palo verde, units 1, 2, and 3, core operating limits ... · palo verde nuclear generating station...

OapsTechnical Specification 5.6.5.d

Palo VerdeNuclear Generating Station5871 S. Wintersburg Road Tonopah, AZ 85354

102-07682-MSC/MDD April 12, 2018

ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

Subject:

Dear Sirs:

Palo Verde Nuclear Generating Station Units 1, 2, and 3 Docket Nos. STN 50-528, 50-529, and 50-530 Unit 1 Core Operating Limits Report (COLR), Revision 25 Unit 2 Core Operating Limits Report (COLR), Revision 21 Unit 3 Core Operating Limits Report (COLR), Revision 24

Pursuant to Palo Verde Nuclear Generating Station (PVNGS) Technical Specifications, Section 5.6.5.d, enclosed are the Units 1, 2, and 3 Core Operating Limits Report (COLR), Revisions 25, 21, and 24, respectively, which were made effective April 6, 2018. The change implemented by these revisions includes the following:

• Revision to Analytical Methods to add the references associated with Westinghouse Next Generation Fuel (NGF).

• Administrative and editorial corrections made for clarity.

These changes affect several pages. Revision bars have been applied to the changes.

No commitments are being made to the NRC by this letter. Should you need further information regarding this submittal, please contact Matthew S. Cox, Licensing Section Leader at (623) 393-5753.

Sincerely,

Michael D. DiLorenzoNuclear Regulatory Affairs Department Leader

MSC/MDD/TMJ/sma

Enclosures:

Unit 1 Core Operating Limits Report, Revision 25 Unit 2 Core Operating Limits Report, Revision 21 Unit 3 Core Operating Limits Report, Revision 24

cc:K. M. Kennedy S. P. Lingam C. A. Peabody

NRC Region IV Regional Administrator NRC NRR Project Manager for PVNGS NRC Senior Resident Inspector for PVNGS

A member of the STARS Alliance LLC Callaway • Diablo Canyon • Palo Verde • Wolf Creek

Enclosure

PVNGS Unit 1 Core Operating Limits Report (COLR)Revision 25

PALO VERDE NUCLEAR GENERATING STATION (PVNGS)

UNITl

CORE OPERATING LIMITS REPORT

Revision 25

Effective April 6, 2018

Responsible EngineerDate

Wenzel,J DN:cn=Wenzel, Richard

Rirh::^rrl /\R(Z99534)rVIV-llOILJ jj Re^on: lam the author of

y?„^thisdocument

R(Z995J4)Independent ReviewerDate

• 1 (P Digitally signed by Geiszler,(j G 1 SZ1 0 r, 11 Keliy J(Z07064))1 DN: cn=Geiszler, Kelly

KpIIv /\j(Z07064)1 vC * * y K Reason: 1 have reviewed this//__ document)

J{Z0706J^)Responsible Section LeaderDate

^9 r 1 S 0 n ^ li p|g|,3||y Oiatles

1 Ef(V55086)1^ ^ ^ 1 ^ C jj \DN: cn=Karlson, Charles F(V55086)

^ 1 1 cl 1 1^0 jJ R^on: lam approving thisM do^n^jit=sa^

r- l\ Mw~ r-^0^8.04.03 08:25:18-07'00'F(V55086)----------------------------------------------------------------------------------------------------------------------- 1

Page 1 of 29

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 25 |

Table of Contents

Description

Cover Page

Table of Contents

List of Figures

List of Tables

Affected Technical Specifications

Analytical Methods

Page

1

2

3

4

5

6

CORE Operating Limits

3.1.1 Shutdown Margin (SDM) - Reactor Trip Breakers Open

3.1.2 Shutdown Margin (SDM) - Reactor Trip Breakers Closed

3.1.4 Moderator Temperature Coefficient (MTC)

3.1.5 Control Element Assembly (CEA) Alignment

3.1.7 Regulating CEA Insertion Limits

3.1.8 Part Strength CEA Insertion Limits

3.2.1 Linear Eleat Rate (LHR)

3.2.3 Azimuthal Power Tilt (Tq)

3.2.4 Departure From Nucleate Boiling Ratio (DNBR)

3.2.5 Axial Shape Index (ASl)

3.3.12 Boron Dilution Alarm System (BDAS)

3.9.1 Boron Concentration

11

11

11

11

11

12

12

12

12

13

13

13

Page 2 of 29


List of Figures

Description

Figure 3.1.1-1

Figure 3.1.2-1

Figure 3.1.4-1

Figure 3.1.5-1

Figure 3.1.7-1

Figure 3.1.7-2

Figure 3.1.8-1

Figure 3.2.3-1

Figure 3.2.4-1

Figure 3.2.4-2

Figure 3.2.4-3

Shutdown Margin Versus Cold Leg Temperature Reactor Trip Breakers Open

Shutdown Margin Versus Cold Leg Temperature Reactor Trip Breakers Closed

MTC Acceptable Operation, Modes 1 and 2

Core Power Limit After CEA Deviation

CEA Insertion Limits Versus Thermal Power (COLSS in Service)

CEA Insertion Eimits Versus Thermal Power (COLSS Out of Service)

Part Strength CEA Insertion Eimits Versus Thermal Power

Azimuthal Power Tilt Versus Thermal Power (COLSS in Service)

COLSS DNBR Operating Limit Allowance for Both CEACs Inoperable In Any Operable CPC Channel

DNBR Margin Operating Limit Based on the Core Protection Calculators (COLSS Out of Service, CEAC(s) Operable)

DNBR Margin Operating Limit Based on the Core Protection Calculators (COLSS Out of Service, Both CEACs Inoperable In Any Operable CPC Channel)

Page

14

16

17

18

20

21

22

23

Page 3 of 29


List of Tables

Description

Table 3.3.12-1 Required Monitoring Frequencies for Backup BoronDilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff> 0.98

Table 3.3.12-2 Required Monitoring Frequencies for Backup BoronDilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for 0.98 > Keff > 0.97



Table 3.3.12-5 Required Monitoring Frequencies for Backup BoronDilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff < 0.95

Page

25

Page 4 of 29


This Report has been prepared in accordance with the requirements of Technical Specification 5.6.5. The Core Operating Limits have been developed using the NRC approved methodologies specified in Section 5.6.5 b of the Palo Verde Technical Specifications.

AFFECTER PVNGS TECHNICAL SPECIFICATIONS '







3.2.1 Linear Heat Rate (LHR)



3.2.5 Axial Shape Index (ASI)



Page 5 of 29


ANALYTICAL METHODS

The COLR contains the complete identification for each of the Technical Specification referenced topical reports (i.e., report number, title, revision, date, and any supplements) and correspondence that provide the NRC-approyed analytical methods used to determine the core operating limits, described in the following documents:

T.SRef#^ Title Report No. Rev Date Suppl

CE Method for Control Element Assem- CENPD- N.A. January N.A.1 bly Ejection Analysis

(NOOl-1301-01204)0190-A 1976

The ROCS and DIT Computer Codes for CENPD- N.A. April 1983 N.A.2 Nuclear Design

(NOOl-1900-01412)266-P-A

Safety Evaluation Report related to the NUREG- N.A. March 1983 1Final Design of the Standard Nuclear 0852

September19830

Steam Supply Reference SystemsJ CESSAR System 80, Docket No. STN L

50-470 December1987 3

Modified Statistical Combination of CEN- 01-P-A May 1988 N.A.4 Uncertainties

(NOOl-1303-01747)356(V)-P-A

System 80™ Inlet Flow Distribution Enclosure N.A. February 1-P4 (NOOl-1301-01228) 1-P toLD-

82-0541993

Calculative Methods for the CE Large CENPD- N.A. March 4-P-A5 Break LOCA Evaluation Model

(NOOl-1900-01192)132 2001 Rev. 1

Calculative Methods for the CE Small CENPD- N.A. April 2-P-A6 Break LOCA Evaluation Model

(NOOl-1900-01185)137-P 1998

Letter: O.D. Parr (NRC) to F. M. Stern N.A. N.A. June 13, N.A.(CE), (NRC Staff Review of the 1975

7 Combustion Engineering ECCS Evaluation Model). NRC approval for: 5.6.5.b.6.

Page 6 of 29


T.SRef#"‘ Title Report No. Rev Date Suppl

8

Letter: K. Kniel (NRC) to A. E. Scherer (CE), (Evaluation of Topical Reports CENPD 133, Supplement 3-P and CENPD-137, Supplement 1-P). NRC approval for 5.6.5.b.6.

N.A. N.A. September 27,1977

N.A.

9 Fuel Rod Maximum Allowable Pressure (NOO1-0201-00026)

CEN-372-P-A

N.A. May1990

N.A.

10

Letter: A. C. Thadani (NRC) to A. E. Scherer (CE), ("Acceptance forReference CE Topical Report CEN-372- P"). NRC approval for 5.6.5.b.9.

N.A. N.A. April 10,1990

N.A.

11

Arizona Public Service Company PWR Reactor Physics Methodology Using CASMO-4/SIMULATE-3 (NFM-005)

NFM-005 1 August2007

N.A.

12Technical Description Manual for the CENTS Code Volume 1 (CENTS-TD MANUAL-VOL 1)

CE-NPD282-P-AVols. 1

2 March2005

N.A.



2 March2005

N.A.



2 March2005

N.A.

13

Implementation ofZIRLO^^ Cladding Material in CE Nuclear Power Fuel Assembly Designs (NOOl-1900-01329)

CENPD-404-P-A

0 November2001

N.A.

13

Optimized ZIRLO^^^(NOOl-0203-00611)

CENPD-404-P-AAddendum1-A

0 July 2006 N.A.

13

Westinghouse Clad Corrosion Model for ZIRLO and Optimized ZIRLOT’M (NOO 1-0205-00006)


0 October2013

N.A.

Page 7 of 29


T.S Title Report No. Rev Date Suppl

14

HERMITE, A Multi-Dimensional Space-Time Kinetics Code for PWR Transients(HERMITE-TOPICAL)

CENPD-188-A

N.A. July1976

N.A.

15

TORC Code, A Computer Code for Determining the Thermal Margin of a Reactor Core (NOOl-1301-01202)

CENPD-161-P-A

N.A. April1986

N.A.

16

CETOP-D Code Structures and Modeling Methods for San Onofre Nuclear Generating Station Units 2 and 3 (NOOl-1301-01185)

CEN-160(S)-P

1-P September1981

N.A.

17

“Safety Evaluation related to Palo Verde Nuclear Generating Station, Unit 2 (PVNGS-2) Issuance of Amendment on Replacement of Steam Generators and Uprated Power Operation, (September29,2003) and“Safety Evaluation related to Palo Verde Nuclear Generating Station, Units 1,2, and 3 - Issuance of Amendments Re: Replacement of Steam Generators and Uprated Power Operations andAssociated Administrative Changes, (November 16, 2005).”

N.A. N.A. September29,2003

November16,2005

N.A.

18CPC Methodology Changes for the CPC Improvement Program (NOOl-1303-02283)

CEN-310-P-A

0 April1986

N.A.

19Loss of Flow, C-E Methods for Loss ofFlow Analysis(NOOl-1301-01203)

CENPD-183-A

0 June1984

N.A.

20Methodology for Core Designs Containing Erbium Burnable Absorbers (NOO1-0201-00035)

CENPD-382-P-A

0 August1993

N.A.

Page 8 of 29


Ref#^ Title Report No. Rev Date Suppl

Verification of the Acceptability of a 1- Pin Burnup Limit of 60 MWD/kgU for Combustion Engineering 16x16 PWR Fuel(NOO1-0201-00042)

CEN-386-P-A

August1992

N.A.

CE 16x16 Next Generation Fuel Core Reference Report (NOO 1-0203-00614)

WCAP-16500-P-A

August2007

N.A.

Application of CE Setpoint Methodology for CE 16x16 Next Generation Fuel (NGF)(NOOl-0205-00063)

WCAP-16500-P-A

December2010

Evolutionary Design Changes to CE 16x16 Next Generation Fuel and Method for Addressing the Effects of End-of-Life Properties on Seismic and Eoss of Coolant Accident Analysis (NOOl-0205-00048)

WCAP-16500-P-A

June 2016 2-P-A

23

VIPRE-01 Modeling and Qualification for Pressurized Water Reactor Non-EOCA Thermal-Hydraulic Safety Analysis(NOO1-0205-00002)

WCAP-14565-P-A

October1999

N.A.

Addendum 1 to WCAP-14565-P-A Qualification of ABB Critical Heat Flux Correlations with VlPRE-01 Code (NOOl-0205-00003)

WCAP-14565-P-A,Addendum1-A

August2004

N.A.

23

Addendum 2 to WCAP-14565-P-A, Extended Applications of ABB-NV Correlation and Modified ABB-NV Correlation WLOP for PWR Eow Pressure Applications (NOOl-0205-00004)

WCAP-14565-P-A,Addendum2-P-A

April 2008 N.A.

ABB Critical Heat Flux Correlations forPWR Fuel(NOO1-0205-00042)

CENPD-387-P-A

May 2000 N.A.

Page 9 of 29



25

Westinghouse Correlations WSSV and WSSV-T for Predicting Critical HeatFlux in Rod Bundles with Side-Supported Mixing Vanes (NOOl-0203-00615)

WCAP-16523-P-A

0 August2007

N.A

26

Implementation of Zirconium Diboride Burnable Absorber Coatings in CE Nuclear Power Fuel Assembly Designs (NOOl-0205-00226)

WCAP-16072-P-A

0 August2004

N.A.

a. Corresponds to the reference number specified in Technical Specification 5.6.5

Page 10 of 29


The cycle-specific operating limits for the specifications listed are presented below.

3.1.1 - Shutdown Margin rSDM) - Reactor Trip Breakers Open

The Shutdown Margin shall be greater than or equal to that shown in Figure 3.1.1-1.

3.1.2- Shutdown Margin CSOM) - Reactor Trip Breakers Closed


3.1.4- Moderator Temperature Coefficient ('MTO

The moderator temperature coefficient (MTC) shall be within the area of Acceptable Operation shown in Figure 3.1.4-1.

3.1.5 - Control Element Assembly rCEAl Alignment

With one or more full-strength or part-strength CEAs misaligned from any other CEAs in its group by more than 6.6 inches, the minimum required MODES 1 and 2 core power reduction is specified in Figure 3.1.5-1. The required power reduction is based on the initial power before reducing power.

3.1.7 - Regulating CEA Insertion Limits

With COLSS IN SERVICE, regulating CEA groups shall be limited to the withdrawal sequence and to the insertion limits' shown in Figure 3.1.7-1^; with COLSS OUT OF SERVICE, regulating CEA groups shall be limited to the withdrawal sequence and to the insertion limits' shown in Figure 3.1.7-2.^Regulating Groups 1 and 2 CEAs shall be maintained > fully withdrawn'’ ^ while in Modes 1 and 2 (except while performing SR 3.1.5.3). When > 20% power Regulating Group 3 shall be maintained > fully withdrawn.'’ ^

' A reactor power cutback will cause either (Case 1) Regulating Group 5 or Regulating Group 4 and 5 to be dropped with no sequential insertion of additional Regulating Groups (Groups 1,2, 3, and 4) or (Case 2) Regulating Group 5 or Regulating Group 4 and 5 to be dropped with all or part of the remaining Regulating Groups (Groups 1,2, 3, and 4) being sequentially inserted. In either case, the Transient Insertion Limit and withdrawal sequence specified in the CORE OPERATING LIMITS REPORT can be exceeded for up to 2 hours.

^ The Separation between Regulating Groups 4 and 5 may be reduced from the 90 inch value specified in Figures 3.1.7-1 and 3.1.7-2 provided that each of the following conditions are satisfied:

a) Regulating Group 4 position is between 60 and 150 inches withdrawn.

Page 11 of 29


b) Regulating Group 5 position is maintained at least 10 inches lower than Regulating Group 4 position.

c) Both Regulating Group 4 and Regulating Group 5 positions are maintained above the Transient Insertion Limit specified in Figure 3.1.7-1 (COLSS In Service) or Figure 3.1.7-2 (COLSS Out of Service).

^ Fully withdrawn (FW) is defined as >147.75” (Pulse Counter indication) and >145.25” (RSPT indication). No further CEA withdrawal above FW is required for CEAs’ to meet the Transient Insertion Limit (TIL) requirements.

3.1.8 - Part Strength CEA Insertion Limits

The part strength CEA groups shall be limited to the insertion limits shown in Figure 3.1.8-1.

3.2.1 - Linear Heat Rate (LHR)

The linear heat rate limit of 13.1 kW/ft shall be maintained.

3.2.3 - Azimuthal Power Tilt ITgl

The AZIMUTHAL POWER TILT (Tq) shall be less than or equal to 10% with COLSS IN SERVICE when power is greater than 20% and less than or equal to 50%. Additionally, the AZIMUTHAL POWER TILT (Tq) shall be less than or equal to 5% with COLSS IN SERVICE when power is greater than 50%. See Figure 3.2.3-1.

3.2.4 - Departure From Nucleate Boiling Ratio lONBR^

COLSS IN SERVICE and Both CEACs INOPERABLE in Any OPERABLE CPC Channel - Maintain COLSS calculated core power less than or equal to COLSS calculated core power operation limit based on DNBR decreased by the allowance shown in Figure 3.2.4-1.

COLSS OUT OF SERVICE and CEAC(s) OPERABLE - Operate within the region of acceptable operation of Figure 3.2.4-2 using any operable CPC channel.

COLSS OUT OF SERVICE and Both CEACs INOPERABLE in Any OPERABLE CPC Channel - Operate within the region of acceptable operation of Figure 3.2.4-3 using any operable CPC channel with both CEACs INOPERABLE.

Page 12 of 29


3.2.5 - Axial Shape Index TASD

The core average AXIAL SHAPE INDEX (ASI) shall be maintained within the following limits:

COLSS OPERABLE-0.18 < ASI <0.17 for power > 50%-0.28 < ASI <0.17 for power >20% and < 50%

COLSS OUT OF SERVICE (CPC)-0.10 < ASI < 0.10 for power >20%

3.3.12 - Boron Dilution Alarm System (BDAS)

With one or both start-up channel high neutron flux alarms inoperable, the RCS boron concentration shall be determined at the applicable monitoring frequency specified in Tables 3.3.12-1 through 3.3.12-5.

3.9.1 - Boron Concentration

The boron concentration of all filled portions of the Reactor Coolant System and the refueling canal shall be maintained at a uniform concentration > 3000 ppm.

Page 13 of 29

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 25

FIGURE 3.1.1-1SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE

REACTOR TRIP BREAKERS OPEN

(500,5.0|l ■REGION OF

ACCEPTABLE

OPERATION

REGIONiOF

UNACCEPTABLE

OPERATION

(350, 1.0)

COLD LEG TEMPERATURE (°F)

Page 14 of 29



REACTOR TRIP BREAKERS CLOSED

<3

gO02<Z

oQHZ00

(500, 6.5)

RE

AC

GION OF

CEPTABLl5

OPERATION

(350, 4.0)

REGION 0

UNACCEP

F

tABLE

OPERATIC

i............... i......... .100 200 300 400

COLD LEG TEMPERATURE (°E)500 600

Page 15 of 29


FIGURE 3.1.4-1MTC ACCEPTABLE OPERATION, MODES 1 AND 2

(I00%,0)V • • ■ •

(50%, 0.0)

MTGAREAGF

ACCEPTABLE

OPERATION

< -3.0

(100%,-4.4

CORE POWER LEVEL (% OF RATED THERMAL POWER)

Maintain Operation within Boundary TECH SPEC 3.1.4 Maximum Upper Limit

Page 16 of 29


FIGURE 3.1.5-1CORE POWER REDUCTION AFTER CEA DEVIATION*

^<100% to >80% RTF

<80% to >70% RTF

‘<70% to >45% RTF

^5% RTF

TIME AFTER DEVIATION, MINUTES

* WHEN CORE POWER IS REDUCED TO 35% OF RATED THERMAL POWER PER THIS LIMIT CURVE, FURTHER REDUCTION IS NOT REQUIRED.

* NO POWER REDUCTION IS REQUIRED FOR A SINGLE CEA MISALIGNMENT IF THE FOLLOWING CONDITIONS ARE CONTINUOUSLY MET FROM THE TIME OF DEVIATION:

- > 95 % RATED THERMAL POWER- COLSS IN SERVICE AND CEACS IN SERVICE- AZIMUTHAL POWER TILT IS LESS THAN 3.0 %- ALL CEAS REMAIN ABOVE 142.5" WITHDRAWN BY PULSE COUNTER

AND ABOVE 140.1" WITHDRAWN BY RSPT INDICATION

Page 17 of 29


FIGURE 3.1.7-1CEA INSERTION LIMITS VERSUS THERMAL POWER

(COLSS IN SERVICE)

0.9

0.8

M

oa.<SocuXHG[S<PSH.Ozo<a:u.

0.6

0.4

0.3

0.1

0.0

NOTE:See Footnote in Section 3.1.7 for applicability following a Reactor Power Cutback.To meet tbe Transient Insertion Limit (TIL) all conditions below must be met:

CEA Groups 1 and 2 must be > fully withdrawn* (see definition below) in MODE 1 and MODE 2.

ANDCEA Group 3 must be > fully withdrawn* for

power levels >20%.CEA Group 3 must be withdrawn > 60” for

power >0% and <20%.AND

CEA Group 4 must be > fully withdrawn* for power levels > 70.87%.CEA Group 4 must be withdrawn > the

group 4 TIL (TIL4) as indicated on the graph or by the equation:T1L4 = (172.5" X Fractional Power) + 25.5" (for power > 20% and < 70.87%).

ANDCEA Group 5 must be withdrawn > the

group 5 TIL (TIL5) as indicated on the graph or by the equation:TIL5 = (172.5" X Fractional Power) - 64.5" (for power > 37.39% and < 100%).

GROUP 5I- 1- 1- 1-

150* 120 90 60

I—

-I I-GROUP 3— I- 1- 1- 1 I-

GROUP1

-I- 1- 1- 1

30 0 150* 120 90 60 30 0 150* 120 90 60 30 0GROUP 4 GROUP 2

-I---1-----1---- 1---- 1 I----1---- 1---- 1---- 1---- 1150* 120 90 60 30 0 150* 120 90 60 30 0

CEA POSITION (INCHES WITHDRAWN)

* Fully Withdrawn (FW) is defined as > 147.75” (Pulse Counter) and > 145.25” (RSPT).No further CEA withdrawal above FW is required for CEAs’ to meet the TIE requirements.

Page 18 of 29


0.9

0.8


(COLSS OUT OF SERVICE)

NOTE:See Footnote in Section 3.1.7 for applicability following a Reactor Power Cutback.To meet the Transient Insertion Limit (TIL) all conditions below must be met:

M

I<QCU

<e:tL.o2;ou<

0.6

0.4

0.3

0.0

ill., iiii!§isi

:



power levels >20%.CEA Group 3 must be withdrawn > 60” for

power > 0% and < 20%.AND


group 4 TIL (TIL4) as indicated on the graph or by the equation:TIL4 = (250.9" X Fractional Power) + 9.82" (for power > 20% and < 54.97%).


group 5 TIL (TIL5) as indicated on the graph or by the equations: ,TIL5 = (250.9" X Fractional Power) - 80.18" (for power > 31.96% and < 75.00%).TIL5 = 108" (for power lever > 75.00%).

GROUP 5I----1---- 1----i-

150* 120 90 60

I —

-I-GROUP 3

I--- 1----1----1----1- -I I--- i-GROUP1-I--- 1----i----1

30 0 150* 120 90 60 30 0 150* 120 90 60 30 0GROUP4 GROUP 2

-I---1-----1---- 1---- 1 I----1-----1---- 1---- 1---- 1150* 120 90 60 30 0 150* 120 90 60 30 0


* Fully Withdrawn (FW) is defined as > 147.75” (Pulse Counter) and > 145.25” (RSPT).No further CEA withdrawal above FW is required for CEAs’ to meet the TIL requirements.

Page 19 of 29


FIGURE 3.1.8-1PART STRENGTH CEA INSERTION LIMITS

VERSUS THERMAL POWER

z<QK

c/5WXozzo

oOh

<:wuXa§aH00HQi<Oh

0.0

10.0

20.0

30.0

40.0

50.0

60.0

70.0

80.0

90.0

100.0

110.0

120.0

130.0

140.0

150.0

TRANSIENT INSERTION LIVIIT (75.0 NCHES).

OPER

UNAC

AT^O^

CEPT/

..1.1 1.. 1

Oij

HW

c«

a, H

.......

ATIG?

iuCTEi.......

p

o a B D B B eLIMIT •C

/5 "

h"

^ a —

GK

) aIf

x ° B PJ

g K

B U

s §

insaaBBB

s) :; LoivfG TER A STEA DY ST/ cTE INSERTIOI

OPERATIOI' EPTAI5LE

i . . . . i . . . .0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2

FRACTION OF RATED THERMAL POWER0.0

Page 20 of 29 '


FIGURE 3.2.3-1AZIMUTHAL POWER TILT VERSUS THERMAL POWER

(COLSS IN SERVICE)20.0

g,t-J

ciwo0.

<XHDSN<

15.0

10.0

5.0

0.0 20.0

REGION OF UNACCEPTABLE OPERATION

REGION OE ACCEPTABLE OPERATION

30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0CORE POWER LEVEL

(% OF RATED THERMAL POWER)

Page 21 of 29


FIGURE 3.2.4-1COLSS DNBR OPERATING LIMIT

ALLOWANCE FOR BOTH CEACs INOPERABLE IN ANY OPERABLE CPC CHANNEL

(95, 20)


Page 22 of 29


FIGURE 3.2A-2DNBR MARGIN OPERATING LIMIT BASED ON

THE CORE PROTECTION CALCULATORS(COLSS OUT OF SERVICE, CEAC(s) OPERABLE)

ACCEPTABLE OPERATION ANY POWER LEVEL AT LEAST 1 CEAC OPERABLE IN EACH OPERABLE CPC CHANNEL

(-0.1,2.28)

Z 2.2I ACCEPTABLE OPERATION ;

I POWER AT OR ABOVE 90% I5 AT LEAST 1 CEAC OPERABLE IN ;

9 ; ; ■ n

I EACH OPERABLE CPC CHANNEL|

(0.05, 2.00)

UNACCEPTABLE

OPERATION

CORE AVERAGE ASI

Page 23 of 29


FIGURE 3.2A-3DNBR MARGIN OPERATING LIMIT BASED ON

THE CORE PROTECTION CALCULATORS (COLSS OUT OE SERVICE, BOTH CEACs INOPERABLE

IN ANY OPERABLE CPC CHANNEL)

3.5

a:PQzQ

IZIo

3.3

3.2

3.1

3.0 -0.20

ACCEPTABLE OPERATION

ANY POWER LEVEL |

BOTH CEACs INOPERABLE

IN ANY OPERABLE CPC

CHANNEL

............:.......... ..............................

(-0.1;,3.27) i

i UNACCEPTABLE

OPERATION

-0.15 -0.10 -0.05 0.00 0.05CORE AVERAGE ASI

0.10 0.15

Page 24 of 29


Table 3.3.12-1

REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING

CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR Keff > 0.98

OPERATIONALMODE

Number of Operating Charging Pumps

0 1 2 3

3 12 hours 0.5 hours ONA ONA

4 not on SCS 12 hours 0.5 hours ONA ONA


4 & 5 on SCS ONA ONA ONA ONA

Notes: SCS = Shutdown Cooling SystemONA = Operation Not Allowed

Page 25 of 29


Table 3.3.12-2


CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR 0.98 > K^ff > 0.97

OPERATIONALMODE


0 1 2 3

3 12 hours 1 hour 0.5 hours ONA

4 not on SCS 12 hours 1.5 hours 0.5 hours ONA


4 & 5 on SCS 8 hours 0.5 hours ONA ONA


Page 26 of 29


Table 3.3.12-3



OPERATIONALMODE


0 1 2 3

3 12 hours 2.5 hours 1 hour ONA

4 not on SCS 12 hours 2.5 hours I hour 0.5 hours

5 not on SCS 8 hours 2.5 hours 1 hour 0.5 hours

4 & 5 on SCS 8 hours 1 hour ONA ONA

Notes: SCS = Shutdown Cooling SystemON A = Operation Not Allowed

Page 27 of 29


Table 3.3.12-4

REQUIRED MONTTORWG FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING

CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR 0.96 > Ke^> 0.95

OPERATIONALMODE


0 1 1 2 3

3 12 hours 3 hours 1 hour 0.5 hours

4 not on SCS 12 hours 3.5 hours 1.5 hours 0.75 hours


4 & 5 on SCS 8 hours 1.5 hours 0.5 hours ONA

Notes: SCS = Shutdown Cooling SystemON A = Operation Not Allowed

Page 28 of 29


Table 3.3.12-5


CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR K^ff < 0.95

OPERATIONALMODE


0 1 2 3

3 12 hours 4 hours 1.5 hours 1 hour

4 not on SCS 12 hours 4.5 hours 2 hours 1 hour


4 & 5 on SCS 8 hours 2 hours 0.75 hours ONA



Page 29 of 29

Enclosure



UNIT 2


Revision 21



Wenzel, CSSSS"""'' U DN: cn=Wenzel, Richard

Rirh;^rH AP(Z99534)I'lV-l IQI^ H R^son: 1 am the author of thisj/^,^d(^umGriDi

R(Z9953^)Independent ReviewerDate

• 1 (P Digitally signed by Geiszler,beiSZler, | KeHyJ(Z07064)

} DN: cn=Geiszler, KellyKpIIv /\j(Z07064)l\d 1 y // Reason: 1 have reviewed this//,^documGrit>

J(Z070^) 08:14:38

Responsible Section LeaderDate Digitally signed by Karlson, Charle:

1 I\F(V55086)1 h ^ ^ 1 O C // cn=Karlson, Charles F(V55086)

1 1 Cl 1 1^^ II Reason: i am approving this// dement =3s^F(V550>)

Page 1 of 29


Table of Contents

Description

Cover Page

Table of Contents

List of Figures

List of Tables


Analytical Methods

Page

1

2

3

4

5

6














2

2

2

12

13

13

13

Page 2 of 29


List of Figures

Description

Figure 3.1.1-1

Figure 3.1.2-1

Figure 3.1.4-1

Figure 3.1.5-1

Figure 3.1.7-1

Figure 3.1.7-2

Figure 3.1.8-1

Figure 3.2.3-1

Figure 3.2.4-1

Figure 3.2.4-2

Figure 3.2.4-3






CEA Insertion Limits Versus Thermal Power (COLSS Out of Service)

Part Strength CEA Insertion Limits Versus Thermal Power





Page

14

16

17

18

20

.21

22

23

Page 3 of 29


List of Tables

Description

Table 3.3.12-1

Table 3.3.12-2

Table 3.3.12-3

Table 3.3.12-4

Table 3.3.12-5

Required Monitoring Frequencies for Backup Boron Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Kefl^ 0.98

Required Monitoring Frequencies for Backup Boron Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for 0.98 > Keff > 0.97



Required Monitoring Frequencies for Backup Boron Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff < 0.95

Page

25

27

Page 4 of 29



AFFECTED PVNGS TECHNICAL SPECIFICATIONS













Page 5 of29


ANALYTICAL METHODS

The COLR contains the complete identification for each of the Technical Specification referenced topical reports (i.e., report number, title, revision, date, and any supplements) and correspondence that provide the NRC-approved analytical methods used to determine the core operating limits, described in the following documents:


1CE Method for Control Element Assembly Ejection Analysis (NOOl-1301-01204)

CENPD-0190-A

N.A. January1976

N.A.

2The ROCS and DIT Computer Codes for Nuclear Design (NOOl-1900-01412)

CENPD-266-P-A

N.A. April 1983 N.A.

3

Safety Evaluation Report related to the Final Design of the Standard Nuclear Steam Supply Reference Systems CESSAR System 80, Docket No. STN 50-470

NUREG-0852

N.A. March 1983

September1983

December1987

1

2

3/

4Modified Statistical Combination ofUncertainties(NOOl-1303-01747)

CEN-356(V)-P-A

01-P-A May 1988 N.A.

4System 80™ Inlet Flow Distribution (NOOl-1301-01228)

Enclosure1-P to LD- 82-054

N.A. February1993

1-P

5Calculative Methods for the CE Large Break LOCA Evaluation Model (NOOl-1900-01192)

CENPD-132

N.A. March2001

4-P-A Rev. 1

6Calculative Methods for the CE Small Break LOCA Evaluation Model (NOOl-1900-01185)

CENPD-137-P

N.A. April1998

2-P-A

7

Letter: O.D. Parr (NRC) to F. M. Stem (CE), (NRC Staff Review of the Combustion Engineering ECCS Evaluation Model). NRC approval for: 5.6.5.b.6.

N.A. N.A. June 13,1975

N.A.

Page 6 of 29


T.SRef#"* Title Report No. Rev Date Suppl

8

Letter; K. Kniel (NRC) to A. E. Scherer (CE), (Evaluation of Topical Reports CENPD 133, Supplement 3-P and CENPD-137, Supplement 1-P).NRC approval for 5.6.5.b.6.

N.A. N.A. September27, 1977

N.A.


CEN-372-P-A

N.A. May1990

N.A.

10

Letter; A. C. Thadani (NRC) to A. E. Scherer (CE), ("Acceptance forReference CE Topical Report CEN-372- P"). NRC approval for 5.6.5.b.9.

N.A. N.A. April 10,1990

N.A.

11



N.A.



2 March2005

N.A.



2 March2005

N.A.



2 March2005

N.A.

13

Implementation of ZIRLO^^ Cladding Material in CE Nuclear Power Fuel Assembly Designs (NOOl-1900-01329)

CENPD-404-P-A

0 November2001

N.A.

13

Optimized ZIRLO™(NOO1-0203-00611)


0 July 2006 N.A.

13

Westinghouse Clad Corrosion Model for ZIRLO and Optimized ZIRLO™(NOOl-0205-00006)


0 October2013

N.A.

Page 7 of 29


T.SRef#"" Title Renort No. Rev Date Suppl

14

HERMITE, A Multi-Dimensional Space-Time Kinetics Code for PWR Transients(HERMITE-TOPICAE)

CENPD-188-A

N.A. July1976

N.A.

15


CENPD- 161-P-A

N.A. April1986

N.A.

, 16


CEN-160(S)-P

1-P September1981

N.A.

17

“Safety Evaluation related to Palo Verde Nuclear Generating Station, Unit 2 (PVNGS-2) Issuance of Amendment on Replacement of Steam Generators and Uprated Power Operation, (September29, 2003) and“Safety Evaluation related to Palo Verde Nuclear Generating Station, Units 1,2, and 3 - Issuance of Amendments Re: Replacement of Steam Generators and Uprated Power Operations andAssociated Administrative Changes, (November 16, 2005).”


November16, 2005

N.A.


CEN-310-P-A

0 April1986

N.A.

19Loss of Flow, C-E Methods for Loss ofFlow Analysis(NOOl-1301-01203)

CENPD-183-A

0 June1984

N.A.

20Methodology for Core Designs Containing Erbium Burnable Absorbers (NOOl-0201-00035)

CENPD-382-P-A

0 August1993

N.A.

Page 8 of 29



Verification of the Acceptability of a 1- Pin Bumup Limit of 60 MWD/kgU for Combustion Engineering 16x16 PWR Fuel(NOO1-0201-00042)

CEN-386-P-A

August1992

N.A.

CE 16x16 Next Generation Fuel Core Reference Report (NOOl-0203-00614)

WCAP-16500-P-A

August2007

N.A.

Application of CE Setpoint Methodology for CE 16x16 Next Generation Fuel (NGF)(NOO 1-0205-00063)

WCAP-16500-P-A

December2010

Evolutionary Design Changes to CE 16x16 Next Generation Fuel and Method for Addressing the Effects of End-of-Life Properties on Seismic and Loss of Coolant Accident Analysis (NOO 1-0205-00048)

WCAP-16500-P-A

June 2016 2-P-A

VIPRE-01 Modeling and Qualification for Pressurized Water Reactor Non-LOCA Thermal-Hydraulic Safety Analysis(NOOl-0205-00002)

WCAP-14565-P-A

October1999

N.A.

Addendum 1 to WCAP-14565-P-A Qualification of ABB Critical Heat Flux Correlations with VIPRE-01 Code (NOO1-0205-00003)


August2004

N.A.

23

Addendum 2 to WCAP-14565-P-A, Extended Applications of ABB-NV Correlation and Modified ABB-NV Correlation WLOP for PWR Low Pressure Applications (NOO 1-0205-00004)


April 2008 N.A.

ABB Critical Heat Flux Correlations forPWR Fuel(NOOl-0205-00042)

CENPD-387-P-A

May 2000 N.A.

Page 9 of 29


T.SRef#"* Title Report No. Rev Date Suppl

25

Westinghouse Correlations WSSV and WSSV-T for Predicting Critical HeatFlux in Rod Bundles with Side-Supported Mixing Vanes (NOO1-0203-00615)

WCAP-16523-P-A

0 August2007

N.A

26


WCAP-16072-P-A

0 August2004

N.A.


Page 10 of 29



3.1.1 - Shutdown Margin ('SDM') - Reactor Trip Breakers Open


3.1.2 - Shutdown Margin ISDMl - Reactor Trip Breakers Closed


3.1.4 - Moderator Temperature Coefficient IMTCl


3.1.5 - Control Element Assembly ICEAl Alignment



With COLSS IN SERVICE, regulating CEA groups shall be limited to thewithdrawal sequence and to the insertion limits' shown in Figure 3.1.7-!^; with COLSS OUT OF SERVICE, regulating CEA groups shall be limited to thewithdrawal sequence and to the insertion limits’ shown in Figure 3.1.7-2.^Regulating Groups 1 and 2 CEAs shall be maintained > fully withdrawn’’ ^ while in Modes 1 and 2 (except while performing SR 3.1.5.3). When > 20% power Regulating Group 3 shall be maintained > fully withdrawn.’’ ^

’ A reactor power cutback will cause either (Case 1) Regulating Group 5 or Regulating Group 4 and 5 to be dropped with no sequential insertion of additional Regulating Groups (Groups 1,2, 3, and 4) or (Case 2) Regulating Group 5 or Regulating Group 4 and 5 to be dropped with all or part of the remaining Regulating Groups (Groups 1,2, 3, and 4) being sequentially inserted. In either case, the Transient Insertion Limit and withdrawal sequence specified in the CORE OPERATING LIMITS REPORT can be exceeded for up to 2 hours.

^ The Separation between Regulating Groups 4 and 5 may be reduced from the 90 inch value specified in Figures 3.1.7-1 and 3.1.7-2 provided that each of the following conditions are satisfied:


Page II of 29





3.1.8- Part Strength CEA Insertion Limits


3.2.1 - Linear Heat Rate rLHRI


3.2.3 - Azimuthal Power Tilt ITgl


3.2.4 - Departure From Nucleate Boiling Ratio (ONBRI



COLSS OUT OF SERVICE and Both CEACs INOPERABLE in Any OPERABLE CPC Channel - Operate within the region of acceptable operation of Figure 3.2.4-3 using any operable CPC channel with both CEACs mOPERABEE.

Page 12 of 29


3.2.5 - Axial Shape Index rASI)


COLSS OPERABLE-0.18 < ASI <0.17 for power > 50%-0.28 < ASI <0.17 for power >20% and < 50%

COLSS OUT OF SERVICE (CPC)-0.10 < ASI < 0.10 for power >20%

3.3.12 - Boron Dilution Alarm System IBDAS')




Page 13 of 29




(500, 5.0jREGION OF

ACCEPTABLE

OPERATION

O 3

REGION

UNACCEPTABLE

OPERATION

(350, 1.0)

COLD LEG TEMPERATURE (°F)

Page 14 of 29




<1g,g0oi.<Sz1QXon

..................

(500, 6.5)

RE

AC

GION OF

CEPTABLI5

OPERATION

(350,4.0)

REGION 0

UNACCEP

F

FABLE

OPERATIC>N

....................... 1 1............ .. i.....................1 1 ........................ i..................100 200 300 400

COLD LEG TEMPERATURE (°F)500 600

Page 15 of 29



’ .................

(0%,0.5)(100%,0)

(50%, p.O)

MTG AREAGF

ACCEPTABLE

OPERATION

< -3.0

(10p%,-4.4(0%,-4.



Page 16 of 29



'<100% to >80% RTP

<80% to >70% RTP

^70% to >45% RTP

^5% RTP






Page 17 of 29



(COLSS IN SERVICE)

02U

oa.J<S02UXHQUH<OCtt.O§

<02H.

0.9

0.8

0.7

0.0

NOTE:See Footnote in Section 3.1.7 for applicabiiity following a Reactor Power Cutback.To meet tbe Transient Insertion Limit (TIL) all conditions below must be met:



power levels >20%.CEA Group 3 must be withdrawn > 60" for






GROUP 5I- 1- ^^1- 1—

150* 120 90 60

-I- 1GROUP 3

-I- 1- 1 — -I -I-

GROUP1

-I- 1- 1- 1

30 0 150* 120 90 60 30 0 150* 120 90 60 30 0GROUP 4 GROUP 2

-I---- 1----1---- 1---- 1 I----1-----1-----1---- 1---- 1150* 120 90 60 30 0 150* 120 90 60 30 0



Page 18 of 29


0.9

0.8



NOTE:See Footnote in Section 3.1.7 for applicability following a Reactor Power Cutback.To meet tbe Transient Insertion Limit (TIL) all conditions below must be met:

2<sOLUKHQUH<a:u.ozoo<Oi.u.

0.6

0.1

0.0

■fill






group 4 TIL (TIL4) as indicated on the graph or by the equation:TIL4 = (250.9" X Fractional Power) + 9.82" (for power >20% and < 54.97%).


group 5 TIL (TIL5) as indicated on the graph or by the equations:TIL5 = (250.9" X Fractional Power) - 80.18" (for power > 31.96% and < 75.00%).TIL5 = 108" (for power lever > 75.00%).

GROUP 5I- 1- 1- 1

150* 120 90 60

-I I-GROUP 3— I- 1- 1- I-

GROUP1

-I- 1—

30 0 150* 120 90 60 30 0 150* 120 90 60 30GROUP 4 GROUP 2

-I---- 1--- 1---- 1---- 1 I----1---- 1-----1---- 1---- 1150* 120 90 60 30 0 150* 120 90 60 30 0



Page 19 of 29




zOSQKH

c/5UXuzzoc/5o0.<uoXH0 z w oc H c/5H01 < a.

0.0

10.0

20.0

30.0

40.0

50.0

60.0

70.0

80.0

90.0

100.0

110.0

120.0

130.0

140.0

150.0

TRANSIENTINSER'hON LIVIIT (75.0 NCHES).

OPER

UNAC

AT^O^

CEPT/

[t

w1..................J. OPER

REST]

ATIO?iilCTE

1............

ABLEiw Ds

Mstea^ a a BB B BERTIO^

n D B a o a BLIMIT

o a a a B B 1

S (112.51 B BBBaa

INCHE

aaaaaaB

s) :i LorvlG TER] DY ST/ cTE INS

OPERATIOr'} ACClEPTAI|LE

. . . . 1i . . . . 1i . . . .0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2


Page 20 of 29




15.0

H02U

O(X

<5sN<

10.0

5.0

0.0 20.0


REGION OF ACCEPTABLE OPERATION

30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0CORE POWER LEVEL


Page 21 of 29




(95, 20)

U.}

(80, 5)


Page 22 of 29


FIGURE 3.2.4-2DNBR MARGIN OPERATING LIMIT BASED ON



(0.;06, 2.38) (0.1,2.38)

(-0.1,2.28)

Z 2.2; ACCEPTABLE OPERATION \^ if; POWER AT OR ABOVE 90% ?I : ; ; ?; AT LEAST I CEAC OPERABLE IN ? ! ; : : ■I EACH OPERABLE CPC CHANNELj

(0.05, 2.00)

UNACCEPTABLE(-0.1,1.93) ;

OPERATION

CORE AVERAGE ASI

Page 23 of 29



THE CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, BOTH CEACs INOPERABLE


os2;Q

si 3.3 ZIuau

3.2

3.1

3.0 -0.20

ACCEPTABLE

ANY POWER 1

BOTH CEACs ]

OPERA

,EVEL

NOPER-

TION

ABLE

IN AN'

CHAN]

Y OPER^

NEL03 r w n O

Ann 'XAw

(-0.1i, 3.27)

UNAC

OPERi H S 1

fLE

........... i i........... i............ i........... i...........-0.15 -0.10 -0.05 0.00 0.05

CORE AVERAGE ASI0.10 0.15 0.20

Page 24 of 29


Table 3.3.12-1


CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR Kgff > 0.98

OPERATIONALMODE


0 1 2 3





Notes; SCS = Shutdown Cooling System ONA = Operation Not Allowed

Page 25 of 29


Table 3.3.12-2


CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR 0.98 > Keff > 0.97

OPERATIONALMODE


0 1 2 3

3 12 hours 1 hour 0.5 hours ONA





Page 26 of 29


Table 3.3.12-3



OPERATIONALMODE


0 1 2 3




4 & 5 on SCS 8 hours 1 hour ONA ONA


Page 27 of 29


Table 3.3.12-4



OPERATIONALMODE


0 1 2 3






Page 28 of 29


Table 3.3.12-5


CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR < 0.95

OPERATIONALMODE


0 1 2 3




4 & 5 on SCS 8 hours 2 hours 0.75 hours ONA



Page 29 of 29

Enclosure



UNIT 3


Revision 24



Wenzel, CSS™"’)l DN: cn=WenzeI, Richard

Richard AS.,he author of

/7 ^this dooJmentR(Z995^4) Da;ej0ia03.30,5:38:32

Independent ReviewerDate

^ • 1 Digitally signed by Geiszler,LlGISZlGT, 1 Kelly J(Z07064))lDN:cn=Geiszler, Kelly

KpIIV /\J(Z07064)1 \C 1 ■ jr u R^son; 1 have reviewed this/^J^,>-'ddcurnent'^

J (Z070^) D=;-^20,8:04.03 08:,6:5,

Responsible Section LeaderDate

X ff Oigitaliy signed by KarlsonKar son, WchanesFlVSSOSe)ll DN: cn=Karlson, Charles

rhArlpc: /W55086)1 1U 1 I ^ J // R^^on: 1 am approving

,^this docurhentF(V55036)

Page 1 of 29


Table of Contents

Description

Cover Page

Table of Contents

List of Figures

List of Tables


Analytical Methods

Page

1

2

3

4

5

6











3.2.5 Axial Shape Index (ASl)



1

1

12

12

12

12

13

13

13

Page 2 of29


List of Figures

Description

Figure 3.1.1-1

Figure 3.1.2-1

Figure 3.1.4-1

Figure 3.1.5-1

Figure 3.1.7-1

Figure 3.1.7-2

Figure 3.1.8-1

Figure 3.2.3-1

Figure 3.2.4-1

Figure 3.2.4-2

Figure 3.2.4-3






CEA Insertion Limits Versus Thermal Power (COLSS Out of Service)

Part Strength CEA Insertion Limits Versus Thermal Power





Page

14

16

17

18

20

21

22

23

Page 3 of 29


List of Tables

Description

Table 3.3.12-1

Table 3.3.12-2

Table 3.3.12-3

Table 3.3.12-4

Table 3.3.12-5

Required Monitoring Frequencies for Backup Boron Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff> 0.98


Required Monitoring Frequencies for Backup Boron Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for 0.97 > Keff> 0.96


Required Monitoring Frequencies for Backup Boron Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff < 0.95

Page

25

Page 4 of 29



AFFECTED PVNGS TECHNICAL SPECIFICATIONS













Page 5 of 29


ANALYTICAL METHODS

The COLR contains the complete identification for each of the Technical Specification referenced topical reports (i.e., report number, title, revision, date, and any supplements) and correspondence that provide the NRC-approved analytical methods used to determine the core operating limits, described in the following documents;

T.SRef#"" Title Report No. Rev Date Suppl

CE Method for Control Element Assem- CENPD- N.A. January N.A.1 bly Ejection Analysis

(NOOl-1301-01204)0190-A 1976

The ROCS and DIT Computer Codes for CENPD- N.A. April 1983 N.A.2 Nuclear Design

(NOO1-1900-01412)266-P-A

Safety Evaluation Report related to the NUREG- N.A. March 1983 1Final Design of the Standard Nuclear 0852

September1983'X

Steam Supply Reference SystemsCESSAR System 80, Docket No. STN Z

50-470 December1987 3

Modified Statistical Combination of CEN- 01-P-A May 1988 N.A.4 Uncertainties

(NOOl-1303-01747)356(V)-P-A

System 80™ Inlet Flow Distribution Enclosure N.A. February 1-P4 (NOOl-1301-01228) 1-P to LD-

82-0541993

Calculative Methods for the CE Large CENPD- N.A. March 4-P-A5 Break LOCA Evaluation Model

(NOOl-1900-01192)132 2001 Rev. 1

Calculative Methods for the CE Small CENPD- N.A. April 2-P-A6 Break LOCA Evaluation Model

(NOOl-1900-01185)137-P 1998

Letter: O.D. Parr (NRC) to F. M. Stern N.A. N.A. June 13, N.A.(CE), (NRC Staff Review of the 1975

7 Combustion Engineering ECCS Evaluation Model). NRC approval for: 5.6.5.b.6.

Page 6 of 29



8

Letter: K. Kniel (NRC) to A. E. Scherer (CE), (Evaluation of Topical Reports CENPD 133, Supplement 3-P and CENPD-137, Supplement 1-P). NRC approval for 5.6.5.b.6.


N.A.


CEN-372-P-A

N.A. May1990

N.A.

10

Letter: A. C. Thadani (NRC) to A. E. Scherer (CE), ("Acceptance forReference CE Topical Report CEN-372- P"). NRC approval for 5.6.5.b.9.

N.A. N.A. April 10,1990

N.A.

11



N.A.



2 March2005

N.A.



2 March2005

N.A.



2 March2005

N.A.

13

Implementation of ZIRLO™ Cladding Material in CE Nuclear Power Fuel Assembly Designs (NOOl-1900-01329)

CENPD-404-P-A

0 November2001

N.A.

13

Optimized ZIRLO™(NOOl-0203-00611)


0 July 2006 N.A.

13

Westinghouse Clad Corrosion Model for ZIRLO and Optimized ZIRLO™(NOO 1-0205-00006)


0 October2013

N.A.

Page 7 of 29



14

HERMITE, A Multi-Dimensional Spaee-Time Kinetics Code for PWR Transients(HERMITE-TOPICAL)

CENPD-188-A

N.A. July1976

N.A.

15


CENPD-161-P-A

N.A. April1986

N.A.

16


CEN-160(S)-P

1-P September1981

N.A.

17

“Safety Evaluation related to Palo Verde Nuclear Generating Station, Unit 2 (PVNGS-2) Issuance of Amendment on Replacement of Steam Generators and Uprated Power Operation, (September29,2003) and“Safety Evaluation related to Palo Verde Nuclear Generating Station, Units 1, 2, and 3 - Issuance of Amendments Re: Replacement of Steam Generators and Uprated Power Operations andAssociated Administrative Changes, (November 16, 2005).”


November16, 2005

N.A.


CEN-310-P-A

0 April1986

N.A.

19Loss of Flow, C-E Methods for Loss of Flow Analysis (NOOl-1301-01203)

CENPD-183-A

0 June1984

N.A.

20Methodology for Core Designs Containing Erbium Burnable Absorbers (NOOl-0201-00035)

CENPD-382-P-A

0 August1993

N.A.

Page 8 of 29


T.SRef#^ Title Report No. Rev Date SuddI

21

Verification of the Acceptability of a 1- Pin Bumup Limit of 60 MWD/kgU for Combustion Engineering 16x16 PWR Fuel(NOO1-0201-00042)

CEN-386-P-A

0 August1992

N.A.

22CE 16x16 Next Generation Fuel Core Reference Report (NOOl-0203-00614)

WCAP-16500-P-A

0 August2007

N.A.

22

Application of CE Setpoint Methodology for CE 16x16 Next Generation Fuel (NGF)(NOO1-0205-00063)

WCAP-16500-P-A

1 December2010

1

22

Evolutionary Design Changes to CE16x16 Next Generation Fuel and Method for Addressing the Effects ofEnd-of-Life Properties on Seismic and Loss of Coolant Accident Analysis (NOOl-0205-00048)

WCAP-16500-P-A

1 June 2016 2-P-A

23

VIPRE-01 Modeling and Qualification for Pressurized Water ReactorNon-LOCA Thermal-Hydraulic Safety Analysis(NOO 1-0205-00002)

WCAP-14565-P-A

0 October1999

N.A.

23

Addendum 1 to WCAP-14565-P-A Qualification of ABB Critical Heat Flux Correlations with VlPRE-01 Code (NOOl-0205-00003)


0 August2004

N.A.

23

Addendum 2 to WCAP-14565-P-A, Extended Applications of ABB-NV Correlation and Modified ABB-NV Correlation WLOP for PWR Low Pressure Applications (NOO1-0205-00004)


0 April 2008 N.A.

24ABB Critical Heat Flux Correlations forPWR Fuel(NOO1-0205-00042)

CENPD-387-P-A

0 May 2000 N.A.

Page 9 of 29


T.SRef#'' Title Report No. Rev Date Suppl

25

Westinghouse Correlations WSSV and WSSV-T for Predicting Critical HeatFlux in Rod Bundles with Side-Supported Mixing Vanes (NOO1-0203-00615)

WCAP-16523-P-A

0 August2007

N.A

26


WCAP-16072-P-A

t

0 August2004

N.A.


Page 10 of 29



3.1.1 - Shutdown Margin TSOM) - Reactor Trip Breakers Open


3.1.2 - Shutdown Margin rSDMl - Reactor Trip Breakers Closed


3.1.4 - Moderator Temperature Coefficient ('MTQ


3.1.5 - Control Element Assembly ICEAl Alignment



With COLSS IN SERVICE, regulating CEA groups shall be limited to thewithdrawal sequence and to the insertion limits' shown in Figure 3.1.7-!^; withCOLSS OUT OF SERVICE, regulating CEA groups shall be limited to the

1 • 0 withdrawal sequence and to the insertion limits shown in Figure 3.1.7-2.Regulating Groups 1 and 2 CEAs shall be maintained > fully withdrawn'’ ^ while in Modes 1 and 2 (except while performing SR 3.1.5.3). When > 20% powerRegulating Group 3 shall be maintained > fully withdrawn.'’ ^

' A reactor power cutback will cause either (Case 1) Regulating Group 5 or Regulating Group 4 and 5 to be dropped with no sequential insertion of additional Regulating Groups (Groups 1,2, 3, and 4) or (Case 2) Regulating Group 5 or Regulating Group 4 and 5 to be dropped with all or part of the remaining Regulating Groups (Groups 1, 2, 3, and 4) being sequentially Inserted. In either case, the Transient Insertion Limit and withdrawal sequence specified in the CORE OPERATING LIMITS REPORT can be exceeded for up to 2 hours.

The Separation between Regulating Groups 4 and 5 may be reduced from the 90 inch value specified in Figures 3.1.7-1 and 3.1.7-2 provided that each of the following conditions are satisfied;


Page 11 of 29





3.1.8- Part Strength CEA Insertion Limits


3.2.1 - Linear Heat Rate (LHR)


3.2.3 - Azimuthal Power Tilt ITg)


3.2.4 - Departure From Nucleate Boiling Ratio lONBR)



COLSS OUT OF SERVICE and Both CEACs INOPERABLE in Any OPERABLE CPC Channel - Operate within the region of acceptable operation of Figure 3.2.4-3 using any operable CPC channel with both CEACs INOPERABLE.

Page 12 of 29


3.2.5 - Axial Shape Index (ASP


COLSS OPERABLE-0.18 < ASI <0.17 for power > 50%-0.28 < ASI < 0.17 for power >20% and < 50%

COLSS OUT OF SERVICE (CPC)-0.10 < ASI <0.10 for power >20%

3.3.12 - Boron Dilution Alarm System (BDASI




Page 13 of 29




<j

g001 <

zoQHPX(Zl

(500, 5.0il

RE

AC

OP

GION OF

CEPTABLI

ERATION

(REGION OF

UNACCEPTABLE

OPERATION

i................ j.....................

(350, I.O)

t..................... i................ 1..................100 200 300 400

COLD LEG TEMPERATURE (°F)500 600

Page 14 of 29




<1

zI—0 oc <z1QzC/3

(500, 6.5)

RE

AC

GION OF

CEPTABL]5

OPERATION

(350, 4.0)

REGION 0UNACCEP^

F

FABLE

OPERATIC>N

............................1

100 200 300 400COLD LEG TEMPERATURE (°F)

500 600

Page 15 of 29



(0%,0.5)

(50%, p.O)

MTGAREAGF

ACCEPTABLE

OPERATION

(100%,-4.4



Page 16 of 29



'<100% to >80% RTF

<80% to >70% RTF

■<70% to >45% RTF

^5% RTF






Page 17 of 29



(COLSS IN SERVICE)

0.9

0.8

«

2<

XHQwH<aU.o§<

0.6

£ 0.3

0.1

0.0

NOTE:See Footnote in Section 3.1.7 for applicability following a Reactor Power Cutback.To meet the Transient Insertion Limit (TIL) all conditions below must be met:









GROUP 5-I--- 1----1- -I----1 I-

GROUP 3— I----1----1- I-

GROUP1|------1----1----1

150* 120 90 60 30 0 150* 120 90 60 30 0 150* 120 90 60 30 0GROUP 4 GROUP 2

I----1--- 1------1--1----1 I----1--- 1----1----1--- 1150* 120 90 60 30 0 150* 120 90 60 30 0


Fully Withdrawn (FW) is defined as > 147.75” (Pulse Counter) and > 145.25” (RSPT).No further CEA withdrawal above FW is required for CEAs’ to meet the TIL requirements.

Page 18 of 29




o0.-J<

u

Pw<a:tt.o§&<

0.9

0.8

0.6

0.0

NOTE:See Footnote in Section 3.1.7 for applicability following a Reactor Power Cutback.To meet the Transient Insertion Limit (TIL) all conditions below must be met;






group 4 TIL (TIL4) as indicated on the graph or by the equation;TIL4 = (250.9" X Fractional Power) + 9.82" (for power > 20% and < 54.97%).


group 5 TIL (TIL5) as indicated on the graph or by the equations:TIL5 = (250.9" X Fractional Power) - 80.18" (for power > 31.96% and < 75.00%).TIL5 = 108" (for power lever > 75.00%).

GROUP 5I- 1- 1- 1-

150* 120 90 60

I—

-IGROUP 3— I 1 1- -I

GROUP 1

-I

30 0 150* 120 90 60 30 0 150* 120 90 60 30 0GROUP4 GROUP 2

|---- 1---- 1----1----1 I----1---- 1-- 1----- 1----1150* 120 90 60 30 0 150* 120 90 60 30 0



Page 19 of 29




z<a:PXH

c/5WXuzc-zop00

o<woXHOzpo:Hc/5H(52<0.

0.0

10.0

20.0

30.0

40.0

50.0

60.0

70.0

80.0

90.0

100.0

110.0

120.0

130.0

140.0

150.0

....

TRANSIEN[T INSERTION LIVilT (75.0 NCHES).

—........ GPER

UNAC

ATIO?

CEPT.

li......iVBLE

11....... 1

sXGPER

REST]

ATIG?

jaCTEi........

D

Io

' LorsIG TER]M STEA DYST/^TE INSERTIO^ LIMITS (112.5 INCHE,s) :

OPERATIO^}ACC]EPTAE5LE

. . . . 1 i . . . . ............ i . . . .1.0 0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2


Page 20 of 29




15.0

Oiug 10.0

<

PsN<

0.0 20.0


REGION OF ACCEPTABLE OPERATION

30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0CORE POWER LEVEL


Page 21 of 29




(95, 20)


Page 22 of 29





,;06, 2.38) (0.1,2.38)

(-6.1,2.28)

Z 2.2S ACCEPTABLE OPERATION ! : : :I POWER AT OR ABOVE 90%

AT LEAST I CEAC OPERABLE IN j; ; ; nEACH OPERABLE CPC CHANNELI

(0.05, 2.00)

UNACCEPTABLE(-0.1,1.93) :

OPERATION

CORE AVERAGE ASl

Page 23 of 29



THE CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, BOTH CEACs INOPERABLE


3.5

3.4

PiaZQsI 3-3Z§o(Xo

3.2

3.1

3.0 -0.20

....................... ... ■

ACCEl

ANY P

BOTH

^TABLE

PWERI

CEACs ]

OPERA

.EVEL

INOPER

TION

ABLE

IN ANl

CHANl

f OPER^

Sel

^BLE Cl»C

(0,0, .3.41) (U.l, J.4IJ

(-0.11,3.27)

UNAC

OPERi

CEPTAI

\TION

Ile

............. i-0.15 -0.10 -0.05 0.00 0.05

CORE AVERAGE ASI0.10 0.15 0.20

Page 24 of 29


Table 3.3.12-1


CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR K^ff > 0.98

OPERATIONALMODE


0 1 2 3






Page 25 of 29


Table 3.3.12-2


CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR 0.98 > > 0.97

OPERATIONALMODE


0 I 2 3

3 12 hours I hour 0.5 hours ONA





Page 26 of 29


Table 3.3.12-3



OPERATIONALMODE


0 1 2 3




4 & 5 on SCS 8 hours I hour ONA ONA


Page 27 of 29


Table 3.3.12-4


CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR 0.96 > Keff > 0.95

OPERATIONALMODE


0 1 2 3






Page 28 of 29


Table 3.3.12-5


CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR K^ff < 0.95

OPERATIONALMODE


0 I 2 3



5 not on SCS 8 hours 4.5 hours 2 hours I hour

4 & 5 on SCS 8 hours 2 hours' 0.75 hours ONA


Notes; SCS = Shutdown Cooling System ONA = Operation Not Allowed

Page 29 of 29

palo verde, units 1, 2, and 3, core operating limits ... · palo verde nuclear generating station...

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