5-11
Shrinkage Hass (System Volume) (1/vf — 1/v.)
BAT Makeup Volume (Shrinkage Mass) / (8.2498 ibm/gallon)
RWST Makeup Volume - (Shrinkage Mass) / (8.2498 ibm/gallon)( '5)
Boric Acid Added (BAT Vol.) x (mass of boric acid/gallon)or
(RWST Vol . ) x (mass of bori c
acid/gallon)
Total Boric Acid = (Initial Boric Acid) + (Boric Acid Added)
Total System Hass = (RCS water mass)( ) + (PZR water mass)( )(7)
+ (Total boric acid)
trat'o - Total Boric Acid 100 1748.34 (9)Final Concentration -
ota ystem Mass)
This calculation process is completed for several temperature
increments (assuming constant plant pressure) until a temperature of350'F is reached. At this temperature two things happen:
1. The RCS is depressurized to 465 psi a to correspond with the
maximum pressure for connecting the RHR system to the RCS.
This pressure reduction actually entails a cooldown of the
pressurizer and, hence, a pressurizer shrinkage mass. This iscalculated by comparing the specific volumes for a saturated
liquid at 2250 psia and 465 psia. The volume to accommodate
this, in all cases, comes from the refueling water storage
tank. As a conservatism, this volume addition is assumed not
to add any boron to the RCS.
(5)
(6)(7)(8)(9)
Density of water at assumed tank temperature 120'F. (Reference10.13)See Appendix 3 for values3of dissolved boric acid in water.RCS water mass = (8015 ft3) / (specific volume)PZR water mass (808 ft ) / (specific volume at indicated P t).See Appendix 4 for the conversion factor between wt.X and ppm.
Report No. 849963-HPS-5MISC-003 REV 0 Page 5-12
2. The RCS is lined up to the RHR system which increases the totalsystem volume and mass for the remainder of the cooldown. The
RHR system is conservatively assumed to have a boron
concentration equal to the RCS concentration so that no boron
addition is credited. Also, the RHR system volume is assumed
to be equal to the RCS volume to conservatively estimate the
refueling water storage tank makeup requirements for the latterstages of the plant cooldown ~
The remainder of the cooldown analysis is handled in the same manner
as described above. To complete the analysis, the final boron
concentration is compared to the required concentration identifiedin Tables 5. 1-1 through 5. 1-5 of Section 5.0 and Appendix 9. An
arbitrary margin of 50 ppm is added to the 200'F, 1.77K ak/k
shutdown margin required boron concentration of Appendix 9 to define
the acceptance criteria for the cooldown analysis.
The purpose of this analysis is to identify the minimum acceptable
volume required from the boric acid tank as input to the plant
technical specifications. This is accomplished by adjusting the
temperature at which the source of makeup water is switched from the
boric acid tank to the refueling water storage tank. This is
accomplished through an iterative process until the switch over
temperature is identified that results in a final concentration justequal to or slightly higher than the established acceptance
criterion. The design basis of the boric acid tank concentration
and minimum volume requirement, therefore, is established. It is
that volume and concentration that is necessary to raise RCS boron
concentration such that subsequent makeup for coolant contraction
supplied by the lower concentration refueling water storage tank
alone will still maintain the required shutdown margin per Tables
5.1-1 through 5.1-5.
5.2.3 Results
A detailed parametric analysis was performed to identify the minimum
acceptable boric acid tank volume for a range of concentrations. In
Report No. 849963-MPS-5MISC-003 REV 0 Page 5-13
particular, boric acid tank concentration was varied from 3.0 weight
percent boric acid to 3.5 weight percent boric acid. This
concentration range strikes the optimum balance between the need tokeep the concentration low (to keep the solubility temperature limitas low as possible) and the need for a higher concentration to keep-
the corresponding volume requirements well within the currentcapacity of the tanks. An optimum concentration of 3.25 +0.25
weight percent achieves this with a control band that is well withinthe accuracy of the boron concentration measurement analysis.
The analyses described in Section 5.2-2 were completed utilizing theCE Utility Code BACR. A Computer Code Certificate and the Turkey
Point Code input are provided as Appendix 10. Tables 5.2-2 through5.2-4 represent the output of this code for the indicated boric acidtank and refueling water storage tank concentrations.
The boron concentration results of Tables 5.2-2 through 5.2-4 were
compared to the required concentrations at each temperatureincrement during a plant cooldown identified in Tables 5. 1-1 through5. 1-5. In each case, the actual system boron concentrations are
greater than that necessary for the required shutdown margin. Thisis illustrated graphically by combining the curves for required
boron�
.concentration and delivered concentration for three separate
cases in Figure 5.2-1 through 5.2-3.
To set the minimum technical specification boric acid tank volume
corresponding to the various boric acid tank and refueling water
storage tank concentrations, the tank volumes from Tables 5.2-2
through 5.2-4 were extracted and are tabulated in Table 5.2-5. The
volumes contained in Table 5.2-5 are the minimum boric acid tank
volumes needed (in conjunction with the refueling water storage
tank) to borate the RCS to the required shutdown margin. These
volumes must be contained in the region of the boric acid tank above
zero percent indicated level. The refueling water storage tank
volumes corresponding to each boric acid tank required volume are
Report No. 849963-HPS-5NISC-003 REV 0 Page 5-14
provided for information only and are not intended for incorporationinto the plant technical specifications. These volumes are wellwithin the volume requirements for emergency core cooling and need
not be included separately.
Table 5.2-6 summarizes the makeup flow rates that could be expected
during the transient analyzed. For the limiting cooldown rate of10'F/hr, the required boric acid flow rate ranges from 8 to 10 gpm.
Such flow r ates are just within the 10 gpm capacity of flow controlvalve FCV-113A for the manual and blended boric acid flow paths
(normal boration) and well within the 60 gpm (nominal) capacity ofthe emergency boration flow path via motor operated valve HOV-350.
Faster cooldown rates will require even greater makeup capacity tocompensate for the faster contraction rate of the coolant. Table5.2-6 shows the effective makeup capacity requirements for a
cooldown rate of 25'F/hr, as well. This is the maximum cooldown
rate allowed for natural circulation cooldowns in accordance withReference 10.10. While the flow rates of 21 to 24 gpm are wellwithin the emergency boration flow path capacity of 60 gpm
(nominal), they exceed the current 10 gpm limit of FCV-113A. A
modification is planned for this valve, however, to ensure the
availability of the normal boration flow path for the cooldown
scenarios evaluated thus far. Two transfer pumps supplying borated
water via the normal or emergency boration flow path will be
adequate for the faster cooldown transients.
5.2.4 Refueling Water Storage Tank Boration Requirements, Modes 1,2,3
and 4
The refueling water storage tank provides an independent source ofborated water that can be used to compensate for core reactivitychanges and expected transients throughout core life. lt should be
noted that in Nodes 1, 2, 3 and 4, the minimum refueling water
storage tank water volume is 320,000 gallons as required by
emergency core cooling considerations. The purpose of this section
Report No. 849963-NPS-5HISC-003 REV 0 Page 5-15
is to demonstrate that the refueling water storage tank minimum
inventory requirements (in modes 1, 2, 3 and 4) required tocompensate for the reactivity changes during a shutdown and cooldown
(using the refueling water storage tank as the only source ofborated water) are much less than the emergency core coolingrequirements.
This calculation derives the minimum volume of refueling waterstorage tank water necessary to bring the plant from hot standby tocold shutdown while maintaining the plant at a 1.77/ sk/k shutdown
margin. The calculation approach is identical to that of the
cooldown described in Section 5.2.2. The major difference is thatall RCS makeup is supplied from the refueling water storage tank ata boron concentration of 1950 ppm. This cooldown is performed as
described below:
1. Perform a feed and bleed with the refueling water storage tankto raise RCS boron concentration from 0 ppm to 535 ppm boron.
This is a 255 minute feed and bleed using 60 gpm letdown.
2. Perform a plant cooldown from an initial RCS temperature and
pressure of 572'F (547'F + 25'F as described in Section
4.2.6.a) and 2250 psia to 350'F and 350 psia. Charge from the
refueling water storage tank only as required to make up forcoolant contraction.
3. Align the RHR system to the RCS. Assume that its volume is8015 ft . Assume that the concentration of the RHR system isequal to that of the RCS at the time of initiation.
4. Continue cooldown from 350'F and 350 psia to a final RCS
condition of 200'F and 14.7 psia. Charge only as necessary to
make up for coolant contraction.
Report No. 849963-MPS-5HISC-003 REV 0 Page 5-16
Table 5.2-7 contains the results of the calculated volumes in steps
1 through 4 above. The refueling water storage tank boration
requirement for Modes 1, 2, 3 and 4 is estimated to be 37, 155
gallons. This value does not account for any RCS leakage during
this process. Figure 5.2-4 shows the RCS boron concentration forthis special case. As expected, the boration requirements impose a
refueling water storage tank minimum volume which is much smaller
than the minimum volume requirements placed on the tank by emergency
core cooling requirements (320,000 gallons). Even with a bounding
assumption of 11 gpm RCS leakage during a 24 hour hold and a 37 hour
cooldown, the maximum expected refueling water storage tank makeup
volume requirement is 77,415 gallons.
Report No. 849963-HPS-5MISC-003 REV 0 Page 5-17
Table 5.2-1
Summary of Initial Conditions and Assumptions
Cooldown from 572'F to 200'F
(Mode 3 to 5)
Parameter Value
RCS Volume
Pressurizer Volume (100% Power Level)
Initial RCS Pressure
Final RCS Pressure
Initial RCS Temperature
Final RCS Temperature
Pressurizer Condition
Pressurizer Level
RCS Leakage
Initial RCS Boron Concentration
Initial Pressurizer Boron Concentration
RHR Volume
RHR Boron Concentration
Letdown AvailableRefueling Water Storage Tank Temperature
Boric Acid Tank Temperature
8015 ft (1)808 ft (2)2250 psia14.7 psia572'F
200'F
Saturated
Constant
0
0
0
8015 ft[= RCS]
(4)
No
120'F
120'F
(1)(2)
(3)(4)
Loop and vessel volumes onlyPressurizer water volume only. In combination with note (1) above,
this corresponds to a total inventory 9343 cubic feet.Overestimated for conservatismUnderestimated for conservatism
Report No. 849963-MPS-5MISC-003 REV 0 Page 5-18
TABLE 5.2-2PLANT COOLDOMH FROH 572 F TO 200 F; BAT AT 3.50 wtX BORIC ACID; RWST AT 1950 ppm BORON
AVG.SYS. TEMP ~
(F)Ti Tf
PZR PRESS SPECIFIC VOLUHE SHRINKAGE BAT VOL Q RMST VOL 9 8/A ADDED TOTAL 8/A TOTAL SYS. HASS FIHAL CONC. i
(psia) (cu.ft./Ibm) HASS(ibm) 120 F (gal) 120 F (gal) (ibm) (ibm) ( lbm) (ppm boron) [
Vi Vf I-I
2250225022502250
2250225022502250225022502250
350350
350350350350
14.75,871.3
13 691.4
572
572560540520500
480467440420390350350
350300260
230200
ITOTAL BAT
TOTAL RMST
572560540520500480467440420390350350350300260230200200
VOLUHE
VOLUHE
1 F 00000 1.000000-02204 0.021650.02165 0.021060.02106 0.020550.02055 0.020090.02009 0.019690.01969 0.019450.01945 0.019000.01900 0.018690.01869 0.018280.01828 0.017810-02698 0.019120.01781 0.017810.01781 0.017430.01742 0.017070.01706 0.016830.01682 0.016620.01912 0.016719
GALLOHS
GALLONS
0.06,669.4
10,376.39,449.68,835.58, 104 ~ 75,001.79,892.16,885.89,738.3
11,577.212,311.3
0.019,369.818,867.712,841.011,468.56,068.8
0.0808.4
1,257.81,145.41,071.0
982.4606.3
0.00.00.00.00.00.00.00.00.00.00.0
0.00.00.00.00.00.00.0
1,199.1834.7
1, 180.41,403.31,492.3
0.02,347.92,287.11,556.51,390.2
735.6
0.0241.9376.3342.7320.5294.0181.4111.677.7
109.8130.6
0.00.0
218.5212.8144.8129.4
0.0
0.0241.9618.2961. 0
1,281.41,575.41,756.81,868.41,946.12,055.92,186.52,186.54, 177.74,396.24,609.04,753.84,883.24,883.2
393,572.1400,483.4411,236.0421,028.3430,184.3438,582.9443,766.0453,769.6460,733.1470,581.3482,289.0494,600.3945,042.1964,630.3983,710.9996,696.7
1,008,294.61,014,363.4
0.0 i105.6 I262.8 /399.1520.8 I628.0 I
692.1 I719.9 I738.5 i763 8 I792.6 i772.9 /772.9 )
796.8 /819.2 /833.9 I846.7 )841.7 i
I
I
TABLE 5.2-3 PLANT COOLDOWN FROM 572 F TO 200 F; BAT AT 3.25 MtX BORIC ACID; RWST AT 1950 ppm BORON
IAVG.SYS. TEMP.
(F)Ti Tf
PZR PRESS SPECIFIC VOLUHE SHRINKAGE BAT VOL Q RWST VOL 9 8/A ADDED TOTAL 8/A TOTAL SYS. MASS FINAL CONC.I
(psia) (cu.ft./Ibm) HASS(lbm) 120 F (98l) 120 F (Bsi) (Ibn) (ibm) ( lbm) (ppn boron) i
Vi Vf I
572
572560540520500470452440420
390350350350300260
230200
ITOTAL BAT
TOTAL RWST
572560540520500470452440420390350350350300260
230200200
VOLUME
VOLUHE
22502250225022502250225022502250225022502250
350350350350
350350
14.76,553.3
13 009.5
1.000000.022040.021650.021060.020550.020090.019510.019190.019000.018690.018280.026980.01781O.O1781
0.017420.017060.016820.01912
GALLONS
GALLONS
1.000000.021650.021060.020550.020090.019510.019190.019000.018690.018280.017810.019120.017810.017430.017070.016830.01662
0.016719
0.06,669.C
10,376.39,449.68,835.5
11,965.66,766.94,265.96,885.89,738.3
11,577.212,311.3
0.019,369.818,867.712,841.011,468.56,068.8
0.0808.4
1,257.81,145.41,071.01,450.4
820.30.00.00.00.00.00.00.00.00.00.00.0
0.00.00.00.00.00.00.0
517.1834.7
1,180.C1,403.31,492.3
0.02,347.92,287.11,556.51,390.2
735.6
0.0224.0348.6317.4296.8401.9227.348.177.7
109.8130.6
0.00.0
218.5212.8144.8129.4
0.0
0.0224.0572.6890.0
1,186.81,588.71,816.01,864.21,941.82,051.72,182.22,182.24,169.74,388.14,600.94,745.84,875.14,875.1
393,572.1400,465.5411, 190.4420,957.4430,089.6442,457.1449,451.4453,765.4460,728.9470,577.1482,284.8494,596.1945,034.0964,622.3983,702.8996,688.6
1,008,286.51,014,355.3
o.o i97.8
243.5 I369.6 I482.4 I627.8 I706.4 I718.3 i736.9 I
7623 I791 1 I771.4 I
771.4 I
795'3 I817.7 i832.5 i845.3 i840.3 i
I
I
TABLE 5.2-4 PLANT COOLDOMN FROH 572 F TO 200 F; BAT AT 3.00 MtX BORIC ACID; RWST AT 1950 ppm BORON
IAVG SYS. TEHP.
(F)Tf
PZR PRESS SPECIFIC VOLUHE SHRINKAGE BAT VOL cI RNST VOL 9 B/A ADDED TOTAL 8/A TOTAL SYS. HASS FINAL CONC.i
(psia) (cu.ft./ibm> HASS(lbn) 120 F (gal) 120 F (gal> (Ibn) (lbn) ( ibm) (ppn boron) iVi Vf I
572 -572572 -560560 -540540 -520520 -500500 -480480 -460460 -431
431 -420420 -390390 -350350 350350 350350 300300 260
260 230
230 200200 200
ITOTAL BAT VOLUHE
ITOTAL RWST VOLUHE
2250225022502250
22502250
22502250225022502250
350350350350350350
14.77,448.8
12,114.0
1.000000.022040.021650.021060.020550.020090.019690.019330.018860.018690.018280.026980.017810.017810.017420.017060.016820.01912
GALLONS
GALLONS
1.000000.021650.021060.020550.020090 '19690.019330.018860.018690.018280.017810.019120.017810.017430.017070.016830.01662
0.016719
0.06,669.4
10,376.39,449.68,835.58,104.77,688.3
'I0,327.23,764.09,738.3
11,577.212,311.3
0.019,369.818,867.712,841.011,468.56,068.8
0.0808.4
1,257.81 ~ 145.41,071.0
982.4931.9
1,251.80.00.00.00.00.00.00.00.00.00.0
0.00.00.00.00.00.00.00.0
456.31,180.41,403.31,492.3
0.02,347.92,287.11,556.51,390.2
735.6
0.0206.3320.9292.3273.3250.7237.8319.442.5
109.8130.6
0.00.0
218.5212.8144.8129.4
0.0
0.0206.3527.2819.4
1,092.71,343.41,581.21,900.61,943 '2,052.82,183.42,183.44,171.94,390.44,603.24,748.04,877.44,877.4
393,572.1400,447.8411, 145.0420,886.8429,995.5438,350.9446,277.0456,923.6460,730.1470,578.3482,286.0494,597.3945,036.3964,624.5983,705.1996,690.9
1,008,288.8'I,O I4,357.6
0.0 (
90.1 I224.2 i340'4 I444.3 Is3s.e i619.4 I727.2 I7373 I762.7 i791.5 )
771.8 i771.e i79S.7 i818.1 I
832.9 I845.7 (
840.7 (
Table 5.2-5
Minimum Required Boric Acid Tank Volumes
Modes 1, 2, 3, and 4
(RWST 9 1950 ppm)
BAT Concentration'(11
wt% m
BAT Volume(
allonsRWST Volume
allons
3.5 (6119)
3.25 (5682)
5,900
6,600
14,000
14,000
3'.0 (5245) 7,500 13,000
(1)
(2)
(3)
The conversion factor between wt% and ppm boron is 1.0 wt/ equals1748.34 ppm boron (Appendix 4).Includes analysis value rounded up to nearest 100 gallons. Thesevolumes doe not include instrument error/inaccuracy since the lowlevel alarm setpoint will be set to accommodate instrument looperrors.Rounded up to nearest 1000 gallons (this volume does not include themakeup for any RCS leakage).
Report No. 849963-HPS-5HISC-003 REV 0 Page 5-22
Table 5.2-6
Summary of Effective Flow Rate Requirements
Source
(BAT wtX)
RuST m
BAT 3.50
RMST 1950
RCSnT(1)
('F)
90
282
(2)Time To Achieve AT
minutes
~10'F hr ~25'F hr ~100'F hr
540 216 54
1692 676.8 169.2
(3)Hekeup
Volume
Effective (4)
Flow Rate m
5,165
14,539
9.6
8.6
23.9
21.5
95.6
85.9
~sl lshs ~10'F hr ~25'5 hr ~100'5 hr
BAT 3.25
R'WST 1950
102
270
612 244.8 61.2
1620 648 162
5,733 9.4 23.4 93.7
13,971 8.6 21.6 86.2
BAT 3.00
RMST 1950
119
253
714 285.6 71.4
1518 607. 2 151.8
6,508
13, 196
9.1
8.7
22.8
21.7
91.1
86.9
(2)(3)(4)
Extracted from Tables 5.2-2 through 5.2-4 corresponding to aT fromcooldown start to switchover temperature (BAT) and from switchovertemperature to finish (RWST)
Time (RCS sT) / (Cooldown Rate)Extracted from Table 5.2-2 through 5.2-4Effective Flow Rate = (Hakeup Volume) / (Time)
Report No. 849963-HPS-5HISC-003 REV 0 Page 5-23
ITABLE 5.2-7I
PLANT COOLDOMH FROM 572 F TO 200 F; RlST FEED AHD BLEED AND MAKEUP AT 1950 ppa BORON
IAVG.SYS. TEMP
(F)Ti Tf
PZR PRESS SPEClFIC VOLUME SHRlHKAGE BAT VOL O RUST VOL c)
(psia) (cu.ft./ibm) MASS(ibm) 120 F (gal) 120 F (gal)Vi Vf
8/A ADDED TOTAL 8/A TOTAL SYS. MASS FINAL COHC.
( ibm) ( ibm) (ibm) (ppn boron) I
572 572572 560
560 540540 520
520 500
500 480480 453
453 440440 420420 390390 350350 350
350 350
350 300
300 260
260 230
230 200
200 200
IFEED AHD BLEED RUST
ITOTAL RNST VOLUME
22502250225022502250225022502250225022502250
350350350350350350
14.7VOLUME
1.000000.022040.021650.021060.020550.020090.019690.019210.019000.018690.018280.026980.0'1781
0.017810.017420.017060.016820.01912
(Oppm to
1.000000.021650.021060.020550.020090.019690.019210.019000.018690.018280.017810.019120.017810.017430.017070.016830.01662
0.016719535ppm) =
0.06,669.4
10,376.39,449.68,835.58,104.7
10,258.14,635.66,885.89,738.3
11,577.212,311.3
0.019,369.818,867.712,841.011,468.56,068.8
17,592.037,154.8
0.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.0
GALLONS (255GALLONS
0.0808.4
1,257.81,145.41,071.0
982.41,243.4
561.9834.7
1,180.41,403.31,492.3
0.02,347.92,287.11,556.51,390.2
735.6minUtes at
0.075.2
117.0106.699.791.4
115.752.377.7
109.8130.6
0.00.0
218.5212.8144.8129.4
0.069gpm)
1,207.01,282.21,399.31,505.81,605.51,696.91,812.61,864.91,942.62,052.42,183.02,183.04,171.14,389.54,602.34,747.24,876.54,876.5
394,779.1401,523.7412,017.0421,573.2430,508.3438,704.4449,078.2453,766.2460,729.6470,577.8482,285.5494,596.8945,035.4964,623.7983,704.2996,690.1
1,008,287.91,014,356.7
534.5558.3 I
593.8 I
624.5 I6S2.0 I676.3 I705.7 I
718.S I737.1 I762.5 I791.4 I771.7 I771.7 I
795.6 I
818.0 I
832.7 I845.6 I
840.S I
900
Figure 5.2 —1 RGS Boron Goncentration
Equlllbrlum Xenon, EOC
800
700
600
500
300
200
100
-100
-200600 500 400 300 200
0 Required(10 F/hr Cooldown)Temperature(Deg F)
+ Delivered(BAT 3.0 wing RIST 1950ppm)
900
Figure 5.2 —2 RCS Boron ConcentrationEqulllbrlum Xenon, EOC
800
700
600
300
100
5000
p .4000
Ql
0K
-100
600 500 400 300 200
0 Required(10 F/hr Cooldown)Temperature (Deg F}
+ Delivered(BAT 3.25 wtX RWST 1950pprn)
900
Figure 5.2 —3 RCS Boron ConcentrationEquilibrium Xenon, EOC
800
700
600
500
300
200
100
-100
-200600 500 300 200
0 Required(10 F/hr Cootdown)Temperature (Deg F)
+ Delivered(BAT 3.5 wtX RNST 1950ppm)
900
Figure 5.2 —4 RCS Boron ConcentrationEqulllbrlum Xenon, EOC
800
700
600
500
400
300
200
100
-100
-200600 500 300 200
0 Required(10 F/hr Cooldown)Temperature (Deg F)
+ Oellvered(RWST 1950ppm)
5.3 COOLDOWN FROM COLD SHUTDOWN TO REFUELING TEMPERATURE, MODE 5
5.3. 1 Purpose
As stated in the plant Revised Technical Specifications (Reference
10.6), the boration capacity required below an average RCS
temperature of 200'F is based upon providing a shutdown margin of 1/
ak/k following xenon decay and a plant cooldown from 200'F to 140'F.
(A cooldown to 135'F will be analyzed for additional conservatism.)
The boron concentration requirements of Table 5. 1-6 are the minimum
required to maintain shutdown margin above the limit of 1.0/ zk/k.This analysis will demonstrate that a cooldown from 200'F to 135'F
can be completed using the boric acid tank or refueling water
storage tank as the source of makeup water to compensate for coolant
contraction and that, accordingly, the RCS boron concentration willbe maintained greater than these requirements.
5.3.2 Analyses
The assumptions and initial conditions for these analyses are
discussed in Section 4.0 and are summarized in Table 5.3-1. They
are essentially identical to those of Section 5.2. A few minor
differences are required to account for the unique circumstances ofthis cooldown. The principal differences are summarized below:
1. The 0/ power pressurizer level is used instead of the 100/
power level.
2. The initial boron concentration coincides with the 200'F, xenon
free 1.0/ ak/k shutdown margin requirement.
3. The RHR system is in service with a volume equal to that of the
RCS to conservatively maximize the total system mass.
Report No. 849963-MPS-5MISC-003 REV 0 Page 5-29
The analysis methodology is identical to that presented in Section
5.2 in that an initial total system mass is calculated and RCS
shrinkage mass increments are calculated based on temperature
increments during the cooldown. The shrinkage mass is then
converted to a makeup water volume that, when added to maintain a
constant pressurizer level, will add incremental amounts of boron.
Changes in total system mass and boric acid content are then broughttogether to determine the resulting RCS boron concentration at each
increment. This process is summarized below:
The exact system volume used in the calculation is determined as:
2 x (RCS volume) + (PZR volume at Oh power),
or
2(8015 ft ) + (520 ft ) = 16,550 ft
Knowing the initial mass of boron in the system, the exact
concentration and makeup requirements can be calculated for discretetemperature increments.
Shrinkage Mass (RCS and RHR Volume) (1/vf - 1/v,.)
Makeup Water Volume = (Shrinkage Mass) / (8.2498 ibm/gallon) (10)
Boric Acid Added = (Water Vol.) x (0.21153 ibm/gallon) (11)
Total Boric Acid (Initial Boric Acid) + (Boric Acid Added)
Total System Mass
Final Concentration =
(Total Initial Mass) + (Shrinkage Mass) +
(Boric Acid Added)
Total Boric Acid 100 1748.34 '12)(Total System Mass)
(10)(11)(12)
Water density at 120'F. (Reference 10. 13)See Appendix 3 for values of dissolved boric acid in water.See Appendix 4 for the conversion factor between wt.% and ppm.
Report No. 849963-MPS-5MISC-003 REV 0 Page 5-30
Only one of two possible boration flow paths and borated water
sources need be available at any given time while in Mode 5 (i.e.,either the boric acid tank or the refueling water storage tank). A
minimum volume and concentration must be specified for each,
therefore, to ensure that either one can be used for the cooldown
and still maintain adequate shutdown margin per the requirements ofTable 5. 1-6. Two separate calculations were performed as discussed
below.
5.3.2. 1 Mode 5 Cooldown with Boric Acid Tank
This analysis starts with an initial boron concentration of 730.70
ppm corresponding to the minimum requirement for a xenon free core
(see Table 5. 1-1), In order to calculate the initial total system
mass, the contribution of the boric acid must be calculated.
From Equation 2.0 of Appendix 3 and the conversion factor that isderived in Appendix 4, the initial boric acid mass in the system can
be calculated as follows:
788.2 m x~
16 030 ft + 520 ft3 3
1748.34 m wt.% 0.01664 ft ibm~ ~0.016719 ftlb'a
100 - (788.2 ppm)/(1748.34 ppm/wt.%)
or
mb= 4503.5 ibm boric acid
ba
The initial total system mass is then obtained as follows:
TSM = (Boric Acid Mass). + (System Water Mass). + (PZR Water Mass).
= 4503.5 ibm + (16,030 ft / 0.01664 ft /ibm) +
(520 ft / 0.016791 ft /ibm)
= 998,947.2 lb01
(13) Specific volume of compressed water at 200'F and 14.7 psia(14) Specific volume of saturated water at 14.7 psia
Report No. 849963-MPS-5MISC-003 REV 0 Page 5-31
The incremental changes in the total system mass and the resultingchanges in boron concentration are accounted for during each
discrete temperature change during the cooldown as discussed
previously.
5.3.2.2 Mode 5 Cooldown with Refueling Water Storage Tank
The refueling water storage tank will not provide enough boric acidto compensate for the reactivity inserted during the cooldown ifcharging is restricted to makeup for coolant contraction only. A
system feed and bleed must be performed to raise the RCS
concentration before the cooldown is commenced. The initial feed
and bleed ensures that the actual RCS boron concentration ismaintained above the required boron concentration for a 1.0% ak/kshutdown margin while the plant is cooled from 200'F to 135'F.
The endpoint RCS boron concentration for the initial feed and bleed
is determined through an iterative process. This process identifiesthe cooldown starting concentration that results in an acceptable
final concentration when boron addition is accomplished only through
makeup for coolant contraction. The acceptable final concentration
was chosen to coincide with the shutdown margin limit for the low
end of the cooldown (135'F)
In order to identify the required time and volume to complete the
initial system feed and bleed, Equation 9.0 of Appendix 1 is used
with values as follows:
C 788.2 ppm0
Cin = 1950 ppm
Report No. 849963-MPS-5MISC-003 REV 0 Page 5-32
16 030 ft 0.01664 ft ibm + 520 ft 0.016719 fl ibm
60 gallons „ 8.2498~ ~ lb(smin gallon
T 2009 min.
C(t) C e + C,.n(l-e )
If one charging pump at 69 gpm and 60 gpm letdown (as assumed incalculating the value of T above) are used to conduct the system
feed and bleed, 47 minutes are required. 'his equates to a feed and
bleed volume of 3235 gallons.
From Equation 2.0 of Appendix 3 and the conversion factor derived inAppendix 4, the mass of boric acid in the system corresponding to a
concentration of 805. 1 ppm can be calculated as follows:
CH„
ba 100 - C
(~81 5
1748.34
(~81 51748.34 ppm/wt%
m 16030 ft 520 ftm wt% 0.01664 ft ibm 0.016719 fX ibm
= 4657.4 ibm boric acid
Knowing the mass of boric acid in the system following the feed and
bleed, the exact concentrations and makeup requirements can be
calculated for each 10 degrees of cooldown from 200'F to 135'F in
the same manner as described in Section 5.3.2.
(15)(16)(17)
Specific volume of compressed water at 200'F and 14.7 psiaSpecific volume of saturated water at 14.7 psiaDensity of water at 120'F (Reference 10. 13)
Report No. 849963-UPS-5HISC-003 REV 0 Page 5-33
5.3.3 Results
The results of these analyses are presented in Tables 5.3-2 and
5.3-3 The resulting minimum volume requirements for the boric acid
tank and the refueling water storage tank for Nodes 5 and 6 are
summarized in Table 5.3-4
The delivered boron vs. required boron concentration is shown
graphically in Figures 5.3-1 and 5.3-2. The initial feed and bleed
of the refueling water storage tank case is shown by the verticalline at the origin in Figure 5.3-2.
Report No. 849963-NPS-5HISC-003 REV 0 Page 5-34
Table 5.3-1
Summary of Initial Conditions and Assumptions
Cooldown From 200'F to 135'F
(Mode 5 to 6)
Parameter Value
RCS Volume
Pressurizer Volume (0/ Power Level)
Initial RCS Pressure
Final RCS Pressure
Initial RCS Temperature
Final RCS Temperature
Pressurizer ConditionPressurizer Level
RCS Leakage
Initial RCS Boron Concentration
Initial Pressurizer Boron Concentration
RHR Volume
RHR Boron Concentration
Letdown AvailableRefueling Water Stot age Tank Temperature
Boric Acid Tank Temperature
Total System Volume
8015 ft520 ft14.7 psia14.7 psia200'F
135'F
Saturated
Constant
0
788 ppm
788 ppm
8015 ft ( )
[= RCS)(')
(3)120'F
120'F
16550 ft
(1)(2)(3)
Overestimated for conservatismUnderestimated for conservatismNo letdown assumed fo} boric acid tank analysis. Letdown is assumedfor RWST analysis.
Report No. 849963-MPS-5MISC-003 REV 0 Page 5-35
TABLE 5.3-2PLANT COOLOONN FROH 200 F to 135 F - BAT AT 3.0 Nt. X BORIC ACID AT 120 F
I AVG.SYS. TEHP.
(F)Ti Tf
PZR PRESS SPECIFIC VOLUHE SHRINKAGE BAT VOL 9
(psia) (cu.f t./Ibm) HASS(ibm) 120 F (gal)Vi Vf
B/A ADDED TOTAL 8/A TOTAL SYS ~ HASS FINAL CONC.
( ibm) ( ibm) (ibm) (ppm boron) )
I
I
200 200200 190
190 180
180 170
170 160
160 150
150 140
140 135
14.7 0.01664 0.0166414.7 0.01664 0.0165714.7 0.01657 0.0165114.7 0.01651 0.01645'14.7 0.01645 0.0163914.7 0.01639 0.0163414.7 0.01634 0.0162914.7 0.01629 0.01627
0.04,069.63,515.73,541.43,567.32,992.83,011.11,209.6
0.0493.3426.2429.3432.4362.8365.0146.6
0.0125.9108.7109.5110.392.693.137.4
4,503.74,629.64,738.34,847.84,958.25,050.75, 143.85,181.3
998,945.51,003,141 ~ 0
1,006,765.51,010,416.41,014,094.01,017,179.31,020,283.61,021,530.7
7882 I
806.9 [
822.8 f838.8
J
854.8 I868.1881.4 /
886.8 [
TOTAL BAT VOLUHE= 2,655.5 gallons
TABLE 5.3-3PLANT COOLDOHH FRY 200 F TO 135 F - RHST AT 1950ppm BORON AT 120 F
IAVG.SYS. TEHP
(F)Ti Tf
200 200200 190190 180
180 170
170 160
160 150
150 140
140 135
815.4 I820 0 I824 0 I828.0 I832.0 (
835.3 )
838.7 )
840.0 /
4,659.54,705.44,745 '4,785.04,825.24,859.04,893.04,906.6
0.0493.3426.2429.3432.4362.8365.0146.6
0.045.939.739.940.233.834.013.6
0.04,069.63,515.73,541.43,567.32,992.83,011.11,209.6
999,101.31,003,216.91,006,772.21,010,353.61,013,961 F 1
1,016,987.61,020,032.71,021,256.0
14.7 0.01664 0.0166414.7 0.01664 0.0165714.7 0.01657 0.0165114.7 0.01651 0.0164514.7 0.01645 0.0163914.7 0.01639 0.0163414.7 0.01634 0.0162914.7 0.01629 0.01627
PZR PRESS SPECIFIC VOLUHE SHRINKAGE RllST VOL 9 B/A ADDED TOTAL B/A TOTAL SYS. HASS FINAL CONC.
(psia) (cu.ft./ibm) HASS(ibm) 120 F (gal) (ibm) (lbm) (lbm) (ppm boron) ]Vi Vf I
I
)FEED 8 BLEED VOLUHE (788ppm to 815ppm) =
]RllST VOLUHE FOR COOLDOOI COHTRACTIOH
I
)TOTAL REQUIRED RWST VOLUHE =
3,260.0 gallons (44 minutes at 69 gpm)2,655.5 gallons
5,915 ' gallons
Table 5.3-4
Minimum Borated Water Source Volumes
(Mode 5)
Boric Acid Tank:
(z 3.0 wt/.)
2,900 gallons
Refueling Water Storage Tank:
(a 1950 ppm)
10,000 Gallons( )
(1)
(2)
Includes analysis value plus 212 gallons for level instrumentinaccuracy (2.5/. of full range) rounded up to nearest 100 gallons.Includes analysis value plus 2% instrument error and approximately3600 gallons unusable volume below the suction tap, all rounded upto nearest 1000 gallons
Report No. 849963-MPS-5MISC-003 REV 0 Page 5-38
890
Figure 5.3 —1 RCS Boron ConcentrationEquillbrlum EOC, Mode 5 Cooldoen
880
870
860
850
830
820
810
790
780200 190
0 Required
180 170 160
Temperature(oeg F)+ Deltv~(S.O wry)
150
Figure 5.3 —2 RCS Boron ConcentrationEquilibrium EOC, Mode 5 Cooldown
830
820
810
800
790
780200
0 Required
180 160
Temperature(Oeg F)+ Delivered(RWST 1950ppm)
. 6.0 OPERATIONS ANALYSES
Section 5.0 presented the design basis analyses for the boric acidconcentration reduction program to support the licensing effortsrequired to fully implement it. A worst case (slow) cooldown tocold shutdown conditions was analyzed to establish the requiredboric acid tank concentration and volume limits to enable operatorcontrol of a challenging reactivity control scenario: borationduring cooldown without the benefit of letdown. A reduction inboric acid concentration will have other effects on plantoperations. This section presents the results of a detailedevaluation of plant operations with reduced concentration boric acidto identify these effects. The specific areas that will be
discussed include blended makeup, feed and bleed, shutdown to coldshutdown, shutdown to refueling and operator response to emergency
situations. Obviously it is an impossible task to evaluate each ofthese five areas and consider all possible combinations of plantconditions. Therefore, initial plant parameters and analyses
assumptions were selected in a conservative manner to present a
worst case analysis.
A number of options exists as to how the three boric acid tanks can
be aligned to provide the required minimum volume for both plantsand to provide operational flexibility in meeting day-to-day
boration demands. Considering the volumes required per Table 5.2-5,
most, if not all, of the operating margin will have to come from the
spare tank. One possible tank configuration is to align all three
tanks to the suctions of all four pumps to utilize the tanks as a
common source. In this manner all three tanks will stay at the same
level with the minimum required volume for both units spread across
all three tanks. This arrangement offers the following advantages:
1. Haximizes volume available for day-to-day boration demands;
Report No. 849963-MPS-5MISC-003 Rev. 0 Page 6-1
2. Offers lower risk of going below technical specificationminimum volume;
3. Offers redundant level indication; and,
4. No manual valve manipulations required to access all availablevolumes.
Another option is for one tank to be dedicated to each unit with theshared tank serving as the source of makeup for both units on a
day-to-day basis. The discussions in this section apply to eitherof these options.
Figure 6-1 presents a flow diagram of the Turkey Point CVCS
extracted from Reference 10. 1. Four flow paths to the charging pump
suction will be considered in the evaluation:
2.
3.
4,
Volume Control Tank (VCT)
Normal Boration (Blended or Hanual)
Emergency BorationRefueling Water Storage Tank
Charging pump discharge will go one of two places: into the RCS orback to the VCT via the reactor coolant pump seal leakoff line. The
flow back to the VCT is important to note because it is not
available for charging, into the plant in those instances when the
VCT is isolated (isolation valve closed or check valve seated) from
the charging pump suction. In this instance, the seal leakoff would
collect in the VCT until, upon high level, it is directed to the
holdup tank via the VCT pressure relief valve. Under normal
conditions with appropriate charging pump speed selection, however,
this seal leakage (nominally 9 gpm) can be expected to recycle back
to the charging pump suction so that it will not constitute a loss.In the calculation of volumes required for blended makeup and feed
and bleed operations, the 9 gpm is assumed to be lost to
Report No. 849963-HPS-5HISC-003 Rev. 0 Page 6-2
conservatively overestimate the volumes required to support the
evolutions under consideration.
Table 6-1 presents the plant parameters used in the analysis of thissection. In general, these parameters differ from those of the
licensing analyses of Section 5.0 in that they are based on normal
plant operations and are chosen to provide a realistic best estimateof plant boration performance while still remaining conservative. A
few of the more important assumptions are discussed below.
1. Pressurizer Volume
Pressurizer volume is assumed to remain constant at the OX
power level (i.e., operators charge to the plant to maintain
pressurizer level) during the cooldown- scenarios analyzed.
2. RCS Leakage
As in Section 5.0, RCS leakage is assumed to be zero since
leakage aids boron delivery to the plant. However, it does
require greater makeup volumes, so that leakage assumptions
should be applied to final results. This can be accomplished
by multiplying an assumed leakage rate by an estimated time forcompletion of the cooldown evolution. This volume is then
added to the contraction makeup volume to derive the totalrequired volume. A more specific analysis of the impact of RCS
leakage on the boric acid inventory requirements is presented
in Section 6.7
3. RHR Volume and Concentration
The concentration is assumed to be at the cold shutdown, 200'F,
xenon free 1.77X ak/k shutdown margin concentration of 775 ppm
(equilibrium xenon scenario per Section 5.5). RHR
concentration is expected to be near, if not equal to, the cold
Report No. 849963-MPS-5MISC-003 Rev. 0 Page 6-3
shutdown boron concentration since shutdown margins must be
maint'ained during a Mode 4 heat up for a transition into Mode
3. RHR concentrations resulting from mid-cycle shutdown, forexample, should be close to the appropriate shutdown marginrequirement. Also, to conservatively estimate the contractionmakeup contribution of this system, a volume of 2000 ft isassumed for the RHR system flow paths.
4. Boric Acid Tank Concentration
Section 5 ' justified a concentration range of 3.0 to 3.5weight percent boric acid to support a safe shutdown to coldshutdown conditions. This will result in a plant technicalspecification boric acid tank operability requirement statingminimum acceptable volumes for this concentration range. It isrecommended that plant operations maintain the concentration inthe middle of the control band. For this reason, theconcentration of 3.25 weight percent will be utilized in theoperations analyses of this section.
5. Cooldown Starting Temperature
The analysis of this section assumes the cooldown initiatesfrom the hot zero power value of 547'F.
The following sections review specific plant operations with reduced
boric acid concentration.
6.1 BLENDED MAKEUP OPERATIONS
During typical plant blended makeup operations, concentrated boricacid from the boric acid tanks is supplied to the blending tee via a
boric acid transfer pump (0 to 60 gpm) and flow control valveFCV-113A (0 to 10 gpm) where it is mixed with pure makeup water
supplied via flow control valve FCV-114A (0 to 150 gpm). The
Report No. 849963-MPS-5MISC-003 Rev. 0 Page 6-4
blended boric acid is then added to the suction of the charging
pumps via flow control valve FCV-1138.
A reduction in the concentration of boric acid in the boric acidtank will decrease the maximum boron concentration available at theoutlet of the blending tee by a factor directly proportional to thedecrease in the boric acid tank concentration. This results in a
decrease in the boron delivery capability of the blending tee duringnormal RCS makeup and reactivity control operations.
This impact, however, can be compensated for by increasing the boricacid delivery rate to the blending tee. A corresponding decrease inthe pure makeup water into the tee will raise the concentration ofthe boric acid mix to levels corresponding to the current boration
capability of the system using 12 weight percent boric acid. This
will be achievable with the modification that is currently planned
for flow control valve FCV-113A. The trim of this valve will be
modified to allow higher flow rates of the reduced concentrationboric acid. Specifically, since a factor of four reduction in the
boric acid concentration is anticipated (12 weight percent to 3
weight percent) a factor of four increase in boric acid flow to the
boric acid blender will be required. In other words, the trim ofFCV-113A must be modified to allow up to 40 gpm. This would assure
the blended boration capability remained identical to the current
system configuration with 12 weight percent boric acid with respect
to the timing of boron delivery.
With this flow control valve upgrade in mind, all further analyses
of the blended makeup capability (i.e., during fast cooldowns) willassume that 40 gpm will be available to the blender.
Hathematically, blended makeup operations are modeled as follows:
F C
Co t (100)(1748'34)a a t w
Report No. 849963-HPS-5MISC-003 Rev. 0 Page 6-5
where:
Co ut c o n c e ntra t i o n of b or i c a c id e x i t i n g th e b 1 e n d i n g te e
F = flow rate of concentrated boric acid from the boric acida
tank
C = concentration of boric acid entering the blending teea
FT - total flow rate exiting the blending tee
D = density of makeup water (assumed at 120'F)
1748.34 = conversion factor for weight percent to ppm
6.2 FEED AND BL'EED OPERATIONS
During a feed and bleed operation to increase system boron content,the charging pumps are used to inject concentrated boric acid intothe RCS with the excess inventory normally being diverted to the
liquid waste system via letdown. The rate of increase in boron
concentration is proportional to the difference between the system
concentration at any given time and the concentration of the
charging fluid. From this basic relationship, an equation
describing feed and bleed can be derived. (Appendix 1 contains the
derivation of the RCS feed and bleed equation.) In general, if the
concentration within the boric acid tanks is reduced to the pointwhere heat tracing is no longer required, the maximum rate of change
of RCS boron concentration that an operator can expect to see duringfeed and bleed will be less than currently achievable.
The purpose of the evaluation performed in this section is to show
the hot zero power feed and bleed rates that can be expected using
boric acid tanks with a reduced concentration. The analysis is done
Report No. 849963-HPS-SHISC-003 Rev. 0 Page 6-6
assuming hot zero power conditions with other key parameters and
conditions as shown in Table 6-1. A one charging pump feed and
bleed was evaluated from two initial system concentrations: zero
ppm and 1100 ppm. The results are presented in Tables 6-2 to 6-5.
Equation 9.0 of Appendix 1 was used to generate the results in these
tables. The value of the system mass used to obtain the timeconstant in Equation 9.0 was calculated as follows:
w RCS w RCS w PZR
or
8015 ft 520 ft0.021251 ft. /ibm 0.02698 ft /ibm
From this system mass (396,432.3 ibm), the value of the feed and
bleed time constant for one charging pump using the 45 gpm letdown
orifice is:
396,432.3 ibm
45 gpm x 8.2498 ibm/gallon
or
T45= 1,067.9 min.
The value of the feed and bleed time constant for one charging pump
using the 60 gpm letdown orifice is:
396,432.3 ibm
60 gpm x 8.2498 ibm/gallon
or
T60 800 ~ 9 mi n ~
(2)(3)
Specific volume of compressed water at 547'F and 2250 psia (assumingHZP).Specific volume of saturated water at 2250 psia (assuming HZP).Water density at 120'F.
Report No. 849963-NPS-5MISC-003 Rev. 0 Page 6-7
For the case where a feed and bleed is conducted while the RHR
system is in operation, a new time constant will result. Using theequation above and substituting the RHR + RCS water mass for the RCS
water mass, the following result is obtained for a 60 gpm feed andbleed at 200'F:
System Massw RCS ( w RHR w PZR
10015 ft 520 ft.01662 ft /ibm .01912 ft /ibm
= 629,783.9 ibm
629 783.9 ibm60 60 gpm x 8.2498 ibm/gallon
Tables 6-2 through 6-5 include the expected boric acid volume to
accomplish the given boration. Two values are presented: one
assuming no loss due to RCP seal leakage (45 gpm and 60 gpm) and the
other assuming the 9 gpm nominal seal leakoff is collected in the
VCT so that it does not immediately contribute to the desired
boration (54 gpm and 69 gpm).
To identify specific changes in boron content through feed and bleed
operations, the values in these tables can be used (interpolated) to
provide reasonable estimates. Analytically, the time to achieve a
specific change in boron content can be calculated as follows.
Appendix 1 presents boron concentration as a function of time as:
C = C/ + C. (1 - e /
)f o in
where:
CfC
0
inT
final system boron concentration
initial system concentration
concentration of feed source
feed and bleed time constant
time
(4) Specific volume compressed water at 200'F and 350 psia(5) Specific volume saturated water at 350 psia
Report No. 849963-MPS-5MISC-003 Rev. 0 Page 6-8
Solving this equation for time yields:
f inn
C -C.o in
Feed and bleed operations will be incorporated into some of the
operations scenarios discussed in later sections utilizing Tables
6-2 through 6-5 and the equations above.
6.3 COOLDOWN TO REFUELING - MODE 6
The plant cooldown to refueling is typically the most limitingevolution that an operator must perform with respect to system
boration (ice., this evolution normally requires the maximum amount
of boron to be added to the RCS). A cooldown to refueling normally
occurs at the end of core cycle when the critical boron
concentration is low and requires an increase to the refueling boron
concentration. In the most limiting case, boron concentration must
be raised from zero ppm to the specified refueling concentration of1950 ppm (2000 ppm).
This section presents the evaluation results of a plant shutdown to
refueling. The evaluation was performed specifically to demonstrate
the effect on makeup inventory requirements of a reduction in boric
acid storage tank concentration. A list of key parameters and
conditions assumed in the analysis is contained in Table 6-1. The
evaluation was performed for EOC conditions in order to maximize the
amount of boron that must be added to the RCS. As a result, the
boron concentration within the RCS was required to be increased from
zero ppm to the present refueling concentration of 1950 ppm. The
shutdown for refueling was assumed to take place as follows:
1. The reactor is shut down via rod insertion to hot zero power
conditions.
Report No. 849963-HPS-5MISC-003 Rev. 0 Page 6-9
2. Following shutdown, at time zero, operators commence a system
feed and bleed using one or more charging pumps and a boricacid transfer pump. (Tables 6-2 through 6-5 show the expectedfeed and bleed volumes and times to complete for variousblended concentrations.)
3. The feed and bleed is conducted for about 180 minutes assuming
60 gpm letdown, after which time it is secured.
4. A plant cooldown and depressurization is commenced from an
average coolant temperature and system pressure of 547'F and
2250 psia to an average coolant temperature and system pressureof 350'F and 465 psia. Unblended boric acid is supplied from
the boric acid tanks.
5. The RHR system is placed in operation at approximately 350'F
and 465 psia.
6. The plant cooldown is continued following RHR initiation from350'F to 135'F at 465 psia.
Evaluation results showing the system concentrations as a functionof time and total boric acid tank inventory requirements are
contained in Table 6-6. Concentrations during the initial feed and
bleed operation were calculated using the methodology discussed inSection 6.2 above. Concentrations during the subsequent plantcooldown were calculated in the same manner as the concentrationsfor the plant cooldowns in Section 5.2. Note that the boron content
of the RCS was raised from zero ppm at the start of the evolution to
greater than 1950 ppm by the time the plant had been cooled and
depressurized to 135'F and 465 psia. A total volume of 27, 188.8
gallons of a 3.25 weight percent boric acid solution was required.Of this volume, 10,800 gallons were used during the initial 180
minute plant feed and bleed operation and 16,388.8 gallons were
charged into the system to compensate for shrinkage during the
cooldown process.
Report No. 849963-HPS-5NISC-003 Rev. 0 Page 6-10
As can be seen from the results in Table 6-6, the volume of a 3.25
weight percent boric acid solution required to perform the shutdown
to refueling is approximately 3.6 times the current capacity of one
boric acid tank (7500 gallons). A plant modification is planned,however, that will increase the capacity of the tank. Assuming
approximately 8500 gallons will be available, the volume requiredfor this evolution will be 3.2 times available capacity. Note thatthis result is conservative, and, therefore, represents the maximum
volume that would be required to be available assuming a refuelingconcentration of 1950 ppm boron and a boric acid tank concentrationof 3.25 weight percent boric acid. Since there is essentially onlyone boric acid tank dedicated to each plant and a third tank shared
between the two plants, additional provisions or operator actionscould be utilized to place the plant in Mode 6. These provisionscould include some combination of the following:
1. Prior to conducting the evolution, all three boric acid tanks
are full and available for use (minus the volume dedicated tothe operating unit).
2. Concurrent with continued cooldown, replenish inventory in the
tanks.
3. Borate as much of the RHR system as possible to the refuelingconcentration of 1950 ppm prior to initiating'he RHR system
cooldown at 350'F.
These provisions, or operator actions, would need to be considered
only once during core cycle: just prior to conducting a shutdown
for refueling. Note that they are relatively simple actions thatshould be well within the current plant operating capabilities. In
addition, they can be planned for in advance so as to have no impact
on maintenance activities or the plant refueling schedule.
Report No. 849963-NPS-5HISC-003 Rev. 0 Page 6-11
6.4 COOLDOWN TO COLD SHUTDOWN — MODE 5
As discussed in the previous section, the shutdown to refueling isthe most limiting evolution that an operator must perform withrespect to system boration from the perspective of available boricacid inventory. This evolution is normally performed once during a
fuel cycle just prior to refueling. Situations (such as unscheduled
plant maintenance, etc.) can occur during a fuel cycle, however,
that would require an operator to perform a plant shutdown to coldshutdown conditions. Although not limiting with respect to borationrequirements, it is important for an operator to be able to performsuch a shutdown quickly and efficiently.
This section presents the evaluation results of a plant shutdown and
cooldown to cold shutdown conditions using only the boric acidtanks. This analysis was performed specifically to demonstrate theeffect of a reduction in boric acid tank concentration on makeup
inventory requirements . A list of key parameters and conditionsassumed in the analysis is contained in Table 6-1. In addition tothe parameters in Table 6-1, the evaluation was performed for EOC
conditions assuming a cold shutdown concentration requirement of 775
ppm boron. As a result, boron concentration had to be increased
from 0 ppm to 775 ppm boron. The operations scenario employed inthe cooldown to cold shutdown is as follows:
l. The reactor is shut down to hot zero power conditions via rod
insertion.
2. A plant cooldown and depressurization is immediately commenced
from an average coolant temperature and system pressure of547'F and 2250 psia to 350 F and 465 psia. Makeup inventory issupplied from the boric acid tanks.
3. The RHR system is placed in operation at 350 F and 465 psia.
Report No. 849963-MPS-5MISC-003 Rev. 0 Page 6-12
4. The plant cooldown is continued following RHR initiation from350'F to 135'F at 465 psia. Makeup inventory is supplied from
the boric acid tanks.
Evaluation results showing the system concentrations as a function=
of time and total boric acid makeup tank inventory requirements are
contained in Tables 6-7 and 6-8. Note that two cases were analyzed
for comparison. In Case 1 the concentration within the RHR system
was assumed to be equal to the concentration of the RCS at the time
of RHR system initiation. In Case 2 the concentration within theRHR system was assumed to be equal to 775 ppm (the maximum 200'F,
xenon free, required boron concentration) at the time of RHR
initiation. Concentrations during the plant cooldown were
calculated using the methodology discussed in Section 5.2. Ouring
those portions of the plant cooldown in which blended makeup was
used, values were calculated using the methodology contained inSection 6. 1.
A total volume of 9,246.0 gallons of a 3.25 weight percent boricacid solution was required in order to perform the shutdown to coldshutdown for Case 1. In Case 2, a total volume of 9,033.6 gallonswas required.
6.5 BATCHING OPERATIONS
As the results of Sections 6.3 and 6.4 demonstrate, more than one
boric acid tank will be required to complete these cooldown and
boration evolutions. This section will evaluate the expected
batching process and how this will impact the overall timing of the
cooldown.
The Turkey Point batching system consists of an 800 gallon batching
tank that is blended to the desired concentration and added to the
boric acid tank via a boric acid transfer pump. The batching
process consists of the following (with time estimates):
Report No. 849963-MPS-5MISC-003 Rev. 0 Page 6-13
1. Fill the batching tank with pure water and increase the water
temperature from 40'F to 90'F (45 minutes).
2. Add the required quantity of boric acid and mix the tankcontents (20 minutes).
3. Transfer boric acid mixture to boric acid tank (20 minutes).
4. Repeat as necessary
The total time to prepare a single 800 gallon batch, therefore, isestimated to take about 1.5 hours. Given that the batching can be
accomplished in only 800 gallon increments, it will take
approximately 10 batches (or 15 hours) to refill a boric acid tank.The availability of a third tank that is shared between the two
units suggests the possibility of using a second tank for one unitwhile the first tank is refilled. For the case where all threetanks are aligned to the transfer pumps and are full to maximum
capacity, however, a total of about 16,000 gallons[(8500x3)-2900-6600] would be available to accommodate a unitshutdown and cooldown without operator action to realign the tanks.
Looking at the results of Section 6.3, the shutdown and cooldown torefueling required a total boric acid tank volume of 27, 188.8
gallons. Assuming the tanks were at the minimum volume for 3.25
weight percent to support two operating units (13,200 gallons)leaving 6,600 gallons to support the shutdown and cooldown, a totalof 20,588 gallons would have to be provided through batching. Ifbatched, this would require about 26 batches for a total of 39
hours. However, if the tanks are full and shared, or at leastfilled prior to initiating the shutdown to refueling evolution, only
11, 188 gallons would have to be batched. This would require 14
batches for a total of 21 hours.
The shutdown to cold shutdown conditions of Section 6.4 required a
total of 9,246.0 gallons. Again, assuming 6,600 gallons in the tank
at the start of the cooldown a total of 2,646 gallons must be
Report No. 849963-HPS-5HISC-003 Rev. 0 Page 6-14
provided from the spare tank or batched. If batched, approximately3.5 batches would be required which would take 5 hours at 1.5 hours
per batch. If the tanks are kept full, however, this evolutionwould require no batching to complete.
The shutdown/cooldown evolutions analyzed thus far have assumed
boration in conjunction with cooldown as analyzed in Section 5.0.This will not be a requirement for normal cooldown evolutions.In some instances FPL may have to conduct these evolutions inessentially. the same manner as they are conducted now (i.e., borate
the plant to the required cold shutdown concentration through feed
and bleed prior to initiating the cooldown, and provide blended
makeup for the coolant contraction).
This evolution is illustrated in Table 6-9 for a 50 F/hr cooldown.
The feed and bleed process can be completed from either the boricacid tank or the refueling water storage tank. For the case where
the boric acid tank alone is utilized, a total of 10,573.2 gallonswill be required. Assuming 6,600 gallons were available, a total of3,973.2 gallons would have to be provided through the batch process
or the spare boric acid tank. At 800 gallons and 1.5 hours a batch,
a total of 5 batches would be required taking approximately 7.5
hours. If the tanks are kept full, however, this evolution would
not require any batching to complete.
6.6 RESPONSE TO EMERGENCY SITUATIONS
This section evaluates several of the operating evolutions that may
have to be completed in response to a variety of emergency
situations. Specifically, accident boration requirements, shutdown
margin recovery, emergency boration, and fast cooldown scenarios
will be evaluated to ensure the operator can continue to operate the
plant safely with reduced boric acid tank concentrations.
Report No. 849963-HPS-5HISC-003 Rev. 0 Page 6-15
6.6. 1 Accident Response
In general, credit is not taken for boron addition to the RCS from
the boric acid tanks for the purpose of reactivity control in theaccidents analyzed in Chapter 14 of the plants'inal SafetyAnalysis Report. The consequences of such events as steam linebreak, overcooling, boron dilution, etc. will not be affected by a
reduction in boric acid tank concentration. Any action to borate
the plant from the boric acid tank will likely improve the
reactivity control margins over those already analyzed and found
acceptable in the safety analysis report.
6.6.2 Shutdown Hargin Recovery
The action statements associated with Technical Specifications3. l. 1. 1, 3. 1. 1.2, 3.9. 1, and 3. 10. 1 require that boration be
commenced at greater than 4 gpm using a solution of at least 20,000
ppm boron in the event that shutdown margin is lost. A reduction inboric acid concentration by a factor of four will require a corres-
ponding increase in delivery capacity to ensure the same amount ofboron is added in the same period of time. Such a deliverycapability will be available with the proposed modification of the
blended makeup flow control valve so that this reactivity control
recovery capability remains unaffected. Specifically, the flow
control valve FCV-113A will be modified to increase its control
range from 0 — 10 gpm to 0 — 40 gpm. The availability of a 40 gpm
flow of boric acid to the blender exceeds the requirement for a fourtimes increase of 4 gpm to 16 gpm in this instance.
6.6.3 Emergency Boration
An emergency boration flow path is available from the discharge ofthe boric acid transfer pump directly to the suction of the charging
pumps via motor operated valve HOV-350. In the event that a reactor
shutdown to hot zero power is required and control rods are not
available (i.e., two or more rods stuck out), an alternate shutdown
Report No. 849963-HPS-5HISC-003 Rev. 0 Page 6-16
capability exists through emergency boration. According to
Reference 10.3, the CVCS (with 12 weight 'percent boric acid) iscurrently capable of making the reactor subcritical in 16 minutes
assuming 60 gpm through the emergency boration flow path to the
charging pumps.
According to Reference 10. 12, emergency boration is achieved by
charging 537 gallons via the emergency boration flow path (withoutletdown —taking advantage of the surge volume available in the
pressurizer) and raising the boron concentration by 195 ppm. This
is stated as requiring 9 minutes at 60 gpm. The effect of reduced
concentration boric acid on this capability is evaluated below.
Analysis of the method of achieving emergency boration by charging
pressurizer level up, without letdown, requires a mass balance ofboron. Assuming a conservatively high BOC boron concentration of1100 ppm, the mass of boric acid required to increase thisconcentration by 195 ppm is calculated. This boric acid mass
addition is equated to the boric acid mass per gallon of makeup
water using the values of Appendix 3. Then this volume of makeup
water is converted to a volume of water at RCS temperature to
compare to the available volume in the pressurizer.
For a conservative analysis of the above, the following is assumed:
l. Boric Acid Tank Temperature
2. Boric Acid Tank Concentration
3. Transfer Pump Delivery4. RCP Seal Injection5. RCP Seal Leakoff
6. VCT Isolated7. Initial RCS Concentration
8. Boration Required
9. RCS Temperature10. Mixing within RCS and Pressurizer
ll. Pressurizer Steam Bubble
120'F
3.0 wtX
69 gpm
24 gpm
9 gpm
(-9 gpm)
1100 ppm
195 ppm
547'F
Uniform
Available
Report No. 849963-MPS-5HISC-003 Rev. 0 Page 6-17
The results of this calculation show that approximately 2024 gallonsof water at 3.0 weight percent boric acid will be required from theboric acid tank and will result in a pressurizer level change wellwithin the available volume when level is initially within the levelcontrol band. At 69 gpm, this will achieve a 195 ppm increase inRCS boron concentration within 29.4 minutes. This volume reduces to1760 gallons if 9 gpm seal leakoff is not a factor. This equates toapproximately 300 cubic feet in the pressurizer which corresponds tothe change from the OX Power programmed level to the lOOX Power
programmed level.
A second option consists of conducting a system feed and bleed toaccomplish the boration objective. Using the method of Section 6.2,approximately 2,670 gallons of 3.0 weight percent boric acid will be
required. At 69 gpm (60 gpm letdown), this will achieve a 195 ppm
increase in RCS boron concentration within 38.7 minutes.
6.6.4 Fast Cooldown Transients
Section 5.0 focused on slow cooldown evolutions since they presented
the worst case boration requirement in compensating for a greateramount of xenon decay. Faster cooldowns are important from a
boration perspective when the limited capacities of the normal
boration flow path (currently limited to 10 gpm boric acid) and the
emergency boration flow path (nominally 60 gpm) are consider ed,
especially when the preferred boration flow path will likely be the
lower capacity normal flow path (manual or blended boration). As
discussed previously, however, it is anticipated that flow controlvalve FCV-113A will be modified to increase its capacity from 10 gpm
to about 40 gpm. This will increase the flow rate. of reduced
concentration boric acid to the point where the boron addition ratethrough the normal boration flow path matches that of the currentsystem configuration with 12 weight percent boric acid. The
remaining consideration, therefore, is the limited volume availableto provide the total boron requirement.
Report No. 849963-UPS-SMISC-003 Rev. 0 Page 6-18
Two specific cases are presented here: 1) makeup with the boricacid tank, and 2) makeup with the refueling water storage tank. The
first case considers a fast cooldown (100'F/hr) for which the normal
process of borating to the cold shutdown limit prior to initiatingthe cooldown has been completed. This case will evaluate thecapability of the boration subsystem to maintain this boron
concentration during the cooldown while blending the boric acid withpure water. This particular evaluation uses the same assumptionsand methodology as discussed in Section 6.4. The results are
presented in Table 6-10.
As shown in Table 6-10, a total boric acid volume of 10,323.4gallons would be required. Of this, 8, 122.7 gallons would be
required to accomplish the feed and bleed from 0 ppm to 775 ppm in117.7 minutes (assuming 69 gpm charging flow and 60 gpm letdown).The remaining volume of 2,200.7 gallons would be required to make up
for coolant contraction. The blend ratio of 6.5 throughout thetransient ensures just enough boric acid is used to maintain the RCS
concentration. fven with the addition of 9 gpm seal leakoff(assumed unavailable for makeup), the required boric acid flow rate(<15 gpm) remains less than the 40 gpm upper limit anticipated forflow control valve FCV-113A.
Under ideal conditions, such a feed and bleed and cooldown could be
accomplished using the available capacity of one full dedicated tankand a portion of the shared tank. Under less ideal conditions, the
minimum allowable volume of 6,600 gallons (Table 5.2-5) would be
available requiring 3,723.4 gallons to be provided by the shared
tank or batched. If batched, a total of 5 batches would be requiredfor a total time of about 7.5 hours.
A variation of the above is to conduct a limited feed and bleed (0
ppm to 446 ppm, for example) and complete the fast cooldown using
the refueling water storage tank as the source of makeup water.
Such an approach would minimize the amount of boric acid tank volume
required and, hence, the amount of batching potentially required.
Report No. 849963-MPS-5MISC-003 Rev. 0 Page 6-19
The results of this evaluation are illustrated in Table 6-11.
Compared to Table 6-10, only 4,485.0 gallons of boric acid at 3.25weight percent would be required to complete the feed and bleed
(well within the required minimum volume of 6,600 gallons per Table5.2-5). The entire evolution could be completed with the refuelingwater storage tank alone using a total of 30,841.3 gallons of waterat 1950 ppm (exclusive of RCS leakage).
6.6.5 Technical Specification Action Statements
Recovery from loss of shutdown margin per the action statements ofTechnical Specifications 3. 1. 1. 1, 3. 1. 1.2, 3.9. 1 and 3. 10. 1 has been
discussed in Section 6.6.2. The purpose of this section is toreview the capability of the boration system to meet the actionrequirements of the remaining technical specifications with reduced
boric acid concentration.
Generally, the action statements of principal concern, with respectto boration capability, occur with Technical Specifications 3. 1.2.2(Flow Paths), 3. 1.2.3 (Charging Pumps), and 3. 1.2.5 (Borated Water
Sources). These action statements follow the sequence outlinedbelow.
2.
3.
Restore (flow path, pump, source) to operable status within 72
hours, orBe in hot standby borated to the shutdown margin for 1.0%%u sk/kat 200 F;
Restore the inoperable condition within an additional 72 hours,
or4. Be in cold shutdown within the next 30 hours.
If the two 72 hour periods are removed, the most limiting action
statement requirement is presented:
1. Be in hot standby, borated to 1.0X nk/k shutdown margin at200'F within 6 hours and,
2. Be in cold shutdown within the following 30 hours.
Report No. 849963-MPS-5MISC-003 Rev. 0 Page 6-20
The timing of the above coincides with the more restrictive actionstatements of Technical Specifications 3. 1.3.5.b (RWST inoperable),3. 1.2.6 (boric acid tank and/or flow paths below specifiedtemperature limit for boric acid solubility), and 3.5.4 (RWST
inoperable). The above specifications do not specifically require-boration to the cold (200'F) shutdown margin of 1.0X a,k/k prior toinitiating the cooldown (within the first 6 hour action). However,
these actions will be assumed in this evaluation so that the actionsof the flow path, source, and charging pump specifications discussedpreviously, are bounded.
As an additional conservatism, the 1.77K sk/k shutdown margincoinciding with the EOC 0 ppm boron condition will be evaluated tomaximize the required boration. The analysis discussed in Section6.5, therefore, is applicable and bounding for the action statementsunder consideration.
The limiting component of the action requirement is the boration to775 ppm within 6 hours in that this action must be performed witheither, the boric acid tank or refueling water storage tank in theworst case. As shown in Table 6-9, a feed and bleed from 0 ppm to775 ppm will require 8, 122.7 gallons of 3.25 weight percent boricacid. Assuming a full boric acid tank (8, 126 gallons per Reference
10.4) is available and 9 gpm is lost to RCP seal leakoff to the VCT,
such a feed and bleed boration could be accomplished inapproximately two hours with 60 gpm letdown and 69 gpm via the
emergency boration flow path (or, more likely, 60 gpm emergency
boration and 9 gpm from the VCT). If, however, only the minimum
required boric acid inventory was available (6,600 gallons per Table
5.2-5), the feed and bleed would require 1522.7 gallons from the
spare tank or from a batching process. If batching is required, 2
batches would be needed, bringing the total time to 5 hours if theoperations were performed in series. If, instead, the batching
operations (if required) are performed in parallel with the feed and
bleed, this very conservative scenario will achieve boration (inexcess of that required) within the allotted time of 6 hours.
Report No. 849963-MPS-5HISC-003 Rev. 0 Page 6-21
0
The remaining cooldown to Mode 5 would require approximately 2,451
gallons for a 50 F/hr cooldown (Table 6-9). Assuming no availableboric acid at this point, approximately 3 batches (4.5 hours) would
be required to provide the necessary volume for boration at a 6.5blending ratio. Continued batching at 800 gallons every 1.5 hours
would provide the necessary makeup for 9 gpm RCS leakage. Periodicpump down of the VCT, as well, will provide additional leakage
makeup and added boration. Altogether, the 50'F/hr cooldown would
require approximately 7 hours of cooldown and 4.5 hours of initialbatching for a series total of 11.5 hours. This is well within the30 hour limit even with consideration of preparation time, RHR
lineup time, etc.
For the case where only the refueling water storage tank isavailable, the required actions have not been affected by a
reduction of the boric acid concentration in the boric acid tanks.No additional evaluation, therefore, is needed for this case.
6.7 IMPACT OF RCS LEAKAGE
Previous evaluations of the cooldown to cold shutdown conditionshave not included RCS leakage as discussed in Section 4.3 Item 4.
The impact of RCS leakage on total makeup inventory requirements can
be significant, however. Estimates of the total inventory require-ment can be made by assuming a constant leakage rate and multiplyingby an estimated time to complete the cooldown evolution. A 347'F
cooldown (547'F to 200'F), for example, completed at an effectivecooldown rate of 50 'F/hr with a constant leakage rate of 11 gpm,
would require a total of 4,580 gallons to replace the RCS leakage.
This volume added to the refueling water storage tank volumes ofTable 5.2-5 could possibly result in available refueling water
storage tank volumes going below the 320,000 gallon limitingcondition for operation for Modes 1 through 4.
Report No. 849963-MPS-5MISC-003 Rev. 0 Page 6-22
Given the total capacity of the three boric acid tanks of about
25,500 gallons, as much as 16,000 gallons could be available to a
unit being shut down and cooled down (after subtracting the minimum
volume for one unit operation). Assuming the boric acid tanks are
maintained as full as possible (i.e., filled to capacity followingeach significant boric acid demand), most, if not all, of the RCS
contraction and leakage makeup can be provided by the boric acid
tanks and/or the pure water system (for blended makeup).
Table 6-12 illustrates a specific case where the effect of RCS
leakage is accounted for during a cooldown using the boric acidtanks for direct and blended makeup. A constant leakage rate isassumed. This is accounted for in .the analysis by adding the
leakage mass to the shrinkage mass term described in Section 5.2.The boron addition provided during the makeup for this new
"shrinkage mass" term is adjusted (decreased) to account for the
mass of boric acid lost with the leaking coolant. This adjustment
is made by taking the RCS boron mass fraction (concentration) times
the water mass that leaks out during each t'ime (temperature)increment.
As shown by Table 6-12, RCS leakage is accommodated during the
specified cooldown using a total of 7,484,7 gallons of boric acid
and 14,969.3 gallons of pure water. The blending ratio varies from
0 to 2. The blending ratio of 2 in this case corresponds to a
blended boric acid solution that is close to the concentration in
the RWST. In this example, therefore, blended boric acid makeup has
replaced the RWST makeup assumed in Section 5.2.
6.8 LONG TERM COOLING AND CONTAINMENT SUMP pH
The impact of the Boric Acid Reduction Effort on post-LOCA long term
cooling and containment sump pH control was reviewed. Each analysis
is discussed qualitatively below.
Report No. 849963-MPS-5MISC-003 Rev. 0 Page 6-23
Performance of the Emergency Core Cooling System (ECCS) duringextended periods of time following a LOCA is typically analyzed toaddress residual heat removal via continuous boil-off of fluid inthe reactor vessel. As borated water is delivered to the coreregion via safety injection and virtually pure water escapes as
steam, high levels of boric acid may accumulate in the reactorvessel. As an input to this analysis, boric acid tank boron
concentration is typically assumed to be at the maximum of 12 weightpercent. Any such calculation will conservatively bound the maximum
boric acid tank boron concentration of 3.5 weight percent proposed
as a result of the analyses of this report.
The containment sump pH analysis is not impacted since it has notassumed injection of boric acid from the boric acid tanks during thedesign basis accident.
Report No. 849963-HPS-5MISC-003 Rev. 0 Page 6-24
Table 6-1
Summary of Initial Conditions and Assumptions
Operations Analysis
Parameter Value
Reactor Coolant System Volume
RHR System Volume
Pressurizer Volume
Reactor Coolant System Pressure
Reactor Coolant System Hot Zero Power Temperature
Pressurizer ConditionReactor Coolant System Leakage
Boric Acid Makeup Tank Temperature
Hakeup Water Temperature
Pressurizer Level
Letdown
Letdown Flowrate From One OrificeLetdown Flowrate From One OrificeEOC Boron ConcentrationBOC Boron Concentration
BAT Boron ConcentrationRWST Boron ConcentrationInitial RHR System Concentration
RCS Boron Concentration (Refueling)
8015 ft2000 ft520 ft2250 psia547'F.
Saturated
0
120'F
120'F
Constant
Available45 gpm
60 gpm
0 ppm
1100 ppm
3.25 wtX
1950 ppm
775 ppm
1950 ppm
Report No. 849963-NPS-5MISC-003 Rev. 0 Page 6-25
TABLE 6 2CB FEEO'Ne BLEED UBINO ONE LETOOUN ORIFICE (45 CPN) FROI AN INITIAL CONCENTRATION Of 0 PPN BORON (SOURCE 0 120 F)
EXPONENTIAL
TINE (l.~ ( AT/Tao)RUST AT
(Nlmtoo) 19SO PPN
BAT A'I
I.SO UT X
BAT AT
1.75 UT N
eaT al2.2S UT N
BAT AT
2 F 50 UT N
BAT AT
3.00 UT N
BAT AT
3.25 UT XBAT AT TOTAL VOL TOTAL VOL
3 ~ So UT N AT CS CPN AT S4 CPN
010
2030405060708090
100110120130140150
160170
160
190200210220230240250260270260290300310320330340
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TARLE d 3
CR fEEO ANO RLEEO USINO ONE LETOOMN OR! fICE I60 GPFI) fROI AN INITIAL CONCENTRATION OF 0 PPN SORON IROMRCE 8 120 f)
EXPONENTIAL
TINE Il ~ 'I ?/TAO)RMST'AT
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SAT A'
1.50 MT X
SAT AT
1.75 MT X
SAT AT
2.2S MT X~AT AT
Z.SO MT X
RAT AT
3.00 MT X
RAT AT
3.25 MI X
RAT AT TOTAL VOL TOTAL VOL
3.SO MT X AT 60 GPN AT 69 GPN
010
203040$ 0
6070
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100
110
120
130140
150160
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IN190
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220230240
250260270260
290
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CONCENTRAT
032. C644264.$ 269d96>19260127.4662156.352T18S>85692$ 6.9634248.7370278.1223307.1C3833S.8060364.113S392.070$419.66144C6.9SOS473.MZISOO.C603
526.7492552.6929578.3'ISS603.d208btb.d129653.2957dll.b?29701 ~ 7CM725.52577CQ. 0067772>2010795 ~ 1063
617.7260640.069d862.$ 347M3.926690S.CCSS
926.70Cd947.69?Z968.4299966.90601009.1261029. 100
IOC6.6251066.3061067.$ Cb
1106.SCS1125.314IIC3.6461162.1521180. 230
1196.0851215 ~ 716
ION RETMLTING Ippa boron)0
4b.d966396. 790CS
ICC.ZMQ191 > 1993237. $ 291
283 >'2SS3
326. C?51
373.$ 0554$ 7.$ 634
C60.71STS03.7091SC6.1702MS. $ 057629.$ 221
670.CZSS710.8232Tso.n04790. 1238829.0394667,C73290$ . C313QC2.9194979.9C3Slole.s091052.622IOM.ZM$ 123. 5131158.3011192.6591226.S921260.1041293.2021325.6901358. 173
1390. 056ICE I.SCSICS2. 64C
ICM.3591513. 6931543>d(51
IS73.2361602.4601631. 3191659.82216bl.971171$ . 772
1743.22917?0.3C61797.1271623.$ 77
037.6?$ 16TS >26146112.2247146.7106ISC.74CS220.HSOZSS.4Nb290> 1932
324 >4?60
358.33C439$ .7737C2C. 7990457. C I56C69.6283521.4C23552.6624S63.6936614.SCOT6C4.806C674.7014704,2tC3733.3816762.$ 763790.d16461d.706384d.CCbb673.6435900.9012927.624095C,0160QN.OSIZ100S.SZ31031.2C71056.3$ 7
1061.1551105.6Cd1129. 8341153.723I IT7.316Izoo.elr1223.630$ 246.3561266.6041290.9721312.666IHC.CSQ1355.6CS13 rd.93b1397.765IC16.337
0$4.'1073T107. $449160. 3210212 ~ 4437263.9212314.761536C.9TZC414. $617463 >53?1
5'11.9063SS'Q.d767
606.655665'SOSd99.Cd90rcC.Qlre769.803S634.1HSblr.915392'1.1549963.M911006.03C1047.686Todd.ste1129.CSC
1169.SN1209.2091246.347IZST. 001
1325.1T?1362.660IC00.116$ 436.d91IC73.2111509.06$154C.50715?Q.CQS
161C. 049Teed.lre1661. 661
1715. 166
I?Cd.OC31760. 511
1612.STT164C.2C6ld?$ .524$ 906. C13
1936.921196?.05$1996.6062026.197
064. 92MSlt9.0539192.3852254.932$3ld.lOSS377.7136C37.9668C97.4740Ssb,ZCC661C.2676671>6121728.2270764.1CIO639.3629893.9011947.76421000.960IOH.CQS1105.365I lsd.b31IZOT.ZCI1257.2251306.$ 91
1355.345ICOS.C96
1451.051IC98. 017I!44.C021590.212163S.CSd1680.139ITZC.2691767.8531610.6971653.4091895.3941936. M919?7.8122016.257ZOM.201209r.esl2136. dl3217$ .0932213.0962250.6262287. 6962324.3052360>461
2396.170ZC31.436
0lb.33956139. NSC206.4173trb>ITM3C3. 0976409>1699474. CbCI
$36.9302602.598366$ .C?SZ
727.5796766.9126649.C661909. 3096968.3929102d.7441064 ~ 374I ICI.2691197.501IZSS. 0$ 61307.8451361.99cIC15.474ICbb. 291
1520.CSC
1571.9?21622.6521673.1021722.7301771. 7CC
1620. 150
$ 66?.9561915.1741961. 605ZOOT.5$ 92053.343209d.26421CZ.6292166.4CS2229.7182272.456231C.6642356.350239T.5202436. 161
2C?6.3362517.9962557.16T2595.651zesc.ose
075 ~ ?$ 032150 S62922C ~ C494297.C212369.C697440.bbblS10.9613SSO. 3664646.952071 d.6689763. S4 ?5849.$ 96$
91C.63129?Q.ZSdrIOC2.M4I IOS ~ 72C
1167.7671229.06$1269.6161349.402ICOS.CCS
IC66.7631524 '561561.23d1637.CIZ1692.6931?C7.6671801. 602$ 855.2481908.0321960. 162
2011. 6CT
Z062.CQS
2112. 7142'I62.3102211. 2932259.669230?.4472354.633ZCO I.235ZCCr.t60ZcQZ.rleZ537.6062561.9CS2625.7332668.979Zl'II.690Z?53.6?Z2?95.5312636.675
0600
12001800ZCOO
30003600C200
4NOSCOO
600066007200?NOSCOO
90009600
10200
10600$ 1400
1200012600
13200IMOO
ICCOO
15000
15600
16200
16600
17400
Ib00018600
19200
19600
ZOCOO
210002160022200228002340024000ZC600
2520025600
Z6COO
270002760028200ZMOO
29COO
30000
0690
$ 360207027603CSO
CICO
CMO
$ 520621069007590628069709660
103501104011730
124201311013d00ICCQO
151601587016560
17250
179CO
$ 663019320200'IO
20700213'90
2208022770
23C60
241502C8CO
ZSHO26220269102(6002d29026980296?0
303603105031740324303!120
3361034500
TABLE 6-4RCS FEED AHD BLEED: OHE LETDOMN ORIFICE (45 GPN) INITIAL COHCEHTRATION OF 1100 PPH BORON (SOURCE 9 120 F)
I TINE
i (min)EXP. VALUE
Y=T-XEXP. VALUE
X
RlST AT
1950 PPH
BAT AT
1.5 MT X
BAT AT BAT AT
1.75 MT X 2.25 IIT X
BAT AT
2.50 MT X
BAT AT
3.00 IIT X
BAT A'I
3.25 IIT X
BAT AT TOTAL VOL TOTAL VOL
3.50 III' AT 45 GPH AT 54 GPN I
-I
0
10
20
304050
60
70ao
i 1OO
I 110
I 120
i 13o
1
0.9907020.9814900.9723640.9633230.9543660.9454930.9367020.9279920.9193640.9108160.9023470.8939570.885645
i lroI 180
I 190
I 200
i 21O
i 22O
i 23O
i 24O
i 2SO
i 26O
I 270
i 2SO
i 290
I 300
i 310
I 320
i 330
i 340
i 350
I 360
i 370380
0.8531630.8452300.8373710.829585o.e21sr20.8142300.8066600.7991590.7917290. 784367
0.7770740.7698490.7626910.7556000.7485740. 741614
0.7347190.7278870.7211190.7144140.7077720.701191
I 140 0'877C10
I 150 0.869252
I 160 0.861170
0.000000.009300.018510.027640.036680.045630.054510 '63300.072010.080640.089180.097650.106040.114350.122590 ~ 13075
0 ~ 13S83
0.146840.154770.162630.170410 ~ 17813
0.185770 '93340.200840.208270.215630.222930.230150.237310.244400.251430.258390.265280.272110.278880.285590.292230.29881
RCS BORON
1100
1107.9031115.7331123.4891131.1741138.7881146.3301153.8031161.2061168.5401175.8061183.0041190.1361197.2011204.2001211.1351218.0051224.8111231.5531238.23C1244.8511251.4081257.9031264.3381270.7141277.0301283.2871289.4861295.6271301.7121307. 739
1313.7111319.6271325.4881331.2951337.0481342.7471348.3931353.987
CONCENTRAT
1100
1114.1561128.1801142.0741155.8391169.4761182.9871196.3711209.6311222.7681235 '831248.6771261.4501274.1051286.6431299.0641311.3691323.5601335.6371347.6031359.4571371.2001382.8351394.3611405.7811C17.094
1428.3021439.4051450.4061461.3041472.1011482.7971493.3941503.8921514. 293
1524.5971534.8061544.919'I554.938
ION RESULT I1100
1118.2201136.2701154.1531171.8701189.4221206.8111224.0381241.1051258.0131274.7641291.3591307.8001324.0881340.2251356.2111372.0491387.7401403.2851C18.6851433.9421449.0571464.0321478.8671493.5651508.1261522 ~ 551
1536.8421551.0011565.0281578.9241592.6911606.3301619.8431633.2301646.4921659.6311672.6471685.543
on)1100
1130.4121160.5411190.3901219.9621249.2591278.2831307.0381335 '251363.7471391.707'I419.4071446.8491474.0361500.9701527.6541554.09015S0.2801606.2271631.9321657.3981682.6281707.6231732.3851756.91S1781.2221805.3001829.1541852.7871876.1991899.3951922.3741945.1401967.6941990.0382012.1752034.1062055.8332077.357
NG (ppm bor1100
1126.3481152.4511178.3111203.9311229.3131254.4591279.3711304.0511328.5021352.7261376.7241400.4991424.0531447.3891470.5071493.4101516.1001538.5791560.8501582.9131604.7711626.4261647.8791669.'l331690.1901711.0501731.7171752.1911772.4761792.5711812.4801832.2031851.7441871.1021890.2S11909.2811928.1041946.753
1100
1138.540
1176.7211214.548
1252 '231289.1501325.931
1362.3711398.471
1434.2361469.6691504.7721539.5481574.001
1608.1341641.9501675.4511708.6411741.5221774.0971806.3691838.3C21870.0171901.3971932.4861963.2861993.7992024.0292053.9772083.6472113.0422142.1622171.0132199.5952227.9112255.9642283.756231'1.289
2338.567
1100
1142.6041184.8121226.6271268.0541309.095'13C9.755
1390.0371429.9451469.4811508.6501547.4541585.8981623.9841661.7161699.09S
1736.1311772.8211809.1691845. 179
1880.8551916.1981951.2141985.9032020.2702054.318208S.0492121.4662154.5722187.3712219.8652252.0572283.9492315.5452346.8472377.8582408.5812439.0182469.172
1100
1146.6681192.9021238.7061284.0841329.0411373.5791417.7041461 ~ 41S
1504.7261547.6311590.1371632.2471673.9671715.2981756.2451796.8121837.0011876.8161916.2621955.3401994.0552032.4112070.4092108.0542145.3502182 '982218.9032255 '682291.0952326.6892361.9512396.SS62431.4952465.7832499.7522533.4062566.7C62599.776
0
450
900
1350
1800
2250
2700
3150
3600
4050
4500
49505400
5850
6300
6750
7200
7650
8100
8550
9000
94509900
10350
10800
11250
11700
12150
12600
13050
13500
13950
14400
14850
15300
15750
16200
16650
17100
I
oi54o i
1OSO )
1620 I216O i27oo i3240 i3780 i4320 [486O iscoo )
5940 I64ao iro2o ir56o i8100 I
Mco /
9180 I9720 /
1O26O /losoo t11340 I11880 i12420 I
12960 [13500 I
1404O i14580 i15120 I
1566O i162OO i16740 /172so /17820 I18360 /18900 I
19440 I19980
J
20520
TABLE 6-5RCS FEED-AHD BLEED USING OME LETDOMM ORIFICE (60 GPH) FROM AM INITIAL CONCENTRATION OF »00 PPH BORON (SOURCE Q 120 F)
I TINE
i(min)
0
10
20
30
co
50
80
) 1OO
I »0I 120
I 130
I 140
i 1SO
I 160
i 1ro
i 180
i 190
[ zoo
i 21O
i 22O
/ Z3O
i 24O
i zso
i 260
i zro
/ zeo
/ Z90
i 300
I 310
/ 320
) 330
I 340
i 350
i 370
3SO
1
0.9876200.9753940.9633200.9513950.9396170.9279860.9164980.9051530.8939480.8828810.8719520.86»580.8504970.8399690.8295710.8193020.8091590.7991430.7892500.779CBO
0.7698300.7603010.7508890.7415930.7324130.7233C60.7143920.7055CS0.6968140.6881880.6796690.6712550.6629460.6547390.6466340.6386290.6307240.622916
0.000000.012380.024610.036680.048600.060380.072010.083500.09C85
0.106050.»7120.128050.13MC0.149500.160030.170430.180700.190840.200860.210750.220520.230170.239700.249»0.258410.267590.276650.285610.294450.303190.3»810.320330.328740.337050.345260.353370.361370.369280.37708
EXP. VALUE EXP. VALUE
T=1-X X RMST AT
1950 PPH
RCS BOROH
»00»10.522»20.914»31.177»41.313»51.324»61.2»»70.976»80.619»90.144»99.5501208.8401218.0151227.0761236.02512C4.864
1253.5931262.2141270.7281279.1371287.4411295.6431303.744
13» .7441319.6451327.4481335.1551342.7661350.2831357.7071365.0391372.2SO
1379.43213S6.4951393.4711400.3601407.1641413.8841420.521
BAT AT
1.50 'MT X
CONCENTRAT
»00»18.847»37.461»55.845»74.001»91.9321209.641
1227.1311244 405
1261.4651278.313129C.953
13» .3871327.6181343.6471359.479
1375. »41390 ~ 5561C05.806
1C20.8681435.7431450.4341C64.944
1479.2731493.4261507.C03
1521.20T1534.8401548.3041561.602157C.735
1587.7061600.5161613 ~ 167
1625.6621638.0021650.189
BAT AT BAT AT
1.75 MT X 2.25 MT X
BAT AT
2.50 llT X
HG (ppn boron)»00»00-»35.079 »40.490»69.724»80.4791203.9C1 1219.9731237.734 1258.9781271.108 1297.5001304.070 1335.5C6
1336.623 1373.1201368.773 1C10.230
1C00.526 14C6.880
1431.885 1CB3.076
1462.856 1518.8241493.444 1554.1301523.653 1588.9981553.488 1623.4351582.954 1657.4461612.055 1691.0351640.796 1724.2091669.181 1756.9721697.21C 1789.3301724.901 1821.2871752.245 1S52.S48
1779.250 1884.019
1805.921 1914.8041832.262 1945.2081858.277 1975.2351M3.970 2004.8911909.34C 2034.1791934.405 2063.1051959.155 2091.6731983.599 2»9.8872007.741 2147.7522031 ~ 583 2175.2722055.130 2202.4522078.386 2229.2942101.354 2255.8052124.038 2281-988
ION RESULTI
»00»24.258»48.215»Ti.err»95.2451218.3241241.»71263.62912S5.861
1307.8181329.50C
1350.9211372.0731392.9631413.5941433.9701CSC.094
1473.9691493.5981512.9831532.1291551.0381569.712158S.1561606.3711624.3611642.1281659.6751677.0051694.12017».0231727.7171744.2051760.4881776.5701792.4531808.139
BAT AT
3.00 IIT X
»00»51.3»1201.9881252.0371301.4671350.2851398.4981446. »51493.1421539.5871585.4571630.7591675.5011719.6881763.3291806.42918C8.9961891.0361932.5551973.5612014 ~ 0592054.0552093.5572132.5692171.0982209.1512246.7322283.8492320.5052356.7082392.4632427.7752462.6502C97.0942531. »12564.7072597.887
BAT AT
3.25 llT X
»00»56.7221212.7421268.0691322.7»1376.67T1429.9741482.6121534.5981585.9411636.6481686.7271736.1861785.0331833.2761880.9211927.9761974.4492020.3472065.6762»0.4452154.6592198.3252241.4522284.0442326.1092367.6532408.6832449.2062489.2262528.7512567.7S72606.3402644.4152682.0192719.1572755.836
»00»62.1331223.4971284.101
1343.9561403.0691461.4501519.1091576.0541632.2941687.8381742.6951796.8721850.3791903.2231955.C13
2006.9572057.8632108.1382157.7922206.8312255 '622303.0942350.3342396.9892443.0672488.5742533.5182577.9062621.7442665.0392707.7992750.0292791.7362832.9272873.6082913.786
0
600
1200
1800
2400
3000
3600
42004800
5COO
6000
6600
7200
7800
8400
9000
960010200
10S00
»40012000
12600
13200
13800
14400
15000
15600
16200
16800
17400
18000
18600
19200
'980020400
2100021600
22200
22800
BAT AT TOTAL VOL
3.50 MT X AT 60 GPN
TOTAL VOL
AT 69 GPH i-I
Io i
690 I
13eo (
zoro i2760 I3450 I41CO I483O
J
5520 i6ZIO i6900 I
TS90 i8280 I8970 I
9660 /10350 I»040 /»73o (
12420 I13»0 I13800 (
14490 I1s1eo
J
15870 I16S6O )
Irzso /17940 /18630 /19320 I20010 I20700 /
21390 I22080 I
22770 /23460 /24150 I24840 iZSS3O i .
26220
TABLE 6 6PLANT COOLDOLIN TO REFUELING: BAT AT 3.25 IIEIGHT X BORIC ACID; RHR = 775 ppm (RHR VOLUME = 2000 FT3)
IAVG~ SYS.TEMP. PZR PRESS SPECIFIC VOLUME SHRINKAGE BLEND BAT VOL 9 RUST VOL Q B/A ADDED TOTAL B/A TOTAL SYS. FINAL CONC TOTAL RCS TOTAL PURE TOTAL BAT
(F) (psia) (cu.ft./tbm) MASS(ibm) RATIO 120 F (gal) 120 F (gal) (tbm) (tbm) - MASS (ibm) (ppm boron) MAKEUP MATER llATER
Ti . Tf Vi Vf 120 F (gal) 120 F (gal) 120 F (gal)
547 547547 500500 450450 400400 370370 350350 350350 350350 300300 250250 200200 160
160 130
22502250
2250225022502250
465465
465465
465465
465
1.000000.021250.020090.019160.018420.018040.026980.017810.017810.017420.016980.016610.01637
1.000000 '20090.019160.018420.018040.017810.019610.017810.017420 ~ 01698
0.016610.016370.01622
0.021,796.019,473.916,814.49,170.65,740.87,243.5
0.012,431.414,897.713,138.58,839.85,657.7
0
0
0
0
0
0
0
0
0
0
0
0
0
0.02,642.02,360.52,038.21,111.6
695.9878.0
0.01,506.91,805.81,592.61,071.5
685.8
0.00.00.00.00.00.00.00.00.00.00.00.00.0
0.0 2,894.0 445,622.6732.2 3,626.2 468, 150.7654.2 4,280.3 488,278.7564.8 4,845.1 505,658.0308.1 5,153.2 515,136.6192.8 5,346.0 521,070.3243.3 5,589.3 528,557.2495.8 6,085.2 636,526.6417.6 6,502.7 649,375.6500.4 7,003.2 664,773.7441.3 7,444.5 678,353.5296.9 7,741.4 687,490.3190.0 7,931.5 693,338.1
1,135.41,354.21,532.61,675.21,749.01,793.71,848.81,671.41,750.81,841.81,918.71,968.72,000.0
0.02,642.05,002.57,040.78,152.38,848.29,726.29,726.2
11,233.113,038.914,631.515,703.016,388.8
0.00.00.00.00.00.00.00.00.00.00.00.00.0
0.02,642.05,002.57,040.78, 152.38,848.29,726.29,726.2
11,233.113,038.914,631.515,703.016,388.8
iCONTRACTION MAKEUP BAT VOLUHE
)FEED 8 BLEED BAT VOLUME (Oppn to 1135ppn)iTOTAL BAT VOLUME
16,388.8 gat lons10,800 ~ 0 gallons (180 min at 60 gpm) ROUNDED UP
27,188.8 gatlons
ITABLE 6-7
)PLANT COOLDOMN TO COLD SMUTDOMN (CASE 1): BLENDED MAKEUP; BAT AT 3.25 MEIGHT )l BORIC ACID; RHR (ppm) = RCS (ppm) (RHR VOLUHE = 2000 FT3) (CASE 1)
[AVG.SYS ~ TEHP. PZR PRESS SPECIFIC VOLUME SHRINKAGE BLEND BAT VOL 9 RUST VOL ol B/A ADDED TOTAL 8/A TOTAL SYS. FINAL CONC. TOTAL RCS TOTAL PURE TOTAL BAT
(F) (psia) (cu.ft./ibm) HASS(ibm) RATIO 120 F (gal) 120 F (gal) (ibm) (ibm) HASS (ibm) (ppm boron) HAKEUP HATER IIATER
Ti 'f Vi Vf 120 F (gal) 120 F (gal) 120 F (gal)
547 547547 . 500500 450
450 400400 370370 350350 350350 350350 320320 290290 260260 230230 200
2250 1 ~ 00000
2250 0.021252250 0.020092250 0.019162250 0.018C2
2250 0. 01804
465 0.02698465 0.01781465 0.01781465 0.01763C65 0.01733465 0.01706465 0.01682
1.000000.020090.019160.018420.018040.017810.019610.017810.017630.017330.017060.016820.01661
0.021,796.019,473.916,814.49,170.65,740.87,243.5
0.05,583.39,833.89,146.18,376.47,527.9
0.30.30.30.30.30.30.30.30.32.42.42.42.4
0.02,032.31,815.81,567.8
855.1535.3675.4
0.0520.6350.6326.1298.6268.C
0.00.00.00.00.00.00.00.00.00.00.00.00.0
0.0563.2503.2434.5237.0148.3187.2426.1144.397.290.482.874.4
0.0563.2
1,066.41,500.91,737.81,8S6.22,073.32,499.42,643.72,740.82,831 ~ 2
2,914.02,988.3
442,728.6465,087.74S5,064.S502,313.7511,721.3517,610.4525,041.2632,940.9638,668.5648,599.4657,835.9666,295.1673,897.4
0.0211.7384.4522.4593.7637.1690.4690.4723.7738.8752.5764.6775.3
0.02,642.05,002.57,040.78,152.38,848.29,726.29,726.2
10,403.011,595.012,703.613,719.014,631.5
0.0609.7
1,154.41,624.81,881.32,041.92,244.52,244.52,400.73,242.14,024.74,741.45,385.5
0
2,032.33,848.15,415.96,271.06,806.37,481.77,481.78,002.38,352.98,679.08,977.69,246.0
ITOTAL BAT VOLUME
iTOTAL RIIST VOLUHE
9,246.0 gallons0.0
I TABLE 6-8
/PLANT COOLDNN TO COLD SHUTDOMN (CASE 2): BLENDED MAKEUP BAT AT 3.25 MEIGHT X BORIC ACIDI RHR (ppm) "- 775 ppm (RHR VOLUME = 2000 FT3) (CASE 2)
JAVG.SYS.TEMP. PZR PRESS SPECIFIC VOLUME SHRINKAGE BLEND BAT VOL 9 RUST VOL 9 B/A ADDED TOTAL B/A TOTAL SYS. FINAL CONC TOTAL RCS TOTAL PURE TOTAL BAT
(F) (psia) (cu.ft./tbm) MASS(ibm) RATIO 120 F (gat) 120 F (gal) (ibm) (ibm) MASS (ibm) (ppm boron) MAKEUP MATER MATER
Ti Tf Vi Vf 120 F (gal) 120 F (gal) 120 F (gal)
547 547547 500500 450
450 400400 370370 350350 350350 350
350 320320 290290 260260 230
230 200
2250
2250
2250
2250
2250
2250
465
465
465
465
465
465
465
1.000000.021250.020090.019160.018420.018040.026980.017810.017810.017630.017330.017060.01682
1.000000.020090.019160.018420.018040.017810.019610.017810.017630.017330.017060.016820.01661
0.021,796.019,473.916,814.49,170.65,740.87,243.5
0.05,583.39,833.89,146.18,376.47,527.9
0.30.30.30.30.30.30.30.30.33.13.13.13.1
0.02,032.31,815.81,567.8
855.1535.3675.4
0.0520.6290.7270.4247.6222.6
0.00.00.00.00.00.00.00.00.00.00.00.00.0
0.0563.2503.2434.5237.0148.3187.2495.8144.380.674.968.661. 7
0.0563.2
1,066.41,500.91,737.81,886.22,073.32,569.22,713.42,794.02,868.92,937.62,999.2
442,728.6465,087.7485,064.8502,313.751'I,721.3517,610.4525,041.2633,010.6638,738.2648,652.6657,S73.6666,318.7673,908.3
0.0211.7384.4522.4593.7637.1690.4709.6742.7753.1762.4770.8778.1
0
2,642.05,002.57,040.78,152.38,848.29,726.29,726.2
10,403.011,595.012,703.613,719.014,631.5
0.0609.7
1,154.41,624.81,881.32,041.92,244.52,244.52,400.73,302.04,140.24,907.95,597.8
0.02,032.33,848.15,415.96,271.06,806.37,481.77,481.78,002.38,293.08,563.48,811.19,033.6
ITOTAL BAT VOLUME
ITOTAL RIIST VOLUME =
9,033.6 gatlons0.0
TABLE 6.9PLANT COOLDOWN To COLD SHUTDOWN: FEED AND BLEED AND BLENDED IIAKEUP FOR 50 F/HR COOLDOWNI BAT AT 3 '5 WT XI RHR (ppm) = 775 m ---------(9 gpa SEAI. LEAKAGE)--------
AVG.STSTEHP. PZR PRESS
(F) (psia)Ti Tf
SPECIFIC VOLUHE
(cu.ft./Ibm)Vi Vf
SHRINKAGE
I(ASS(ibm)BLEND
RATIO
BAT VOL a RuSt VOI. O 8/A ADDEO
120 F (gal) 120 F (gal) (Ibm)TOTAL 8/ TOTAL SYS. FINAL CONC TOTAL RCS TOTAL PURE TOTAL BAT
(Ibm) IIASS (Ibm) (ppa boron) HAKEUP WATER MATER
120 F (gal) 120 'F (gal) 120 F (gal)
547547540530520510500490480470460450440430420410400390380370360350350350
330310290
270250
230210
5475CO
530
520510500490480470460450440430420410400
390380370360350350350330
310290270
250
230
210200
2250
2250
2250
2250
2250
22502250
2250
2250
225022502250
2250
22502250
2250
2250
22502250
22502250
465
465
465
465
465
465
465
465
465
465
1.000000.021250.021060.020790.020550.020310.020090.019890.019690.019510.019330.019160.019000.018840.018690.018550.018420.018280.018160.018040.017920.026980.017810.01781
0.017730.017630.017420.017240.017060.016900.01675
1.000000.021060.020790.020550.020310.020090.019890.019690.019510.019330.019160.019000.018840.018690.018550.018420.01828o.oie160.018040.017920.017810.019610.017810.017730.01T630.017420.017240.017060.016900.016750.01661
0.03,511.04,852.24,597.44,513.94,321.54,011.64,093.13,860.93,827.53,680.93,524.53,471.53,414.33,353.03,051.03,334.32,898.92,937.52,976.82,764.07,2C3 as
0.02,379.43,204.06,848.16,002.66,129.25,557.85,306.95,039.6
6.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.5
0.056.778.474.373.069.864.866.262.461.959.557.056.155.254.249.353.946.947.548.144.7
117.10.0
38.551.8
110.797.099.189.885.881.4
0.00.00.00.00.00.00.00.00.00.00.00.0-0.00.00.00 ~ 0
0.00.00.00.00.00.00.00.00.00.00.00.00.00.00.0
0.015.721.720.620.219.418.018.317.317.116.515.815.515.315.013.71C.913.013.213.312.432.4
495.810.714.430.726.927.524.923.822.6
1,962.51,978.22,000.02,020.52,040.82,060.12,078.12,096.C2,113.72,130.92,147.32,163.12,178.72,194.02,209.02,222.62,237.62,250.62,263.72,277.12,289.42,321.9z,eir.r2,828.42,842.72,873.42,900.32,927.72,952.62,976.42,998.9
442,728.6446,255.2451,129.2455,747.1460,281.3464,622.2468,651.7472,763.2C76,641.3480,485.9484,183.3487,723.6491,210.6494,640.2498,008.3501,073.0504,422.2507,334.1510,284.7513,274.8516,051.2523,327.2633,259.1635,649.2638,867.5645,746.3651,775.7657,932.4663,515 '668,845.8673,908.0
775.0775.0775.1775.1775.2775.2775.2775.3775.3775 ~ C
775.4775.47T5.4775 ~ 5
775 ~ 5
775.5775.6775.6775.6775.6775.6775.7777.9777.97T7.97TS.O
rre.o778.0778.0778.0778.0
0501.2
1,197.31,862.62,517.83,149.63,743.94,348.04,924.05,496.06,050.16,585.47,114.27,636.08,150.58,628.39,140.59,599.8
10,063.910,532.710,975.811,853.811,853.812,358.212,962.614,008.71C,952.315,911.216,800.917,660.218,379.1
0.0434.4
1,037.71,614.32,182.12,729.73,24C.73,768.34,267.54,763.25,243.45,707.36,165.66,617.97,063.77,477.97,921.78,319.98,722.19,128.49,512.3
10,273.310,273.310,710.51'1,23C.2
12,140.912,958.713,789.714,560.815,305.515,928.5
o.o I66.8 I
159.6 I
248.3 I335.7 I
419.9 I
499.2 I579.7 I
6s6.s I73z.s I
806.7 Isrs.o I
948.6 I
1,018.11,086.7 I
1,150.4 I
1,218.7 I
1,280.0 I
1,341.9 I
I,co4.4 I
1,463.4 I1,580.5 I
1,Seo.S I1,647.8 I
1,728.3 I
1,867.8 I
1,993.6 I
2,121.5 I
2,240.1 I
2,354.7 I
z,4so.s I
FEED AND BLEED BAT VOLUHE (Oppm to 775ppm)FEED AND BLEED RWST VOLUNE (Oppm to 775ppm)
8,122.7 gallons28,060.0 gallons
(117.7 minutes at 69 gpm, 3.25 wt X)(406.7 minutes at 69 gpm, 1950 ppm)
TOTAL BAT VOLUIIEt FEED AND BLEED PLUS HAKEUP 10,573.2 gallons
TABLE 6-10
PLANT COOLDOWN TO COLD SHUTDOWN: BLENDED MAKEUP FOR 100 F/HR COOLDOWN; BAT AT 3.25 WEIGHT X BORIC ACID; RHR (ppm) = 775 ppm ---------(9 gpm SEAL LEAKAGE)-------
AVG.SYSTEMS PZR PRESS
(F) (psia)Ti Tf
SPECIFIC VOLUME
(cu.ft./Ibm)Vi Vf
SHRINKAGE BLEND
MASS( ibm) RATIO
BAT VOL 9 RWST VOL 9 8/A ADDED
120 F (gal) 120 F (gal) ( ibm)
TOTAL B/ TOTAL SYS ~
(ibm) MASS (ibm)FINAL CONC TOTAL RCS TOTAL PURE TOTAL BAT
(ppm boron) MAKEUP WATER WATER
120 F (gal) 120 F (gal) 120 F (gal)
SC7
547540
530520510500490480470460450440430420410400390380370360350350350
330320300280260240220
547540530520510500490480470460450440430420410400390380370360350350350330320300280260240
220200
225022502250
22502250
22502250
22502250225022502250
225022502250
22502250
2250225022502250
465465465
465
465465
465465
465465
1.00000 1.000000.02125 0.021060.02106 0.020790.02079 0.020550.02055 0.02031
0.02031 0.020090.02009 0.019890.01989 0.019690.01969 0.019510.01951 0.019330.01933 0.019160.01916 0.019000.01900 0.018840.01884 0.018690.01869 0.018550.01855 0.018420.01842 0.018280.01828 0.018160.01816 0.018040.01804 0.017920.01792 0.017810.02698 0.019610.01781 0.017810.01781 0.017730.01773 0.017630.01763 0.017420.01742 0.017240.01724 0.017060.01706 0.016900.01690 0.016750.01675 0.01661
0.03,511.04,852.24,597.44,513.94,321.54,011.64,093.13,860.93,827.53,6S0.93,524.53,/71.53,414.33,353.03,051.03,334.32,898.92,937.52,976.82,764.07,243.5
0.02,379.43,204.06,848.16,002.66,129.25,557.85,306.95,039.6
6.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.56.5
0.056.778.474.373.069.864.S66 '62.461.959.557.056.155.254.249.353.946.947.548.144.7
117.10.0
38.551.8
110.797.099.189.885.881.4
0.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.0
0.015.721.720.620.219.418.018.317.317.116.515.815 ~ 5
15.315.013.714.913.013.213.312.432.4
495.810.714.430.726.927.524.923.822.6
1,962.51,978.22,000.02,020.52,040.82,060.12,078.12,096.42,113.72,130.92, 147.32,163.12, 178.72,194.02,209.02,222.62,237.62,250.62,263.72,277.12,289.42,321.92,817.72,828.42,842.72,873.42,900.32,927.72,952.62,976.42,998.9
442,728.6446,255.2451,129.2455,747.1460,281.3C64,622.2468,651.7472,763.2476,641.3480,485.9484, 183.3487,723.6491,210.6494,640.2498,00S.3501,073.0504,422.2507,334.1510,284.7513,274.8516,051.2523,327.2633,259.1635,649.2638,867.5645,746.3651,775.7657,932.4663,515.2668,845.8673,908.0
775 ~ 0
775.0775.1775 ~ 1
775.2775.2775.2775.3775.3775.4775. C
775.4775.4775.5775.5775.5775.6775.6775.6775.6775.6775.7777.9777.9777.9778.0778.0rre.o778.0778.0778.0
0.0463.4
1,105.51,716.82,318.02,895.83,436.13,986.24,508.25,026.25,526.36,007.66,482.46,950.27,410.77,834.58,292.78,698.09,108.19,522.99,912.0
10,790.010,790.011,186.411,62e.e12,566.913,402.514,253.415,035.115,786.416,505.3
0.0401.6958.1
1,487.92,008.92,509.72,977.93,454.73,907.14,356.04,789.55,206.65,618.06,023.56,422.66,789.97, 187.07,538.37,893.78,253.28,590.49,351.39,351.39,694.9
10,078.310,891.311,615.512,353.013,030.513,681.614,304.6
0.0 i61.8 i
1474 I
228.9 I309.1 I
386.1458 1 I531.5 I
601.1 I
670.2 I736.8 /801.0 I
864.3 i926.7 I
988.1 I
1,044.6 I
1,105.7 i1,159.7 I
1,214.4 i1,269.7 I
1,321.6 i1,438.7 I
1,438.7 i1,491.5 I
1,550 5 I
1,675.6 i1 787.0 I
1,900.5 I2,004.7 (
2,104.9 J
2,200.r /
FEED AND BLEED BAT VOLUME (Oppm to 775ppm)
FEED AND BLEED RWST VOLUME (Oppm to 775ppm)
8,122.7 gallons2S,060.0 gallons
(117.7 minutes at 69 gpm, 3.25 wt )l)(406.7 minutes at 69 gpn, 1950 ppm)
TOTAL BAT VOLUME: FEED AND BLEED PLUS MAKEUP 10,323.4 gallons
TABLE 6-11PLAN'I COOLDOMN TO COLD SHUTDONN: FEED AND BLEED AND RNST HAKEUP FOR 100 F/HR COOLDONNI RWST AT 1950 ppm BORONI RHR (ppm) = 775 ppn -----(9 gpm SEAL LEAKAGE)------
AVG.SYSTEHP. PZR PRESS
(F) (psia)Ti Tf
SPECIFIC VOLUME
(cu.ft./Ibm)Vi Vf
SHRINKAGE
MASS( ibm)BLEND BAT VOL 9 RUST VOL 8 B/A ADDED
RATIO 120 F (gal) 120 F (gal) (lbn)TOTAL B/ TOTAL S'YS.
(ibm) MASS (ibm)FINAL CONC TO'IAL RCS TOTAL PURE TOTAL BAT
(ppn boron) MAKEUP MATER MATER
120 F (gal) 120 F (gal) 120 F (gal) (
-I547547540
530520
510500490480470460450440430420
410400
390380370360350350350330320300280260240220
54754053052051050049D
4804704604504CO
430420410400390380370360350350350330320300280260240220200
22502250
2250
22502250
225022502250
225022502250225022502250225022502250
225022502250
2250465465
465
465465465
465465465
465
1.000000.021250.021060.020790.020550.020310.020090.019890.019690.019510.019330.019160.019000.01MC0.01S690.018550.01S420.018280.01816o.oleoc0.017920.026980.017810.017810.017730.017630.017420.017240.017060.016900.01675
1.000000.021060.020790.020550.020310.020090.019890.019690.019510.019330.019160.019000.018840.018690.018550.018420.018280.018160.018040.017920.017810.019610.017810.017730.017630 ~ 01742
0.017240.017060.016900.016750.01661
0.03,511.04,852.24,597.44,513.94,321.54,011.64,093.13,860.93,827.53,6S0.93,524.53,471.53,414.33,353.03,051.03,334.32,898.92,937.52,976.82,764.07,243.5
0.02,379.43,204.06,848.16,002.66,129.2s,ssr.e5,306.95,039.6
0.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00 ~ 0
0.00.00.00.00.00.00.00.00.00.00.00.00.00.00.0
0.0425.6588.2557.3547.2523.8486.3496.1468.0463.9446.2427.2420.8413.9406.4369.8404.2351.4356.1360.8335.0ere.o
0.0288.4388.4830.1727.6743.0673.7643.3610.9
0.039.654.751.950.948.745.246.243.543.241.539.839.238.537.834 '37.632.733.133.631.281.7
495.826.836.177.267.769.162.759.9s6.e
1,130.01,169.61,224.31,276.21,327.11,375.81,421.11,467.31,510.81,554.01,595.51,635.21,674.41,712.91,750.71,785.11,822.71,855.41,888.61,922.11,953.32,035.02,530.82,557.72,593.82,671.12,738.82,807.92,870.62,930.42,987.3
442,728.6446,279.1451,186.0455,835.3460,400.1464,770.4468,827.2472,966.5476,870.94S0,7C1 as
484,463.9488,028.2491,538.9494,991.7498,382.5501,468.0504,839.9507,771.5510,742.0513,752.4516,547.6523,872.9632,972.3635,378.5638,618.6645,543.9651,614.2657,812.6663,433.1668,799.9673,896.3
446.2458.2474.4489.5504.0517.6529.9542.4553.9565.1575.8585.8595.6605.0614.2622.4631.2638.9646.5654.1661.1679.2699.0703.8710.1723.4734.8746.3756.5766.1775.0
0.0463.4
1,105.51,716.82,318.02,895.83,436 '3,986.24,508.25,026.25,526.36,007.66,482.46,950 '7,410.77,834.58,292.78,698.09,108.19,522.99,912.0
10,790.010,790.011,186.C11,628.812,566.913,402.514,253.415,035.115,786.416,505.3
0.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.0
o.o (
o.o (
o.o (
o.o (
o.o (
o.o (
o.o (
o.o (
o.o (
o.o (
o.o (
o.o (
o.o (
o.o (
o.o (
o.o (
o.o (
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FEED AND BLEED BAT (3.25llTX) VOLUHE (oppm to 446ppn)FEED AND BLEED RMST (1950ppm) VOLUME (Oppn to 446ppm)Tol'AL RIIST VOLUME: FEED AND BLEED PLUS MAKE UP
4,485.0 gallons14,336.0 gallons30,841.3
(65 minutes at 69 gpn)(207 minutes at 69 gpm)
PLAHT COOLDOMN TO COLD SNUTDOMN: 11 gpm RCS LEAKAGE;
TABLE 6-12BLENDED NAKEUP FOR 50 F/NR COOLDOMH; BAT AT 3.25 MT X; RNR = rrsppm R ---------(9 gpm SEAL LEAKAGE)---"--
(TINE AVG.SYSTENP. PZR PRESS
((min) (F) (psia)Ti . Tf
SPEC IF I C VOLUNE
(cu.ff./Ibm)Vi Vf
SNRINKAGE BLEND
HASS( ibm) RATIO
BAT VOL 9 RMST VOL oi B/A ADDED TOTAL B/A TOTAL STS.
120 F (gal) 120 F (gal) (ibm) (ibm) MASS (ibm)FINAL CONC TOTAL RCS
(ppm boron) MAKEUP
120 F (gal)
TOTAL PURE TOTAL BAT (
MATER MATER I
120 F (gal) 120 F (gal)(-I
0.00.00.00.00.00.00.00.00.00.0
3,543.95,157.15,585.36,009.56,429.36,825.37,244.77,629.58,017.98,410.08,785.49,370.89,370.S9,867.9
10,279.611,140.711,935.112,741.613,503.414,246.4'14,969.3
0
8.412
12
12
12
12
12
12
12
12
12
12
12
12
12
12
12
12
12
12
00
24
12
24
24
24
24
24
24
547547
547540
530520
510500490
480470460450
440430420
410400
390380370360350350350
330320300280260
240220
520510500
490480
4704604504404304204104003903803703603503503503303203002eo260240220200
540 530
2250
2250
2250
22502250
2250
2250
2250
22502250
22502250
2250
22502250
2250
22502250
2250
22502250
465
465
465
465465
465
465465465465
1.000000.021250.021060.020790.020550.020310.020090.019890 ~ 01969
0.019510 '19330.019160.019000.018840.018690.018550.018420.018280.018160.018040.017920.026980.017810.017810.017730.017630.017420.017240.017060.016900.01675
1.000000.021060.020790.020550.020310.020090.019890.019690.019510.019330.019160.019000.018840.018690.018550.018420.018280.018160.018040 ~ 01792
0.017810.019610.017810.017730.017630.017420.017240.017060.016900.016750.01661
0.04,097.45,700.75,456.05,382.55,199.64,898.54,989.04,765.24,740.34,601.84,453.24,407.84,358.14,304.24,009.04,299.53,870.53,915.63,961.53,754.77,243.5
0.04,369.24,204.58,873.48,049.08,197.27,645.47,413.27,163.6
0.0496.7691.0661.3652.4630.3593.8604.7577.6574.6278.9179.9178.1176.1173.9162.0173.7156.4158.2160.1
151.7292.7
0.0176.5169.9358.5325.2331.2308.9299.5289.4
0.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.00.0
0.0137.6191.2182.6179.8173.C
162.9165.6157.8156.774.546.946.345.745.041.644.839.940.340.838.481.1
495.840.843.090.981.482.976.473.670.6
0.0137.6328.9511.5691.4864.7
1,027.61, '193.3
1,351.11,507.81,582.21,629.11,675.41,721.11,766.01,807.61,852.41,892.21,932.61,973.32,011.72,092.82,588.62,629.42,672.32,763.32,844.72,927.63,00C.O3,077.63, 148.3
442,728.6446,963.6C52,855.5458,494.2464,056.5469,429.4474,490.8479,645.4484,568.5489,465.4494, 141.7498,641.8503,095.8507,499.6511,848.8515,899.4520,243.7524,154.1528,109.9532 112.1
535,905.2SC3,229.9633,030.1637,440.1641,687.6650,651.8658,782.2667,062.3674,784.2682,271.0689,505.2
0.053.8
127.0195.1
'60.5
322.0378.6435.0487.5538.6559.8571.2se2.2592.9603.2612.6622.5631.2639.8648.4656.3673.5714.9721.2728.1742.5755.0767.3778.3788.7798.3
0.0572.3
1,371.32,140.62,901 ~ 1
3,639.34,341.15,053.85,739.56,422.07,087.97,735.68,377.99,014.29,643.9
10,237.910,S67.111,444.212,026.912,615.013,178.214,056.214,056.214,801.815,419.516,711.117,902.719,112.320,255.121,369.722,454.0
o.o (
572 3 I
1 371 3 I
2,140.6 I
2,901.13,639.3 (
4,341.1 I
5,053.8 (
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6,422.O (
3,543.9 I
2,578.5 I
2,792.6 (
3,004.7 (
3,214.6 I
3,412.6 I
3,622.4 (
3,814.7 I
4,009.0 (
4,205.0 (
4,392.r (
4,68S.C (
4,68S.4 (
4,933.9 (
5,139.8 (
s,sro.4 (
5,967.6 I
6,370.8 I
6,751.7 (
7,123.2 (
7,484.7 (
Figure 6-1 CVCS Flow Diagram
I Namd Opereboa -~ kiowa I
lOENT1F IEOLEAKAGE
GPM
UH IOENT 1 f1EOLEAKAGE
RCS
60 GPM
LETDOWN L lNE
LABYR1NTHSEAL
9 GPM
IS NO I SEALGP M LEAKAGE
SEALINJECT lQN
0 GPMHOLOUP TANK
LC V - I I 5A60 GPM
VCT
RMWLCV-IISC 0 GPhl
0 GPMBLENOER
CHAR G lN GL INK
W5 GPM
Z+ GPM
69 GPM
0 GPM
CHAR 6 lN 8PUMPS
0 GPM
0PM
350
FCV-II3A
RWST
BAT
LCV- I ISB
7.0 TECHNICAL SPECIFICATIONS
7.1 RECOMMENDED CHANGES
1. TECHNICAL SPECIFICATION 3/4.1 - REACTIVITY CONTROL SYSTEM
S ecification 3. 1. 1. 1 - Action Statement
Substitute "16 gpm" for "4 gpm" and "3.0 wt./ (5245 ppm)
boron" for "20,000 ppm boron."
Evaluation: The required flow rate is increased by a factorof four to conservatively accommodate the decrease in the
boric acid tank minimum concentration by a factor ofapproximately four (20,000 ppm, or 11.4 weight percent (wt.%),
down to 3.0 weight percent). This adjustment ensures equal
boration capability for shutdown margin recovery. The 16 gpm
will be available via the emergency boration path or the
manual boration path following the modification of FCV-113A.
The required boron concentration is adjusted to reflect the
minimum concentration of 3.0 weight percent to be available
from the boric acid tank.
S ecification 3. 1. 1.2 - Action Statement
Substitute "16 gpm" for "4 gpm" and "3.0 wt.% (5245 ppm)" for"20,000 ppm."
Evaluation: Same as Specification 3. 1. l. l.
S ecification 4. 1.2. 1 - Surveillance Re uirement
Change Surveillance Requirement 4. 1.2. l.a :
"... by verifying that the temperature of the heat traced
portion of the flow path is greater than or equal to 145'F
when a flow path from the boric acid tank is used"
Report No. 849963-MPS-5MISC-003 REV 0 Page 7-1
to read,
"... by verifying that the temperature of the rooms containing
flow path components is greater than or equal to 55'F when a
flow path from the boric acid tanks is used"
Evaluation: The boration system flow path surveillance
requirement is modified to reflect the reduced boric acid
solubility temperature. The maximum boric acid concentration
to be specified is 3.5 weight percent with a solubilitytemperature limit of 50'F. A margin of 5'F is added to thisto make 55'F the critical temperature for boric acid
solubility. The 7 day surveillance interval is justifiedbecause the temperature of the rooms containing boration
system flow paths and components will be provided with an
alarm in the control room. The actions required in the event
that temperature decreases below the critical temperature are
identical to the current specification (i.e., if temperature
is less than 55'F, the flow path in question becomes
inoperable and the appropriate actions carried out).
S ecification 3. 1.2.2 - L'imitin Condition for 0 eration
Add the following words to the footnote:
"from the boric acid transfer pump discharge to the charging
pump suction."
Evaluation: The footnote regarding flow path separation is
modified to reflect the recommended boric acid tank lineup
where all three tanks are interconnected via the transfer pump
suction lines. This lineup maximizes the available volume
from the boric acid tanks with no valve manipulations required
to access the entire inventory. Boric acid tank inventory
control in accordance with Technical Specification 3. 1.2.5
Report No. 849963-HPS-5MISC-003 REV 0 Page 7-2
will ensure that the tanks shared between the two units willhave the total minimum required volume necessary to support
both units. Haintaining the separation criteria for the
remaining flow path from the boric acid transfer pumps to the
charging pumps assures the appropriate level of activecomponent redundancy for each unit.
S ecification 4. 1.2.2 - Surveillance Re uirement
Change Surveillance Requirements 4. 1.2.2.a :
"... by verifying that the temperature of the heat traced
portion of the flow path from the boric acid tanks is greater
than or equal to 145'F when it is a required water source;"
to read,
"... by verifying that the temperature of the rooms containing
flow path components are greater than or equal to 55'F when a
flow path from the boric acid tank is used;"
Substitute "16 gpm" for "4 gpm" in Surveillance Requirement
4.1.2.2.c
Evaluation: Same as Specification 4.1.2. 1. This change also
makes Surveillance Requirement 4. 1.2.2.c consistent with
Limiting Conditions for Operation 3. 1.1. 1 and 3. 1. 1.2.
S ecification 3. 1.2.4 - Limitin Condition for 0 eration
For the Horic Acid Storage System (3. 1.2.4.a) change:
1. "A minimum indicated borated water volume of 500
gallons,"
Report No. 849963-HPS-5HISC-003 REV 0 Page 7-3
to read,
1. "A minimum indicated borated water volume of 2,900
gallons per unit,"
change:
2. "A boron concentration between 20,000 ppm and 22,500
ppm, and"
to read,
2. "A boron concentration between 3.0 wt./ (5245 ppm) and
3.5 wt./ (6119 ppm), and"
change:
3. "A minimum solution temperature of 145'F."
to read,
3. "A minimum boric acid tanks room temperature of 55'F."
Evaluation: The boric acid tank operability requirements are
revised to reflect the analysis of Reference 1. A minimum
volume of 2,900 gallons per unit is specified, and includes an
instrument accuracy of 2.5%%u of full range for the tank level
instrument. Unusable volume is not accounted for here since
the tank level instrumentation will have its indicated range
calibrated to account for unusable volumes at the bottom ofthe tank. The concentration is limited to the recommended
band of 3.0 weight percent to 3.5 weight percent. The
temperature limit corresponds to the solubility limit for 3.5
weight percent boric acid (50'F) with 5'F added margin.
Report No. 849963-MPS-5HISC-003 REV 0 Page 7-4
The minimum refueling water storage tank volume is not changed
since this is known to be conservative from the analysis ofReference 1.
S ecification 4. 1.2.4 - Surveillance Re uirement
Change Surveillance Requirement 4.1.2.4.a.3):
"Verifying the boric acid storage tank solution temperature
when it is the source of borated water."
to read,
"Verifying that the temperature of the boric acid tanks room
is greater than or equal to 55'F, when it is the source ofborated water."
Evaluation: The borated water source surveillance requirement
is modified to reflect the reduced boric acid solubilitytemperature. The maximum boric acid concentration to be
specified is 3.5 weight percent with a solubility temperature
limit of 50'F. A margin of 5'F is added to this to make 55'F
the critical temperature for boric acid solubility. The 7 day
surveillance interval is justified because the temperature ofthe room containing the boric acid tanks will be provided with
an alarm in the control room. Action statement requirements
for temperatures below 55'F remain identical to the current
required actions for temperatures below the current limit of145'F. In this respect, the required actions remain as
limiting as the current Technical Specifications.
S ecification 3. 1.2.5 - Limitin Condition for 0 eration
For the Boric Acid Storage System (3. 1.2.5.a) change:
1. "A minimum indicated borated water volume of 3080
gallons,"
Report No. 849963-MPS-5NISC-003 REV 0 Page 7-5
to read,
1. "A minimum indicated borated water volume in accordance
with Figure 3. 1.2.5,"
change:
2. "A boron concentration between 20,000 ppm and 22,500
ppm, and"
to read,
2. "A boron concentration in accordance with Figure
3. 1.2.5, and"
change:
3. "A minimum solution temperature of 145'F."
to real,
3. "A minimum boric acid tanks room temperature of 55'F."
Action Statement
Add an asterisk (*) to ACTION 'a'o reference a note at the
bottom of the page.
Add note at the bottom of the page:
"* If this action applies to both units simultaneously, be in
at least HOT STANDBY within the next 12 hours."
Add the following:
I
Report No. 849963-HPS-5MISC-003 REV 0 Page 7-6
C. With the boric acid tank inventory concentration greaterthan 3.5 wt./, verify that the boric acid solutiontemperature for boration sources and flow paths isgreater than the solubility limit for the concentration.
Add Figure 3.1.2.5 as provided
Evaluation: The boric acid tank operability requirements
regarding volume and concentration will consist of a
concentration vs. volume curve. Note that the volumes
represent the combined volumes in all three tanks withallowance for the minimum required volume for two operatingunits (Modes 1-4) and for one operating and one shutdown unit(Mode 5 or 6). The minimum temperature for boric acid tank
operability coincides with the solubility limit for 3.5 weight
percent boric acid (50'F) plus 5'F margin. ACTION times allow
for an orderly sequential shutdown of both units when the
inoperability of a component(s) affects both units with equal
severity. When a single unit is affected, the time to be in
HOT STANDBY is 6 hours. When an ACTION statement requires a
dual unit shutdown, the time to be in HOT STANDBY is 12 hours.
S ecification 4. 1.2.5 - Surveillance Re uirements
Change Surveillance Requirement 4.1.2.5.a.3) :
"Verifying the Boric Acid Storage System solution temperature
when it is the source of borated water."
to read,
"Verifying that the temperature of the boric acid tanks room
is greater than or equal to 55'F, when it is the source ofborated water."
Report No. 849963-HPS-5NISC-003 REV 0 Page 7-7
Evaluation: The borated water source surveillance requirement
is modified to reflect the reduced boric acid solubilitytemperature. The maximum boric acid concentration to be
specified is 3.5 weight percent with a solubility temperature
limit of 50'F. A margin of 5'F is added to this to make 55'F
the critical temperature for boric acid solubility. The 7 day
surveillance interval is justified because the temperature ofthe room containing the boric acid tanks will be provided withan alarm in the control room. Action statement requirements
for temperatures below 55'F remain identical to the currentrequired actions for temperatures below the current limit of145'F. In this respect, the required actions remain as
limiting as the current technical specifications.
S ecification 3. 1.2.6 - Limitin Condition for 0 eration
Add note at the bottom :
"This is no longer applicable once boric acid tanks inventoryand boric acid source and flow path inventories have been
diluted to less than or equal to 3.5 weight percent (wt.%)."
Evaluation: This specification is retained to allow the
concentration transition (from 12 weight percent boric acid to3.5 weight percent boric acid) of the boric acid tank
inventory and boric acid source and flow path inventories.The boric acid tank operability requirements regarding volume
and concentration will remain in accordance with specification3. 1.2.5. Action statement requirements regarding temperature
and heat tracing remain identical to the current Technical
Specifications. As identified in reference 1, a reduction in
the boric acid concentration corresponds to a reduction in the
solubility limit. FPL remains conservative by maintaining the
boric acid storage tank and flow path temperatures greater
than the appropriate solubility limit.
Report No. 849963-HPS-5MISC-003 REV 0 Page 7-8
2. TECHNICAL SPECIFICATION 3/4.9 - REFUELING OPERATIONS
S ecification 3.9. 1 - Action Statement
Substitute "16 gpm" for "4 gpm" and "3.0 wt.% (5245 ppm)" for"20,000 ppm"
Evaluation: Same evaluation as provided for in Specification
3.1.1.1.
3. TECHNICAL SPECIFICATION 3/4.10 - SPECIAL TEST EXCEPTIONS
S ecification 3. 10. 1 - Action Statement
Substitute "16 gpm" for "4 gpm" and "3.0 wt.% (5245 ppm)" for"20,000 ppm"
Evaluation: Same evaluation as provided for in Specification3.1.1.1.
4. TECHNICAL SPECIFICATIONS BASES 3/4.1 - REACTIVITY CONTROL
SYSTEMS
S ecification Bases 3 4. 1. 1 - Boration Control
Substitute "16 gpm" for "4 gpm" and "3.0 wt.% (5245 ppm)" for"20,000 ppm"
Evaluation: The increase in the required flow rate by a
factor of four (4 gpm to 16 gpm) conservatively accommodates
the decrease in the minimum boric acid tank concentration by a
factor of approximately four (20,000 ppm, or 11.4 weight
percent, down to 3.0 weight percent). This adjustment assures
equal minimum boration capability for shutdown margin recovery
as compared to the current capability at 11.4 weight percent.
Report No. 849963-NPS-5HISC-003 REV 0 Page 7-9
The capability to restore the shutdown margin with one
OPERABLE charging pump is consistent with the current
Technical Specifications.
S ecification Bases 3 4. 1.2 - Boration S stems
o Delete the wording:
"(5) associated Heat Tracing Systems, and (6) an
emergency power supply from OPERABLE diesel generators."
Evaluation: Wording revised to reflect the basis ofthis program and the Emergency Power System (EPS)
Enhancement Project submittal.
Insert the wording:
"ACTION times allow for an orderly sequential shutdown
of both units when the inoperability of a component(s)
affects both units with equal severity. When a singleunit is affected, the time to- be in HOT STANDBY is 6
hours. When an ACTION statement requires a dual unitshutdown, the time to be in HOT STANDBY is 12 hours."
Evaluation: Wording inserted to reflect the basis of
the previous EPS Enhancement Project submittal.
o Delete the wording:
"with independent power supplies", and
"However, the ACTION Statement restrictions allow 7 days
to restore an inoperable pump provided that two charging
Report No. 849963-HPS-5MISC-003 REV 0 Page 7-10
pumps are available. This restriction is acceptable
based on the low probability of losing the power source
common to both charging pumps."
Substitute the words "Each bus" for "The bus" and the
words "a startup transformer." for "the startuptransformer."
Evaluation: Wording revised to reflect the basis of the
previous EPS Enhancement Project submittal.
o Delete the wording:
"... BOL from full power equilibrium xenon conditions
and require 3080 gallons of 20,000 PPH borated water
from the boric acid storage tanks or 320,000 gallons of1950 PPN borated water from the refueling water storage
tank (RWST)."
and replace with the wording:
"... EOL peak xenon conditions without letdown such thatboration occurs only during the makeup provided forcoolant contraction. This requirement can be met for a
range of boric acid concentrations in the boric acid
tank and the refueling water storage tank. The range ofboric acid tank requirement is defined by Technical
Specification 3. 1.2.5."
o Substitute "2,900 gallons of at least 3.0 wt.% (5245
ppm) borated water per unit" for "500 gallons of 20,000
ppm borated water"
Report No. 849963-HPS-5HISC-003 REV 0 Page 7-11
Substitute the wording "... requirement of 55'F and
corresponding surveillance intervals..." for the wording
"... of the redundant heat tracing channels..."
o Insert the wording - "The temperature limit of 55'F
includes a 5'F margin over the 50'F solubility limit of3.5 wt.%%u boric acid. Portable instrumentation may be
used to measure the temperature of the rooms containing
boric acid sources and flow paths."
o Add the footnote - "This is no longer applicable once
boric acid tanks inventory and boric acid source and
flow path inventories have been diluted to less than or
equal to 3.5 weight percent."
Evaluation: The basis for the boric acid tank minimum
volume required for modes 1 through 4 is modified to
reflect the analyses of Reference 1. Specifically, the
worst case expected plant boration requirement occurs at
EOL peak xenon conditions without letdown such thatboration occurs only during the makeup provided forcoolant contraction. This requirement can be met for a
range of boric acid concentrations in the boric acid
tank and the refueling water storage tank. This range
is bounded by Figure 3. 1.2.5.
Below 200'F, the boric acid tank minimum volume
requirement is based on the minimum volume of 3.0 weight
percent boric 'acid required to maintain a 1.0/ ak/k
shutdown margin during a cooldown from 200'F to 140'F.
(The analysis of Reference 1 conservatively assumed
135'F as the cooldown endpoint.) The refueling water
storage tank minimum volume with RCS temperature less
than 200'F remains unchanged since it is conservative
with respect to the cooldown analysis. Reference to
Report No. 849963-MPS-5MISC-003 REV 0 Page 7-12
heat tracing in this section is deleted since it isanticipated that all heat tracing will be removed. The
basis of the 55'F temperature limit is established as
the 50'F solubility limit for 3.5 weight percent boricacid plus 5'F margin. Continuous surveillance of the
temperature of the rooms containing boration system flowpaths and components is provided and verified by an
alarm in the control room. A footnote is added to the
heat tracing discussion. This identifies the heat
tracing as not being applicable once boric acid tanks
inventory and source and flow path inventories have been
diluted to less than 3.5 weight percent.
5. TECHNICAL SPECIFICATION BASES 3/4.9 - REFUELING OPERATIONS
S ecification 3 4.9. 1 - Boron Concentration Bases
Substitute the wording "16 gpm of 3.0 wt.h (5245 ppm)" for "4
gpm of 20,000 ppm".
Evaluation: Same as Specification Bases 3/4. 1. 1
7.2 NO SIGNIFICANT HAZARDS EVALUATION
The proposed changes have been deemed not to involve a significanthazards consideration focusing on the three standards set forth in
10 CFR 50.92(c) as quoted below:
The Commission may make a final determination, pursuant to the
procedures in 50.91, that a proposed amendment to an operating
license for a facility licensed under 50.21(b) or 50.22 or for a
testing facility involves no significant hazards considerations, ifoperation of the facility in accordance with the proposed amendment
would not:
Report No. 849963-HPS-5HISC-003 REV 0 Page 7-13
1. Involve a significant increase in the probability or
consequences of an accident previously evaluated; or
2. Create the possibility of a new or different kind of accident
from any accident previously evaluated; or
3. Involve a significant reduction in a margin of safety.
It has been determined that the activities associated with thisamendment request do not meet any of the significant hazards
consideration standards of 10 CFR 50.92(c) and, accordingly, a no
significant hazards consideration finding is justified. A
discussion of each of the above three significant hazards
consideration standards is provided below.
Introduction
The current Turkey Point CVCS design employs three boric acid tanks,
containing 12 weight percent (wt.l) boric acid, for the two units.One tank is dedicated to each unit and the third is available as a
backup for either dedicated tank. Each dedicated tank has adequate
volume to store the cold shutdown boric acid volume required for one
unit. The boric acid tanks provide a source of concentrated boric
acid to the reactor to offset slow reactivity changes caused by
normal changes in power level, or to establish hot shutdown, cold
shutdown or refueling shutdown conditions. The safety function ofthe boric acid tanks is to maintain adequate boric acid volume and
concentration to borate the RCS to a cold shutdown concentration at
any time during the core cycle, with a shutdown margin consistent
with the Technical Specifications.
A reduction in the boric acid concentration to 3.0 to 3.5 weight
percent provides the opportunity to delete the system heat tracing
presently required for 12 weight percent boric acid. The basis fordeletion is the corresponding reduction in the solubility
Report No. 849963-MPS-5MISC-003 REV 0 Page 7-14
temperature from 135'F for 12 weight percent boric acid to 50'F for3.5 weight percent boric acid. At this lower solubilitytemperature, the normally occurring ambient room temperatures are
adequate to maintain fluid temperatures above the solubility limitrather than relying on tank heaters or heat tracing.
This proposed amendment improves the availability of the boration
system and, therefore, improves plant safety. It also reduces
routine maintenance requirements by eliminating the need for boricacid tank internal heaters and boration flow path heat tracingchannels. Furthermore, potential problems associated with boricacid crystalization, flow path blockage, and component corrosion are
significantly reduced.
Evaluation
The following evaluation demonstrates that the proposed amendment
involves no significant hazards considerations.
1. Involve a si nificant increase in the robabilit or
conse uences of an accident reviousl evaluated.
The operation of the facility in accordance with the proposed
changes does not involve a significant increase in the
probability or consequences of any accident previouslyevaluated. Deleting the requirement for a heat tracingcircuit by reducing the boron concentration in the boric acid
tank is accounted for by increasing the volume of boric acid
solution that must be contained in the tanks and also by
crediting borated water from the refueling water storage tank.
Since the components (or their function) necessary to perform
a safe shutdown have not been changed or modified, this change
does not significantly increase the probability or
consequences of any accident previously evaluated. In
Report No. 849963-HPS-5HISC-003 REV 0 Page 7-15
addition, technical specification controls on the boric acid
tank temperature and boron concentration ensure that the lackof heat tracing does not result in precipitation of the boron.
Credit is not taken for boron addition to the RCS from the
boric acid tanks for the purpose of reactivity control in theaccidents analyzed in Chapter 14 of the Final Safety AnalysisReport. Response to such events as steam line break, over-
cooling, boron dilution, etc. will not be affected by a
reduction in the boric acid tank concentration.
The action statements associated with Technical Specification3. l. l. 1 currently require that boration be commenced atgreater than 4 gallons per minute using a solution of at least20,000 ppm boron in the event that shutdown margin is lost.This Specification has been changed to 16 gpm at 3.0 weight
percent (5245 ppm) to accomplish the same minimum borationrate. A plant modification to flow control valve FCV-113A
will increase blended makeup capacity and assure this system's
capability to deliver this flow rate. Boration via the
emergency boration flow path already exits at a rate of 60 gpm
(nominal).
2. Create the ossibilit of a new or different kind of accident
from an accident reviousl evaluated.
The operation of the facility in accordance with the proposed
changes does not create the possibility of a new or differentkind of accident from any accident previously evaluated. This
is because such operation will not increase the likelihood ofboric acid source or flow path failure nor will such failuresinitiate any new or different kind of accident from any
previously evaluated. The boron dilution analysis performed
for Turkey Point Units 3 and 4 is not impacted by a reduction
from a nominal 12 weight percent boric acid to 3.0 to 3.5
Report No. 849963-MPS-5MISC-003 REV 0 Page 7-16
weight percent. The boron concentration in the boric acid
tanks is greater than any anticipated RCS boron concentration,thus, an inadvertent RCS boron dilution due to the addition ofboric acid from the boric acid tanks is precluded.
The reason for requiring a heat tracing circuit was to ensure
that the dissolved boric acid remained in solution and, hence,
available for injection into the RCS to adjust core reactivitythroughout core life. By lowering the boron concentration toa maximum of 3.5 weight percent, chemical analyses have shown
there is no possibility of the boron precipitating out ofsolution as long as the temperature of the boric acid solutionremains above 50'F. Normal ambient temperatures in the
vicinity of these components remain above this temperature.
Therefore, there is no longer a need for heat tracing. Since
the boron will be in solution when the boric acid tank flowpaths are credited for reactivity control during a cooldown tocold shutdown scenario, heat tracing is no longer required tomaintain the boric acid storage system operable. In
conclusion, this change does not create the possibility of a
new or different kind of accident from those previouslyevaluated.
3. Involve a si nificant reduction in a mar in of safet .
The operation of the facility in accordance with the proposed
Technical Specification changes does not involve a significantreduction in the margin of safety. The intent of these
Technical Specifications is to ensure that there are two
independent flow paths from the two independent borated water
sources (boric acid tanks and refueling water storage tank) to
the RCS to allow control of core reactivity throughout core
life. This requires that sufficient quantities of boron be
stored in the tanks, and that this borated water can be
Report No. 849963-HPS-5HISC-003 REV 0 Page 7-17
delivered to the RCS when required. Reducing the maximum
boric acid concentration to less than or equal to 3.5 weightpercent has been compensated for by increasing the requiredvolumes of borated water. Elimination of the separationcriteria for the flow paths for the two units between thethree shared boric acid tanks and the boric acid transferpumps has been compensated for by technical specificationvolume control that accounts for the needs of both units.
In addition to the boric acid transfer pumps delivering theboric acid tank contents to the charging pumps, the charging
pumps also can take suction from the refueling water storagetank. Since these independent boration capabilities controlthe RCS boron inventory, the original licensing basis of theplant does not require the boric acid tanks to meet singlefailure criteria.
Additionally, reducing the maximum boron concentration allowsa deletion of the requirement to heat trace the boric acid
storage system since chemical analyses have shown that a 3.5weight percent solution of boric acid will remain in solutionat temperatures above 50'F. An operability requirement of55'F minimum temperature for the rooms containing borationsources and flow paths includes a 5'F margin above the
solubility limit of 50'F. Technical Specification controls on
the boric acid tank and boration flow path room temperatures
and boron concentration ensure that a lack of heat tracingdoes not result in precipitation of the boron.
In conclusion, the reduction of boric acid concentration and
the deletion of heat tracing in the Horic Acid Makeup System
does not cause a significant reduction in the margin of safetyfor this plant.
Report No. 849963-MPS-5MISC-003 REV 0 Page 7-18
~Summar
In summation, it has been shown that the proposed
modifications and proposed Technical Specifications do not:
I. Involve a significant increase in the probability orconsequences of an accident previously evaluated; or
2. Create the possibility of a new or different kind ofaccident from any accident previously evaluated; or
3. Involve a significant reduction in a margin of safety.
Therefore, it is determined that the proposed amendment
involves no significant hazards considerations.
Report No. 849963-MPS-5MISC-003 REV 0 Page 7-19
8.0 SAFETY EVALUATION
Operation with reduced boric acid concentration in a manner similarto that analyzed in Sections 5 and 6 will involve a change in themanner in which the facility is operated as compared to the currentdescriptions in the updated Final Safety Analysis Report (FSAR).
Reference 10.3 was reviewed in detail to identify the necessary
changes to reflect full implementation of reduced boric acidconcentration. Although, changes are required in several locations,the changes consist of the following basic elements:
1. Revision of boric acid tank concentration range (3.0 to 3.5weight percent);
2. Revision of boric acid tank minimum volume design basis toinclude:
a. Boration completed in conjunction with the makeup forcoolant contraction during cooldown,
b. Credit given to refueling water storage tank volume;
3. Revision of alternate shutdown capability (boration rate);
4. Deletion of heat tracing and boric acid tank heaters; and,
5. Revision of boric acid evaporator bottoms concentration.
Specific descriptions of each of these changes is provided in
Section 8. 1. This will be followed by a No Unreviewed Safety
guestion evaluation in Section 8.2.
8.1 RECOMMENDED FSAR CHANGES
Recommended markups of the specific pages to be changed are provided
in Appendix 7. The following is a page by page discussion of the
recommended changes.
Report No. 849963-MPS-5MISC-003 REV 0 Page 8-1
Pa e 1.3-13
The design basis of the minimum volume maintained in the boric acidtank is revised to reflect the analyses of Section 5.0.Specifically, the minimum volume maintained in this tank is thatvolume necessary to increase the RCS boron concentration during thecourse of a cooldown, through makeup for coolant contraction alone,such that subsequent use of the refueling water storage tank forcontraction makeup will maintain adequate shutdown margin throughoutthe remaining cooldown.
Additionally, the alternate shutdown capability is revised toreflect the analysis of Section 6.6.3. Less than forty minutes offeed and bleed would be required to raise the RCS boron
concentration from 1100 ppm to 1295 ppm. Since both sixteen minuteperiods listed in the FSAR are feed and bleeds per Reference 10. 1,forty minutes should be required to accomplish the second borationrequirement to compensate for xenon decay.
Outside power is corrected to Offsite power and reference to hotshutdown is corrected to hot standby.
Pa e 3.1.2-6
Same as page 1.3-13.
Pa e 8.2-18
Reference to the boric acid tank heaters is deleted since these
heaters will be electrically deenergized.
Pa e 9.2-3
Same as page 1.3-13.
Report No. 849963-MPS-5MISC-003 REV 0 Page 8-2
Pa e 9.2-6
The boric acid tank concentration is revised to 3.0 to 3.5 weightpercent and all reference to heat tracing is deleted. It isanticipated that all heat tracing circuits will be disconnectedsince the ambient temperatures within the auxiliary building willmaintain boric acid tank and boration flow path temperatures above
the solubility limit of 50'F.
Pa e 9.2-6a
Same as page 9.2-6.
Pa e 9.2-7
Same as page 9.2-6.
Pa e 9.2-8
Operation of the boric acid evaporator must be revised such that theboric acid that remain's within the evaporator as the bottoms of thedistillation process does not concentrate above the boric acid tankcontrol band of 3.0 to 3.5 weight percent.
Pa e 9.2-11
The discussion of boration without letdown is modified toincorporate the analyses of Section 5.0 and Section 6.6.3.Specifically, since the boric acid tank concentration is reduced by
a factor of four, the volume required to be charged using the
available volume in the pressurizer has increased by a factor offour. Achieving boration to the cold shutdown concentration through
this method, therefore, is not possible with reduced concentrations.Per the analysis of Section 6.6.3, however, boration to hot zero
power is achievable using the available volume in the pressurizer.
Report No. 849963-HPS-5MISC-003 REV 0 Page 8-3
Boration to cold shutdown is still achievable without letdown usingthe methodology outlined in Section 5.0. Specifically, if boricacid is injected to maintain constant pressurizer level during a
cooldown to cold shutdown (using a boric acid tank and the refuelingwater storage tank to make up for coolant contraction) sufficientboric acid will be added to the RCS to maintain the requiredshutdown margins.
Pa e 9.2-23
The design basis of the boric acid tank minimum volume is modifiedper the discussion for page 1.3-13 changes. Batching tankcapabilities are revised to reflect the impact of reduced
concentrations.
Pa e 9.2-24
The batching tank steam jacket design basis is modified to maintainthe boric acid batching solutions above the solubility limit withoutspecific reference to temperature limits. The addition of the perunit qualifier to the boric acid transfer pump description reflectsthe actual redundancy of the pumps.
Pa e 9.2-27
Same as page 9.2-8.
Pa e 9.2-29
Reference to boration system heat tracing is deleted since it isanticipated that all heat racing will be removed. This isachievable since the normally expected ambient temperatures withinthe auxiliary building will maintain system temperatures above thesolubility limit of
50'F.'eport
No. 849963-MPS-5MISC-003 REV 0 Page 8-4
Pa e 9.2-30
Same as page 9.2-29.
Pa e 9.2-31
Same as page 9.2-29.
Table 9.2-2
The maximum rate of boration is revised based on the analysis ofSection 6.2. A feed and bleed of 60 gpm will establish a borationrate of 5.4 ppm per minute starting from the 1800 ppm initialconcentration listed in the table. Should the available volume inthe pressurizer be utilized in accordance with the analysis ofSection 6.6.3, a boration of 195 ppm in 29.4 minutes (6.6 ppm perminute) is achievable starting from the assumed maximum BOC
concentration of 1100 ppm. The equivalent cooldown rate was dividedby the same factor of reduction shown for the maximum boration rate.
The boric acid tank minimum volume is revised per the analyses ofSection 5.0 as discussed for changes to page 9.2-3. A curve similarto the recommended technical specification is suggested forinclusion in the FSAR.
Table 9.2-3
The boric acid tank is being modified to maximize the usable volume.
This table should be updated once the maximum available volume isidentified.
Additionally, the refueling water storage tank is added to the listof tanks available to the CYCS. This reflects the possible use ofthis tank for contraction makeup during the design basis cooldown
analyzed in Section 5.0.
Report No. 849963-HPS-5MISC-003 REV 0 Page 8-5
8.2 NO UNREVIEMED SAFETY QUESTIONS DETERHINATION
Introduction
The current Turkey Point CVCS design employs three boric acid tankscontaining 12 weight percent boric acid shared between the two
units. One tank is currently dedicated to each unit and the thirdis currently available as a backup for either dedicated tank. Each
dedicated tank has adequate volume to store the cold shutdown boricacid volume required for one unit.
The boric acid tanks provide a source of concentrated boric acid tothe reactor to offset slow reactivity changes caused by normal
changes in power level, or to establish hot shutdown, cold shutdown
or refueling shutdown conditions. The safety function of the boricacid tanks is to maintain adequate boric acid volume and
concentration to borate the RCS to a cold shutdown concentration atany time during the core cycle, with a shutdown margin consistentwith the technical specifications.
The high boron solubility temperature required by 12 weightpercent boric acid (135'F minimum) is maintained by internal tankheaters and flow path heat tracing. The need to perform maintenance
on the heaters and heat tracing affects the'availability of the
boric acid tanks. Therefore, the capability to perform maintenance
on the boric acid tank without taking the units off-line was
considered necessary for the present CVCS design. This capabilityis currently accomplished by the backup tank. The third boric acid
tank, as a backup tank, permits either dedicated tank to be taken
out-of-service for maintenance while both units remain on-line.
A reduction in the boric acid concentration to 3.0 to 3.5 weight
percent provides the opportunity to delete system heat tracing,presently required for 12 weight percent boric acid. The basis fordeletion is the corresponding reduction in the solubility
Report No. 849963-HPS-5HISC-003 REV 0 Page 8-6
temperature from 135 F for 12 weight percent boric acid to 50 F for3.5 weight percent boric acid. At this lower concentration, thenormally occurring ambient room temperatures are adequate tomaintain fluid temperatures above the solubility limit without usingtank heaters or heat tracing.
The proposed modification would improve plant availability and
reduces maintenance requirements by eliminating the demand of theboric acid tank internal heaters and boration flow path heat tracingchannels.
Evaluation
An evaluation of the Turkey Point CVCS boration capabilities was
completed in Sections 5.0 and 6.0 of this report. Specifically, theanalysis of Section 5.0 justified a reduction in the concentrationof boric acid maintained in the boric acid tanks from 12 weightpercent down to a range of 3.0 to 3.5 weight percent. This was
accomplished by demonstrating that the required shutdown margin
could be maintained during a cooldown if boration was accomplished
in conjunction with the makeup for coolant contraction. This
analysis was completed with the following significant changes from
the current manner in which a cooldown to cold shutdown isaccomplished:
1. Basis: Cooldown transient initiated from peak xenon
concentration (8 hours) without the use of letdown;
2. Heans: Boration accomplished only through the makeup provided
for coolant contraction; and,
3. Sources: Credit given to the availability of refueling water
storage tank volume to supplement the boron addition of the
boric acid tanks.
Report No. 849963-HPS-5MISC-003 REV 0 Page 8-7
4. Configuration: Tank lineup consisting of all three tanks linedup to the common suction header for the boric acid transferpumps.
The acceptability of these considerations from the perspective ofplant safety is reviewed in the following safety evaluation. The
considerations discussed above, in conjunction with the reduced
boric acid tank inventory concentrations, have been found not toraise an unreviewed safety question as documented in the following.
As defined in IOCFR50.59, an unreviewed safety question exists: (i)if the probability of occurrence or the consequences of an accidentor malfunction of equipment important to safety previously evaluated
V
in the Updated Final Safety Analysis Report (FSAR) may be increased;or (ii) if a possibility of an accident or malfunction of a
different type than any previously evaluated in the FSAR may be
created; or (iii) if the margin of safety as defined in the basis ofany Technical Specification is reduced.
In accordance with IOCFR50.59, the following evaluation serves todetermine whether this modification constitutes an unreviewed safetyquestion:
1. Does the ro osed chan e increase the robabilit of occurrence
of an accident reviousl evaluated in the FSAR?
The probability of occurrence of an accident previouslyevaluated in the FSAR will not increase because thismodification does not affect any equipment whose malfunction ispostulated in the FSAR to initiate an accident. Specifically,maintenance of shutdown margin in accordance with technicalspecification limits during plant cooldowns assures the
acceptability of reactivity excursions analyzed in the FSAR.
Borating the plant through the makeup for coolant contractionduring a plant cooldown has been shown to maintain RCS boron
Report No. 849963-NPS-5NISC-003 REV 0 Page 8-8
concentration well above that required to maintain adequate
shutdown margin.
The boron dilution analysis performed for Turkey Point Units 3
and 4 is not impacted by a reduction in boric acidconcentration from a nominal 12 weight percent down to 3.0 to3.5 weight percent. The boron concentration in the boric acidtanks is greater than any anticipated RCS boron concentrationand thus, an inadvertent RCS boron dilution due to the additionof boric acid from the boric acid tanks is precluded.
Therefore, the probability of an accident previously evaluatedin the FSAR would not be increased.
2. Does the ro osed chan e increase the conse uences of an
accident reviousl evaluated in the FSARP
The consequences of an accident previously evaluated in theFSAR will not increase because the equipment affected by these
modifications is not credited for operation during any
accidents analyzed in the FSAR. System operation ormalfunction will not impact the consequences of any of these
analyses nor will it affect any other equipment whose
malfunction could adversely affect any safety relatedstructures, systems, or components. With the proposed
modification to FCV-113A, an equivalent boration capability has
been retained such that response to any event requiringemergency boration is not adversely impacted.
Therefore, the consequences of an accident previously evaluated
in the FSAR would not be increased.
Report No. 849963-HPS-5NISC-003 REV 0 Page 8-9
3. Does the ro osed chan e increase the robabilit of an
occurrence of a malfunction of e ui ment im ortant to safetreviousl evaluated in the FSAR7
The pr'oposed reduction in boric acid concentration for TurkeyPoint Units 3 and 4, will not adversely impact the structuralintegrity or performance capability of the boric acid tanks,heaters, pumps, and associated piping, valves and
instrumentation. A reduction in the boric acid concentrationto 3.0 to 3.5 weight percent provides the opportunity to deletesystem heat tracing, and subsequently, provides the potentialto reduce maintenance requirements. In addition, since thecorrosive property of boric acid is accelerated at higherconcentrations and temperatures, nominal 3.25 weight percentboric acid actually decreases the potential for corrosion ofequipment, valves and piping surfaces.
Thus, the probability of a malfunction of equipment importantto safety previously evaluated in the FSAR would not be
increased.
4. Does the ro osed chan e increase the conse uences of a
malfunction of e ui ment im ortant to safet reviouslevaluated in the FSAR?
The consequences of a malfunction of equipment important tosafety are not increased by this modification from thatpreviously evaluated in the FSAR. This is because the
oper ation of the equipment affected by this modification is not
credited in any of the equipment malfunctions analyzed in the
safety analysis report. The consequences of these events,
therefore, remain unchanged.
Therefore, the boric acid tanks continue to provide a source ofconcentrated boric acid to the reactor for offsetting slow
Report No. 849963-MPS-5MISC-003 REV 0 Page 8-10
reactivity changes caused by normal changes in power level, orto establish hot shutdown, cold shutdown or refueling shutdown
conditions, and the consequences of a malfunction of equipment
important to safety previously evaluated in the FSAR would not
be increased.
5. Does the ro osed chan e create the ossibilit of an accidentof a different t e than an reviousl evaluated in the FSAR?
While this approach modifies the system configuration(interconnection and sharing of all three tanks) and the design
basis of the boration sources, it does not introduce failuremodes of a different type than any previously analyzed in the
FSAR. Specifically, the likelihood of a boric acid tank,transfer pump, flow path or charging pump failure is not
increased. In addition, none of these failures initiates a new
and different kind of accident from any previously evaluated.
Therefore, there is no possibility that an accident may be
created that is different from any already evaluated in the
FSAR.
6. Does the ro osed chan e create the ossibilit of .a
malfunction of e ui ment im ortant to safet of a differentt e than an reviousl evaluated in the FSAR?
While this approach modifies the system configuration(interconnection and sharing of three tanks) and the design
basis of the boration sources, it does not introduce failuremodes of a different type than any previously analyzed in the
FSAR.
A reduction from nominal 12 weight percent boric acid to 3.0 ton
3.5 weight percent boric acid concentration will not adversely
impact the structural integrity or performance capability of
Report No. 849963-HPS-5MISC-003 REV 0 Page 8-11
the boric acid tanks, heaters, pumps, associated piping,valves, instrumentation, or related equipment. A reduced boricacid concentration provides the opportunity to delete systemheat tracing. Elimination of the technical specificationrequirement for heat tracing will eliminate the time spent inaction statements due to inoperability of the heat tracingchannels.
In addition, a reduction in boric acid concentration reduces
the potential for precipitation of boric acid crystals.Elimination or reduction of precipitation will reduce
maintenance requirements on equipment susceptible to boron
precipitation.
Therefore, the possibility of a malfunction of equipment
important to safety different than any already evaluated in theFSAR will not be created.
7. Does the ro osed chan e reduce the mar in of safet as definedin the basis for an Technical S ecifications?
The design basis of the boration subsystem of the CVCS is toprovide a sufficient volume of boric acid at a concentrationthat will maintain shutdown margin during a design basiscooldown. While the design basis cooldown has been modifiedwith regard to boration methodology, the design basis, functionor operating logic of any safety related equipment has not been
changed. Additionally, this change does not adversely affectany other safety related structures, systems and components.
Therefore, this modification does not reduce the margin ofsafety as defined in the bases for the TechnicalSpecifications. The technical specifications of particularinterest include: 3.4. 1. 1, Boration Control; 3/4. 1.2, Boration
systems; 3/4.9. 1, Boron Concentration (Refueling); and 3/4. 10. 1
Shutdown margin (Special Test Exceptions). Changes to these
Report No. 849963-HPS-5NISC-003 REV 0 Page 8-12
Specifications have been recommended in Section 7.0 and are
required to implement the analysis results of Section 5.0.
Complete implementation of the boric acid concentrationreduction will entail some plant modification. Specifically,the proposed flow control valve modification increases its flowcapacity so that the boration rate achievable through thisvalve for the normal blended or manual boration flowpath atleast matches the current boration rate achievable with higherboric acid concentrations.
Removal of heat tracing does not lower any margins of safetyfor boration source and flow path requirements because theconcentration of boric acid has been decreased sufficiently toallow Auxiliary Building ambient temperatures to maintain boron
solubility. The 5'F margin on top of the 50'F solubility limittemperature for the maximum allowable boric acid concentrationassures that ambient temperatures will maintain source and flowpath operability with the same margin of safety as theinstalled heat tracing used for 12 weight percent boric acid.
In addition to the boric acid transfer pumps delivering the
boric acid tank contents to the charging pumps, the charging
pumps also can take suction from the refueling water storagetank. Due to these redundant sources of boration capabilityprovided by the Turkey Point CVCS to control the RCS boron
inventory, the original licensing basis of the plant does not
require the boric acid tanks to meet single failure criteria.Sharing the three boric acid tanks, therefore, is acceptable
with appropriate technical specification controls over the
minimum available volume to account for the needs of both
units.
Report No. 849963-NPS-5HISC-003 REV 0 Page 8-13
Plant Restrictions
None.
Conclusions
This modification has been reviewed against the requirements of10CFR50.59 and has been found not to constitute an unreviewed safetyquestion.
Report No. 849963-HPS-5HISC-003 REV 0 Page 8-14
9.0 OPERATING PROCEDURE GUIDELINES
Section 5.0 provides technical justification for reduction of boricacid tank concentrations and minimization of required volumes.
These analyses were based on a worst case cooldown scenario where
letdown was not available. Hence, boration to cold shutdown limitshad to occur in conjunction with the cooldown evolution (i.e.,through makeup for coolant contraction).
Normal'ooldowns, however, do not have to be conducted in thismanner. FPL may opt to minimize the impact on operating proceduresand continue the current practice of borating to the cold shutdown
limit through a feed and bTeed process (prior to initiatingcooldown). Then a blended makeup will be provided during thecooldown process to maintain the boron concentration. This processwill require greater volumes from the boric acid tank(s) and, hence,
more frequent boric acid batching as discussed in Section 6.5.
If this is the option FPL selects, procedure changes will be limitedto such items as the following:
1. Delete heat tracing related procedures to the extent that allheat tracing is disconnected and removed.
2. Revise all procedures that reference the boric acid tankavailable (usable) volume, minimum required volumes, and boricacid concentration ranges.
3. Revise the emergency boration procedure (Reference 10. 12) toreflect the analysis of Section 6.6.3.
4. - Revise procedures for operation of the boric acid evaporator tomaintain the boric acid concentration of the bottoms of thedistillation process within the new boric acid tank controlband of 3.0 to 3.5 weight percent.
Report No. 849963-MPS-5NISC-003 Rev. 0 Page 9-1
5. Revise procedures for boric acid blender operation (or ones
that reference blender capacity) to reflect the proposedmodification to FCV-113A (PC/H as-building).
6. Revise procedures for boric acid batching to reflect the new
boric acid concentration range of 3.0 to 3.5 weight percent.
7. Develop a procedure to conduct a cooldown in response to thescenario analyzed in Section 5.0. Such a procedure would be
required for cases where a cooldown would be necessary on one
boric acid tank (and the refueling water storage tank) or forcases where letdown is not available. Such a procedure should
make provisions for more frequent boron sampling during thecooldown process.
8. The analysis presented in Sections 5 and 6 assumed an RHR boron
concentration in the range of 500 to 800 ppm boron. This is a
realistic assumption given that cold shutdown boron
concentrations are maintained in the RCS/RHR until after theRCS is disconnected from the RHR. Efforts should be made toensure the RHR concentration is maintained as high as
reasonably possible so that the boron addition from this system
will help minimize batching requirements. This would entailrecirculating portions of the system that have this capabilityand refilling it with borated water whenever the system isdrained for maintenance.
If all subsequent cooldowns are to be completed in the manner
described in Section 5 (i.e., boration in conjunction with cooldown)
all shutdown, cooldown, and boration related procedures will requiremodification in addition to the changes discussed above. Provisionsshould be made, however, to accommodate the use of letdown, batching
to replenish boric acid, and desired plant lineups to accommodate
this mode of operation.
Report No. 849963-NPS-SNISC-003 Rev. 0 Page 9-2
Optimum use can be made of the available boric acid by considerationof the following:
l. Haintain boric acid tanks as full as possible. Align thesuctions of all transfer pumps to all three tanks, therebyinterconnecting the three tanks. Allow the technicalspecification minimum allowable volume for both units to be
spread among the three tanks. This will maximize the volume
available in the tanks for day to day boration needs.
2. When using one or more boric acid tanks as the source ofboration (emergency, manual, or blended) with RCP seal
injection in service, borated water will be lost to the VCT viaRCP seal leakoff (nominally 9 gpm) if the VCT is isolated(isolation valve shut or check valve seated). The batchingevaluation of Section 6.5 assumed this to be the case tomaximize the volumes required for feed and bleeds and blended
makeup operations. By adjusting charging pump speed
accordingly to provide seal injection flow from the VCT, theconcentrated boric acid diverted to the VCT will be utilized.In this manner, VCT level should remain roughly constant, and
eventual loss of RCP seal leakoff to the holdup tank (via VCT
pressure relief) will not occur.
Report No. 849963-HPS-5HISC-003 Rev. 0 Page 9-3
10.0
10.1
10.2
10.3
10.4
10.5
10.6
10.7
10.8
10.9
REFERENCES
Turkey Point Units 3 and 4 Design Basis Document, Chemical andVolume Control System, 5610-046-DB-001, Revision l.Turkey Point Units 3 and 4 Design Basis Document, Chemical andVolume Control System, 5610-046-DB-002, Revision l.Turkey Point Units 3 and 4 Updated Final Safety Analysis Report(UFSAR), Revision 8.
Deleted
Turkey Point Units 3 and 4 10CFR50 Appendix R Fire ProtectionReview.
Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251, RevisedTechnical S ecifications, Amendments 137 and 132.
C-E Letter F-CE-10852, J. H. Westhoven (CE) to S. T. Hale (FPL)dated February 23, 1990; Proposal 90-241-55A.
FPL Purchase Order No. B90671-10032, DWA No. 626610.
Technical Data Sheet IC-ll, US Borax and Chemical Corporation,3-83-J. W.
10. 10 Turkey Point Emergency Operating Procedure 3/4-EOP-ES-0.2, NaturalCirculation Cooldown.
10. 11 ASHE Steam Tables, Third Edition.
10. 12 Turkey Point Operating Procedure 3/4-ONOP-046. 1, Emergency Boration.
10. 13 Crane, Flow of Fluids Through Valves, Fittings and Pipe TechnicalPaper No. 410, 1981.
Report No. 849963-NPS-5NISC-003 Rev. 0 Page 10-1
BORIC ACID CONCENTRATION REDUCTION
TECHNICAL BASES
AND
OPERATIONAL ANALYSES
APPENDICES
Report No. 849963-HPS-5HISC-003 Rev. 0
Appendix 1
Derivation of the Reactor Coolant System
Feed-and-Bleed Equation
Pur ose of Definitions
This appendix presents the detailed derivation of an equation which can
be used to compute the reactor coolant system (RCS) boron concentrationchange during a feed and bleed operation. For this derivation, thefollowing definitions were used:
m,.n = mass flowrate into the RCS
mout mass f1 owrate out of the RCS
mb= boron mass flowrate
mw water mass flowrate
mb- boron mass
mw- water mass
C,.n = boron concentration going into RCS
Gout boron concentrati on go ing out of RCS
C - initial boron concentration0
C(t) = boron concentration as a function of time
CRCS= RCS boron concentration
Sim lif in Assum tions
During a feed and bleed operation, the RCS can be pictured as a closed
container having a certain volume, a certain mass, and an initial boron
concentration. Coolant is added at one end via the charging pumps. The
rate of addition is dependent on the number of charging pumps that are
running with the concentration being determined by the operator. Coolant
is removed at the other end via letdown at a rate that is approximately
equal to the charging rate and at a concentration determined by fluidmixing within the RCS. The mass flowrate into the RCS is given by the
following equation:
in b w in
For typical boron concentrations within the chemical and volume controlsystem, m„ is very much greater than mb. (For example, a 3.5 weightpercent boric acid solution contains only 0.04 ibm of boric acid per ibmof water). Therefore, the above equation can be simplified to thefollowing:
ln W 1tl (I.0)
In a similar manner, the mass flowrate coming out of the RCS, given by
~ ~
out b ™wout
can be simplified by again realizing that m is very much greater than mb
or
out~ ™w out (2 0)
For a feed and bleed operation with a constant pressurizer level and a
constant system temperature, the mass flowrate into the RCS will be equal
to the mass flowrate out of the RCS, or
in out w in w out (3.0)
Finally, if it assumed that the boron which is added to the RCS mixes
completely and instantly with the entire RCS mass, the concentration ofthe fluid coming out of the system will be equal to the system
concentration, or
out RCS(4.0)
Derivation
THe rate of change of boron mass within the RCS is equal to the mass ofboron being charged into the system minus the mass of boron leaving vialetdown. In equation form, this becomes
AI-2
b RCS min in-
mout outdt
From Equation 3.0,
b RCS m. (CD - C ut) — (m )i„(Ci„ - C ut)1 1(5.0)
The concentration of boron in the RCS, (i.e., the weight fraction ofboron), is defined as follows:
m
RCS =
b w RCS
Since mw » mb,
C mbRCS =—
w RCS
Where (mRCS
is a constant for a constant system temperature. The rateof change of the RCS concentration is, therefore:
d( b)RCSdc dt
(4) RCS
(6.0)
Substituting Equation 5.0 into Equation 6.0 yields the following:
dC ( w in ( in out)RCS =
dt w RCS
and from Equation 4.0,
dC w)in (C,.n -CRCS
RCS—dt w RCS
(7.0)
Solving Equation 7.0 for concentration yields:
dCRCS (m ).dt
Cin-
CRCS (mw RCS
C(t)
RCS ( w)in
in RCS w RCS
C
Integrating from some initial concentration C to some finalconcentration C(t) and multiplying through by negative one gives the
following:
or
ln (CRCS- CIN)
C(t)
C
(S)in( w)RCS
C(t) - C,.n (mw),.nln =- t
o in (w) RCS
Continuing to solve for C(t), this equation becomes:
or
~Ct -Ci e win wRCS-(I ). t/ (m )
o in
-(m„..)in t / (m„., )RCSC(t) = C,.n + (C - C,.n) e
" " " (8.0)
If we define the time constant T to be as follows:
( w) RCS
(m„)in
then Equation 8.0 becomes
C(t) = C, e t/T+C,.n (1
-t/T) (g 0)
Appendix 2
A Proof that Final System Concentration isIndependent of System Volume
Pur ose of Definitions
This appendix presents a detailed proof that during a plant cooldown
where an operator is charging only as necessary to makeup for coolantcontraction, the final system concentration that results using a givenboration source concentration will be independent of the total system
volume. For this proof, the following definitions were used:
c. = initial boron concentration Plant 11
mb. = initial boron mass Plant 1bimw,. initial water mass Plant 1
cf = final boron concentration Plant 1
c = boron concentration of makeup solution Plant 1a
mb= mass of boron added Plant 1
ba
mw- mass of water added Plant 1
mbf final boron mass Plant 1
CD = initial boron concentration Plant 21
Hb. = initial boron mass Plant 2biH . = initial water mass Plant 2
wiCf = final boron concentration Plant 2
C = boron concentration of makeup solution Plant 2a
Hb = mass of boron added Plant 2ba
N„ = mass of water added Plant 2
Proof
For this proof, consider two plants at the same initial temperature, the
same initial pressure, and the same initial boron concentration. One
plant, Plant 2, has exactly twice the system volume as the other plant,Plant l. Initially, boron concentration Plant 1 boron concentration
Plant 2,
or
c -C- bib,. * ~ . ~b. ~
1 w1(1.0)
Since the volume of Plant 2 is twice that of Plant 1 M = 2mWl wl
Substituting this relationship into Equation 1.0 and solving yieldsthe following:
bimbi + wi bi wib''™i bi b' bi
and
Mbi 2mbi (2.0)
Therefore, the initial boron mass in Plant 2 is exactly twice the initialboron mass in Plant 1.
During the cooldown process for Plant 1, the final boron mass in thesystem will equal the initial boron mass plus the added boron mass, or
mbf mbi + mba (3.0)
If, during this cooldown process, operators charge only as necessary tomakeup for coolant contraction, water and boron will be added only as
space is made available in the system due to coolant shrinkage. The
final boron concentration from Equation 3.0 can therefore be expressed as
follows:m bf
bf bi ba™wi wa m .+m +m . +mbi ba mwi wa
If concentration is expressed in terms of weight percent, this lastequation becomes
mbf =mbi ™ba + mwi + mwa cf (4.0)
A2-2
Similarly, the remaining two components of Equation 3.0 become
IAb ~ =mba
+ Al ~ cd (5.0)
and
ba ™ba wa a (6.0)
Substituting Equations 4.0, 5.0, and 6.0 into Equation 3.0 and solvingfor the final concentration yields the following:
m' +m''+ IAb +Al cbl Wl 1
Aiba+ mb + .+ (7.0)
For Plant 2, Equation 7.0 becomes
bl wl 1Mb. + M . C. + Mb + M C
bi ba wi wa(8.0)
During a cooldown, the shrinkage mass, (i.e., the mass of fluid that must
be added to the system in order to keep pressurizer level constant), iscalculated by dividing the system volume by the change in specificvolume, or
and
S stem Volume Plant 1
wa a peel 1 c vo UAle
S stem Volume Plant 2wa a peel lc vo ume
(9 0)
(10.0)
where System Volume Plant 1 = (1/2) System Volume Plant 2.
For a given cooldown, dividing Equation 9.0 by Equation 10.0 gives the
following:
Mw= 2mw (11.0)
A2-3
In addition, if the charging source for both plants is at the same
concentration and temperature,
Ca ca (12.0)
and
Mb 2mb (13.0)
Substituting Equations 2.0, 11.0, 12,0, and 13.0 into Equation 8.0yields the following:
2mbi + Mwi C. + 2mba + 2mw
+ + M . +
Since the initial concentrations are the same, C. - c., and since1 1
Plant 2 is twice as large as Plant 1, M„. = 2mw.,wi wi
Cf =2mbi + 2mwi i + 2mba + 2mwa ca -'
mba+
b+ ~ + m
or
(14.0)
Therefore, for a cooldown where pressurizer level is maintained
constant, the final boron concentration for Plant 2 is equal to thefinal boron concentration for Plant 1 (i.e., the change in boron
concentration is independent of the exact system volume).
A2-4
0
Appendix 3
Methodology for Calculating Dissolved Boric Acid
per Gallon of Water
~Pur ose
The purpose of this appendix is to show the methodology used to calculatethe mass of boric acid dissolved in each gallon of water for solutions ofvarious boric acid concentrations. Two solution temperatures are
presented corresponding to the maximum expected refueling water tank and
boric acid tank temperature of 120 F and a nominal temperature of 70 F.
Methodolo and Results
Boric acid concentration expressed in terms of weight percent is definedas follows:
or
Cmass of boric acid „ 100tota so u >on mass
mass of boric acidmass o oretc aci + mass o water (1 0)
If we define mb to be the mass of boric acid and mw to be the mass
of water, and if we substitute these defined terms into Equation 1.0
and solve for the mass of boric acid we have the following:
'ba 'wor
A3-1
From Appendix A of the Crane Company Manual (Flow of Fluids Through
Valves, Fittings, and Pipe, Crane Co., 1981, Technical Paper No. 410),
the density of water at 70'F is 8.3290 ibm/gallon and at 120'F is 8.2498
ibm/gallon. Using these water masses and Equation 2.0 above, the mass ofboric acid per gallon of solution is as follows:
Concentrat on
Mass of acid per gallonof solution at
source wt.% boric acid m boron 70'F 120'F
RWST
RWST
RWST
boric acid tankboric acid tankboric acid tankboric acid tankboric acid tankboric acid tankboric acid tankboric acid tank
1.11534
1.22974
1.34413
1.50
2.50
2.75
3.00
3.25
3.50
3.75
4.00
1950
2150
2350
2622
4371
4808
5245
5682
6119
6556
6993
0.09394
0.10370
0.11348
0.12684
0.21356
0.23552
0.25760
0.27979
0.30209
0.32451
0.34704
0.09305
0.10271
0.11240
0.12563
0.21153
0.23328
0.25515
0.27712
0.29922
0.32142
0.34374
A3-2
Appendix 4
methodology for Calculating the Conversion FactorBetween Weight Percent Boric Acid and ppm Boron
~Pur use
The purpose of this appendix is to show the methodology used to derivethe conversion factor between concentration in terms of weight percentboric acid and concentration in terms of parts per million (ppm) ofnaturally occurring boron.
Results
For any species (solute) dissolved in some solvent, a solution having a
concentration of exactly 1 ppm can be obtained by dissolving 1 ibm ofsolute in 999,999 ibm of solvent. An aqueous solution having a
concentration of 1 ppm boric acid, therefore, can be obtained by
dissolving 1 ibm of boric acid in 999,999 ibm of water, or
1 ibm boric acid 119 9 1 dd
9 1 19 999,999 11 1 19 11
For any species (solute) dissolved in some solvent, a solution having a
concentration of 1 weight percent (wt.X) can be obtained by dissolving 1
ibm of solute in 99 ibm of solvent. An aqueous solution having a
concentration of 1 wt.X boric acid, therefore, can be obtained by
dissolving 1 ibm of boric acid in 99 ibm of water, or
1 wt.XTR
1 ibm boric acidm orle acl + 99 m water
1 ibm boric acidm so Utlon
Dividing these last two equations yields a ratio of 10 , or
1 wt.X boric acid = 10,000 ppm boric acid (1 0)
A4-1
To convert from ppm boric acid (weight fraction) to ppm boron (weightfraction), multiply Equation 1.0 by the ratio of the molecular weight ofboric acid (naturally occurring H3B03) to the atomic weight of naturallyoccurring boron. From the Handbook of Chemistry and Physics, CRC Press,
or
1 wt.X boric acid (10,000) ~'~ ppm boron10.81
1 wt.X boric acid 1748.34 ppm boron.
A4-2
Appendix 5
Bounding Physics Data Inputs
A5-I
APL
P.O. 8ox14000, Juno Beach, FL 33408-0420
(Pffft)
JPN-PTP-90-1248
ASH ap tggg
Combustion Engineering, Inc.1000 Prospect Hill RoadWindsor, Connecticut 06095
Attention: Hr. J. H. Westhoven
TURKEY POINT UNITS 3'L 4BORIC ACID CONCENTRATION REDUCTION
REA TPN-88-733 IS MOD 1311CCO NO. 30383 PC/H: N/A
FILE: TPN-88-733-2
Reference: C-E letter F-CE-10852 dated February 23, 1990
Gentlemen:
Table II in the letter referenced above described the type of data you requirefrom FPL to develop the technical documents to support a technical specificationchange to reduce boron concentration. Table II was subsequently updated by youafter conversations between your Hr. Carl Gimbrone and Hr. Abe Ortega. We areenclosing the data requested in the updated version of Table II.The data was generated by our Fuel Technology Department and has been reviewedand approved for release to you. If you have any questions strictly regardingthe nature of the data, please contact Mr. Modesto Jimenez at (305)552-3427.
Ifyou have any other questions, please contact Mr. Abe Ortega at (407)694-5094.
Very truly yours,
~NO/lh
Copies:H.J.C.J.R.A.
S. BowlesKruminsL. Larsen (w/)PorterS. Sanders (w/)T. Zielonka
S. T. HaleEngineering Project Manager
an FPL Group company
!neer-Otfics Correspondence
To:NF-90-140
Date: April 3, 1990
From: M. Jimenez Department: Nuclear Fuel
Subject: Turkey Point Units 3 & 4 Boric AcidConcentration Reduction Pro'ect - Ph sics Data
Attached is the physics data requested in RAA 3065 to support the boric acidconcentration reduction project at Turkey Point. The information provided consistsof best estimate calculated average values covering several fuel cycles. Uncertaintiesnoted in the attachment represents the range of variation among the cycles and donot include calculational uncertainty, Additional conservatisms should be applied tothese results to envelope all future cycles. The data provided in the attachment havebeen reviewed in accordance to Nuclear Fuel's Quality Instructions.
If you have any questions or comments, please contact me at 552-3427.
M. JimenezReactor Support
Approved By:J.. FerrymanReactor Support Supervisor
Copies To: T3. CahillG.l MarshJ.l Petry manD.C. PoteralskiLS. Rudicel ~~W. SkelleyD.G. Weeks
fqre 1001 (Qockad) Rev. X1$
TURKEY POINT UNITS 3 & 4BORIC ACID CONCENTRATION REDUCTION PROJECT
RE UIRED PHYSICS DATA
1. Required shutdown margins:
Gzuhtion
a T-avg > 200'F.
b. T-avg ( 200'F.
See Figure 1
1000
2. Moderator cooldown curve from Hot Full Power (HFP) equilibriumconditions to 68 'F for the rodded condition when all rods are insertedminus the most worthy rod (ARI/wrso). The moderator cooldown curveshould be normalized such that the corresponding All Rods Out (ARO) HFPModerator Temperature Coefficient (MTC) is equal to the most negativeTechnical Specification limit.
Figure 2
3. Doppler curve down to 68'F.
Table 1
4. Xenon worth versus time (100 hours) after shutdown Qom 100% power.
Tables 2 & 3 presents xenon worth versus time after shutdown from100% at EOC 11 for Turkey Point Units 3 and 4, respectively. Thesexenon worth tables are representative of all recent cycles at TurkeyPoint. As shown in these tables, the xenon worth is negligible after 100hoar@
5. HZP scaun worths for the ARI/wrso condition. (Moderator and Dopplerdistribution and xenon concentration held constant between the rodded andunrodded calculation).
6500+/- 5% ctn. The 5% uncertainty in this value represents the range ofvariation or the most recent cycles at Turkey Point and does not includecalculational uncertainty of 10%.
6. Differential Boron Worth (DBW) versus Temperature from HZP to CZP.
Figurc 3. The following data points were used to generate this figure:
68350547
-145 +/-1.0-125 +/45-105 +/4.4
7. PPM measurement uncertainty for the boronometer (or measurement methodused during normal and off-normal shutdowns).
19o or 5 ppm, whichever is greater.
8. Power Defect (Moderator and Doppler) for ARO, 0% to 100% power,constant HFP equilibrium xenon concentration at EOC EFPH.
Figure 4. The following data points were used to generate this figure:
0305070100
0- 800+/- 50-1270 +/- 50-1700 +/-100-2300 +/-100
9. Beta-Eff. ifreactivity data is given in terms of dollars ($).
Allreactivities given in pcm.
10. HFP PDIL
The HFP PDIL or Insertion Limit is control Bank D at 171 stepswithdrawn (75%). The calculated worth to this insertion limit is240 +I- 50 m. The rod insertion allowance in the calculation ofs ut wn margm is conservatively estimated at 500 pcm by the fuelvendor.
TABLE 1
TURKEY POINT UNITS 3 & 4DOPPLER ONLY FUEL TEMPERATURE COEFFICIENTVs. FUEL TEMPERATURE
Fuel Temperature (oF)
68100200300400500600700800900
10001100120013001400150016001700180019002000
Doppler Coefficient(pcm/oF)
-2 90-2 ~ 75
2 ~ 37-2 '7-1.84-1 ~ 67-1. 54-1.45-1 '8
1 ~ 33-1. 30-1.26-1. 24
1 ~ 2 1-1. 17-1 '4-1 '0-1 '7-1.04-1.02-1 '2
TABLE 2
HR AFf'SD"n.o2. rj4.o6). 08.0
10.012.014.016.0lid.n20.022.024.026.0
TURKEY POINT UNIT 3 CYCLE 11
XE WRTH(PCN)2775.13709.54261 '4532.44h00.34525.14352.241)5.0.)041. 53548.1)249. 32954.62670.62401.7
HR AFT SD56.058.060.062.064.066.068.070.075.080.085.090.095.0
100.0
XENON WORTH AFTER TRIP AT EOL (12000)ENTER PRE TRIP POWER LEVEL (X) OR ENTER -E- 10 END
)00SUHNARY OF RESULTS
HR AFT SD XE WRTH(PCN)28.0 2150.430.0 1918 ~ 132.0 1705.334. 0 1511.636.0 133h.438.0 11/8.840.0 1037.642. 0 911.744.0 799 746.0 7nO.34A.O 6.l2.550.0 535.052.0 466.854.0 406.8
XF. WRTH(PCN)354.3308.2267.9232./202.0175.2151.9131.h
'Yl 8'3.8
44.330.721.214.7
FNTFR 0 TO CONTINUE CALCULATIONS, 0 1'n 8RAPH OR -E- TO END
TABLE
>If<.AFT.SD.0.02.04.06.08.0
10.012.014.016.018.020. CI
22.024.026.0
TURKEY POINT UNIT 4 CYCLE 11
XE.WRTH(PCN)2874.63834 '4401.34678.64747.14668.34489.14244.7.>961. 43658.6>350. 2
3046>.22753 ..>2475
HR.AFT.SD.56.058.'060. 062.064.0
~ 66 068.070.07S.Q80.085.090. Il'4S. 0
100.0
XENON WORTH AFTER TRIP AT EOL (12000)ENTER PRE-TRIP POWER LEVEL (X) OR ENTER -E- TO END
100SUNNAI<Y OF RESULTS
HR.AFT.SD. XE.Wf(TH(PCN)28.0 2;?16.030 ' i~rr.332.0 1757.834.0 1558.136.0 1377.538.0 1215.040.0 1069.542.0 939.7nn.ontj.O 7:? I. 848. 0 631.350 ' 551.452.0 481.J54.0 4Ja
XI";.WRTI I(PCH)r 1317.627~.12&9 8208.2180.6156.5135;694.665.845.631.621 9I 5>. 1
f='NTFR C TA CONTINLII.. CALCULATIONS, G TO GfIAPH OR -E- IO END
FIGURE 1
Turkey Point Units 3 R 4Required Shutdown Margin Vs. Boron Concentration
For T-Avg o 200 oF2,000
~ ~ ~ ~ ~ ~ ~ ~ OO ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ \ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ IA1 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
g 1400
W 1,000
500
~ ~ ~ ~ ~ ~ OO ~ ~ ~ ~ ~ ~
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 10 ~ ~ ~ ~ ~ ~ ~
~ ~ ~ ~ \ ~ ~ ~ ~ ~ ~ ~ A
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0
~ ~ ~ ~ ~ I~ ~ 0
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~ ~ ~ ~ 0
~ ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ Ot&O~ ~ ~
1,500
0 00 500 1,000 1,500 2,000
RCS Boron Concentration (pptn)
FISH& 2
10
Turkey Point Units 3 8c 4Moderator TemperatUre Coefficient Vs. Moderator Temperanue
( 0
-50
Average Moderator Temperature ('F)
FIGUIM3
Turkey Point Units 3 & 4Diffe
-8rential Boron Worth Vs. Temperature
~ -108
-12
8Og -14
CtQ
-16
~ ~ ~ ~ ~ Qo ~
~ ~ ~ ~ ~ ~ ~ ~o
~ ~ ~ ~ ~ do ~
~ $ ~
l ~
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0oo ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ Ao
~ ~ ~ ~ ~ oo ~
o
~ 'o ~
o~ ~ ~ ~ ~ oo ~
o~ ~ ~ ~ ~ +o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~ ~ ~ ~ ~ ~ ~
~ 1o~ ~ ~ ~ ~ ooo ~
~ ~ ~ ~ ~ 4o ~ ~ to
o
~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ( ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~ ~ ~
( ~ ~
I ~ ~
~ o ~
~ ~ ~
~ ~
} ~ ~
l ~ ~
~ ~ ~
~ ~ ~
~ op
~ ~ ~
~ oo ~ ~ ~ ~ ~ ~ ~ ~ ~ ohio ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ + ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~~ ooo
~ op
~ ~ ~o
~ ~ 0
~ oOo
o
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ )o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ oo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ +o ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ I ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~
-180 100 200 300 400 500
Moderator Temperature (oF)
FIGUI&4
"-turkey Point Units 3 4 4Total Power Defect Vs. Percent of Full Power
0At EOC, EQ. XE, ARO.
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ + ~ ~ ~ $ t ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ \ ~
0
-500 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~
o -1000
0 -1500
\~ ~ ~ ~ 4t
~ ~ ~ ~ tO
~ ~ ~ ~ ~ ~ ~ ~ 1 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ 1 ~ ~
~ ~ e ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ to ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~ ~ ~ ~ J ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ J ~ ~ ~ ~ ~ ~
~ ~ ~ ~ $ ~
~ ~ ~ ~ ~ 0
\
~ ~ ~ ~ ~ f ~~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
-2000
~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ 10 ~ ~ 1 ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
-25000 20 40 60 80
Percent Of Full Power
Appendix 6
Harked-Up Revised Technical Specifications
These draft technical specification revisions reflect the
proposed boric acid tank configuration where all threetanks are tied together via the transfer pump suctionlines. In this manner, the combined volume of these tanks
is shared between the two units. Required minimum
volumes, therefore, have been doubled to ensure adequate
volume is available to either unit.
A6-I
Technical S ecification Inserts
Insert A:
...EOL peak xenon conditions without letdown such that boration occurs onlyduring the makeup provided for coolant contraction. This requirement can be
met for a range of boric acid concentrations in the boric acid tank and the
refueling water storage tank. The range of boric acid tank requirements isdefined by Technical Specification 3.1.2.5.
Insert B:
...requirement of 55'F and corresponding surveillance intervals...
Insert C:
The temperature limit of 55'F includes a 5'F margin over the 50'F solubilitylimit of 3.5 wt./ boric acid. Portable instrumentation may be used to measure
the temperature of the rooms containing boric acid sources and flow paths.
Insert D:
ACTION times allow for an orderly sequential shutdown of both units when the
inoperability of a component(s) affects both units with equal severity. When
a single unit is affected, the time to be in HOT STANDBY is 6 hours. When an
ACTION statement requires a dual unit shutdown, the time to be in HOT STANDBY
is 12 hours.
Insert E:
...by verifying that the temperature of the rooms containing flow path
components is greater than or equal to 55'F when a flow path from the boric
acid tanks is used;
A6-2
Insert F:
Verifying that the temperature of the boric acid tanks room is greater than or
equal to 55'F when it is the source of borated water.
A6-3
3/4. 1 REACTIVITY CONTROL SYSTEMS
3/4. 1. 1 BORATION CONTROL
SHUTDOWN MARGIN - T GREATER THAN 200 Fav
LIHIT ING COND IT ION FOR OPERATION
3. 1. l. 1 The SHUTDOWN MARGIN shall be greater than or equal to the applicablevalue shown in Figure 3.1-1.
APPLICABILITY: MODES 1, 2", 3, and 4.
ACTION:
With the SHUTDOWN MARGIN less than the applicable value shown in Figure 3.1-1,immediately initiate and continue boration at greater than or equal togpm of a solution containing greater than or equal to boron requivalent until the required SHUTDOWN MARGIN is restored.
a.o w'f,(etA6 g~)SURVEILLANCE RE UIREHENTS
4. l. 1. l. 1 The SHUTDOWN MARGIN shall be determined to be greater than or equalto the applicable value shown in Figure 3. 1-1:
a. Within 1 hour after detection of an inoperable control rod(s) andat least once per 12 hours thereafter while the rod(s) is inoperable.If the inoperable control rod is immovable or untrippable, the aboverequired SHUTDOWN MARGIN shall be verified acceptable with an increasedallowance for the withdrawn worth of the immovable or untrippablecontrol rod(s);
b. When in MODE 1 or MODE 2 with K ff greater than or equal to 1 ateffleast once per 12 hours by verifying that control bank withdrawal iswithin the limits of Specification 3. 1.3 ';
c. When in MODE 2 with K ff less than 1, within 4 hours prior to achievingreactor criticality b$ verifying that the predicted critical controlrod position is within the limits of Specification 3. 1.3.6;
d. Prior to initial operation above 5X RATED THERMAL POWER after eachfuel loading, by consideration of the factors of Specification4. l.l.l.le. below, with the control banks at the maximum insertionlimit of Specification 3. 1.3.6; and
"See Special Test Exceptions Specification 3. 10.1.
TURKEY POINT - UNITS 3 6 4 3/4 1-1 AMENDMENT NOS.l37 AND 132
REACTIVITY CONTROL SYSTEMS
SHUTDOWN MARGIN - T LESS THAN OP ""EQUAL TO 200 Fav
LIMITING CONDITION FOR OPERATION
3.1.1.2 The SHUTDOWN MARGIN shall be greater than or equal to lX ~k/k.
APPLICABILITY: MODE 5.
ACT10M:
With the SHUTDOWN MARGINboration at great thanthan or equal toMARGIN is restore .
less than 'k/k, immedi ately initiate and continueor equal to pm of a solution containing greater
oron or equivalent until the required SHUTDOWN
a.o W'I (~iW~)SUR",El'ANCE RE UIREMENTS
4. 1. 1.2 The SHUTDOWN MARGIN shall be determined to be greater than or equalto 1 Dk/k:
Within 1 hour after detection of an inoperable control rod(s) and atleast once per 12 hours thereafter while the rod(s) is inoperable.If the inoperable control rod is immovable or untrippable, theSHUTDOWN MARGIN shall be verified acceptable with an increasedallowance for the withdrawn worth of the immovable or untrippablecontrol rod(s); and
b. At least once per 24 hours by consideration of the following factors:
1) Reactor Coolant System boron concentration,
2) Control rod position,
3) Reactor Coolant System average temperature,
') Fuel burnup based on gross thermal energy generation,\
5) Xenon concentration, and
6) Samarium concentration.
TURKEY POINT - UNITS 3 8' 3/4 1-4 AMENDMENT NOS.137AND 132
REACTIVITY CONTROL SYSTEMS
3/4. 1. 2 BORATION SYSTEMS
FLOW PATH - SHUTDOWN
LIMITING CONOITION FOR OPERATION
3.1.2.1 As a minimum, one of the following boron injection flow paths shallbe OPERABLE and capable of being powered from an OPERABLE emergency powersource:
A flow path from the boric acid storage tanks via a boric acidtransfer pump and a charging pump to the Reactor Coolant System ifthe boric acid storage tank in Specification 3. 1.2.4a. isOPERABLE. or
b. The flow path from the refueling water storage tank via a chargingpump to the Reactor Coolant System if the refueling water storagetank in Specification 3. 1.2.4b. is OPERABLE.
APPLICABILITY: MODES 5 and 6.
ACTION:
With none of the above flow paths OPERABLE or capable of being powered from anOPERABLE emergency power source, suspend all operations involving COREALTERATIONS or positive reactivity changes.
SURVEILLANCE RE UIREMENTS
4.1.2.1 At least one of the above required flow paths shall be demonstratedOPERABLE:
a. At leas once er 7 d s
and
b. At least once per 31 days by verifying that each valve (manual,power-operated, or automatic) in the flow path that is not locked,sealed, or otherwise secured in position, is in its correctposition.
MHitCT
TURKEY POINT - UNITS 3 8; 4 3/4 1-8 AMENOMENT NOS. l37AND 132
REACTIVITY CONTROL SYSTEMS
FLOW PATHS - OPERATING
LIMITING CONDITION FOR OPERATION
3.1.2.2 The following boron injection flow paths shall be OPERABLE:
a. The source path from a boric acid storage tank via a boric acidtransfer pump to the charging pump suction", and
b. At least one of the two source paths from the refueling water storagetank to the charging pump suction; and,
c. The flow path from the charging pump discharge to the ReactorCoolant System via the regenerative heat exchanger.
APPLICAEILITY: MODES 1, 2, 3, and 4.
ACTION:
a. With no boration source path from a boric acid storage tank OPERABLE,
1. Demonstrate the OPERABILITY of the second source path from therefueling water storage tank to the charging pump suction byverifying the flow path valve alignment; and
2. Restore the boration source path from a boric acid storage tankto OPERABLE status within 72 hours or be in at least HOT STANDBY
and borated to a SHUTDOWN MARGIN equivalent to at least 1X b,k/kat 200'F within the next 6 hours; restore the boration sourcepath from a boric acid storage tank to OPERABLE status withinthe next 72 hours or be in COLD SHUTDOWN within the next 30hours.
b. With only one boration source path OPERS E or the regenerative heatexchanger flow path to the RCS inoperable, restore the required flowpaths to OPERABLE status'ithin 72 hours or be in at 'least HOT
STANDBY and borated to a SHUTDOWN MARGIN equivalent to at least lXb,k/k at 200'F within the next 6 hours; restore at least twoboration source paths to OPERABLE status within the next 72 hours orbe in COLD SHUTDOWN within the next 30 hours.
~The flow require ithe other uni
With the'boration source path from a boric acid storage tank and thecharging pump discharge path via the regenerative heat exchangerinoperable, within one hour initiate boration to a SHUTDOWN MARGIN
equivalent to lX hk/k at 200'F and go to COLD SHUTDOWN as soon as
possible within the limitations of the boration and pressurizerlevel control functions of the CVCS.
+ Iso sec maid femme a ssw tt' ~''~ ~pec ica son 3. 1.2.2.a above shall be isolated from
TURKEY POINT - UNITS 3 8 4 3/4 1-9 AMENDMENT NOS. 137AND 132
REACTIVITY CONTROL SYSTEMS
SURVEILLANCE RE UIREHENTS
4.1.2.2 The above required flow paths shall be demonstrated OPERABLE:
a. At least once er 7 da s
b. At least once per 31 days by verifyihg that each valve (manual,power-operated, or automatic) in the flow path that is not locked,sealed, or otherwise secured in position, is in its correct position;
c. At least once per 18 months by verifying that the fl w path requiredby Specification 3. 1.2.2a. and c. delivers at least pm to the RCS.
TURKEY POiNT - UNITS 3 & 4 3/4 1-10 AMENDMENT NOS.l37AND l32
REACTIVITY CONTROL SYSTEMS
BORATED WATER SOURCE - SHUTDOWN
LIMITING CONDITION FOR OPERATION
3. 1.2 ' As a minimum, one of the following borated water sources shall beOPERABLE:
z,ceo 1lwc Pt m<ipa. A Boric Acid Storage System with:
1) A minimum indicated borated water volume of
2) A boron concentration between
3)
and
b. The refueling
1) A minimum
2) A minimum
3) A minimum
water storage tank (RWST) with:
indicated borated water volume of 20,000 gallons,
boron concentration of 1950 ppm, and
solution temperature of 39'F.suwkf (sz4sH )
OAAQ 3.6 l4t li (gill~)and 6.APPLICABILITY: MODES
ACTION: 4 w'wiiiiVmloAACaii44414~ tc+emvutc of ~'P.With no borated water source OPERABLE, suspend all operations involving COREALTERATIONS or positive reactivity changes.
SURVErLLANCE RE UIREMENTS
4. 1.2.4 The above required borated water source shall be demonstrated OPERABLE:
a. At least once per 7 days by:
1) Verifying the boron concentration of the water,
2) Verifying the indicated borated water volume, and
3)
TURKEY POINT - UNITS 3 5 4 3/4 1-12i.
AMENDMENT QQ5.137AND 132
REACTIVITY CONTROL SYSTEMS
BORATED WATER SOURCES - OPERATING
LIMITING CONOITION FOR OPERATION
3. 1.2.5 The following borated water sources shall be OPERABLE:'llcdssIC wl%
Vi use. 8.L2.5>a. A Boric Acid Storage System with:
1) A minimum indicated borated water volume
2) A boron concentration and
3) illCIAO~(CwitVttwss
p ~ ~ ggb. The refueling water storage tank (RWST) with:
1) A minimum indicated borated water volume of 320,000 gallons,
2) A minimum boron concentration of 1950 ppm,
3) A minimum solution temperature of 394F, and
ACTION
With the required Boric Acid Storage System inoperable verify thatthe RWST is OPERABLE; restore the system to OPERABLE status wigh'n72 hours or be in at least HOT STANDBY within the next 6 hourPandborated to a SHUTDOWN MARGIN equivalent to at least A Dk/k at 200'F;reo .re the Boric Acid Storage System to OPERABLE status within thenex. 72 hours or be in COLD SHUTDOWN within the next 30 hours.
b. With the RWST inoperable, restore the tank to OPERABLE statuswithin 1 hour or be in at least HOT STANDBY within the next6 hours and in COLD SHUTDOWN within the following 30 hours.
IPli'4 '6 Lscc oci g tohK. ITAlcll~ooli co<el T~l's L> < alt%, qcoc'f~ 'ALA( 0 Hoes clcclt &4agp
o. J)scot'a~ sou ccc cAAAl. 4sw IA~~ ls )ocotcc. <4so44ggh 4 L 4 r ~cc~tost'os.
4) A maximum solution temperature of 100'F.
APPLICABILITY: MODES 1, 2, 3, and 4. P WialWSW ~ ACC +C~~ tink! A~%w SAfikSC, 0) ~ T ~
TUR YP IN - NITS3K 3/4 1-14 AMENDMENT NOS.l37AND l
WXf44csc ma)) 'co a Iso us'Tt'c sIlNu.,+scoos l c. wl
to14ig 'f4. we+ LQU4 4,ovlLs .
Figure 3. 1.2.5BORIC ACID TANK MINIMUM VOLUME (1)
Modes 1,2,3 and 4
0
0
I—
CQ
E
E
16
1515,000
o UnitAcceptable TwOperationn
14
13
12
11
10
9
8
10,400
AcceptaOpe
Una c ceptable..........O.p.e.r..aj.j q.o..................
13,200
ble One Unitration (2)
9,500
1 1,800
8,800
3.0 wt.%(5245ppm)
3.25 wt.% 3.5 wt.% )3.5 WT.%(5682ppm) (6119ppm)
BAT Inventory ConcentrationMinimum Acceptable Minimum AcceptableTwo Unit Operation One Unit Operation
Notes:(1) Combined volume of all available boric acid
tanks assuming RWST boron concentrationgreater than or equal to 1950 ppm.
(2) Includes 2900 gallons for shutdown unit.
REACTIVITY CONTROL SYSTEMS
SURVEILLANCE RE UIREMENTS
4. 1.2.5 Each borated water source shall be demonstrated OPERABLE:
a. At least once per 7 days by:
1) Verifying the boron concentration in the water,
2) Verifying the indicated borated water volume of the watersource, and
3)
b. By verifying the Rk'ST temperature is within limits whenever theoutside air temperature is less than 39'F or greater than 100'F atthe following frequencies:
1) within one hour upon the outside temperature exceeding its limitfor 23 consecutive hours, and
2) At least once per 24 hours while the outside temperature exceedsits limits.
TURKEY POINT - UNITS 3 6 4 3/4 1-15 AMENDMENT NOS. l37AN0 l3
REACTIVITY CONTROL SYSTEMS
HEAT TRACING
LIMITING CONDITION FOR OPERATION
(0'. 1.2.6 At least two independent channels of heat tracing sha'll be OPERAOLEfor the boric acid storage tank and for the heat traced portions of theassociated flow paths required by Speci fication 3. 1. 2. 2.
APPLICABILITY: MODES 1, 2, 3 and 4MODES 5 and 6 (when the boric acid storage tank is the borated,water source per Specification 3. 1.2.4)
ACTjON:
MODES 1 2, 3 and 4
With only one channel of heat tracing on either the boric acid storage tank oron the heat traced portion of an associated flow path OPERABLE, operation maycontinue for up to 30 days provided the tank and flow path temperatures areverified to be greater than or equal to 145'F at least once per 8 hours;otherwise, be in at least HOT STANDBY within 6 hours and in COLO SHUTDOWN
within the following 30 hours.
MODES 5 and 6
With only one channel of heat tracing on either the boric acid storage tank oron the heat traced portion of an associated flow path OPERABLE, operationsinvolving CORE ALTERATIONS or positive reactivity additions ma>f continue forup to 30 days provided the tank and flow path temperatures are verified to begreater than or equal to 145'F at least once per 8 hours; otherwise, suspendall activities involving CORE ALTERATIONS or positive reactivity changes.
SURVEILl ANCE RE UIRE!lENTS
a. At least once per 31 days by energizing each heat tracing channel,and
At least once per 7 days by verifying the tank and flow pathtemperatures to be greater than or equal to 145 F. The tanktemperature shall be determined by measurement. The flow pathtemperature shall be determined by either measurement orrecirculation flow until establishment of equilibrium temperatures
b.
within the tank.
'ticno ion st+ W ohck~ikkt4+anW i vc o i~kck ctng [ood )ogo inytntoaaks. 4avt >En i!A'twttk<
k ~ %.68 lest.$% taktsnC (Nt 'fo) ~
4. 1.2.6 Each heat tracing channel for the boric acid stnrag tank andassociated flow path required by Specification 3. 1.2.2 shall be demonstratedOPERABLE:
TURKEY POINT - UNITS 3 8c 4 3/4 1 16 AMENDMENT NOS.137ANP 132
3/4. 9 REFUELING OPERATIONS
3/4.9. 1 BORON CONCENTRATION
LIMITING CONDITION FOR OPERATION
3.9.1 The boron concentration of all filled portions of the Reactor CoolantSystem and the refueling canal shall be maintained uniform and sufficient toensure that the more restrictive of the following reactivity conditions is met;either:
a. A K ff of 0.95 or less, oreffb. A boron concentration of greater than or equal to 1950 ppm.
APPLICABILITY: HODE 6. "
ACTION:
With the requirements of the above specification not satisfied, immediatelysuspend all operations involving CORE ALTERATIONS or positive reactivitchanges and initiate and continue boration at greater han or equal t gpmof a solution containing greater than or equal to oron or > sequivalent until K ff is reduced to less than or eq o .95 or the boroneffconcentration is restored to greater than or equal to 1950 m whichever isthe more restrictive.
S.O INt'I, (SNS ~'ISURVEILLANCE RE UIREMENTS
4.9. 1. 1 The more restrictive of the above two reactivity conditions shall bedetermined prior to:
a. Removing or unbolting the reactor vessel head, and
b. Withdrawal of any full-length control rod in excess of 3 feet fromits fully inserted position within the reactor vessel.
4.9.1.2 The boron concentration of the Reactor Coolant System and the refuelingcanal shall be determined by chemical analysis at least once per 72 hours.
4.9. 1.3 Valves isolating unborated water sources*" shall be verified closedand secured in position by mechanical stops or by removal of air or electricalpower at least once per 31 days.
4.9.1.4 The spent fuel pit boron concentration sh'all be determined at leastonce per 31 days.
"The reactor shall be maintained in NODE 6 whenever fuel is in the reactorvessel with the vessel head closure bolts less than fully tensioned or withthe head removed.
" The primary water supply to the boric acid blender may be opened unde~administrative controls for makeup.
TURKEY POINT - UNITS 3 4 4 3/4 9-1 AMENDMENT NOS.137AND 132
3/4.10 SPECIAL TEST EXCEPTIONS
3/4. 10. 1 SHUTDOWN MARGIN
LIMITING CONDITION FOR OPERATION
APPLICABILITY: MODE 2.
ACTION:
With any full-length control rod not fully inserted and with lessthan the above reactivity equivalent available for trip insertion,i ediately initiate and continue boration at greater than o" equal
m of a solution containing greater than or equal toboron or its equivalent until the SHUTDOWN MARGIN required
by pecification 3. l. 1.1 is restored.
ao
B.O oN:fo(sa4s p~)
b. With all full-length control rods fully inserted and the reactorsubcritical by less than the above reactivity 'eouivalent, i~edi-tely initiate and continue boration at greater than or ual o
m of a solution containing greater than or equal tooron or its equivalent until the SHUTDOWN MARGEN requir y
Specification 3. 1.1.1 is restored.9.0 laEels ~h
SURVEILLANCE RE UIREMENTS
3.10.1 The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 may besuspended for measurement of control rod worth and SHUTDOWN MARGIN providedreactivity equivalent to at least the highest estimated control rod worth isavailable for trip insertion froa OPERABLE control rod(s).
4.10.1.1 The position of each full-length control rod either partially orfully withdrawn shall be determined at least once per 2 hours.
4. 10. 1.2 Each full-length control rod not fully inserted shall be demonstratedcapable of full insertion when tripped from at least the 50K withdrawn positionwithin 24 hours prior to reducing the SHUTMWN MARGIN to less than the limits of.Specification 3.1.1.1.
TURKEY POINT - UNITS 3 Ea 4 3/4 10-1 AMENDMENT NOS J37 AND 132
3/4.1 REACTIVITY CONTROL SYSTEMS
BASES
3/4. 1. 1 BORATION CONTROL
3/4. 1. 1. 1 and 3/4. 1.1. 2 SHUTDOWN MARGIN
A sufficient SHUTDOWN MARGIN ensures that: (1) the reactor can be made
subcritical fr'om all operating conditions, (2) the reactivity transients asso-ciated with postulated accident conditions are controllable within acceptablelimits, and (3) the reactor will be maintained sufficiently subcritical topreclude inadvertent criticality in the shutdown condition.
SHUTDON MARGIN requirements vary throughout core life as a function offuel depletion, RCS boron concentration, and RCS T „ . The most restrictivecondition occurs at EOL, with T „ at no load operating temperature, and isassociated with a postulated steam line break accident and resulting uncon-trolled RCS cooldown. Figure 3. 1-1 shows the SHUTDOWN MARGIN equivalent to1.77X 4k/k at the end-of-core-life with respect to an uncontrolled cooldown.Accordingly, the SHUTDOWN MARGIN requirement is based upon this limitingcondition and is consistent with FSAR safety analysis assumptions. With T
less than 2004F, the reactivity transients resulting from an inadvertentcooldown of the RCS or an inadvertent dilution of RCS boron 'mal anda 1% ak/k SHUTOONN MARGIN ProvIdee ade te Protection.
The boron rate requirement of m of boron or equivalentensures the capability to restore the shutdown margin with one OPERABLE
char ging pump.
3/4. 1. 1. 3 MODERATOR TEMPERATURE COEFFICIENT
The limitations on aoderator temperature coefficient (h. ') are providedto ensure that the value of this coefficient reNains within the limitingcondition assumed in the FSAR accident and transient analyses.
The MTC values of this specification are applicable to a specific set ofplant conditions; accordingly, verification of MTC values at conditions otherthan those explicitly stated will require extrapolation to those conditions inorder to permit an accurate comparison.
The most negative MTC, value equivalent to the most positive aoderatordensity coefficient (MOC), was obtained by increaentally correcting the MOC
used in the FSAR analyses to nominal operating conditions. These corrections
TURKEY POINT - UNITS 3 4 4 B 3/4 1-1 AMENDMENT NOS 137AND 132
REACTIVITY CONTROL SYSTEMS
BASES
MODERATOR TEMPERATURE COEFFICIENT (Continued)
involved subtracting the incremental change in the MDC associated with a corecondition of all rods inserted (most positive MDC) to an all rods withdrawncondition and, a conversion for the rate of change of moderator density withtemperature at RATED THERMAL POWER conditions. This value of the MDC was thentransformed into the limiting MTC value -3.5 x 10-~ hk/k/4F. The MTC valueof -3.0 x 10-~ bk/k/4F represents a conservative value (with corrections forburnup and soluble boron) at a core condition of 300 ppm equilibrium boronconcentration and is obtained by making these corrections to the limiting MTCvalue of -3.5 x 10-~ hk/k/4F.
The Surveillance Requirements for measurement of the MTC at the beginningand near the end of the fuel cycle are adequate to confirm that the MTC remainswithin its limits since this coefficient changes slowly due principally to thereduction in RCS boron concentration associated with fuel burnup.
3/4.1.1.4 MINIMUM TEMPERATURE FOR CRITICALITY
This specification ensures that the reactor will not be made criticalwith the Reactor Coolant System average temperature less than 5414F. Thislimitation is required to ensure: (1) the moderator temperature coefficientis within it analyzed temperature range, (2) the trip instrumentation is withinits normal operating range, (3) the pressurizer is capable of being in anOPERABLE status with a steam bubble, and (4) the reactor vessel is above itsminimum RTNDT temperature.
3/4. 1. 2 BORATION SYSTEMS
The Boron Injection System ensures that negative reactivity control isavailable during each mode of facility operation. The components required to
0~4 erform this function include: (1) borated water sources 2 char ',separa e ow a s 4 boric acid transfer pcs,
With the RCS average temperature above 2004F, a minimum of two boroninjection flow'paths are required to ensure single functional capability inthe event an assumed failure renders one of the flow paths inoperable. Oneflow path from the charging pump discharge is acceptable since the flow pathcomponents subject to an active failure are upstream of the charging pumps.
TURKEY POINT - UNITS 3 4 4 B 3/4 1-2 AMENDMENT NOS 137AND 132
REACTIVITY CONTROL SYSTEMS
BASES
BORATION SYSTEMS (Continued)
The boration flow path specification allows the RWST and the boric acidstorage tank to be the boron sources. Oue to the lower boron concentration inthe RWST, borating the RCS from this source is less effective than boratingfrom the boric acid tank and additional time may be required to achie e thedesired SHUTDOWN MARGIN required by ACTION statement restrictions.
The ACTION statement restrictions for the boration flow paths allowcontinued operation in mode 1 for a limited time period with either borationsource flow path or the normal flow path to the RCS (via the regenerative heatexchanger) inoperable. In this case, the plant capability to borate andcharge into the RCS is limited and the potential operational impact of thislimitation on mode 1 operation must be addressed. With both the flow pathfrom the boric acid tanks and the regenerative heat exchanger flow pathinoperable, immediate initiation of action to go to COLD SHUTDOWN is requiredbut no time is specified for the mode reduction due to the reduced plantcapability with these flow paths inoperable.
Two charging pumps are required to beOPERABLE to ensure single unctlona capabs s y >n t e event an assumefa'1 re e ders one of the pumps or power su lies inoper ble.
us su >n the pumps can be ed rom e> er t eEmergency Diesel enera or o he offsite grid through %Ac tar tuptransformer. c4
The boration capability of either flow path is sufficient to provide the.required SHUTDOWN MARGIN in accordance with Figure 3.1-1 from expectedoperating conditions after xenon d cay and cooldown to 2004F. The maximum A
p cte bor tion capabilit re ui :ment occurs at
With the RCS temperature below 2004F, one boron infection source flowpath is acceptable without single failure consideration on the basis of thestable reactivity condition of the reactor and the additional restrictionsprohibiting CORE ALTERATIONS and positive reactivity changes in the event thesingle boron injection system source flow path becomes inoperable.
The boron capability required belowSHUTDOWN MARGIN of lX dk/k after xenon1404F. This condition requires of thefrom the borfc acid storage tanks orfrom the RWST.
2004F is sufficient to provide aay and cooldown from 2004F to
allons ofgallons o ppa borated water
TURKEY POINT - UNITS 3 4 4 B 3/4 1-3
44ak a.s wt3. 5'&+3h~*~n. )ca u 'itNENOMENT NOSZ3 AND 132
REACTIVITY CONTROL SYSTEHS
BASES
BORATION SYSTEHS (Continued)
The charging pumps are demonstrated to be OPERABLE by testing as requiredby Section XI of the ASME code or by specific surveillance requirements in thespecification. These requirements are adequate to determine OPERABILITYbecause no safety analysis assumption relating to the charging pump performanceis more restrictive than these acceptance criteria for the pumps.
The boron concentration of the RWST in conjunction with manual addition ofborax ensures that the solution recirculated within containment after a LOCA
will be basic. The basic solution minimizes the evolution of iodine andminimizes the effect of chloride and caustic stress corrosion on mechanicalsystems and components. The temperature requirements for the RWST are basedon the containment integrity and large break LOCA analysis assumptions.
The OPERABILITY of one Boron Injection System during REFUELING ensuresthat this system is available for reactivity control while in
N QjCLTThe OPERABILITY associa e with the
boric acid tank e ensures t at he so ubl >ty of the oron solution willbe maintained. mdiv Q
(+)One channel of heat tracing is sufficient to maintain the specifiedtemperature limit. Since one channel of heat tracing is sufficient to maintainthe specified temperature> operation with one channel out-of-service ispermitted for a period of 30 days provided additional temperature surveillancei s per formed..
3/4. 1. 3 MOVABLE CONTROL ASSEHBLIES
The specifications of this section ensure that: (1) acceptable power distri-bution limits are maintained, (2) the minimum SHUTDOWN MARGIN is maintained, and(3) the potential effects of rod misalignment on associated accident analyses
are'imited.OPERABILITY of the control rod position indicators is required todetermine control rod positions and thereby ensure compliance with the controlrod alignment and insertion limits continue. OPERABLE condition for theanalog rod position indicators is defined as being capable of indicating rodposition to within RI2 steps of the demand counter position. For the ShutdownBanks and Control Banks A and B, the Position Indication requirement is definedas the group demand counter indicated position between 0 and 30 steps withdrawninclusive, and between 200 and 228 steps withdrawn inclusive. This permitsthe operator to verify that the control rods in these banks are either fullywithdrawn or fully inserted, the normal operating modes for these banks.Knowledge of these bank positions in these two areas satisfies all accidentanalysis assumptions concerning their position. For Control Banks C and 0, the.Position Indication requirement is defined as the group demand counter indicatedposition between 0 and 228 steps withdrawn inclusive.
s ss 'no (omit )4, ~ sat g ml4 I Ys<f $ mal c+ci'O'-'NI,"" I ">'s-' %a e"k 0mL ~ ti S.S sm
'I cattnt Csdt ls) .
3/4. 9 REFUELING OPERATIONS
BASES
3/4.9. 1 BORON CONCENTRATION
The limitations on reactivity conditions during REFUELING ensure that:(1) the reactor will remain subcritical during CORE ALTERATIONS, and (2) a
uniform boron concentration is maintained for reactivity control in the watervolume having direct access to the reactor vessel. These limitations areconsistent with the initial conditions assumed for the boron dilution incidentin the safety analyses. With the required valves closed during refuelingoperations the possibility of uncontrolled boron dilution of the filled portionof the RCS is precluded. This action prevents flow to the RCS of unboratedwater by closing flo aths f sources of unborated water. The borationrate requirement of pm of boron or equivalent ensures thecapability to restore th SHU ARG N with one OPERABLE charging pump.
3/4. 9. 2 INSTRUMENTATION 0 <1I (sdsH )The OPERABILITY of the Source Range Neutron Flux Monitors ensures that
redundant monitoring capability is available to detect changes in the reactivitycondition of the core. There are four source range neutron flux channels, twoprimary and two backup. All four channels have visual and alarm indication inthe control room and interface with the containment evacuation alarm system.The primary source range neutron flux channels can also generate reactor tripsignals and provide audible indication of the count rate in the control room
and containment. At least one primary source range neutron flux channel toprovide the required audible indication, in addition to its other functions,and one of the three remaining source range channels shall be OPERABLE tosatisfy the LCO.
3/4 ~ 9. 3 DECAY TIME
The minimum requirement for reactor subcriticality pi.or to movement ofirradiated fuel assemblies in the reactor vessel ensures that sufficient timehas elapsed to allow the radioactive decay of the short-lived fission products.This decay time is consistent with the assumptions used in the safety analyses.
3/4. 9. 4 CONTAINMENT BUILDING PENETRATIONS
The requirements on containment building penetration closure and OPERABILITY
ensure that a release of radioactive material within containment will be
restricted from leakage to the environment. The OPERABILITY and closurerestrictions are sufficient to restrict radioactive material release from a
fuel element rupture based upon the lack of containment pressurization potentialwhile in the REFUELING HODE.
3/4. 9. 5 COHHUNICATIONS
The requirement for coaeunications capability ensures that refuelingstation personnel can be promptly informed of significant changes in thefacility status or core reactivity conditions during CORE ALTERATIONS.
TURKEY POINT - UNITS 3'8 4 8 3/4 9-1 AHENDHENT NOS.137 AND 132
Appendix 7
Marked-up Safety Analysis Report Pages
A7-1
Safet Anal sis. Re ort Inserts
Insert A
...to support a cooldown to cold shutdown conditions without letdown. Under
these conditions, adequate boration can be achieved simply by providing makeup
for coolant contraction from a boric acid tank and the refueling water storage
tank. The minimum volume maintained in the boric acid tanks, therefore, isthat volume necessary to increase the RCS boron concentration during the earlyphase of the cooldown of each unit such that subsequent use of the refuelingwater storage tank for contraction makeup will maintain the required shutdown
margin throughout the remaining cooldown. In addition, the boric acid tanks
have sufficient boric acid solution to achieve cold shutdown for each unit ifthe most reactive RCCA is not inserted.
Insert B
...forty minutes when a feed and bleed process is utilized (less than 30
minutes when the available pressurizer volume is utilized). In forty...
Insert C
The solubility limit for 3.5 weight percent boric acid is reached at a
temperature of 50'F. This temperature is sufficiently low that the normally
expected ambient temperatures within the auxiliary building will maintain
boric acid solubility.
Insert 0
Boration to the cold shutdown concentration is also achievable without letdown
when boration is performed in conjunction with the plant cooldown through the
required makeup for coolant contraction. Specifically, if boric acid is
A7-2
injected first from the boric acid tanks and then from the refueling water
storage tank to maintain constant pressurizer level during the cooldown,
sufficient boric acid will be added to the RCS to maintain the required
shutdown margins.
A7-3
The reactivity control systems provided are capable of making and
holding the core subcritical from any hot standby or hot operating
condition, including those resulting from power changes.
The Rod Cluster Control (RCC) assemblies are divided into two
categories comprising control and shutdown rod groups. One control
group of RCC assemblies is used to compensate for short term reactivitychanges at power such as those produced due to variations in reactor
power requirements or in coolant temperature. The chemical shim controlis used to compensate for the more slowly occurring changes in reactivitythroughout core life such as those due to fuel depletion and fissionproduct buildup and decay.
The shutdown groups are provided to supplement the control groups
of RCC assemblies to make the reactor at least one per cent subcritical(k 0.99) following trip from any credible operating conditioneffto the hot, zero power condition assuming the most reactive RCC assembly
remains in the fully withdrawn position.
Any time that the reactor is at power, the quantity of boric acid retained
in the boric acid tanks and ready for injection will always exceed
that quantity require Wns e.rj
cfgSik
Boric acid is pumped from the boric acid tanks by one of two boric
acid transfer pumps to the suction of one of three charging pumps
which inject boric acid into the reactor coolant. Any charging pump
and either boric acid transfer pump can be operated from diesel generator
power on loss o ower. Boric acid can be injected by oneS>o.mlo
pump at a rate which takes the reactor to hot ~th no rods
inserted in less than additional minutes,KA,5<'tT
enough boric acid can be injected to compensate for xenon decay although
xenon decay below the equilibrium operating level does not begin untilapproximately I5 hours after shutdown. If two boric acid pumps are
available, these time periods are reduced..Additional boric acid
injection is employed if it is desired to bring the reactor to cold
shutdown conditions.
1.3-13
Z'e.rk 8Any time that the reactor is at pover, the quantity of boric acid 'retained inthe boric acid tanks an ready for injection alvays exceeds that required
This quantity also exceeds that required to bring thereactor to hot and to compensate for subsequent xenon decay.
oPfsi 4Boric acid is pumped from the, boric acid tanks by one ofpumps to the suction of one of three charging pumps vhichthe reactor coolant. Any charging pump and either boric
tvo boric acid transferinject boric acid intoacid trans fer pump can
be operated from diesel generator pover on loss of ~~ pover. Boric ac'd
can be injected by one pump at a rate vhich takes the reactor to hot
vith no rods inserted in less than additionalminutes, enough boric acid can be injected to compensate for xenon decay
although xenon decay belov the equilibrium operating level does not begin untilC
approximately 15 hours a fter shu tdovn. If tvo boric acid pumps are available,these time periods are reduced. Additional boric acid injection is employed ifit is desired to bring the reactor to cold shutdovn conditions.
. Znsmt'
On the basis of the above, thc injection of boric acid is shovn to afford backup
reactivity shutdovn capability, independent of control zod clusters vhich
normally serve this function in the short term situation. Shutdown for long
term and reduced temperature conditions can be accomplished vith boric acid
injection using redundant components, thus achieving thc measure of reliabilityimplied by the criterion.
Alternately, boric acid solution at lover concentration
refueling vater tank. This solution can bc transferred
pumps. The zeduced boric concentration lengthens the
equivalent shutdown.
can bc supplied from the
directly by the charging
time required to achieve
If pressuzc is reduced in the primary, a second alternative method comprises the
injection of boric acid solution by operation of the safety injection pumps
taking suction from thc zefueling water storage tank.
3.1.2-6 Rev. 1-11/83
Event specific analyses were performed to evaluate the acceptability of securingvarious loads at given times for the one EDG available case. It is acceptable, forthe operator to secure the RHR pump at about 30 minutes after accident initiatibnor both small break and large break loss of coolant accidents (LOCA). The
operator may also secure one containment spray pump at approximately 30 minutes
following initiation of a LOCA. These actions serve to reduce EDG loading.
The normal containment coolers (NCCs) which are required for normal operation are
tripped on loss of offsite power and are blocked from automatically restarting upon
restoration of bus voltage. Manual control capabilities are provided in the
control room. Operator actions required to manually load the NCCs for a unit in a
non-accident condition are specified in the EOPs which includes assessing the
available capacity of the EDGs. Containment heat removal for a unit in an accidentcondition is accomplished via the Emergency Containment Coolers and Containment
Spray Systems.
The Boric Acid (BA) transfer pump upon Loss of OffsitePower (LOOP) remain deenergized for the short term (up to 8 hours). Manual controlis available in the control room for the BA transferpumps. The EOPs specify operator actions required to manually load the BA transfer
umps which include assessing the available capacity of the EDG.
The Instrument Air Compressors (IACs) are blocked (by administrative control ofbreakers) from automatic starting whenever offsite power is not available. The
unavailability of the IACs following a LOOP is adequately compensated for through
the use of air receivers, nitrogen accumulators, and non-safety related,self-contained air compressors that do not require the EDG for power.
The turbine auxiliaries such as the turbine turning gear oil pump, turbine bearinglift pump, and turbine turning gear drive provide a protective function to the main
turbine generator. Accordingly, these turbine auxiliaries are blocked from
automatic starting whenever offsite power is not available. While these loads are
not required to be powered following a LOOP, the operator may manually initiatethese as specified in the EOPs which include assessing the available capacity ofthe
EDG'he
CRDM cooler fans are required for normal operation only and are shed during
diesel loading. If required, CRDM cooler fans can be manually loaded onto the
EDGs. Strict administrative controls must be used in the addition of manual loads
in this condition of plant operation to ensure that the EDGs are not overloaded.
8.2-18 Rev 5 7/87
Criterion: The reactivity control systems provided shall be capable of makingthe core subcritical under credible accident conditions vithappropriate margins for contingencies and limiting any subsequentreturn to pover such that there will be no undue risk to thehealth and safety of the public. (GDC 30)
Normal reactivity shutdovn capability is provided by RCC assemblies, withboric acid injection used to compensate for the long term xenon decaytransient and for cooldown. Any time that the unit is at power, the quantityof boric acid retained in the boric acid tanks and ready for injection villalways exceed that quantity required Thisquantity vill alvays exceed the quantity of boric acid required to bring thereactor to hot d to compensate for subsequent xenon decay.
sf~>4 Z~se& AThe boric acid solution is trans erred from the boric acid tanks by boric acidpumps to the suction of the charging pumps vhich inject boric acid into thereactor coolant. Any charging pump and any boric acid transfer pump can be
operated from diesel generator power on loss of power. Boric acid can be
injected by one charging pump and one boric acid transfer pump at a rate whichshuts the reactor down vith no rods inserted in less than
~s4eoa additional minutes, enough boric acid can be injected to compensate
for xenon decay although xenon decay bolos the equilibrium operating levelvillnot begin until approximately 12-15 hours after shutdown. Zf tvo boric Mec-acid pumps and tvo charging pumps are available, these time periods are
treduced. Additional boric acid is employed if it is desired to bring the
reactor to cold shutdown conditions.
On the basis of the above, the injection of boric acid is shown to affordbackup reactivity shutdown capability, independent of control rod clustersvhich normally serve this function in the short term situation. Shutdown forlong term and reduced temperature conditions can be accomplished vith boric
acid injection using redundant components.
0134F 9.2-3 Rev 8 7/90 '
Hydrogen is automatically supplied, as determined by pressure control, to the
vapor space in the volume control tank, vhich i.s predominantly hydrogen an'd
atcr vapor. The hydrogen supply line has an excess flov valve (Fig 11.1-2)
upstream and outside of the Charging Pump Room which vill automatically close
if the hydrogen flov increases beyond its specific flow setting due to a
downstream pipe rupture. The hydrogen wi.thin this tank i.s supplied to the
reactor coolant for maintainiag a low oxygen concentration. Fission gases are
periodically removed from the system by ventiag the volume control tank to the
Waste Disposal System.
The charging pumps take suction from the volume control tank and return the
coolant to thc Reactor Coolant System through the tube side of the
regcncrative heat exchanger.
The cation bed dcmineraliser, located downstream of the mixed bed
demincralisers, is used intermittently to control cesium activity ia the
coolant and also to remove excess li.thium vhich i.s fozmed from B (n, o, )10
Li reaction.7Q.O 4o 3.S
Boric acid is di.ssolved in hot vatcr in the batching tank to a concentration
of approximately +9- percent by vcight. The lover portion of the batching tank
i.s jacketed to permit heating of thc hatching tank solution «ith lov pressure
steain. A transfer pump is used to transfer the batch to the boric acid
tanks. Small quantities of boric acid solutioa are aetered from the discharge
of an operating transfer puap for blending vith priInary vatcr as makeup fornormal leakage or for increasing the reactor coolant boroa concentration
during normal operation.
'
0081F 9.2-6 Rev 8 7/90
9.2-6aRev 4 7/86
Excess liquid effluents containing boric acid flow from the Reactor Coolant
System through the letdown line and are collected in the holdup tanks. As
liquid enters the holdup tanks, the nitrogen cover gas is displaced to the gas
decay tanks in the Waste Disposal System through the waste vent header. The
concentration of boric acid in the holdup tanks varies throughout core life from
the refueling concentration to essentially zero at the end of the core cycle. A
recirculation pump is provided to transfer liquid from one holdup tank to
another and to recirculate the contents of individual holdup tanks.
9 '-7 Rev. l-ll/5
Liquid effluent in the holdup tanks is processed as a batch operation.Thj.s ljquid is pumped through the evaporator base and cation exchangerswhich primarily remove lithium and fission-products such as long-livedcesium. It then flows through the ion exchanger filter and into the gas
stripper where dissolved gases are removed from the liquid. The gases
are vented to the Waste Disposal System. The liquid effluent from thegas stripper enters the boric acid evaporator.
The vapor produced in the boric acid evaporator leaves the evaporator condenser
and is pumped through a condensate cooler where the distillate is cooled tothe operating temperature of the evaporator condensate demineralizers. Afternon-volatile evaporator carry over is removed by one of the two evaporatorcondensate demineralizers the condensate flows through the condensate
filter and accumulates in one of two monitor tanks. The dilute boricacid solution originally in the boric acid evaporator remains as the bottomsof the distillation process and is concentrated to approximately ~skisper cent boric acid.
3. 4 3.w ~e'%Subsequent handling of the condensate is dependent on the results of sample
'I
analysis. Discharge from the monj.tor tanks may be pumped to the primary
water storage tank, recycled through the evaporator condensate demineralizers,returned to the holdup tanks for reprocessing in the evaporator trainor discharged to the environment with the condenser circulating water when
within the allowable activity concentration as discussed in Section 11.
If the sample analysis of the monitor tank contents indicates that itmay be discharged safely to the environment, two valves must be opened to
provide a discharge path. As the effluent leaves, it is continuously
monitored by the waste disposal system liquid effluent monitor. If an
unexpected increase in radioactivity is sensed, one of the valves in the
discharge line to the condenser circulating water closes automatically and
an alarm sounds in the control room.
Boric acid evaporator bottoms are discharged through a concentrates filterto the concentrates holding tank. Solution collected in the concentrates
holding tank is sampled and then transferred to the boric acid tanks j.f
9. 2-8
Reactor Makeu Control
The reactor makeup control consists of a group of instruments arrangedto provide a manually pre-selected makeup composition to the chargingpump suction header or the volume control tank. The makeup controlfunctions are to maintain desired operating fluid inventory in thevolume control tank and to adjust reactor coolant boron concentrationfor reactivity and shim control.
Makeup for normal leakage is regulated by the reactor makeup
control which is set by the operator to blend water from the primarywater storage tank with concentrated boric acid to match the reactorcoolant boron concentration.
The makeup system also provides concentrated boric acid or primary water toeither increase or decrease the boric acid concentration in the ReactorCoolant System. To maintain the reactor coolant volume constant, an
equal amount of reactor coolant is let down to the holdup tanks; Should
the letdown line be out of service during operation, sufficient volume
exists in the pressurizer to accept the amount of boric acid necessary
for ho& sf~ 4'4g.
Makeup water to the Reactor Coolant System is provided by the Chemical
and Volume Control System from the following sources:
a) The primary water storage tank, which provides water for dilutionwhen the reactor coolant boron concentration is to be reduced
b) The boric acid tanks, which supply concentrated boric acid solutionwhen reactor coolant boron concentration is to be increased
c) The refueling water storage tank, which supplies borated water
for emergency makeup ~r~(d) The chemical mixing tank, which is used to inject small quantities
of solution when additions of hydrazine or pH control chemical
are necessary.
9.2-11
I ~
Boric Acid Tanksense.r+ 6
The boric acid tank capacities are sized to store sufficient boric acidsolutio
3,SThe concent n o r ac solut on in storage is maintained between
by weight. Periodic manual sampling is performed and cor-rective action is taken, if necessary, to ensure that these limitsare maintained. Therefore, measured amounts of boric acid solution can
be delivered to the reactor coolant to control the concentration. The
combination overflow and breather vent connection has a water loop sealto minimize vapor discharge during storage of the solution. The tanks are
constructed of austenitic stainless steel.
Batchin Tank
solution for the boric acid tank. The basis for makeup is reactor coolant
leakage of 1/2 gpm at beginning of core life. The tank may also be used
for solution storage. A local sampling point is provided for verifyingthe solution concentration prior to transferring it to the boric acid tank
or for draining the tank.
9.2-23 Rev. 3-7/85
The tank manway is provided with a removable screen to prevent entry of foreignparticles. In addition, the tank is provided with an agitator to improve mixingduring batching operations'he tank 'is constructed of austenitic stainlesssteel, and is not used 'to handle radioactive substances'he tank is providedwith a steam jacket for heating the boric acid solution to+A~
Boric Acid Transfer Pum s
P8.r ~i[Two 100X capacity centrifugal pumps are used to circulate or transfer chemical
solutions. The pumps circulate boric acid solution through the boric acid tanks
and inject boric acid into the charging pump suction headers
Although one pump is normally used for boric acid batching and transfer and the
other for boric acid ,injection, either pump may function as standby for the
other. The design capacity of each pump is equal to the normal letdown flowrate. The design head is sufficient, considering line and valve losses, todeliver rated flow to the charging pump suction header when volume control tank
pressure is at the maximum operating value (relief valve setting) ~ All parts incontact with the solutions are austenitic stainless steel and other adequately
corrosion-resistant materials
The transfer pumps are operated either automatically or manually from the
control room or from a local control panel. The reactor makeup control operates
one of the pumps automatically when boric acid solution is required for makeup
or boration.
Boric Acid Blender
The boric acid blender promotes thorough mixing of boric acid solution and
reactor makeup water from the reactor coolant makeup circuit. The blender
consists of a conventional pipe fitted with a perforated tube inserts Allmaterial is austenitic stainless steel. The blender decreases the pipe 1ength
required to homogenize the mixture for taking a representative local sample.
9.2-24 Rev. 3-7/85
The gas strippers consist of a hot well with heating coil to stare strippedwater, a stripping section packed with pall rings, a spray type liquid inletheader and an overhead integral reflux condenser. Liquid flowing to the gas
strippers is controlled to constant rate by a flow controller. The gas
strippers are designed for the same flow rate as the evaporator and are5
designed to reduce the influent gas concentration by a factor of 10
Two gas stripper bottom pumps per gas stripper, operated from level control,transfer effluent from the gas stripper hot wells to the boric acid evapor-
ator via the gas stripper preheaters. Each centrifugal pump is rated
at the evaporator processing rate. The pumps are austenitic stainless
steel and one is an installed standby for the operating pump.
Boric Acid Eva orator E ui ment
Two boric acid evaporators concentrate boric acid for reuse in the Reactor
Coolant System. Borated water enters the evaporator and the liquid isconcentrated to approximately +R. eight per cent boric acid. Vapors leave
the evaporator and are condensed. The solids decontamination factor between6
the condensate and the bottoms is approximately 10 . All evaporator equipmer
is constructed of austenitic stainless steel and is supplied as a unit.Each boric acid evaporator package consists of the boric acid evaporator
feed tank, two boric acid evaporator concentrates pumps, boric acid evaporate
boric acid evaporator condenser, two boric acid evaporator condensate pumps,
boric acid evaporator condensate cooler, two vacuum pumps and associated
pi'ping. and instrumentatioe.
The boric acid evaporator feed tank has sufficient capacity to hold one
production of per cent boric acid solution produced from refueling
concentration feed. The evaporator and condenser heat transfer area is
sufficient to maintain the required feed rate. The evaporator is steam
heated. Component cooling water flows through the tube of the condenser.
9.2-27
Concentrates Filters
Two disposable synthetic cartridge type filters remove particulates from
the evaporator concentrates. Design flow capacity of each filter is equal
to the boric acid evaporator concentrates transfer pump capacity. The
vessels are made of austenitic stainless steel.
Concentrates Holdin Tank
The concentrates holding tank is sized to hold the production of concentrates
from one batch of evaporator operation. The tank is supplied with an
electrical heater which prevents boric acid precipitation and is constructed
of austenitic stainless steel.
Concentrates Holdin Tank Transfer Pum s
Two holding tank transfer pumps discharge boric acid solution from the
concentrates holding tank to the boric acid tanks or the hold up tanks. Each
canned centrifugal pump is sized to empty the concentrates holding tank in
approximately 10 minutes. The wetted surfaces are constructed of authen=ic
stainless steel and other adequately corrosion-resistant material.~ g
9.2-29
Valves
Valves that perform a modulating function are equipped with two sets of packingand an intermediate leakoff connection that discharges to the Waste Disposal
System. All other valves have stem leakage control. Globe valves are installedwith flow over the seats when such an arrangement reduces the possibility ofleakage. Basic material of construction is stainless steel for all valves
except the batching tank steam jacket valves which are carbon steel.
Isolation valves are provided at all connections to the Reactor Coolant System.
Lines entering the reactor containment also have check valves inside the
containment to prevent reverse flow from the containment.
9.2-30 Rev. 1-11/83
Relief valves are provided for lines and components that might be pressurizedabove design pressure by improper operation or component malfunction.Pressure relief for the tube side of the regenerative heat exchanger isprovided by the auxiliary spray line isolation valve which is designed to openwhen pressure under the seat exceeds reactor coolant pressure by 250 psi.Relief valves settings and capacities are given in Table 9.2-3.
Turkey Point Unit 3 has installed manual operating features to selectedair-operated valves (Table 9.6A-ll) in the Chemical and Volume ControlSystem. The installation of these features provides an alternate means ofoperating these valves if the valve misoperates due to receipt of a spuriouselectrical signal resulting from a postulated fire. These changes implementrecomnendations made as part of the Appendix R Safe Shutdown Analysis in orderto met the licensing coamitments of 10CFR50 Appendix R (see Subsection9.6A-5.6).
I~ne
All Chemical and Volume Control System piping handling radioactive liquid isaustenitic stainless steel. All piping joints and connections are welded,except where flanged connections are required to facilitate equipment removalfor maintenance and hydrostatic testing.
9 2 3 SYSTEM DESIGN EVALUATION
A high degree of functional reliability is assured in this system by providingstandby components where performance is vital to safety and by assuringfail-safe response to the most probable mode of failure.
The system has three charging pumps, each capable of supplying the normal
reactor cool'ant pump seal and makeup flow.
0081F 9.2-31 Rev 8 7/90
TABLE 9 ~ 2-2
NOMINAL CHEMICAL AND VOLUME CONTROL SYSTEM PERFORMANCE
Unit design life, years
Seal water supply flow rate, gpm*~
Seal water return flow rate, gpm
Normal letdown flow rate, gpm
Maximum letdown flow rate, gpm
Normal charging pump flow (one pump), gpm
Normal charging line'low, gpm
40
24
60
120
69
45
Maximum rate of boration with one transfer andone charging pump, ppm/min, (from inititalRCS concentration of 1800 ppm)
Equivalent cooldown rate to above rate ofboration, P/min
Maximum rate of boroa dilution (two chargingpumps) ppm/hour rom initial RCSconcentration of 2500 ppm) 350
Two~ump rate of boration, using refuelingwater, ppm/min (from initial RCSconcentration of 10 ppm) 6.2
Equivalent cooldown rate to above rate ofboration, P/min
1,7
Temperature of reactor coolant entering systemat full power, P (design) 555.0
Temperature of coolant return to ReactorCoolant System at &QJ. power, F (design) 493.0
Normal coolant discharae temperature toholdup taaks, P
3.'C) wa,lAmount of ron so ution uired to
meet cold utdown requirements
gallons nc ding considera on or one stu rod) 98ee- 7WV0
Sl Ml 42-
*eVolumetric flow rates in gpe are based on 130 F and 2350 psig.
0133P Rev 8 7/90
TABLE 9.2-3
PRINCIPLE COHPONENT DATA SUH HARY
Sheet 1 of 2
Quantity1
HeatTransferBtu/hr
Letdown LetdownFlow QTlb/hr F
Design DesignPressure Temperaturepsig,shell/tube F,shell/tube
Heat ExchangersRegenerativeNon regenerativeSeal waterExcess letdown
8.65 x 10614.8 x 1062.17 x 1064.75 x 106
29,826 26529,826 163126,756 1712,400 360
2485/2735150/600150/150150/2485
650/650250/400250/250250/650
Quantity Type
CapacityEachgpm Head
DesignPressurePslg
DesignTemperatureF
PumpsChargingBoric acid transferHoldup tank recirculationH onitor tankConcentrates holdingtank transferGas stripper feedGas stripper bottom
34*1*2*
2*3*2
Pos. disp].C entrifugalCentrifugalCentrifugal
CannedCannedC entrifugal
7760500100
202512.5
2385 psi235 ft.100 ft.150 ft.
150 ft.185 ft.93 ft
3000150150150
7515075
250250200200
250200300
P7
TanksVolumeBoric acid.Chemical mixingBatchingHo du
Q uantity1
1
3*1
1*3*
Type
Vert.Vert.Vert.Jacket Btm.
ert.
Volume, Each
300 ft3gal
6.0 gal800 ga]13 000
Q3$ ',oM p~l
DesignPressurePslg
75 Int/15ExtAtmos+150.Atmos.15
//~os.
DesignTemperatureF
250250250250
00
Appendix 8
Future Fuel Cycle Review for Comparison of Bounding Physics Parameters( )
Parameter
Core Power (100%%uo)
Shutdown Margin T>200'F
Shutdown Margin T/200'F
RCS Average Temperature (0/ Power)
Moderator Temperature Coefficient
Hot Zero Power Net Rod Worth
Hot Zero Power Rod Insertion Limit (%%uDq)
Hot Full Power Rod Insertion Limit (%%uDq)
Power Defect (/Dq)
Xenon Worth
Doppler Coefficient
Moderator Cooldown Curve
Differential Boron Worth
Scram Worth Data Uncertainty
Moderator Data Uncertainty
Doppler Data Uncertainty
IBW Data Uncertainty
Excess Scram Worth (T>200'F)
Excess Scram Worth (T$200'F)
Turke Point Units 3 and 4
<2200 MWt
<1.77%%u Dk/k
<1.0/ Dk/k
<547'F
<-3.5E(-4)Dk/k/'F (less negative)
>6.175
<2.0
<0.5
<2.4
<Table 3 (2)
Table 1 (2) (less negative)
Figure 2 (2) (less negative)
Figure 3 (2) (more negative)
<10/
<10/
<20/
<10. 9%%
>0.697% Dk/k
>1.468/ Dk/k
Notes:
(1) This table allows cycle to cycle comparison of core reload physicsparameters to those utilized in the boric acid concentration analyses.
(2) Extracted from bounding physics data provided by FPL and included as
Appendix 5 of the base report. Uncertainties and cycle to cyclevariations included in this data where applied in the conservativedirection.
Appendix 9
Analysis of Peak Xenon Scenario
1. 0 INTRODUCTION
This appendix presents the results of an analysis that is identical tothat presented in Section 5.0 of the base report with the exception ofhow the xenon transient is accounted for. Similar analyses have been
reviewed by other boric acid concentration reduction evaluations and are
included here for consideration of the reactivity design basis of theplant (see Section 2.2.6 of the base report). The final RCS boron
concentration required to maintain adequate shutdown margin is actuallyhigher in this analysis, the peak xenon case establishes the boric acidtank inventory requirement. This is discussed in greater detail in thesections that follow. Table and figure numbers in this appendix are
assigned in a manner that matches those in Section 5 of the base report.This allows direct comparison of the results of the two analyses.
2.0 BASIS
The basic differences between this analysis and the analysis of the base
report is the following:
(1) the cooldown transient is initiated at eight hours of 24 hours
(corresponding to the peak xenon condition instead of the full power
equilibrium xenon concentration) and,
(2) the subsequent cooldown boration must compensate for the decay of the
entire xenon inventory from its peak value (instead of its full power
equilibrium value).
This scenario presents a worst case near the end of the cycle when
sufficient RCS boron concentration (>0 ppm) is available to allow RCS
boron concentration to be diluted by the operator to compensate for the
post-shutdown xenon buildup in anticipation of a rapid return to power.
Starting a design basis cooldown to cold shutdown from the peak xenon
condition under these conditions will effectively increase the amount ofboron required to be charged to the RCS to compensate for the decay ofthe xenon peak back to its full power equilibrium value where theanalysis of Section 5.0 of the base report started. This is a
conservative assumption but is still achievable with reduced boric acidconcentration and the appropriate balance of boration from the boric acidtank and the refueling water storage tank during cooldown (contractionmakeup).
3.0 ANALYSIS SCENARIO
This scenario is suggested for analysis in response to the worst case
shutdown, cooldown, and boration scenario presented in References 10. 1
and 10.3 of the base report. Although it is a conservative assumption/scenario it has been analyzed in a similar manner as the scenarios ofSection 3. 1 of the base report to assess the boration system capabilitywith reduced boric acid concentration. Specifically, the borationrequired to maintain shutdown margin will be completed from the boricacid tank and refueling water storage tank in conjunction with the plantcooldown such that the volume of boric acid charged into the plant willmake up for cooldown contraction. The proposed scenario for thisanalysis is discussed below:
SHUTDOWN AND COOLDOWN AT PEAK XENON
(1) The conservative physics parameters of the base report will be used
to maximize the xenon and moderator cooldown reactivity effects.
(2) Reactor initially at hot full power (574.2 F), all rods out,equilibrium xenon at an equilibrium cycle exposure corresponding toa critical boron concentration of approximately 100-200 ppm. The
boron concentration is arbitrarily chosen to allow for dilution to 0
ppm presenting the worst case (EOC) physics parameters.
A9-2
(3) Reactor brought to hot zero power (547'F) with rods initiatingxenon transient (increase).
(4) While at hot zero power (547'F), operator maintains criticalityby diluting RCS boron to compensate for xenon buildup(anticipating a quick return to full power).
(5) At hot zero power (547'F), peak xenon condition, core is criticalwith approximately 0 ppm boron..
(6) Plant forced to go to cold shutdown (200 F): cooldown rates of100 F/hr, 90'F/hr, 50'F/hr, 25 F/hr, and 10'F/hr will be
analyzed.
(7) Zero RCS leakage (conservatively limits boron addition tocontraction makeup).
(8) Boric acid tank and refueling water storage tank used to make up forRCS contraction during cooldown and to maintain shutdown margin.
4. 0 ANALYSIS ASSUMPTIONS
Other than the variation in the treatment of xenon and the starting pointof the cooldown transient, the assumptions for this analysis are
identical to those presented in Section 4.0 of the base report.
5.0 ANALYSIS RESULTS
The analysis methodology is identical to that presented in Section 5.0 ofthe base report. The results of the peak xenon reactivity analysis are
presented in Tables 5. 1-1 through 5. 1-6. Because the endpoint boron
concentration requirement is higher in this scenario the value presented
here is used as the basis for determining the minimum boric acid tankinventory. The boron delivery analysis of Section 5.2 is based on
providing a 50 ppm margin over the minimum required cold shutdown boron
concentration of 788 ppm.
A9-3
Table 5.1-1
Required Boron Concentration vs. Temperature
Peak Xenon, Near EOC, 10'F/hr Cooldown Rate
Tem erature 'F Re uired Boron m
572.0
552.0
532.0
512.0
492.0
472.0
452.0
432.0
412.0
392.0
372.0
352.0
332.0
312.0
292.0
272.0
252.0
232.0
212.0
202.0
200.0
200.0
200.0
-321.94-222.14-114.12
-10.0085.31
171.90
250.19
320.79
384.39
441.72
493.48
540.34
582.90
621.71
657.25
689.94
720.14
748.16
774.26
786.67
789.10
726.54
788.15
A9-4
Table 5.1-2
Required Boron Concentration vs. Temperature
Peak Xenon, Near EOC, 25'F/hr Cooldown Rate
Tem erature 'F Re uired Boron m
572.0
522.0
472.0
422.0
372.0
322.0
272.0
222.0
200.0
200.0
200.0
-321.94-91.31
90.91
227.79
336.66
428.35
509.38
583.32
614.08
551.52
788.15
A9-5
Table 5.1-3
Required Boron Concentration vs. Temperature
Peak Xenon, Near EOC, 50'F/hr Cooldown Rate
Tem erature F Re uired Boron m
572.0
472.0
372.0
272.0
222.0
200.0
200.0
200.0
-321.94
73.43
288.98
433.46
495.98
522.37
459.81
788.15
A9-6
Table 5.1-4
Required Boron Concentration vs. Temperature
Peak Xenon, Near EOC, 90 F/hr Cooldown Rate
Tem erature F Re uired Boron m
572.0
482.0
392.0
302.0
212.0
200.0
200.0
200.0
-321.94
39.94
241.61
370.69
474.27
487.07
424.51
788.15
A9-7
Table 5.1-5
Required Boron Concentration vs. Temperature
Peak Xenon, Near EOC, 100'F/hr Cooldown Rate
Tem erature 'F Re uired Boron m
572.0
472.0
372.0
272.0
200.0
200.0
200.0
-321.94
68.13
272.80
404.19
483.58
421.02
788.15
A9-8
Table 5.1-6
Required Boron Concentration vs. Temperature
Mode 5 Cooldown to Refueling(Near EOC Peak Xenon Scenario)
Tem erature 'F Re uired Boron m
200 (Xenon Free)
180
160
140
135
788.15
803.68
819.21
834.74
838.62
A9-9
Appendix 10
Computer Code Certificate and Input
A10-1
COIIBUSTIOX KXCIXKEiBXC
COMPUTER CODE CERTIFICATE
The following code, as noted by its name, version number, and permanent file identification, is herebyapproved for design application.
Code NameBACR
Version Number REV. 00
Permanent File Identification BACR (00)
C IBII PC OR IBM PC COMPATIBLE
I CODE CLASSiFICATION
0 C-E Proprietary Code
Q C-E UtilityCode
0 C-E NRC Approved Code
0 Non C-E IState of the Art) Code
DESIGNATED PROGRAM ENGINEER
G.F. CAIIUTIIERS 9421/Iiechanical P I S
Msnger 5 Oept/Section Name
9421-423CEP Code
Code TestingCompleted By
W. E.. IIIGGIIISIndependent Reviewer
Date 0-
r 0 -(3 815
C.E 0013183 (5/ddt
7/Z/90 FPSL - (120 F BAT AHD RMST)
TURKEY POINT SORIC ACID COHCEHI'RATION REDUCTION EFFORT
EQUILIBRIUN XEHOH SCENARIO RUST AT 1950 PPN
TABLE I THROUGH TABLE X PARAHETERS
RCS vatet voluneNODES 1-4Specific volune ofconpressed vater at572 F 4 2250 psia
PZR vater vol.(100K PONER)
Specific voLLsne ofsatul'ated vater at2250 psia
Specific volune ofccrrpressed vater at200F S 3SO psia
RCS pressure
PZR OX POMER (NOOFSS-6)
Specific vol. of vater200F 8 14.7 psia
Specific voL, ofsaturated eater0 14.7 psia
RCS vater voluneNCOES 5-6
RCS NASS NODES 5 6
RUST terperature
BAT tenpcrature
Density of vaterat 120 F
Nass of boric acidper gal of solutiona 120 dog F, 1950 PPN
Density of vater0 120 deg F
Ness of boric acidper gal of solution8 120 dcg F, 3.5 vt.y.
Ness of boric acid
8,015.00000 cu.ft
0.02204
808,0000
cu.ft./Lbn
cu.ft
0.0269 cu.ft./Lbm
0.01662 cu.ft./ibm
400.00000f
520.00000 cu.ft.
0.01664 cu.ft./Lbm
0.016?2
8,015.00000
cu. ft./Lbrn
cu.ft
LSN
deg. F
degy F
8.24980 ibm/gal
0.0930S
8.24980 Lbm/sal
0.29922
963,341.34615
120.00000
120.00000
Rtà ¹10
11
12}31415
16
1718
192021
22232425
26272829303'1
32333435363738394041
42434445
464748495051
52535455
565?585960
per gaL of solutionQ 120 deg F, 3.25 xt.X
Hass of boric acidper gal of solutionQ 120 degF, 3.0 xt.X
Hase of boric acidper gal of solutionQ 120 F, 2350 pprn
Density of xaterat 120 deg.F
Nasa of boric acidper gaL of solutionQ 120 F, 2150 ppm
Xass of boric acidper gaL of solutionQ 120 F, 3.75 xtX
Nasa of boric acidper gal of solutionQ 120 F, 4.00 xt)L
IHLTlhi. SYSTEH HASS
COHYERSLOM FACTOR BETMEEN
xt.X b/a 8 ppm boron
RCS MATER NASS =H(RlES1-4
PZR INTER NASS ~NOOES1 4
(Q2250 psia)
PZR MATER NASS =modes'i-4
(Q350 psia)
PZR WLTER NASS modes5-6
(Q14.7 pain)
LXITIALTOTAL STS HASS
NOES 5 6
Kass of boric acidper gaL of solutionQ 120 F, 2.75 xtX
Hans of boric acidper gal of solutionQ 'l20 F, 2.50 xtX
IHLT)AL TOTAL SYS NASS
8 c0.27712 Lbm
0.25515 Lbn
0.11240 Lbn
8.24980i lbn/gal
0.10271 Lbn
0.32142i Lbn
0.343?4 lbn
363,623.99056 Lbm
29,948.109?1 Lbm
48,325.35885 Lbn
31,100.4?84?I ibm
994,441. 82462 LSH
0.23328
0.21153
393, 572. 10027; lbnl
1,748 '4000 ppn
61
62636465666768697071
727374
?5767778?9eo81
82838485868?88899091
929394
95
96979899
100101
102103104
105106107108109
110
111
112113
114
115
116
117118119120
HOOSS 5 6after fCb
TOTAL RCS/SDCS MATER HASS
AT SDCS START
TOTAL MATER NSSAT SDCS START
994,441 .82462
892538.9755
940864.33435
LBN 'l21
122123'l24125
126
127128129
130131
132'lt t $$ ttt » ttt Qttt tttt t t It
TOTAL PAGE 885
J
C.