76. during a loca with a loop the following plant conditions … · a. oaop-12.0, loss of...

76. During a LOCA with a LOOP the following plant conditions exist:

2A RHR pump Injecting and has just exceeded its NPSH Limit2A CS pump Injecting and approaching its NPSH LimitAll other ECCS Pumps UnavailableReactor Water Level 2/3 core height and steady

Which one of the following identifies:

(1) if continued RHR Pump operation outside its NPSH limit is authorized lAW001-37.4, Reactor Vessel Control Procedure Basis Document, and

(2) the required procedure to maintain adequate core cooling lAW RVCP?

A. (1) Continued RHR pump operation is NOT allowed.(2) LFP-01 Alternate Coolant Injection, Section 5, Fire Protection! Demineralized

Water Tank Injection

B. (1) Continued RHR pump operation is NOT allowed.(2) 20P-18, Core Spray System Operating Procedure, Section 8.3, Shifting Suction

Source from CST to Suppression Pool

C. (1) Continued RHR pump operation is allowed.(2) LP-01, Alternate Coolant Injection, Section 5, Fire Protection! Demineralized

Water Tank Injection

D. (1) Continued RHR pump operation is allowed.(2) 2OP-18, Core Spray System Operating Procedure, Section 8.3, Shifting Suction

Source from CST to Suppression Pool

Page: 76

77. Unit Two was operating at rated power with the OPRMs inoperable when a trip of2A RFP occurred followed immediately by a trip of the 2B Reactor Recirc pump.

Which one of the following completes the statement below?(assume first 5 minutes of event)

The RO is required to determine the current operating point on the OPRM Inoperable,(1) Power to Flow Map, which is directed by (2) Supplementary actions.

A. (1) Two Loop Operation(2) ONLY 2AOP-04.O, Low Core Flow,

B. (1) Two Loop Operation(2) 2AOP-04.O, Low Core Flow AND OAOP-23.O, Condensate/Feedwater System

Failure,

C. (1) Single Loop Operation(2) ONLY 2AOP-04.O, Low Core Flow,

D. (1) Single Loop Operation(2) 2AOP-04.O, Low Core Flow AND OAOP-23.O, Condensate/Feedwater System

Failure,

Page: 77

78. During normal power operations on Unit One, two weeks following a refueling outage,a loss of both Fuel Pool Cooling pumps occurs.

Which one of the following completes the statement below based on the aboveconditions lAW OAOP-38.O, Loss of Fuel Pool Cooling? -

The procedure that will mitigate the rising fuel pool temperature is (1) andthe Fuel Pool temperature will be monitored using (2)

A. (1) 1OP-17, Residual Heat Removal System Operating Procedure,(2) E41-TR-R605, Point 17, on Panel H12-P614 (Control Room Back panel)

B. (1) 1OP-17, Residual Heat Removal System Operating Procedure,(2) a calibrated thermocouple near the skimmer surge tankinlet (RB 117’ elevation)

C. (1) OOP-13.1, Supplemental Spent Fuel Pool Cooling System OperatingProcedure,

(2) E41-.TR-R605, Point 17, on Panel H12-P614 (Control Room Back panel)

D. (1) OOP-13.1, Supplemental Spent Fuel Pool Cooling System OperatingProcedure,

(2) a calibrated thermocouple near the skimmer surge tank inlet (RB 117’ elevation)

Page: 78

79. Which one of the following choices complete the statements below identifying thestatus of the Main Turbine Bypass System lAW TS 3.7.6, Main Turbine Bypass Systemif two Turbine Bypass Valves are inoperable on each Unit?

The Unit One Main Turbine Bypass System is (1)

The Unit Two Main Turbine Bypass System is (2)

A. (1) OPERABLE(2) OPERABLE

B. (1) OPERABLE(2) Inoperable

C. (1) Inoperable(2) OPERABLE

D. (1) Inoperable(2) Inoperable

Page: 79

80. During accident conditions on Unit Two, primary containment is being vented throughSBGT trains due to high containment pressure.

SBGT 2A Train red Emerg Oper light on XU-51 is extinguished.

Which one of the following completes the statements below?

The minimum charcoal compartment temperature that will tripSBGT2AFanis (1)

If a fire were to occur in the SBGT train, the deluge system is nianually initiatedlAW (2)

A. (1) 180° F(2) 20P-10, Standby Gas Treatment System Operating Procedure

B. (1) 180° F(2) OOP-41, Fire Protection and Well Water System

C. (1) 210° F(2) 2OP-10, Standby Gas Treatment System Operating Procedure

D. (1) 210° F(2) OOP-41, Fire Protection and Well Water System

Page: 80

81. During an equalizing charge on 125 VDC Battery 1B, the following annunciators arereceived:

UA-14 4-1 BATTRM lB VENT FAN TRIPUA-06 2-5 SUB IF 480V FEEDER BKR TRIP

Which one of the following completes the statement below with 1 B Battery Roomtemperature at 60°F?

The procedure that directs securing the equalizing charge to mitigate the aboveconditions is (1)

The equalizing charge is secured due to a concern with (2)

A. (1) APP UA-14, BATTRM lB VENT FAN TRIP(2) room temperature

B. (1) APP UA-14, BATTRM lB VENT FAN TRIP(2) hydrogen concentration

C. (1) 1OP-51, DC Electrical System Operating Procedure(2) room temperature

D. (1) lOP-Si, DC Electrical System Operating ProOedure(2) hydrogen concentration

Page: 81

82. Unit One is operating at power when a nitrogen leak causes Drywell Pressure to rise to2 psig.

Which one of the following completes the statements below based upon the conditionsabove?

RBHVAC (1) to maintain Secondary Containment integrity.

Drywell pressure control is provided by isolating the affected pneumatic systemlAW (2)

A. (1) automatically isolates(2) PCCP, Primary Containment Control Procedure

B. (1) automatically isolates(2) OAOP-14.O, Abnormal Primary Containment Conditions

C. (1) must be manually aligned(2) PCCP, Primary Containment Control Procedure

D. (1) must be manually aligned(2) OAOP-14.O, Abnormal Primary Containment Conditions

Page: 82

83. Unit Two is operating at rated power when the following alarms are received:

DG-4 CTL POWER SUPPLY LOSTDG-4 LO STARTAIR PRESSDG4/E4 ESS LOSS OF NORM POWERDG-2 CTL POWER SUPPLY LOST

Subsequently, DG4 control power was transferred to its alternate DC source and DG4was returned to Standby.

Which one of the following identifies the DC panel that is currently supplying DG4control power and the impact on the operability of DG4 lAW LCO 3.8.1, AC SourcesOperating and [CO 3.8.7, Distribution Systems - Operating?

A. 125V DC Distribution Panel 1B;DG4 is operable on its alternate source for up to 7 days.

B. 125V DC Distribution Panel 1B;DG4 must be declared inoperable the entire time it is on its alternate source.

C. 125V DC Distribution Panel 2B;DG4 is operable on its alternate source for up to 7 days.

D. 125V DC Distribution Panel 2B;DG4 must be declared inoperable the entire time it is on its alternate source.

Page: 83

84

MOM fORBOP PARAMETERS

034

Which one of the following identifies an AOP for one of the primary BOP systemsspecified in this step that the operator would enter and execute concurrently with theRSP lAW 001-37.3, Reactor Scram Procedure Basis Document?

A. OAOP-12.0, Loss of Uninterruptible Power Supply (UPS)

B. OAOP-16.0, RBCCW System Failures

C. OAOP-23.0, Condensate! Feedwater System Failures

D. OAOP-37.1, Intake Structure Blockage

Page: 84

85. Unit Two is operating at rated power when a failure of the Feedwater Level ControlSystem causes maximum feedwater flow and rising reactor water level.

Which one of the following is the reason a REACTOR SCRAM is indirectly initiatedduring this event lAW the Bases for TS 3.3.2.2, Feedwater and Main Turbine HighWater Level Trip Instrumentation?

A. Mitigates the reduction in MCPR during the overfeed event.

B. Prevents fuel damage during significant reactivity increases.

C. Prevents filling of the Main Steam Lines by collapsing voids.

D. Protects the main turbine from damage due to water entering.the turbine.

Page: 85

86. OAOP-32.O, Plant Shutdown From Outside Control Room, is in progress.


The Auxiliary Operator assigned the position of MCC Operator on Unit One is directedto perform Attachment (1) to ensure RCIC availability.

Based on the indications below, after the 1-E51-F007, RCIC Steam Supply InboardIsolation Valve, NORMAL / LOCAL Switch is placed in LOCAL, indicatior will (2)

(red light is on)

A. (1) 3A, Unit 1, Station 3, Remote Shutdown Panel Initial Switch Alignment(2) change

B. (1) 3A, Unit 1, Station 3, Remote Shutdown Panel Initial Switch Alignment(2) remain the same

C. (1) 5A, Unit 1, Contingency Action, Equipment Status(2) change

D. (1) 5A, Unit 1, Contingency Action, Equipment Status(2) remain the same

Page: 86

87. Unit Two is operating at rated conditions.

2-RCC-V28, RBCCW Drywell Supply Valve, had an electrical short resulting in closureof the valve.

lAW Tech Spec LCO 3.6.1.3, Primary Containment Isolation Valves, which one of thefollowing statements is correct?

(Reference provided)

A. No Required Action because 2-RCCV28 is in its required ispIation.position.

B. No Required Action because 2-RCC-V28 is not a designated PCIV.

C. Enter Condition A and take the appropriate Required Actions.

D. Enter Condition C and take the appropriate Required Actions.

Page: 87

88. Unit One is in a Refueling Outage when a fuel bundle is dropped in the Spent FuelPool.

0815 Refuel SRO reports lowering Spent Fuel Pool level0830 FUEL POOL LEVEL LOW annunciator is received0845 Refuel SRO reports Spent Fuel Pool level is recovering0900 PROCESS RX BLDG VENT RAD HI annunciator is received

Which one of the following meets the declaration and reporting time requirementsspecified in the emergency plan for the conditions above?

(Reference provided)

Declaration of an ALERT by (1) and notification of State/Counties by (2)

A. (1) 0845(2) 0900

B. (1) 0845(2) 0945

C. (1) 0915(2) 0930

D. (1) 0915(2) 1015

Page: 88

89. Which one of the following identifies the procedure that directs the following step andthe bases for the step?

AlBEFORE

SUPPRESSION POOL TEMPREACHES 15OF

ESTABLISH CTMT COOLINGREQUIREMENTS PER

REDUCINGLPCI INJECTION FLOW

IF NECESSARY

This step is directed by (1) and is required to (2)

A. (1) PCCP(2) assure long term core cooling

B. (1) PCCP(2) minimize off-site releases per Alternative Source Term calculations

C. (1) RVCP(2) assure long term core cooling

D. (1) RVCP(2) minimize off-site releases per Alternative Source Term calculations

Page; 89

90. Following a small break LOCA on Unit Two, the following conditions exist:

Drywell temperature on CAC-TR-778Point #1 320° FPoint #3 263° FPoint #4 250° F

Drywell pressure 4.5 psigSuppr Chamber pressure 3.5 psig

• Suppr Pool level +5 inches

Which one of the following completes the statements below?(References provided)

The calculated Drywell Average Air temperature is (1)

The procedure that is required to be performed based on these conditions is (2)

A. (1) 265°F(2) SEP-02, Drywell Spray Procedure

B. (1) 265°F(2) SEP-03, Suppression Pool Spray Procedure

C. (1) 277°F(2) SEP-02, Drywell Spray Procedure

D. (1) 277°F(2) SEP-03, Suppression Pool Spray Procedure

Page: 90

91. Unit Two is operating at rated power when the following annunciators are received:

PROCESS RX BLDG VENT RAD HIGHPROCESS RX BLDG VENT RAD HI-HIAREA RAD RXBLDG HIGH

OAOP-05.O, Radioactive Spills, High Radiation, and Airborne Activity, has beenentered.


The cause of these radiation alarms is due to a (1)

QAOP-05.O is (2)

A. (1) RWCU line leak in the triangle room(2) performed concurrently with RRCP

B. (1) RWCU line leak in the triangle room(2) exited and RRCP is performed ONLY

C. (1) dropped and damaged new fuel bundle(2) performed concurrently with RRCP

D. (1) dropped and damaged new fuel bundle(2) exited and RRCP is performed ONLY

Page: 91

92. With Unit Two operating at rated power a complete loss of UPS occurs.The SCO has directed the RO to insert a manual reactor scram due to rising drywellpressure. Plant conditions are:

Manual Scram pushbuttons DepressedMode Switch Shutdown positionRPS Lights NOT litARI InitiatedDrywell pressure 2.1 psigAPRM Downscales Not litSCRAM VALVE PIL AIR HDR PRESS HI/LO In alarm

Which one of the following choices completes the statement below?

The SCO will direct the RO to perform Section

_____

of LEP-02, Alternate ControlRod Insertion.

A. 2, De-energize the Scram Pilot Valve Solenoids

B. 3, Reset RPS and Initiate a Manual Scram

C. 5, Insert Control Rods with the Reactor Manual Control System

D. 7, Maximize Cooling Water Header Pressure

Page: 92

93. Following a LOCA on Unit One, with NO RBCCW pumps in service, the following peakDrywell air temperatures were obtained:

CACJR-778 347° F @ 88 ft elevationCAC-TR-4426 347° F @ 23 ft elevation

Which one of the following completes the statements below forRBCCW pump restartlAW 1 OP-21, Reactor Building Closed Cooling Water System Operating Procedure?

(Reference Provided)

Attachment (1) is used to determine when the RBCCW pumps may be started.

The RBCCW pumps may be restarted (2) minutes after the peak localtemperatures have cooled to <230°F.

A. (1) 4, RBCCW Pump Restart Determination Using CAC-TR-4426(2) 30

B. (1) 4, RBCCW Pump Restart Determination Using CAC-TR-4426(2) 4 hours and 21

C. (1) 5, RBCCW Pump Restart Determination Using CAC-TR-778(2) 30

D. (1) 5, RBCCW Pump Restart Determination Using CAC-TR-778(2) 4 hours and 21

Page: 93

94. Unit One is t 20% power during plant shutdown with plans to perform a rapidshutdown from the current power level.

Excessive cooldown is of concern due to recent power history.

Which one of the following actions is allowed to be performed pjQr to inserting themanual scram to minimize cooldown?

A. Raise reactor water level to 195 inches lAW OGP-05, Unit Shutdown.

B. Secure both Steam Jet Air Ejectors and start Mechanical Vacuum Pumps lAWOGP-05, Unit Shutdown.

C. Raise reactor water level to 195 inches lAW OGP-12, Power Changes.

D. Secure both Steam Jet Air Ejectors and start Mechanical Vacuum Pumps lAWOGP-12, Power Changes.

Page: 94

95. Unit One is in an accident condition and is executing RVCP with the followingconditions:

Reactor Water Level -60 inchesReactor Pressure 800 psigReference Leg Temperature 208° FInjection sources available None

(Reference Provided)

Which one of the following identifies the required procedure(s) that is/are required tomaintain adequate core cooling? .

A. Enter STOP. Do NOT perform Emergency Depressurization.

B. Enter STOP and perform Emergency Depressurization.

0. Remain in RVCP. Do NOT perform Emergency Depressurization.

D. Remain in RVOP and perform Emergency Depressurization.

Page: 95

96. Considering the following sequence of events:

10:00 12/18/10 2A SLC Pump declared INOP14:00 12/20/10 2B SLC Pump declared INOP18:00 12/20/10 2A SLC Pump declared OPERABLE

Which one of the following is the latest time the Reactor would be required to be inMODE 3 lAW Tech Spec 1.3, Completion Times and LCO 3.1.7, Standby LiquidControl (SLC) System?

A. 10:00 12/25/10

B. 22:00 12/25/10

C. 22:00 12/26/10

D. 02:00 12/28/10

Page: 96

97. At the start of your shift (0800 hours) an l&C technician plans to work on a nuisancealarm. The annunciator audible alarm feature will be altered by installing a modifiedannunciator card. The work will be completed in 6 hours.

Which one of the following completes the statements below lAW 001-01 .01, BNPConduct of Operation Supplement?

The installation of the modified annunciator card requires a (1) dot to be placed onthe annunciator.

Attachment 24, Annunciator Removal From Service Form, is (2) to be completedfor documentation of the disabled annunciator.

A. (1) white(2) required

B. (1) white(2) NOT required

C. (1) black(2) required

D. (1) black(2) NOT required

Page: 97

98. Unit Two is shutdown to support Drywell entry due to Recirculation Pump oil levelconcerns. Reactor coolant temperature is 200° F.

E&RC has determined by sampling that the Drywell atmosphere is not suitable forunfiltered release.

Which one of the following completes the statements below lAW 20P-24, Section8.13, Primary Containment Purging (Deinerting) Through the SBGT System?

This section (2) be performed under the current plant conditions.

If Drywell pressure was above 0.7 psig, deinerting could result in (1)

A. (1) can(2) contamination of the RB 50’

B. (1) cannot(2) contamination of the RB 50’

C. (1) can(2) exceeding ODCM Main Stack release rates

D. (1) cannot(2) exceeding ODCM Main Stack release rates

Page: 98

99.

Unit Two is in an ATWS condition with the givenDrywell Monitor indications.

Which one of the following identifies the Loss orotf Potential Loss of the Fission Product Barrier(s)

lAW OPEP-02.1, Brunswick Nuclear Plant InitialEmergency Action Level Matrix?(Reference provided)

A. Fuel Clad Barrier ONLY.

B. Reactor Coolant System Barrier ONLY.

C. Both the Fuel Clad and Containment Barriers.

D. Both the Containment and Reactor Coolant System Barriers.

1O-C6I

Page: 99

100. The NRC has notified the Control Room of an Imminent Airborne Threat.

Which one of the following completes the statement below?

The Control Room is required to dispatch (1) operator(s) to both Unit One andUnit Two Reactor Buildings lAW (2)

A. (1) one(2) OAOP-40.0, Security Events

B. (1) one(2) OEDMG-001, Extreme Damage Mitigation Initial Response

C. (1) two(2) OAOP-40.0, Security Events

D. (1) two(2) OEDMG-001, Extreme Damage Mitigation Initial Response

Page: 100

LIST OF REFERENCES FOR SRO WRITTEN EXAM

1. Steam Tables

2. OEOP-01-UG, ATTACHMENT 5, FIGURE 6, RHR NPSH Limit

3. EOP-UG Attachment 6, Figure 21 (MSL)

4. OEOP-O1-UG, Attachment 5, Figure 1, Drywell Spray Initiation Limit

5. Unit Two Technical Specification, LCO 3.6.1.3

6. OPEP-2.1, Emergency Action Levels

7. EOP-O1 -UG Attachment 4, Drywell Average Air Temperature Calculation

8. 1 OP-21, Attachments 4-6, RBCCW Pump Restart

9. EOP-UG Attachment 6, Figures 17, 18, & 19 (Unit One TAF, LL4, and LL5 graphs)

ATTACHMENT 5

L10

w

Page 21 of27FIGURE 6

RHR NPSH Limit

RHR PUMP FLOW (GPM)

SUBTRACT 0.5 PSIG FROM INDICATED SUPPRESSION CHAMBERPRESSURE FOR EACH FOOT OF WATER LEVEL BELOW A SUPPRESSIONPOOL WATER LEVEL OF -31 INCHES (-2.6 FEET).

*SUPPRESSION CHAMBER PRESSURE (CAC-PI-1257-2A ORCAC-PI-1257-2B)

OEOP-01-UG Rev. 57 Page 80 of 151

290

280

270

260

250

240

230

220

210

200

190

180

170

160

0 5,000 10,000 15,000 20,000

LiiIC-)z-JLU>LU-J

LUI—

ci

z

60 200 400 600 800 1,000

REACTOR PRESSURE (PSIG)

WHEN REACTOR PRESSURE IS LESS THAN60 PSIG, USE INDICATED LEVEL.

MSL IS +250 INCHES.


ATTACHMENT 6Page 19 of 19

FIGURE 21Reactor Water Level at MSL

(Main Steam Line Flood Level)

300

250

200

REF LEGTEMPABOVE OREQUAL TO2OOFREF LEGTEMPBELOW2OOF

1,150


FIGURE 1Drywell Spray Initiation Limit

U0

w

w

UJI

w0

0::U-’

r

5 1510 20

UNSAFE

30 40 50 60 70

DRYWELL PRESSURE (PSIG)

DRYWELL AVERAGE AIR TEMPERATURE MAYATTACHMENT 4.

BE DETERMINED USING

OEOPO1-UG Rev. 57 Page 75 of 151

---

450

400

350

300

250

200

150

100

50

- SAFE —

-

025 35 45 55 65 75

- PCIVs3.6.1.3

3.6 CONTAINMENT SYSTEMS

3.6.1.3 Primary Containment Isolation Valves (PCIVs)

LCO 3.6.1 .3 Each PCIV, except reactor building-to-suppression chamber vacuumbreakers, shall be OPERABLE. .

APPLICABILITY: MODES 1, 2, and 3,

When associated instrumentation is required to be OPERABLE perLCO 3.3.6.1, “Primary Containment Isolation Instrumentation.”

ACTIONSV

NOTES1. Penetration flow paths may be unisolated inte’rmittently under administrative controls.

2. Separate Condition entry is allowed for each penetration flow path.

3. Enter applicable Conditions and Required Actions for systems made inoperable by PCIVs.

4. Enter applicable Conditions and Required Actions of LCO 3.6.1.1, “Primary Containment,”when PCIV leakage results in exceeding overall containment leakage rate acceptancecriteria.

CONDITION REQUIRED ACTION COMPLETION TIME

A. NOTE A.1 Isolate the affected 8 hoursOnly applicable to penetration flow path bypenetration flow paths with use of at least one closed - V

two PCIVs. and de-activated automatic

valve,

closed manual valve,blind flange, or check valve

One or more penetration with flow through the valveflow paths with one PCIV secured.inoperable except for MSIVleakage not within limit. AND

(continued)

Brunswick Unit 2 3.6-7 Amendment No. 233

ACTIONS

PCIVs3.6.1.3


A. (continued) A.2 NOTEIsolation devices in highradiation areas may beverified by use ofadministrative means.

Verify the affected Once per 31 dayspenetration flow path is for isolation devicesisolated. outside primary

containment

AND

Prior to enteringMODE 2 or 3 fromMODE 4, if primarycontainment wasde-inerted while inMODE 4, if notperformed within theprevious 92 days, forisolation devicesinside primarycontainment

(continued)


ACTIONS (continued)

PCIVs3.6.1.3


B. NOTE B.1 Isolate the affected 2 hoursOnly applicable to penetration flow path bypenetration flow paths with use of at least one closedtwo PCIVs. and de-activated automatic

valve,

closed manual valve,or blind flange.

One or more penetrationflow paths with two PCIVsinoperable except for MSIVleakage not within limit.

C. NOTE C.1 Isolate the affected 8 hours except forOnly applicable to penetration flow path by excess flow checkpenetration flow paths with use of at least one closed valves (EFCVs)only one PCIV. and de-activated automatic

valve,

closed manual valve, INior blind flange.

One or more penetration 12 hours for EFCVsflow paths with one PCIV ANDinoperable.

C.2 NOTEIsolation devices in highradiation areas may beverified by use of -

administrative means.

Verify the affected Once per 31 dayspenetration flow path isisolated.

(continued)


ACTIONS (continued)

PCIVs3.6.1.3


D. One or more penetration D.1 Restore leakage rate to 8 hoursflow paths with one or more within limit.MSIVs not within MSIVleakage rate limits.

E. Required Action and E.1 Be in MODE 3. 12 hoursassociated Completion Timeof Condition A, B, C, or D INInot met in MODE 1, 2, or 3.

E.2 Be in MODE 4. 36 hours

F. Required Action and F.1 Initiate action to suspend Immediatelyassociated Completion Time operations with a potentialof Condition A, B, C, or D for draining the reactornot met for PCIV(s) required vessel (OPDRVs).to be OPERABLE duringMODE4or5. OR

F.2 Initiate action to restore Immediatelyvalve(s) to OPERABLEstatus.


3 CI1JCAS

'"

2

3 HI.U,do~.

0 ..

4

5

6

E

Modes:

"'u.I"''''''di'('~''''''i>c.o''oll.reu CM"";"9S.faSh~'d<)w~

£~"ipmon'<>'C<)mp<>~.ol5

...... ", T"~j"," l"y OJ"',':","" 20

r<l.yf"dmS:~'"i,·I""'

• HPClC02S'.",. .. ,R"<)rr,,

. Bw~~' R",,,,,.,l1 E"D","'e, (6RE')

. """"P''''-''''''g Byld,,,;(RW lOM"y 0<>,,")

i 1 i 1 ! l i, I 5 IbUI

I! II! l!'! 5 iDEf!

8

F Finlo" Product

!.!pcp",,,",. Ir.mpo",uno

fG1.1 i

Fuel Clad Barrier

~~,,'~I ,.,...",...,. ... ~.,'..-".."~~""''''''..,,..~ ... ~~\.,; "" .... "",-

fSl.l ! F111.1 i

Any'"'' ",.ny~,""","'lkI" of "ilnOffvd CI.~ "f Res IToikF.ll

Table F-1 Fission Product Barrier Matrix

Reactor Coo!ant System Barrier

Potential Loss Loss

Containment Barrier

Potentia! Loss

2 f,roe,

£'<plo.icn

3

E

Modes: IT]

"".nCoo,.inhgS~"'Sh"'do.m

Equip,...,ni o,Com~on.nl>

· tJ~,d Gp"e,.tr" B"!~"'~

" ... ""I':.n.y r,o" "''''"' S",,,,",cW",,,r6~ld.·;

C<l",,,"s"a~",g

. CST,

In,.", .. 1 Flo~<lon~ ... ~OS C~~""~'n9 S ....

Sh~'d~wo (q"'~m."' '" Compo""""

• 0",,01 Ge"c",'nr B"ld"'~

·Oe,el4·0.yT'<"Room,

· Sr.N<""W'WI,,'"'nS<'''''~m

S~""C~ W.'~r 6"ld",~

R'"".'i,'I.l"'d"g r"~J"'~ 8uld";

C<l "~>l9~'lo'''~

1 j 1 i 1 i • i ~ i Ste I

Rp,","",,,',,,.,,,,, "yi"",,1 """"y or ,·.'c "·", .• 1,,., .,,"""'" or '""'.f ','0 ~<"~",,d ~""'" ~,' ~~"" ~v"",

CO"""""'~'" C[o,u", na' e",~",,"od (NO'e~)

Oc~.".,.," """000''''''''''' c,," ",,,ole PC (H21F;·\."M)02>5~1

Notes

c_" t"""",,",""OC,'M" ' .• ,~.~""". ,,, .... I j j , i ~

< 100 \lDC~, 1""",;;~'"~",."""o,,.11 r,,,M,,,.1 S"",1oc""", ""I~"~d 125VOC 1""0"",, 15 """ (N,,'" J)


Drywell Average Air Temperature Calculation



Drywefl Average Air Temperature Calculation

NOTE: Inputs for calculating Drywell Average Air Temperature may be obtainedfrom:

Recorders CAC-TR-4426-1A, -1B, -2A, -2B, OR

- Microprocessors CAC-TY-4426-1, -2, OR

- IF power is NOT available to Items 1 and 2, THEN RecorderCAC-TR-778, on the Remote Shutdown Panel.




RECORDER CAC-TR-4426-1A, -1B, -2A, -2B

90’ elevation

TR-4426-1A, Point 1258-22

TR-4426-2A, Point 1258-23

______ ____

÷

___________ ______

x 0.05 =

_______

Total No. of Average WeightedTemperatures Temp Average

TR-4426-2A, Point 1258-24 Temp

Between 70’ and 80’ elevation

TR-4426-1B, Point 1258-3

TR-4426-2B, Point 1258-2

______ ____ ___________ ______

x 0.09

_______


TR-4426-2B, Point 1258-4 Temp


TR-4426-1B, Point 1258-5

TR-4426-1B, Point 1258-7

_____ ____ ___________ ______

x 0.40 =

_______


TR-4426-2B, Point 1258-6 Temp

TR-4426-2B, Point 1258-8


TR-4426-1A, Point 1258-12

TR-4426-1B, Point 1258-9

_____ ____ ___________ ______

x 0.38 =

_______


TR-4426-2B, Point 1258-13

_____

Temp




RECORDER CAC-TR-4426-1A, -1B, -2A, -2B (Cont)

Below 5 elevation

TR-4426-1A, Point 1258-17-

TR-4426-1A, Point 1258-18

_____ ____

÷

___________ ______

x 0.08 =

_______


TR-4426-2A, Point 1258-19 Temp

TR-4426-2A, Point 1258-20

Drywell Average Air Temperature —

(Sum of Weighted Average Temps)




MICROPROCESSOR CAC-TY.-4426-1 ,-2

90 elevation

TY-4426-1, Point 5822

______

TY-4426-2, Point 5823

______ ____

÷

____________ ______

x 0.05

________


TY-4426-2, Point 5824

______

Temp

Between 70 and 80’ elevation

TY-4426-1, Point 5803

______

TY-4426-2, Point 5802

______ ____

±

____________

=

______

x 0.09 =

_______


TY-4426-2, Point 5804

______

Temp


TY-4426-1, Point 5805

______

TY-4426-1, Point 5807

______ ____

÷

____________

=

______

x 0.40 =

________


TY-4426-2, Point 5806

______

Temp

TY-4426-2, Point 5808

______


TY-4426-1, Point 5812

______

TY-4426-1, Point 5809

______ ____

÷

____________

=

______

x 0.38 =

_______


TY-4426-2, Point 581 3

______

Temp




MICROPROCESSOR CAC-TY-4426-1, -2 (Cont)

Below 5 elevation -

TY-4426-1 Point 5817

TY-4426-1, Point 5818

______ ____ ____________ ______

x 0.08

________


TY-4426-2, Point 5819 Temp

TY-4426.-2, Point 5820

Drywell Average Air Temperature —

(Sum of Weighted Average Temps)



DryweH Average Air Temperature Calculation

RECORDER CAC-TR-778

Above 70 elevation

TR-778 Point 1

______________

x 014 =

______________

WeightedTemp

Between 28 and 45’ elevation

TR-778 Point 3

______________

x 0.40 =

______________

°FWeighted

Temp

Below 23’ elevation

TR-778 Point 4

______________

x 0.46 =

______________

°FWeighted

Temp

Drywell Average Air Temperature(Sum of Weighted Temps)

0EOP01-UG Rev. 57 Page 59 of 151

RATTACHMENT 4

_____

Page 1 of 1R19 RBCCW Pump Restart Determination Using CAC-TR-4426

YES

Did it occur on Elevation 29’or below?

Restart RBCCW pumps.

1 OP-21 Rev. 50 Page 78 of 82 1

ReferenceUse

Did a local drywell maximum airtemperature reach or exceed

260 deg F?

Did it exceed285 deg F?

Was the maximum localtemperature equal to

260 deg F?

NO

Use Table I on YESAttachment 6

(for temperaturegreater than260 deg F.)

Use Table 2 onAttachment 6.

ATTACHMENT 5 R

_______

Page 1 of 1 ReferenceUse

R19J RBCCW Pump Restart Determination Using CAC-TR-778

Did a local drywell maximum airtemperature reach or exceed

258 deg F?

YES

Did it occur on Elevation 29’or below?

Was the maximum local Did it exceedtemperature equal to 284 deg F?

258 deg F?

NO

Use Table Ion

greate / Attachment 6.

Attachment 6Use Table 2 on(for temperature

258 deg F.)

Restart RBCCW pumps.

1OP-21 Rev. 50 Page 79 of 82

ATTACHMENT 6

_____

Page 1 of 1R19j Required Drywell Cooldown Time Prior to RBCCW Pump Restart R

ReferenceUse

NOTE: For the local drywell temperature ranges given below, the peak localtemperature must have cooled to equal to or less than 230°F for the timeindicated before RBCCW pumps may be restarted.

NOTE: CAC-TR-4426 only: If any air temperature indication at or below the 29elevation reached or exceeded 285°F, then the Required Drywell CooldownTime shown in Table 1 or Table 2 will be determined using the highestindicated air temperature 260°F currently existing at or below the 29’elevation. This action takes precedence over temperature indications abovethe 29’ elevation.

NOTE: CAC-TR-778 only: If any air temperature indication at or below the 29’elevation reached or exceeded 284°F, then the Required Drywell CooldownTime shown in Table 1 or Table 2 will be determined using the highestindicated air temperature 258°F currently existing at or below the 29’elevation. This action takes precedence over temperature indications abovethe 29’ elevation.

____________

TABLE_I>450°F >400°F and >350°F and >300°F and CAC-TR-4426:

450°F 400°F 350°F >260°F and300°FCAC-.TR-778:>258°F and

, 300°F

43 minutes 39 minutes 36 minutes 30 minutes 22 minutes

TABLE_2>450°F >400°F and >350°F and >300°F and CAC-TR-4426:

450°F 400°F 350°F >285°F and300°F

‘ CAC-TR-778:>284°F and

300°F

7 hr 4 mm 6 hr 23 mm 5 hr 30 mm 4 hr 21 mm 2 hr 27 mm

1 OP-21 Rev. 50 Page 80 of 82

C/)LU:E0z-JLU>LU-J

DLU

C-)Uz

OEOP-O1-UG Rev. 57 Page 98 of 151


FIGURE 17Unit 1 Reactor Water Level at TAF

0

-10

-20

-30

-40

-50

- 60

-70

- 80

-90

-100

REF LEGTEMPABOVE200°F

REF LEGTEMPBELOW OREQUAL TO200°F

,150

1,10060 200 400 600 800 1,000



TAF IS -7.5 INCHES.

C,)LUIC)z-JLU>LU-J

ULU

C)Uz


FIGURE 18Unit I Reactor Water Level at LL-4(Minimum Steam Cooling Level)


0

-10

- 20

- 30

-40

-50

-60

- 70

-80

- 90

- 100

1,10060 200 400 600 800 1,000



LL-4 IS -30.0 INCHES.

LUzC-)z-JLU>LU-JCLUF

C-:,Cz


LL-5 IS -47.5 INCHES.



FIGURE 19Unit I Reactor Water Level at LL-5

(Minimum Zero Injection Level)

0

-10

- 20

- 30

-40

- 50

- 60

- 70

- 80

- 90

-100

60 200 400 600 800 1,000


76. during a loca with a loop the following plant conditions … · a. oaop-12.0, loss of...

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