ML101590396

301 Reactor Operator Written Exam (Section 2)

ML101590396
Person / Time
Site:	Turkey Point
Issue date:	03/28/2010
From:	NRC/RGN-II
To:
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Download: ML101590396 (202)

Text

NRC DRAFT 07/24/07 07124/07 Q#1 0#1 100% power with all systems in normal alignment except for 3A S/G Unit 3 is at 100% SIG level transmitter, LLT-3-474 T-3-474 (red channel) which has failed LOW.

3-ONOP-049.1, Operators have tripped associated bistables in accordance with 3-0NOP-049.1, Deviation "Deviation or Failure of Safety Related or Reactor Protection Channels.

Channels."

Subsequently, 3A S/G feed flow transmitter, FT-3-477 (blue channel), fails LOW.

Which ONE of the following describes the correct operator response?

A. 3-ONOP-049.1 again and trip all bistables associated with Perform 3-0NOP-049.1 FT-3-477.

B. 3-ONOP-049.1 again and trip all bistables associated with FT-3-477 Perform 3-0NOP-049.1 FW to SF Mismatch Logic" except for the "FW Logic bistable, BS-3-478B-1.

BS-3478B-1.

C. Declare Unit 3 is in TS 3.0.3 and be in Hot Standby within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />.

D. Reactor Trip or Safety Trip the reactor and transition to 3-EOP-E-0, "Reactor Injection Injection"

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 QQ#1

1. 1 ANSWER:

ANSWER: DD KA: 000007EA2.02 KA: 000007EA2.02 Able to Able to determine determine or or interpret interpret following following as as they they apply apply to to reactor reactor trip:

trip: Proper Proper actions actions to be taken ifif the to be taken the automatic automatic safety safety functions functions have have not not taken taken place.

place. 4.3/4.6 4.3/4.6 IOCFR55:

10CFR55: 41.b.5, 41.b.7, 41.b.5, 41.b.7, 41.b.10 41.b.1O

Reference:

5610-T-L1, 5610-T-L 1, Sheet 22 5610-T-L1, 5610-T-L Sheet 19 1, Sheet 19 5610-T-D-17 , Sheet 1 5610-T-D-17,Sheet1 3-ONOP-049.1, Pages 3-0NOP-049.1, Pages 33 & 45 Cog Level: Comprehension 2 Comprehension Level 2 because the operator must recognize that a red (Channel 11)) S/G level transmitter with its bistables tripped includes a low level trip bistable. When the blue channel (Channel 3) feed flow transmitter fails, a steam flow/feed flow mismatch logic is made up that combines with the existing low level signal to generate a reactor trip signal.

New Question Response Analysis:

A. Incorrect because the reactor should have tripped. Operators should transition to EOP-EO.

EOP-E-O. Plausible, because this is the normal response to aa failure of FT-3-477 if a reactor trip signal had not been generated generated.

B. Incorrect because the reactor should have tripped. Operators should transition to EOP-E-O. Plausible, because this is the response to aa failure of FT-3-477 following aa failure of of LT-3-474 LT-3-474 ifif aa reactor trip signal hadhad not not been been generated.

generated.

C.

C. Incorrect Incorrect because because the the reactor should should have have tripped.

tripped. Operators Operators should should transition transition to to EOP-E-O.

EOP-E-O. Plausible, Plausible, because because the the unit unit would would be in TS be in TS 3.03 3.03 ifif the the reactor had not tripped.

had not tripped.

D.

D. Correct Correct per the references.

per the references. TheThe reactor reactor should should havehave tripped tripped as as aa result result ofof the Low S/G level with steam the Low S/G level with steam flow/feedflow/feed flow flow mismatch mismatch signal signal generated generated by by the FT-3-477 the FT-3-477 failure.

failure.

92

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q#2 0#2 Following aa pressure Following pressure transient transient inin the the RCS, RCS, aa pressurizer pressurizer safety safety valve valve lifted lifted and and subsequently remained subsequently remained open.

open.

• • Operators are Operators performing 3-EOP-ES-1.2, are performing 3-EOP-ES-1 .2, "Post Post LOCA LOCA Cooldown Cooldown andand Depressuriza tion.

Depressurization.

• • RCS subcooling RCS subcooling isis less less than than the minimum required.

the minimum required.

• • With RCS With RCS T-hot T-hot less less than than 350°F, 350° F, operators operators start start one one RHR pump and RHR pump and stop stop one one HHSI pump.

HHSI pump.

following describes Which ONE of the following describes the effect of starting starting the the RHR RHR pump pump andand stopping the HHSI HHSI pump?

pump?

A.

A. Secondary heat sink will be improved by RHR flow collapsing reactor head voids after stopping the HHSI pump.

B. RCS subcooling will decrease after stopping the HHSI pump until the RHR pumps injects into the RCS.

C. Subsequent steam generator U-tube cooldown will be enhanced by the addition of RHR flow through the steam generators.

D. RCS subcooling will NOT be affected by stopping the HHSI pump because the RHR pump is already injecting into the RCS.

33

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q#2 Q#2 ANSWER:

ANSWER: BB KA:

KA: 000008AK3.05 000008AK3.05 Knowledge for Knowledge for the the reasons reasons for for the the following following responses responses as as they they apply apply to to the the PRZ PRZ vapor space accident: ECCS vapor space accident: ECCS terminating terminating or or throttling throttling criteria.

criteria. 4.0/4.5 4.0/4.5 IOCFR55:

10CFR55: 41.b.5, 41.b.7, 41.b.5, 41.b.7, 41.b.8, 41.b.8, 41.b.10 41.b.10

Reference:

3-EOP-ES-1.2, Step 3-EOP-ES-1.2, Step 17 17 BOBD Cog Level:

Cog Level: 2 Comprehension Comprehension Level 2 because the operator must analyze plant conditions and apply thermodynamic principles thermodynamic principles to determine the effect starting and stopping various injection flows has on subcooling and the effect that the HHSI pumps have on maintaining pressure higher and thus subcooling greater.

New Question Response Analysis:

A. Incorrect because the RHR pump is no more effective at collapsing head voids than the previously running HHSI pump and this is not the reason given by the reference. Plausible because head voids should be expected for a steam space LOCA and SI pumps do help collapse head voids.

B. Correct per the reference.

C. Incorrect because the addition of RHR flow will not not significantly increase increase flow though though thethe S/Gs and this is S/Gs and is not not the the reason givengiven by by the reference.

Plausible because S/G S/G U-tube U-tube cooldown would would be be enhanced enhanced by by additional additional cooling cooling flow.

D.

O. Incorrect Incorrect because because the the pressure pressure mustmust drop drop until until itit is is less less than than the the RHR RHR pumppump shutoff shutoff head.

head. Thus Thus subcooling subcooling must must decrease decrease whenwhen the the HHSI HHSI pump pump is is shut shut off.

off.

44

NRC DRAFT NRC DRAFT 07124/07 07/24/07 Q#3 Q#3 Operators are Operators are responding responding to to aa large large break break LOCA LOCA on Unit 4.4.

on Unit

• • When When thethe BOP BOP attempts attempts to to reset reset 81 SI on on VPB, VPB, aa circuit circuit failure failure occurs occurs andand the the 81 SI signal CANNOT signal CANNOT be be reset.

reset.

• • Operators have Operators have transitioned transitioned to to 4-EOP-E8-1.3, 4-EOP-ES-1 .3, "Transfer Transfer to to Cold Cold Leg Leg Recirculation and expect Recirculation" and expect to to subsequently subsequently establish establish "piggy-back" piggy-back recirc recirc alignment.

alignment.

Which ONE Which ONE of of the the following following describes describes the the effect effect of being unable of being unable to to reset reset 81?

SI?

A.

A. The running The running RHR RHR pump(s) pump(s) can can NOT NOT be stopped preventing be stopped preventing operators operators from from closing RHR closing RHR pump pump suction suction valves, valves, MOV-4-862A MOV-4-862A & & B.B.

B.

B. Once stopped, Once stopped, thethe RHR RHR pump(s) can NOT NOT bebe restarted until until the 81 SI signal isis reset.

C. RHR discharge to cold leg isolation valves, MOV-4-744A & & B, can NOT be closed requiring local closure of BOTH RHR heat exchanger manual outlet valves, 4-759A & B.

D. RHR discharge to cold leg isolation valves, MOV-4-744A & & B, can NOT be closed requiring local closure of EITHER RHR heat exchanger manual outlet valve, 4-759A or B.

55

NRCDRAFT NRC DRAFT 07/24/07 07/24/07 Q#3 Q#3 ANSWER:

ANSWER: CC KA:

KA: 00001IEA2.0 000011 EA2.022 Able to Able to determine determine and and interpret interpret the the following following as as they they apply apply toto aa LBLOCA:

LBLOCA:

Consequence Consequences to s to RHR RHR of of not not resetting resetting SI.

SI. 3.3/3.7 3.3/3.7 10CFR55:

10CFR55: 41.b.7 41.b.7

Reference:

4-EOP-ES-1.3, Step 4-EOP-ES-1.3, Step 19 19 RNO RNO 5613-M-3050, Sheet 5613-M-3050, Sheet 11 5610-T-L1, 5610-T-L Sheet 11 1, Sheet 11 Cognitive Level:

Cognitive Level: 22 Comprehension Comprehension Level 22 because Level because the the operator operator must must understand understand integrated integrated plant plant operations, operations, interlocks interlocks and response not response not obtained actions to recognize recognize the effect of not not being able to reset SI. Once recognized that the 744 valves cannot be closed, the able operator must determine the correct response to close both RHR HX outlet valves operator EOP-ES-1 .3, Step 19.

per EOP-ES-1.3, New Question New

Response

Response Analysis:

A. Incorrect becaus because e the running RHR pumps can be stopped by placing their control switches in Pull-to-Lock Pull-to-Lock.. Plausible, because there is aa continuous start start signal to the RHR pumps as aa result of of the active SI signal present.

B.

B. Incorrect Incorrect becaus because e the the running RHR RHR pumps pumps can be be manually manually started from VPB.

VPB. Plausible, Plausible, because because the the RHR RHR pumps pumps can can be be stopped stopped by by placing placing their their control switches in Pull-to-Lock control switches in Pull-to-Lock..

C.

C. Correct Correct per per thethe references.

references. IfIf SI SI cannot cannot be be reset, reset, there there isis aa continuous continuous OPEN OPEN signal signal to to MOV-4-744A MOV-4-744A && B. B. IfIf the the valves valves cannot cannot be be closed, closed, EOP-E EOP-ES- S 1.3, 1.3, Step Step 19 19 RNO RNO requires requires closure closure of of bothboth RHR RHR heat heat exchanger exchanger outletoutlet valves.

valves.

D.

D. Incorrect Incorrect becaus because e IfIfthe the valves valves cannot cannot be be closed, closed, EOP-ES-1.3, EOP-ES-1.3, Step Step 19 19 RNO RNO requires requires closure closure of of both both RHRRHR heatheat exchanger exchanger outlet outlet valves, valves, not notjust just one.

one.

Plausible Plausible becaus because e IfIfSISI cannot cannot be be reset, reset, there there isis aa continuous continuous OPEN OPEN signal signal to MOV-4-744A to MOV-4-744A && B. B.

66

NRCDRAFT NRC DRAFT 07/24/07 07/24/07 Q#4 0#4 Unit33 isisatat100%

Unit 100% power powerwhen when annunciator annunciator8B2/5, 2/5, RCP RCP 8B OIL OIL RESERVOIR RESERVOIRHIILO HI/LO LEVE L, alarms LEVEL, alarms..

Which ONE Which ONE of ofthe thefollowing following describes describes thethe correct correct operator operator response?

response?

the cause IfIfthe cause isis verified verified toto be be from from a:a:

A.

A. Low reservoir Low reservoir level, level, plot plot 38 3B RCP RCP motor motor bearing bearing temperatures temperatures everyevery 15 15 minutes.

minutes.

B.

8. Low reservoir Low reservoir level, level, stop stop the the 383B RCP RCP and and isolate isolate CCW CCW flow flow to to the the oil oil coolers coolers within 30 minute within 30 minutes. s.

C.

C. High reservoir High reservoir level, level, plot plot 38 3B RCP RCP motor motor and and shaft shaft vibration vibration every every 1515 minute minutes. s.

D.

D. High reservoir High reservoir level, level, stop the 38 3B RCP RCP and increase increase CCW flowflow to the oiloil coolers within 30 minutes.

coolers minutes.

77

NRCDRAFT NRC DRAFT 07/24/07 07/24/07 Q#4 Q#4 ANSWER:

ANSWER: AA KA:

KA: 00001 5/1 7AAI .02 000015/17AA1.02 Able to operate and/ormonitor Able to operate and/or monitorthe the following following asas they theyapply applyto to the the RCP RCP Malfunctions Malfunctions (Loss of RC flow): RCP Oil Reserv oir (Loss of RC flow): RCP Oil Reservoir level and level and alarm alarm indicators.

indicators. 2.8/2.7 2.8/2.7 10CFR55:

10CFR55: 41.b.7 41.b.7

Reference:

3-ARP-097.CR, Ann.

3-ARP-097.CR, Ann. B2/5 B2/5 3-ONO P-041.

3-0NOP-041.11,, StepsSteps 88 and and 43 43 Cognitive Level:

Cognitive Level: 11 Recall Recall New Question New Question Response Analysis:

Response Analysis:

A.

A. Correct per 3-0NOP-041.1, Correct 3-ONOP-041 .1, Step 43.

B.

B. Incorrect because Incorrect because this is the action to be taken if high reservoir reservoir level is discov ered, discovered, not low reservoir level as stated in the response.

reservoir response. Plausible Plausible because this would be the correct action if the problem was discovered because discovered to to be be high reservo high reservoir ir level.

C.

C. Incorrect Incorrect becaus because e bearing temper atures should be plotted, not vibration.

temperatures Plausib Plausiblele becaus because e this is the correct freque frequency ncy of monitoring.

D.

D. Incorrect Incorrect becaus because e this is is the the incorrect respon response for high se for high reservo reservoir level. COW ir level. CCW flow flow should should bebe isolated, isolated, not not increas increased Plausible ed Plausib because CCW flow le because COW flow to the to the oil oil coolers coolers must must be be altered altered within within 3030 minute minutes in the s in the event event ofof high high reservo reservoir ir level..

level..

88

NRCDRAFT NRC DRAFT 07/24/07 07/24/07 Q#5 0#5 Unit33 isis atat 100%

Unit 100% power powerwithwith all all systems systems inin normal normal alignment.

alignment. 3A 3A Charging Charging pump pump isis operating.

operating.

3-267, 3A 3-267, Chrg pump 3A Chrg pump suct, suct, isolation isolation valve, valve, experiences experiences aa body-to-bonnet body-to-bonnet leakleak resulting in a loss of charging resulting in a loss of charging flow. flow.

Which ONE Which ONE of of the the following following describes describes the the correct correct operator operator response response and and the the reason reason for that response?

for that response?

A.

A. Verify all Verify charging pumps all charging pumps are are stopped stopped andand then then close close valve valve 3-268, 3-268, Chrg Chrg Pump Suct Pump Suct HdrHdr X-Conn X-Conn valve, valve, because because no no charging charging pumps pumps can deliver flow can deliver flow to the to the RCS. RCS.

B.

8. Stop the Stop the 3A3A Charging Charging pumppump andand start start the the 38 3B Charging Charging pump pump after after closing closing valve 3-268, valve 3-268, Chrg Chrg Pump Pump Suct Suct Hdr Hdr X-Conn X-Conn valve, valve, because because only 38 Charging only 3B Charging pump can pump can deliver deliver flow flow to the RCS.RCS.

C. Stop the 3A Charging pump and start 3C 30 Charging pump after closing valve 3-268, Chrg Pump Suct Hdr X-Conn valve, because because only the 3C Charging pump can deliver flow to the RCS.

D. Start either of the 38 3B or 3C Charging pump after closing valve 3-268, Chrg Pump Suct Hdr X-Conn valve, because because either 38 3B or 3C Charging pump can deliver flow to the RCS.

REFERENC REFERENCE E PROVIDED 99

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q#5 Q#5 ANSWER:

ANSWER: CC KA:

KA: 000022AK3.07 000022AK3.07 Knowledge for Knowledge for the the reasons reasons forfor the the following following responses responses asas they they apply apply toto the Loss of the Loss of Reactor Coolant Reactor Coolant Makeup:

Makeup: Isolating Isolating charging.

charging. 3.0/3.2 3.0/3.2 IOCFR55:

10CFR55: 41.b.5, 41.b.10 41.b.5, 41.b.10

Reference:

3-ONOP-047.1, Step 4.1 3-0NOP-047.1, 5613-M-3047, Sheet 2 5613-M-3047,Sheet2 NOTE: 5613-M-3047, Sheet 2 AS A REFERENCE PROVIDE 5613-M-3047, REFERENCE Comprehension Cog Level: 2 Comprehension Level 2 because the RO must evaluate the location of the leak and determine that the leak location disables both the 3A and 3B Charging pumps. The 3C Charging pump is still viable but valve 3-268 must be closed first.

New Question Response Analysis:

A. Incorrect because 3C Charging pump is still available once valve 3-268 is closed. Plausible because all charging should be stopped and because even if charging could not be recovered, valve 3-268 should be closed to isolate the leak.

B. Incorrect because the 3B Charging pump is disabled as well as the 3A pump is Charging pump. Plausible because the 3A Charging pump needs to be stopped and valve 3-268 should be closed.

C.

C. Correct Correct because the 3A 3A Charging Charging pump pump needs needs to be be stopped andand only the 3C Charging 3C Charging pumppump can deliver deliver flow but but only only after after valve valve 3-268 3-268 isis closed.

closed.

D.

D. Incorrect Incorrect because because the 3B Charging the 3B Charging pump pump is is disabled disabled as as well well as as the the 3A 3A Charging pump. Plausible because Charging pump. Plausible because the 3C the 3C Charging Charging pump pump cancan deliver deliver flow but only but only after after valve valve 3-268 3-268 isis closed.

closed.

10 10

NRC DRAFT NRC DRAFT 07124/07 07/24/07 Q#6 Q#6 Unit 44 isis inin Mode Unit Mode 44 andand onon RHR RHR cooling.

cooling.

• • AA Loss Loss of of Off-Site Off-Site Power Power (LOOP)

(LOOP) occurs.

occurs.

• • The The 4A 4A sequencer sequencer failsfails to to start start its its components.

components.

Which ONE Which ONE of of the the following following describes describes the the correct correct operator operator response response regarding regarding restoration of restoration of CCW CCW pump pump andand RHR RHR pumppump operation?

operation?

The operator The operator will: will:

A. NOT have NOT have to start any to start any CCW 0GW pumps pumps or RHR pumps.

or RHR pumps.

B. NOT have to start any CCW 00W pumps but will start one RHR pump.

C. have to start one CCW pump and will NOT have to start any RHR pumps.

D. have to start one CCW COW pump and start one RHR pump.

1111

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q#6 Q#6 ANSWER:

ANSWER: DD KA:

KA: 000025AA1.04 000025AA1.04 Able to Able to operate operate and/or and/or monitor monitor the the following following asas they they apply apply to to the the Loss Loss ofof RHR RHR System: Closed cooling System: Closed cooling water water pumps.

pumps. 2.8/2.6 2.8/2.6 IOCFR55:

10CFR55: 41.b.7 41.b.7

Reference:

4-ONOP-004, Steps 4-0NOP-004, Steps 77 and and 88 5614-T-L1, Sheet 5614-T-L1, Sheet 12A&

12A & 12B12B Cog Level:

Cog Level: 22 Comprehension Comprehension Level 22 because Level because the the operator operator must must evaluate evaluate thethe effect effect of of the the loss loss of of the the 4A 4A sequencer on on the final CCW and and RHR RHR pumppump configuration and and then the operator operator must recall the CCW COW and RHR RHR pump pump requirements of ONOP-004.

New Question Response Analysis:

A. Incorrect because the operator will have to start one CCW COW pump and start one RHR pump. Plausible because if the sequencer had operated properly, the operator would not have had to start any CCW COW pumps.

B. Incorrect because the operator will have to start one COW CCW pump and start one RHR pump. Plausible because ifif the sequencer had operated properly, the operator would not have had to start any any COW CCW pumps and the operator will have will have to to start start one one RHR RHR pump.

pump.

C.

C. Incorrect Incorrect because the operator operator will have have to to start start one one RHR RHR pump.

pump. Plausible Plausible because because the the operator operator will will have have toto start start one one COWCCW pump.

pump.

D.

D. Correct Correct because because thethe operator operator will will have have toto start start one one COW CCW pumppump andand start start one one RHR pump.

RHR pump.

1212

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q#7 0#7 Operators are Operators are responding responding to to aa main main steam steam line line break break inside inside Unit Unit 33 containment.

containment.

• • Containment pressure Containment pressure peaked peaked at at 26 psig and 26 psig and isis now now 1515 psig.

psig.

• • The 3B SG WR level is 15% and The 3B SG WR level is 15% and lowering. lowering.

• • No charging pumps No charging pumps areare running running

• • Step 10 of 3-EOP-E-1, Step 10 of 3-EOP-E-1, "Loss Loss ofof Reactor Reactor or Secondary Coolant,"

or Secondary Coolant, directs directs establishment of establishment of maximum maximum charging charging flow.

flow.

• • Seal Water Seal Water Return Return temperatures temperatures are are at at 245°F.

245°F.

• • The Unit Supervisor orders closure of The Unit Supervisor orders closure of the local the local seal seal injection injection valves, valves, 297 297 AlBIC, A/B/C, before starting before starting the first charging the first charging pump.

pump.

Which ONE of the following describes why the local local seal seal injection injection valves areare closed this time?

at this A. CCW flow to the thermal barriers has been lost.

RCP seals already have elevated temperatures and initiation of cold seal injection flow will cause RCP damage.

B. CCW flow to the thermal barriers has been lost.

RCP seal temperatures are still in the allowed range and maximum charging flow to the RCS loops via the normal charging path is required.

C. CCW flow to the thermal barriers has NOT been interrupted.

Seal injection is NOT needed to maintain seal integrity and maximum charging flow to the RCS loops via the normal charging path is required.

D. CCW flow to the thermal barriers has NOT NOT been interrupted.

Seal injection is NOTNOT needed to maintain seal integrity and and initiation of of cold seal injection flow will cause RCP RCP damage.

damage.

13 13

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q#7 Q#7 ANSWER:

ANSWER: AA KA:

KA: 000026AK3.03 000026AK3.03 Knowledge for Knowledge for the the reasons reasons for for the the following following responses responses as as they they apply apply to to the the loss loss of of CCW: Guidance contained CCW: Guidance contained in in EOP EOP forfor loss loss of of CCW.

CCW. 4.0/4.2 4.0/4.2 IOCFR55:

10CFR55: 41.b.5, 41.b.10 41.b.5, 41.b.10

Reference:

3-EOP-E.1, Step 3-EOP-E-1, Step 10 10 RNO RNO SD BD 5610-T-L1, Sheet 5610-T-L1, Sheet 11 11 5613-M-3030, Sheet 5 5613-M-3030, Cog Level: 1I Recall New Question Response Analysis:

A. Correct per the references.

B.

S. Incorrect because RCP seal temperatures are already heated up per the basis document. Plausible because CCW flow to the thermal barriers has been lost.

C. Incorrect because CCW flow to the thermal barriers has been lost. Plausible because maximum charging flow to the RCS loops loops via the normal charging path is required.

D.

D. Incorrect Incorrect because because CCWCCW flow to to the thermal thermal barriers barriers has has been been lost.

lost. Plausible Plausible because initiation initiation of of cold seal injection flow will cause RCP damage.

damage.

14 14

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q#8 Q#8 Unit 44 is Unit is initially initially at at 70%

70% power power with with all all systems systems in automatic except in automatic except the the master master pressurizer pressure pressurizer pressure controller, controller, PC-4-444J, PC-4-444J, which which isis in in manual manual due due to to an an instrument instrument failure.

failure.

• • 4B Steam 4B Steam Generator Generator Feed Feed pump pump (SGFP)

(SGFP) breaker breaker subsequently subsequently trips.

trips.

Which ONE Which ONE of of the following describes the following describes the the effect effect of this event of this event on on the the RCS RCS and and the the correct operator response?

correct operator response?

The resulting turbine runback runback will initially initially cause RCS RCS temperature to:

A. increase resulting in expansion of reactor coolant into the pressurizer causing RCS pressure to increase.

The RO RO will drive the PC-4-444J controller output higher (toward 100%) to stabilize pressure.

B. increase resulting in expansion of reactor coolant into the pressurizer causing RCS pressure to increase.

The RO will drive the PC-4-444J controller output lower (toward 0%) to stabilize pressure.

C. decrease resulting in contraction of reactor coolant from the pressurizer causing RCS pressure to decrease.

The RO will drive the PC-4-444J controller output higher (toward 100%) to stabilize pressure.

D. decrease resulting in contraction of reactor coolant from the pressurizer causing RCS pressure to decrease.

The RO will drive the PC-4-444J controller output lower (toward 0%) to stabilize pressure.

15 15

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q#8 Q#8 ANSWER:

ANSWER: AA KA:

KA: 000027AK1.02 000027AK1.02 Knowledge of Knowledge of the operational implications the operational impl!cations of the following of the following concepts concepts as as they they apply apply to to the pressurizer pressure control malfunctions the pressurizer pressure control m'alfunctions:: Expansion Expansion of of liquids liquids as as temperature temperature increases. 2.8/3.1 increases. 2.8/3.1 10CFR55:

10CFR55: 41.b.5, 41.b.7, 41.b.5, 41.b.7, 41.b.10, 41.b.10, 41.b.14 41.b.14

Reference:

4-ONOP-041 .5, Step 4-0NOP-041.5, Step 1.a l.a RNO RNO SD-009, Figure SO-009, Figure 22 22 Cog Level:

Cog Level: 22 Comprehension Comprehension Level 2 because the operator must analyze that with turbine load reduced first, Tavg will initially increase and then be higher than Tref, and pressurizer level will increase raising pressure. The system will need more spray output to maintain programmed pressure. This requires an increase in controller output to open sprays.

New Question Response Analysis:

A. Correct per the references.

B. Incorrect because the RO will drive the PC-4-444J controller output higher (toward 100%)

100%) to stabilize pressure. Plausible because the resulting turbine runback will initially cause RCS temperature to increase increase resulting in expansion of of reactor coolant into into the the pressurizer causing causing RCS pressurepressure to to increase.

C.

C. Incorrect Incorrect because because the the resulting turbine turbine runback will initially initially cause cause RCSRCS temperature temperature to increase to increase resulting resulting in in expansion expansion of of reactor reactor coolant coolant into into the the pressurizer pressurizer causing causing RCS RCS pressure pressure to to increase.

increase. Plausible Plausible because because the the RO RO will drive the PC-4-444J controller will drive the PC-4-444J controller output output higher higher (toward (toward 100%)100%) to to stabilize stabilize pressure pressure D.

O. Incorrect Incorrect because because the the resulting resulting turbine turbine runback runback will will initially initially cause cause RCSRCS temperature temperature to to increase increase resulting resulting in in expansion expansion of of reactor reactor coolant coolant into into the pressurizer the pressurizer causing causing RCS RCS pressure pressure to to increase increase and and thethe RO RO will will drive drive the the PC-4-444J PC-4-444J controller controller output output higher higher (toward (toward 100%)

100%) to to stabilize stabilize pressure.

pressure.

Plausible Plausible the the response response isis consistent consistent ifif the the operator operator doesdoes notnot realize realize that that aa turbine turbine runback runback causes causes the the RCS RCS temperature temperature to to increase.

increase.

16 16

NRC DRAFT NRC DRAFT 07124/07 07/24/07 Q#9 0#9 Unit 44 was Unit was at at 100% power with 100% power with all all systems systems inin normal normal alignment alignment when when the the following following events occurred:

events occurred:

• • 4C4C S/G faulted outside SIG faulted outside containment.

containment.

• • The The reactor reactor failed failed to to trip trip automatically automatically or manually.

or manually.

• • All other All other safeguards safeguards systems systems actuated actuated as as required.

required.

Operators are Operators are performing performing Step Step 14 14 of of 4-EOP-FR-S.1, 4-EOP-FR-S.1, "Response Response toto Nuclear Nuclear Power Power Generation/A TWS, which directs Generation/ATWS," which directs them to them Verify steam to "Verify steam supply supply aligned aligned to to both both trains of trains of AFW AFW pumps pumps fromfrom intact intact S/G(

S/G(s).

s )."

Which ONE Which ONE of the following of the following describes describes the the correct correct operator operator response?

response?

(Note: AFSS-4-006 and (Note: and AFSS-4-007 AFSS-4-007 are are AFW AFW steam supply crosscross connect connect valves.)

Direct the NSO Direct NSO to locally:

A.

A. open AFSS-4-006 only.

B.

B. open AFSS-4-007 only.

C.

C. close AFSS-4-007 and then open AFSS-4-006 AFSS-4-006..

D.

D. open AFSS-4-007 and then close AFSS-4-006 AFSS-4-006..

1717

NRC DRAFT NRC DRAFT 07124/07 O7/24/7 Q#9 Q#9 ANSWER:

ANSWER: 0D KA:

KA: 000029G2.1.30 000029G2.1.30 As itit relates As relates toto the ATWS event:

the ATWS event: Able Able to to locate locate and and operate operate components, components, including including local controls.

local controls. 3.9/4.0 3.9/4.0 I OCFR55:

10CFR55: 41 .b.4, 41.b.7,41.b.10 41.b.4, 41 .b.7, 41 .b.10

Reference:

4-EOP-FR-S.1, Step 4-EOP-FR-S.1, Step 14.d.RNO 14.d.RNO 5614-M-3075, Sheet I 5614-M-3075,Sheet1 Cog Level:

Cog Level: 22 Comprehension Comprehension Level 2 because the operator must must recognize that the goal is to restore steam supply from two intact steam generator trains and to maintain train separation and maintain steam supply during the process. The correct way to achieve this is to AFSS-4007 and then close AFSS-4-006.

locally open AFSS-4-007 AFSS-4-006.

New Question Response Analysis:

A. Incorrect because the RO RD will direct the NSO to open AFSS-4-007 and then close AFSS-4006 AFSS-4-006 lAW EOP-FR-S.1 EOP-FR-S.1,, Step 14.d.RNO.

14.d.RNO. Plausible because the procedure step does not specify the desired position of AFSS-4-006 AFSS-4-006.. It merely directs operators to manipulate AFSS-4-006AFSS-4-006..

B. Incorrect Incorrect because the RD RO will direct the NSO to open AFSS-4-007 and then close close AFSS-4-006 lAW lAW EOP-FR-S.1 EOP-FR-S.1,, Step Step 14.d.RNO.

14.d.RNO. Plausible Plausible because because itit is is correct (but not not complete) to locally locally open AFSS-4-007 AFSS-4-007..

C.

C. Incorrect Incorrect because because thethe RD RO will direct direct the the NSO NSO toto open open AFSS-4007 AFSS-4-007 and and then then close AFSS-4-006 close AFSS-4-006 lAW lAW EOP-FR-S.1 EOP-FR-S.1,, StepStep 14.d.RNO.

14.d.RNO. Plausible Plausible because because the procedure the procedure step does not step does not specify specify the the desired desired position position of of AFSS-4006 AFSS-4-006 or or AFSS-4-006 . It merely directs operators AFSS-4-006. It merely directs operators to to manipulate manipulate AFSS-4-006 AFSS-4-006 and and AFSS-4-006 AFSS-4-006..

D.

D. Correct per the Correct per the references references 18 18

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q#1O Q#10 Operators are Operators are performing performing 3-EOP-E-3, 3-EOP-E-3, "Steam Steam Generator Generator Tube Tube Rupture."

Rupture.

• • All All RCPs RCPs areare stopped.

stopped.

After dumping After dumping steam steam fromfrom intact intact S/Gs S/Gs to to increase increase subcooling, subcooling, the the RO RO has has been been directed to directed to open open oneone pressurizer pressurizer PORV.

PORV.

Which ONE Which ONE ofof the the following following describes describes the the effect effect of of opening opening the the PORV PORV on on pressurizer level, RCS subcooling and pressurizer level, RCS subcooling and S/G tube SIG tube break break flow flow rate?

rate?

Pressurizer level Pressurizer level RCS subcooling RCS subcoolinq S/G S/G break break flow flow A.

A. Decreases Decreases Decreases Decreases Increases Increases B. Increases Decreases Decreases Decreases C. Increases Increases Increases D. Decreases Increases Decreases 19 19

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q#10 Q#10 ANSWER:

ANSWER: BB KA:

KA: 000038 EKI .02 000038EK1.02 Knowledge of Knowledge of the the operational operational implications implications of of the the following following concepts concepts as as they they apply apply to to the SGTR:

the SGTR: Leak Leak rate rate vs vs pressure pressure drop.

drop. 3.2/3.5 3.2/3.5 IOCFR55:

10CFR55: 41 .b.5, 41.b.10, 41.b.5, 41 .b.10, 41.b.14 41 .b.14

Reference:

3-EOP-E-3, NOTE 3-EOP-E-3, NOTE prior prior to to Step Step 25, 25, Step Step 25 25 3-EOP-E-3, Step 3-EOP-E-3, Step 25 25 BO BD Cog Level: 1I recall Cog Level: recall New Question New Response Analysis:

A. Incorrect because pressurizer level will increase, not decrease and break flow will decrease, not increase. Plausible because subcooling will decrease.

B. Correct per the references.

C. Incorrect because subcooling will decrease, not increase and break flow will decrease, not increase. Plausible because pressurizer level will increase.

D.

O. Incorrect because pressurizer level will increase, not decrease and subcooling will decrease, not increase. Plausible because break flow will decrease decrease 20 20

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 QQ#11

1. 11 Unit 44 isis at Unit at 50% power when 50% power when aa large large main main steam steam line line break break outside outside containment containment downstream (turbine downstream (turbine side) side) of of the the 4B 4B MSIV MSIV and and non-return non-return check check valve valve occurs.

occurs.

Which ONE Which ONE of of the the following following describes describes thethe response response of of the the Unit Unit 44 MSIVs MSIVs and and the the reason for that response?

reason for that response?

A.

A. None of None of the the Unit Unit 44 MSIVs MSIVs will will automatically automatically close close as as NO NO protective protective signal signal isis generated generated for for this this condition.

condition.

B.

B. 4B MSIV 4B MSIV will automatically close will automatically close due due to to high high steam steam flow flow on on the the 4B 4B S/G SIG with with aa low 4B low SIG pressure.

4B S/G pressure. 4A 4A and and 4C4C MSIVs MSIVs will will NOT NOT automatically automatically close.

close.

C. All of All of the Unit Unit 44 MSIVs MSIVs will automatically automatically close close due due to high high steam steam flow with low Tavg or low SG pressure sensed on all S/Gs. S/Gs.

D.

D. All of the UnitUnit 4 MSIVs MSIVs will automatically close due to high differential pressure between each S/G SIG and the main steam header.

2121

NRC DRAFT NRC DRAFT 07124/07 07/24/07

1. 11 QQ #11 ANSWER:

ANSWER: CC KA:

KA: 000040AK2.O1 000040AK2.01 Knowledge of Knowledge of the the interrelations interrelations between between the the steam steam line ilne rupture rupture and and the the following:

following:

Valves. 2.6/2.5 Valves. 2.6/2.5 10CFR55:

10CFR55: 41.b.4, 41.b.7, 41.bA, 41.b.7, 41.b.8 41.b.8

Reference:

5610-T-L1, 5610-T-L Sheet 11 1, Sheet 11 5610-T-L1, 5610-T-L Sheet 19 1, Sheet 19 5614-M-3072, Sheet I 5614-M-3072,Sheet1 Cog Level: 2 Comprehension Comprehension Level 2 because the operator must recognize that the location of the break determines the response of the MSIVs. Because the break is downstream of the MSIV/non-return check valve, it does not matter that it is located on the 4B header.

MSIV/non-return All S/Gs will feed the break and all MSIVs will close.

New Question Response Analysis:

A. Incorrect because all Unit 4 MSIVs will close. Plausible because the stem implies the problem is associated with only the 4B steam header. If the problem was really associated with only one header, no protective signal would be generated.

B.

B. Incorrect Incorrect because because allall Unit Unit 44 MSIVs MSIVs will close.

close. Plausible Plausible because because the the break break is is located located on the 4B 4B steam header header aridand 4B4B MSIV MSIV will automatically automatically close.

close.

C.

C. Correct Correct per per the the references D.

D. Incorrect Incorrect because because high high steam steam lineline /1S/G S/G pressure pressure differential differential does does notnot close close MSIVs. Plausible because MSIVs. Plausible because all all of of the the MSIVs MSIVs will will automatically automatically close close 22 22

NRC DRAFT NRC DRAFT 07/24/07 07/24/07

1. 12 QQ #12 With Unit Unit 33 critical critical at at 10- 8 amps I 08 With amps IR IR power, power, 3A 3A main main feedwater feedwater header headersheared sheared immediately outside Unit immediately outside Unit 33 containment.

containment.

Which ONE Which ONE of the following of the following describes describes the the effect effect on on Unit Unit 3?

3?

3A S/G 3A SIG will:

will:

A.

A. NOT depressurize.

NOT depressurize.

SI will NOT SI will NOT actuate.

actuate.

B.

B. NOT depressurize.

NOT depressurize.

Low pressurizer Low pressurizer pressure pressure reactor reactor trip trip and and SISI will will occur.

occur.

c.

C. depressurize.

depressurize.

Low pressurizer Low pressurizer pressure pressure reactor reactor trip trip and and SI SI will occur.

occur.

D.

D. depressurize.

depressurize.

Hi Steam Line ~p AP SI will actuate.

23 23

NRC DRAFT NRC DRAFT 07/24/07 07/24/07

1. 12 QQ #12 ANSWER:

ANSWER: D D

KA:

KA: 000054AK1.O1 000054AK1.01 Knowledge of Knowledge of the the operational operational implications implications of of the the following following concepts concepts asas they they apply apply to to the Loss of the Loss Main FW:

of Main FW: MFW line break MFW line break depressurizes depressurizes the the S/G S/G (similar (similar to to aa steam steam line break) line break) 4.1/4.3 4.1/4.3 IOCFR55:

10CFR55: 41.b.4, 41.b.7, 41.bA, 41.b.7, 41.b.8 41.b.8

Reference:

561 O-T-L 561 O-TL1, Sheet 11 1, Sheet 11 5610-T-L1, Sheet 19 561 O-T-L 1, Sheet 19 5613-M-3074, Sheet 3 5613-M-3074,Sheet3 Comprehension Cog Level: 2 Comprehension Level 2 because the operator must recognize that a feedwater header break at that depressurization will be sensed on location will depressurize the 3A S/G and the depressurization the 3A steam header which will result in the High steamline L'1P AP logic (1/3 S/Gs) being initiated which is not blocked at low power levels.

New Question Response Analysis:

A. Incorrect because 3A S/G will depressurize and SI will actuate. Plausible because the SI protection is needed for aa steam line break, not aa feed line break.

B.

B. Incorrect Incorrect because 3A 3A S/G S/G will depressurize depressurize and the low low pressurizer pressurizer pressure trip is blocked and the 3A s/g will depressurize. PlausiblePlausible because SI SI would be be expected expected subsequently subsequently C.

C. Incorrect Incorrect because because the the low low pressurizer pressurizer trip is blocked.

trip is blocked. Plausible Plausible because because the the S/G S/G will will depressurize depressurize and SI would and SI would be be expected expected subsequently subsequently D.

D. Correct Correct perper the the references.

references.

24 24

NRC DRAFT NRC DRAFT 07/24/07 07/24/07

1. 13 QQ #13 Operators are Operators are performing performing 4-EOP-ECA-0.0, 4-EOP-ECA-O.0, "Loss Loss ofof All All AC AC Power" Power and and are are inin the the process of process depressurizing all ofdepressurizing all intact SIGs to intact S/Gs to 180 180 psig.

psig.

What isis the What the consequence consequence ifif the the SGSG depressurization depressurization isis NOTNOT stopped stopped until until 50 50 psig?

psig?

A.

A. reactor vessel AA reactor vessel head head void void could could become become largelarge enough enough to to partially partially uncover uncover the core.

the core.

B.

B. AA Nitrogen Nitrogen gas gas bubble bubble in in the the pressurizer pressurizer could could cause cause aa loss loss of of pressure pressure control.

control.

C.

C. The pressurizer The pressurizer would would go go water-solid water-solid resulting resulting in in aa loss loss of of pressure pressure control.

control.

D.

D. Nitrogen could Nitrogen could enter enter the SIG U-tubes the S/G U-tubes disrupting disrupting natural natural circulation.

circulation.

25 25

NRC DRAFT NRC DRAFT 07124/07 07/24/07

1. 13 QQ #13 ANSWER:

ANSWER: DD KA:

KA: 000055EK1 .02 000055EK1.02 Knowledge of Knowledge of the the operational operational implications implications of of the the following following concepts concepts as as they they apply apply to to the station the station blackout:

blackout: Natural Natural Circulation Circulation Cooling.

Cooling. 4.1/4.4 4.1/4.4 IOCFR55:

10CFR55: 41.b.3, 41.b.4, 41.b.3, 41.b.4, 41.b.7 41.b.7

Reference:

3-EOP-ECA-0.0 BD, 3-EOP-ECA-O.O BD, CAUTION CAUTION before before Step Step 26 26 Cog Level:

Cog Level: Recall 1I Recall New Question New Question Response Analysis:

Response

A. Incorrect because there is too little nitrogen to be released to cause core uncovery and a head void may occur but will not uncover the core, this is not the reason given by the reference. Plausible because nitrogen is expected to accumulate in the reactor vessel head and the rapid depressurization depressurization will cause a head void.

B. Incorrect because nitrogen accumulating in the pressurizer will not result in aa loss of pressure control which is being provided by the PORVs (no spray or heaters) and this is not the reason given by the reference. Plausible because nitrogen is expected to migrate to the pressurizer (RCS high point).

C. Incorrect because the pressurizer would be expected to empty under these conditions. Plausible because large pressurizer level changes are expected and aa loss of pressurizer pressure control is loss of is expected expected ifif the pressurizer empties.

D.

D. Correct Correct per per the references.

26 26

NRC DRAFT NRC DRAFT 07124/07 07/24/07 Q#14 0#14 Unit 33 isis at Unit at 100%

100% power power when when the the following following events events occur:

occur:

• • Unit 33 reactor Unit reactor automatically automatically trips.

trips.

• • Unit 3 MSIVs automatically Unit 3 MSIVs automatically close. close.

• • Unit 33 annunciators Unit annunciators go go dark.

dark.

Which ONE Which ONE of of the the following following identifies identifies the the procedure procedure operators operators will will implement implement after after the unit is stabilized using 3-EOP-ES-0 .1, Reactor the unit is stabilized using 3-EOP-ES-0.1, "Reactor Trip Trip Response"?

Response?

A.

A. 3-ONOP-005.4, "4KV 3-0NOP-005.4, 4KV Bus Bus 3A, 3B3B or 3D Ground" or 3D Ground B. 3-ONOP-003.9, "Loss 3-0NOP-003.9, Loss of 120 120 VAC Vital Instrument Panel 3P09"3P09 C. 3-ONOP-003.5, "Loss 3-0NOP-003.5, Loss of DC Buses 3023 3D23 and 3D23A (3B)

D. 3-ONOP-003.4, "Loss 3-0NOP-003.4, Loss of DC Bus 3001 3D01 and 3D01A 3DO1A (3A) 27 27

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q#14 Q#14 ANSWER:

ANSWER: DD KA:

KA: 000058G2.4.4 000058G2.4.4 As it relates As it relates to to the the loss loss of of DC DC power power event:

event: Able Able to to recognize recognize abnormal abnormal indications indications for system operating parameters which are for system operating parameters which are entry levelentry level conditions conditions for for emergency emergency and abnormal and abnormal operating operating procedures.

procedures. 4.0/4.3 4.0/4.3 10CFR55:

10CFR55: 41.b.7, 41.b.1O 41.b.7,41.b.10

Reference:

3-ONOP-003.4, Step 3-0NOP-003.4, Step 1.1 1.1 && 2.1, 2.1, 2.2 2.2 && 3.5 3.5 Cog Level:

Cog Level: 11 Recall Recall New Question New Question Response Analysis:

Response

A. Incorrect because Incorrect because operators are directed to enter ONOP-003.4 immediately immediately following EOP-ES-0.1. Plausible because a reactor trip, MSIV closure or loss of annunciators could be related to various grounds.

B.

B. Incorrect because operators are directed to enter ONOP-003.4 immediately following EOP-ES-0.1. Plausible because the first step of ONOP-003.9 procedure checks for a reactor trip and analyzes if one is needed and loss of 3P09 previously required a reactor trip.

C. Incorrect because all of the symptoms listed are indicative of aa loss of 3D01, not 3D23. Plausible because the reactor will automatically trip and MSIVs will automatically close upon aa loss of 3D23 D.

D. Correct per the references 28 28

NRC DRAFT NRC DRAFT 07124/07 07/24/07 Q#15 0#15 Operators are Operators are responding responding to to aa line line break break inin the the Instrument Instrument Air Air (IA)

(IA) system.

system.

• • IA pressure as IA pressure as seen seen by P1-3-1444 (VPA) by PI-3-1444 (VPA) isis 91 91 psig psig and and lowering.

lowering.

• • All All available available IA IA compressors compressors are are running running andand crossties crossties are are open.

open.

The NSO The NSO isis sent sent to investigate and to investigate and reports reports the the following following local local IA IA pressure pressure indications:

indications:

P1-3-1516, Turbine PI-3-1516, Turbine Area:

Area: 86 86 psig psig lowering lowering P1-3-1517, Containment PI-3-1517, Containment Area: Area: 75 75 psig psig lowering lowering P1-3-1518, PI-3-1518, Aux Bldg, Intake Aux Bldg, Intake Area, Area, Control Room:Room: 88 psig psig lowering lowering Which ONE of the following describes the correct operator response?

A.

A. Isolate IA to the Containment.

Containment. Trip the reactor and perform 3-EOP-E-O, Reactor Trip or Safety Injection."

"Reactor Injection.

B. Containment. If IA pressure continues to decrease, then Isolate IA to the Containment.

trip the reactor and perform 3-EOP-E-O, "Reactor Reactor Trip or Safety Injection".

Injection.

C. Do NOT isolate IA to the Containment.

Containment. Trip the reactor and perform Reactor Trip or Safety Injection."

3-EOP-E-O, "Reactor Injection.

D. Do NOT isolate IA to the Containment Containment.. If IA pressure continues to decrease,

. then trip the reactor and perform 3-EOP-E-O, Reactor "Reactor Trip or Safety Injection.

Injection".

29 29

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q #15 Q #15 ANSWER:

ANSWER: AA KA:

KA: 000065G2.1.23 000065G2.1.23 As itit relates As relates to to the the loss loss of of instrument instrument air air event:

event: Able Able to to perform perform specific specific system system and and integrated plant integrated plant procedures procedures during during all all modes modes of of plant plant operation. 3.9/4.0 operation. 3.9/4.0 IOCFR55:

10CFR55: 41.b.4, 41.b.10, 41.bA, 41.b.10, 45.2 45.2

Reference:

0-ONOP-013:

0-ONOP-013: CAUTION before CAUTION before Step Step 16, 16, NOTE before NOTE before Step Step 16, 16, Step 17 RNO, FO Page Unit Trip Criteria Cog Level: Comprehension 2 Comprehension Level 2 because the operator must compare the indicated containment IA pressure to IA system pressure and calculate the difference to determine if the pressure drop exceeds 10 psig and then apply procedure actions as required.

New Question Response Analysis:

A. Correct per the references.

B. Incorrect because the reactor must be tripped when IA is isolated to containment regardless of subsequent air pressure. Plausible because isolating IA to containment should isolate the leak, mitigating the event.

C. Incorrect because IA IA must be isolated to containment when its pressure drop exceeds 10 10 psi. Plausible because the reactor must be tripped under under these conditions.

D.

D. Incorrect Incorrect because IA IA must must bebe isolated to containment containment when its its pressure pressure drop drop exceeds exceeds 10 psi. Plausible 10 psi. Plausible because because the the reactor must be tripped must be tripped under under these these conditions.

conditions.

30 30

NRC DRAFT NRC DRAFT 07124/07 07/24/07

1. 16 QQ #16 Unit 33 operators Unit operators are are performing performing 3-EOP-ECA-1.2, 3-EOP-ECA-1 .2, "LOCA LOCA OutsideOutside Containment."

Containment.

• After closing After closing thethe RHR RHR Discharge Discharge to Cold Leg to Cold Leg Isolation Isolation valves, MOV-3-744A &

valves, MOV-3-744A & B, B,

and SI and SI to Cold Leg to Cold Leg Isol Isol valves, valves, MOV-2-843A MOV-2-843A && B, B, RCSRCS pressure pressure isis still still decreasing.

decreasing.

Which ONE Which ONE of of the the following following describes describes the the correct correct operator operator response response and and the the reason reason for the response?

for the response?

A.

A. Return to Return to Step Step 1I of of 3-EOP-ECA-1.2, 3-EOP-ECA-1 .2, "LOCA LOCA Outside Outside Containment,"

Containment, and and perform the perform the isolation isolation steps steps again again as as the the leak leak isis NOT NOT isolated.

isolated.

B.

B. Transition to Transition 3-EOPES-1 .2, "Post to 3-EOP-ES-1.2, Post LOCA LOCA Cooldown Cooldown and and Depressurization" Depressurization as the steps in ECA-1 as the steps in ECA-1.2 .2 have have been been successful successful in in isolating isolating the the leak leak so so subsequent cooldown subsequent cooldown and and depressurization depressurization will be be required required to gogo onto RHR onto RHR cooling.

cooling.

C. Transition to step in effect in 3-EOP-E-1, "Loss Loss of Reactor or Secondary Coolant as the steps in ECA-1.2 Coolant" ECA-1 .2 have NOT been successful and the completion of 3-EOP-E-1 will mitigate the situation.

completion D.

D. 3-EOP-ECA-1 .1,, "Loss Transition to 3-EOP-ECA-1.1 Loss of Emergency Coolant Recirculation" Recirculation as the steps in ECA-1.2 ECA-1 .2 have NOT been successful so the ECA-1.1 ECA-1 .1 actions to prolong injection from the RWST will be required.

31 31

NRC DRAFT NRC DRAFT 07/24/07 07/24/07

1. 16 Q #16 Q

ANSWLR:

ANSWER: DD KA:

KA: W/EO4EA2.1 W/E04EA2.1 Able to Able determine and to determine and interpret interpret the the following following as as they they apply apply to to the the LOCA LOCA OC: DC:

Facility conditions and selection Facility conditions and selection of appropriate procedures of appropriate procedures during during abnormal abnormal and and emergency operations.

emergency operations. 3.4/4.3 3.4/4.3 IOCFR55:

10CFR55: 41.b.5, 41.b.1O 41.b.5,41.b.10

Reference:

3-EOP-ECA-1 .2:

3-EOP-ECA-1.2: Step 3.a.RNO Step 3.a.RNO Cog Level: 1I Recall New Question New Response Analysis:

A. Incorrect because the correct transition is to go to EOP-ECA-1.1 EOP-ECA-1 .1 if pressure is still stable or decreasing. Plausible because returning to step 11 implies another effort to identify and isolate the leak which is reasonable under these circumstances.

circumstances.

B. Incorrect because the correct transition is to go to EOP-ECA-1.1 EOPECA-1 .1 if pressure is still stable or decreasing. Plausible because the stem implies operators is are responding to a LOCA and with pressure still stable, EOP-ES-1.2 EOP-ES-1 .2 is a logical choice to deal with an active LOCA.

C. Incorrect because the correct transition is to go to EOP-ECA-1 EOP-ECA-1.1 .1 if pressure is still stable or decreasing. Plausible because per the same procedure step, the transition would be to EOP-E-1 if pressure were increasing.

D. Correct per the references 32 32

NRC DRAFT NRC DRAFT 07124/07 07/24/07

1. 17 Q #17 Q

Upon entry Upon entry into into 4-EOP-ECA-1.1, 4-EOP-ECA-1 .1, "Loss Loss ofof Emergency Emergency Coolant Coolant Recirculation" Recirculation the the RO reports RO reports Unit Unit 44 RWST RWST levellevel has has decreased decreased to 59,000 gallons.

to 59,000 gallons.

Which ONE Which ONE of of the the following following describes describes thethe correct correct operator operator response?

response?

A.

A. Depressurize all Depressurize all intact intact S/Gs SIGs toto atmospheric atmospheric pressure pressure at at aa rate rate NOT NOT to to exceed an RCS cooldown rate of exceed an RCS cooldown rate of 100°F/hour to 100°F/hour to ensure ensure the the Unit Unit 44 Accumulators fully Accumulators fully inject.

inject.

B.

B. Stop the Stop the running running UnitUnit 44 HHSI, HHSI, RHRRHR andand CS CS pumps.

pumps.

Align and Align and start one Unit start one Unit 33 HHSI HHSI pump pump to deliver flow from Unit to deliver Unit 33 RWST.

RWST.

C. Stop the running Unit 4 RHR and CS pumps.

Stop Continue to run one Unit 4 HHSI HHSI pump for as long as it will deliver flow from Unit 4 RWST.

D. Establish minimum charging to deliver flow from Unit 4 RWST.

When minimum charging flow has been established, stop the running HHSI RHR and CS pumps.

33 33

DRAFT NRC DRAFT 07/24/07 07/24/07 Q#17 Q#17 ANSWER:

ANSWER: B B

KA:

KA: W/EIIEK2.2 W/E11EK2.2 Knowledge of Knowledge of the interrelations interrelations between between the lossloss of emergency coolant recirc recirc and facilitys heat removal systems incl the following: facility's md primary coolant, emergency coolant, the decay coolant, decay heat removal systems, heat removal systems, and and relations relations between between the proper proper operation of these systems operation systems to the operation operation of of the facility. 3.9/4.3 3.9/4.3 IOCFR55:

10CFR55: 41.b.7, 41.b.10 41.b.7,41.b.10

Reference:

4-EOP-ECA-1 .1:

4-EOP-ECA-1.1: Steps 1, 1, 30, 31, 32 Cog Level: Comprehension 2 Comprehension Level 2 because the operator must link the knowledge that RWST level < < 60,000 gallons requires stopping the safety pumps. The 60,000 criteria is provided in in Step 1I of the procedure and stopping the pumps is in Step 31. Additionally the operator must realize that stopping the safety pumps stops safety injection flow to the core and an alternate method of core cooling (opposite unit HHSI flow) is immediately required.

New Question Response Analysis:

A. Incorrect because the correct response is to stop all safety pumps pulling from that RWST and align the opposite unit's units HHSI pump. Plausible depressurizing S/Gs is a subsequent procedure step but if done it because depressurizing will be performed at the maximum rate.

B. Correct per the references C. Incorrect because all safety pumps are stopped, including HHSI pumps.

Plausible because the RHR and CS pumps are stopped and continuing to run HHSI HHSI pumps would continue to provide core cooling flow.

D. Incorrect because the safety pumps need to be stopped now. Plausible because the charging pumps are probably already running (but at maximum speed) and and will be be allowed to to run until until RWST level drops drops to 20,000 20,000 gallons.

gallons.

34 34

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q #18 Q #18 Unit 33 operators Unit operators are are performing performing 3-EOP-FR-H.1, 3-EOP-FR-H.1, "Response Response to to Loss Loss of of Secondary Secondary Heat Sink."

Heat Sink.

The BOP The BOP isis attempting attempting to to restore restore AFW AFW flow flow when when the the RO RO reports reports the the following following S/G SIG levels:

levels:

• • 3A SIG:

3A S/G: 35%

35% WR WR lowering lowering

• • 3B SIG:

3B S/G: 25%

25% NR NR lowering lowering

• • 3C SIG:

30 S/G: 30% NR NR lowering lowering The BOP BOP is is unable unable to immediately immediately restore restore secondary heatheat sink.

The STA reports containment temperature has increased increased to 190°F.

Which ONE of the following describes the correct operator response?

A. Maintain RCPs running. Continue to perform procedure steps to restore secondary heat sink.

B. RCP5 running.

Maintain RCPs Immediately initiate bleed and feed.

C. Stop RCPs. Continue to perform procedure steps to restore secondary heat sink.

D. RCP5. Immediately initiate bleed and feed.

Stop RCPs.

35 35

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q #18 Q #18 ANSWER:

ANSWER: DD KA:

KA: W/EO5EKI .2 W/E05EK1.2 Knowledge of Knowledge of the the operational operational implications implications of of the the following following concepts concepts as as they they apply apply to to the Loss the Loss of of secondary secondary heat heat sink:

sink: Normal, Normal, abnormal abnormal and emergency operating and emergency operating procedures associated procedures associated with with the the loss loss of of secondary secondary heat heat sink.

sink. 3.9/4.5 3.9/4.5 10CFR55:

10CFR55: 41.b.4, 41.b.8, 41.bA, 41.b.8, 41.b.10 41.b.10

Reference:

3-EOP-FR-H.1::

3-EOP-FR-H.1 CAUTION prior CAUTION prior to to Step Step 2, 2, Step Step 12 12 Comprehension Cog Level: 2 Comprehension Level 2 because the operator must evaluate the S/G levels provided based on adverse containment conditions (>180°F). The operator must also recognize that 35% WR S/G level is < < 32% NR level and bleed and feed criteria are met.

New Question Response Analysis:

A. Incorrect because RCPs need to be tripped immediately. Plausible because operators will continue efforts to restore secondary heat sink.

B. Incorrect because RCPs need to be tripped immediately. Plausible because operators will immediately initiate bleed and feed.

C. Incorrect because bleed and feed needs to be established immediately.

Plausible because RCP5 RCPs need need to be stopped.

D.

D. Correct per the references 36 36

NRC DRAFT NRC DRAFT 07/24/07 07/24/07

1. 19 QQ #19 Unit 44 isis inin Mode Unit Mode 66 whenwhen the the RO RD isis notified notified that that aa spent spent fuel fuel element element hashas dropped dropped onto the onto the Region Region IIII fuel fuel racks.

racks.

Which ONE Which ONE of of the following identifies the following identifies control control room room indications indications that that can can bebe used used to to determine if the fuel element determine if the fuel element cladding cladding has has been been breached?

breached?

A.

A. CVCS Letdown CVCS Letdown PRMSPRMS R-20 R-20 monitor monitor alarms alarms B.

B. Spent Fuel Spent Fuel Building Building Area Area rad rad monitors monitors alarm alarm C.

C. Containment Building Containment Building Area Area rad rad monitors monitors alarm alarm D.

D. Containment Atmosphere PRMS Containment PRMS R-11R-1 1 or or R-12 R-1 2 monitors monitors alarm alarm 37 37

DRAFT NRC DRAFT 07/24/07 07/24/07

1. 19 Q #19 Q

ANSWER:

ANSWER: BB KA:

KA: 000036AA2.O1 000036AA2.01 Able to Able to determine determine and and interpret interpret the the following following as as they they apply apply to to the the fuel fuel handling handling incidents: ARM system incidents: system indications.

indications. 3.2/3.9 3.2/3.9 IOCFR55:

10CFR55: 41.b.1O, 41.b.11 41.b.10,

Reference:

4-ONOPO33.3:

4-0NOP-033.3: Section 2.2 Cog Level: 11 Recall New Question Response Analysis:

A. Incorrect because the letdown monitor alarming is not identified as an indication of a dropped rod and this dropped rod is in the SFP, not the containment. Plausible because there is an indirect path from the SFP SEP to the letdown monitor (through the keyway, transfer canal and RHR system)

B. Correct per the reference C. Incorrect because the event did not occur in containment. Plausible because the question does not state that the event occurred in the Spent Fuel Pool area.

D. Incorrect because the event did not occur in containment. Plausible because the question does not state that the event occurred in the Spent Fuel Pool area.

38 38

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q #20 Q#20 Unit 44 isis 100%

Unit 100% power power with with all all systems systems inin normal normal operation operation when when aa tube tube leak leak occurs occurs in the in 4A S/G.

the 4A SIG.

The tube The tube leak leak increases increases to to 250 250 gpm over aa period gpm over period of of 55 minutes.

minutes.

Which ONE Which ONE of of the following describes the following describes the the effect effect on on charging charging and and letdown letdown flow flow rates rates as the leak starts (before operator as the leak starts (before operator response) response) and and AFTER AFTER operators operators have have performed performed the prompt the prompt actions actions of of 4-EOP-E-0, 4-EOP-E-0, Reactor Reactor Trip Trip or or Safety Safety Injection?

Injection?

Early in Early in S/G Tube Leak SIG Tube Leak Event Event After After Prompt Prompt Actions Actions Complete Complete Chging Flow Chqinq Flow Ltdwn Flow Ltdwn Flow Chging Chging Flow Flow Ltdwn Ltdwn Flow Flow A. Unchanged Unchanged Zero Unchanged Unchanged B. Increasing Decreasing Maximum Zero C. Increasing Unchanged Zero Zero D. Unchanged Unchanged Zero Unchanged 39 39

NRC DRAFT 07124/07 07/24/07 Q #20 Q#20 ANSWER: C ANSWER: C KA:

KA: 000037AK3.03 000037 AK3.03 Knowledge for the reasons for the following responses Knowledge responses as they apply to the SGTL:

makeup flow and letdown comparison of makeup letdown flow for various modesmodes of operation.

operation.

3.1/3.3 10CFR55: 41.b.7 10CFR55:

Reference:

4-ONOP-071.2, FO Page Item 1.b, 4-0NOP-071.2, 1.b, 561 O-T-L 1, Sheet 32A 5610-T-L1, SD009, Page 37, SO-013, SO-009, SD-013, Page 18 18 Cog Level: 2 Comprehension Level 2 because the operator must evaluate the size of the SGTL. Before SI actuation, Charging pump speed will increase in response to lowering pressurizer level and letdown flow rate will be constant. SI actuation will result in Phase A actuation which will isolate letdown. Charging pumps will be tripped directly by the SI actuation.

New Question Response Analysis:

A. Incorrect because charging pump speed will increase before operators respond and letdown will isolate following SI SI/actuation

/actuation as a result of Phase A isolation. Plausible because letdown flow will be unchanged initially and charging flow will go to zero after SI actuation.

B. Incorrect because letdown flow will initially be unaffected and charging flow will go to zero after SI actuation. Plausible because charging pump speed will increase before operators respond and letdown flow will isolate following Phase A actuation.

C. Correct because charging pump speed will increase before operators respond and charging pumps will trip when SI SI actuates.

actuates. Letdown flow will initially be unaffected initially be unaffected and letdown letdown flow will isolate isolate following Phase A actuation.

D.

O. Incorrect because charging pump speed will increase before operators respond andand letdown isolate following SI letdown will isolate SI actuation as as aa result of of Phase Phase A A

isolation.

isolation. Plausible because Letdown Plausible because Letdown flow will initially be unaffected initially be unaffected andand charging charging pumps pumps will trip trip when SISI actuates.

actuates.

40 40

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q #21 Q#21 Operators are Operators are performing performing 3-0NOP-100, 3-ONOP-100, "Fast Fast Load Load Reduction" Reduction inin response response to to rapidly dropping rapidly dropping condenser condenser vacuum.

vacuum.

• • Unable to Unable recover vacuum, to recover vacuum, operators operators trip trip the the unit unit and and enter enter the the EOPs.

EOP5.

CC 8/3, 8/3, STEAM STEAM DUMP DUMP ARMED ARMED // ACTUATED, ACTUATED, has has alarmed.

alarmed.

Two minutes Two minutes after after the the unit trip and unit trip with the and with the plant plant stable stable at at 545°F, 545°F, the the BOP BOP notes notes annunciator C annunciator C 8/3 8/3 has has cleared.

cleared.

Which ONE Which ONE ofof the following describes the following describes thethe reason reason for for annunciator annunciator C C 8/3 8/3 clearing clearing AND the status of the SteamSteam Dump Dump to to Condenser Condenser (SDTC)(SDTC) System?

System?

The SDTC arming signal cleared when:

A. vacuum dropped below below 20".20.

The SDTC System is disabled.

B. vacuum dropped below 20". 20.

The SDTC System remains fully functional.

C. Tavg dropped to the low Tavg setpoint.

The SDTC System is disabled.

D. Tavg dropped to the low Tavg setpoint.

The SDTC System remains fully functional.

41 41

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q#21 Q#21 ANSWER:

ANSWER: A A

KA:

KA: 000051AK3.01 000051AK3.01 Knowledge Knowledge for for the the reasons reasons for for the the following following responses responses as as they they apply apply to to the the loss loss of of condenser vacuum:

condenser vacuum: loss loss of of steam steam dump dump capability capability, upon upon loss of condenser vacuum.

loss of condenser vacuum.

2.8/3.1 2.8/3.1 100FR55:

10CFR55: 41.b.4, 41.b.5 41.bA,41.b.5

Reference:

0-T-L1, 561 O-T-L 1, Sheet 22A Cog Level: 2 Comprehension Comprehension Level 2 because the operator must recognize Level recognize that 20" 20 is is aa condition that maymay bebe expected for this situation and is a signal that disables the SDTC while the 545°F Tavg is a condition that could also be expected for this situation but does not disable the SDTC. Additionally the operator must recognize that the alarm may extinguish because the system has been disabled or has merely been reset and in this case the alarm is out because the system has been disabled.

New Question Response Analysis:

A. Correct per the references B. Incorrect because the SDTC system has become disabled. Plausible because it became disabled when vacuum dropped below 20. 20".

C. Incorrect because even though Tavg did drop below the no-load Tavg under the influence of the SDTC system, no-load Tavg is not aa signal that disables the system. Plausible because Tavg did drop to no-load Tavg following the trip and the system has has been disabled.

disabled.

D. Incorrect because the SDTC SDTC system has has been disabled. Plausible Plausible because Tavg Tavg did did drop below the no-load drop below no-load Tavg setpoint following the trip. trip.

42 42

NRCDRAFT NRC DRAFT 07/24/07 07/24/07 Q #22 0#22 TheShift The ShiftManager Managerdirects directsevacuation evacuation ofofthe thecontrol control room.

room.

• • AtAtthe the Alternate Alternate Shutdown Shutdown PanelPanel (ASP),

(ASP), thethe RO RO inserts inserts handles handles into into the the yellow yellow bordered switches bordered switches and and places placesthem them inin the the LOCAL LOCAL position.

position.

Which ONE Which ONE ofofthe the following following describes describes thethe purpose purpose of ofthe the transfer transfer switches switches associa ted with the AFW flow control associated with the AFW flow control valves valves (FCVs)?

(FCVs)?

A.

A. transfers control transfers control ofof Train Train 22 FCVs FCVs to to the the ASP ASP B.

B. enables local enables local control control ofof Train Train 22 FCVs FCV5 C.

C. aligns "8" aligns B train train electrical electrical control control to Train 11 FCVs to Train FCVs D.

D. aligns backup aligns backup nitrogen nitrogen toto the the Train Train 1I FCVs FCVs 4343

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q#22 Q#22 ANSWER:

ANSWER: AA KA:

KA: 000068G2.1.28 000068G2.1.28 As itit relates As relates to to the the control control room room evacuation evabuation event:

event: Knowledge Knowledge of of the the purpose purpose and and function of function of major major system system components components and and controls.

controls. 3.2/3.3 3.2/3.3 IOCFR55:

10CFR55: 41.b.4, 41.b.7, 41.b.8 41.b.4,

Reference:

O-ONOP-1 05, Attachment 3, NOTE prior prior to Step 6, Step 6 SD-I SD-153, 53, Page Page 41, Figure Figure 4C, 40 4D Cog Level: 11 Recall New Question Response Analysis:

A. Correct per the reference B. Incorrect because local control of the AFW valves is independent of the transfer switch. Plausible because these are the same Train 2 FCVs.

C. Incorrect because the affected valves are Train 2 not Train 1. Plausible because the transfer switches transfer electrical control.

D. IN correct because transfer of backup nitrogen is independent of the transfer switch. Plausible because Train 1 1 FCVs have backup nitrogen.

44 44

NRC DRAFT NRC DRAFT 07124/07 07/24/07 Q#23 Q#23 The crew The crew isis doing doing aa post post LOCA LOCA cooldown cooldown and and depressurization depressurization inin accordance accordance withwith 4-EOP-ES-1 .2, "Post 4-EOP-ES-1.2, Post LOCA LOCA Cooldown Cooldown andand Depressurization."

Depressurization.

• • 4B RCP 4B RCP has has been been started started for for forced forced cooling cooling and RCS pressure and RCS pressure control.

control.

• • Two ECCs Two ECC5 are running are running

• • All NCCs All NCCs areare operating operating Containment pressure Containment pressure just increased increased greater greater than than 20 20 psig.

psig.

Which ONE of the following following describes actions actions associated associated with operation operation of the Normal Containment Normal Containment Coolers Coolers (NCCs)

(NCCs) AND AND thethe bases bases for for those those actions?

actions?

A. Continue Operation of the NCCs to maintain RCP operation and to assist assist in pressure reduction.

containment pressure reduction.

B. Continue operation of the NCCs NCC5 to maximize containment cooling and atmosphere circulation to prevent stratification and eliminate pockets of hydrogen.

C. Stop all NCCs to start the 3rd Emergency Containment Coolers without violating CCW System load requirements.

requirements.

D. Stop all NCCs because the 4B RCP must be secured and to prevent violating CCW System load requirements.

requirements.

45 45

DRAFT NRC DRAFT 07/24/07 07/24/07 Q #23 Q#23 ANSWER:

ANSWER: D D

KA:

KA: WIEI4EK3.3 W/E14EK3.3 Knowledge for the reasons Knowledge reasons for the following responses responses as they apply to the high high containment pressure: manipulation of controls required to obtain desired operating results during results during abnormal abnormal andand emergency emergency situations.

situations. 3.5/3.5 3.5/3.5 I OCFR55:

10CFR55: 41 .b.7, 41.b.8, 41.b.7, 41 .b.8, 41.b.10 41 .b.1O

Reference:

4-EOP-F-O, Enclosure 5 4-EOP.-FR-Z.1, Step 1I 4-EOP-FR-Z.1, 4-EOP-FR-Z.1, Step 1I BD Cog Level: Comprehensive 2 Comprehensive Level 2 because the operator must recognize that that the conditions have changed requiring transition to EOP-FR-Z.1 which will direct securing of the RCPs which in turn allows the NCCs to be secured.

New Question Response Analysis:

A. Incorrect because the NCCsNCC5 and RCPs have to be stopped per EOP-FR-Z.1.

Plausible because running NCCs NCC5 would help to maximize containment pressure reduction and cool the RCP if it was left running.

B. Incorrect because the NCCs have to be stopped per EOP-FR-Z.1. Plausible because running NCCs would help to maximize containment air circulation.

C. Incorrect because procedural limitations restrict operators from running three ECC. Plausible because an additional ECC would help with the containment pressure reduction.

D. Correct, the NCCs NCCs are required to be stopped lAWlAW FR-Z.1 guidance.

46 46

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q#24 0#24 3-EOP-FR-C.2, "Response 3-EOP-FR-C.2, Response to Degraded Core to Degraded Cooling, directs Core Cooling," directs operators operators to to depressurize the depressurize the RCS RCS to to inject inject the the accumulators accumulators into into the the RCS.

RCS.

Which ONE Which ONE of of the following describes the following describes how how the the RCS RCS will will be be depressurized depressurized to to inject inject the accumulators and the accumulators and how how operators operators will will prevent prevent accumulator accumulator nitrogen nitrogen injection?

injection?

A.

A. Open one Open pressurizer PORV one pressurizer until RCS PORV until RCS pressure pressure is is less less than than 180 180 psig.

psig.

Isolate accumulators Isolate accumulators when when RCS RCS pressure pressure isis less less than than 350 350 psig.

psig.

B.

B. Open both Open pressurizer spray both pressurizer spray valves until RCS pressure until RCS pressure is is less less than 180180 psig.

psig.

Isolate accumulators Isolate accumulators when when RCS RCS pressure pressure isis less less than than 350 350 psig.

psig.

C. steam from intact S/Gs Dump steam S/Cs until SG SC Pressure is less than 180 180 psig.

psig.

Isolate Isolate accumulators when RCSRCS CET CET subcooling is is less less than 30°F.

30°F.

D. Dump steam from intact S/Gs S/Cs until S/G S/C pressure is less than 80 psig.

Isolate accumulators when RCS hot leg temperatures are less than 340°F. 340° F.

47 47

NRC DRAFT NRC DRAFT 07124/07 07/24/07 Q #24 Q#24 ANSWER:

ANSWER: D D KA:

KA: WIEO6EKI.1 W/E06EK1.1 Knowledge Knowledge of of the operational implications the operational implications of of the the following following concepts concepts asas they they apply apply to to the degraded core the degraded cooling: components, core cooling: components, capacity capacity andand function of emergency function of emergency systems. 3.6/4.0 systems. 3.6/4.0 IOCFR55:

10CFR55: 41.b.3, 41.bA, 41.b.3, 41.b.4, 41.b.5, 41.b.5, 41.b.7 41.b.7

Reference:

3-EOP-FR-C.2, Steps 3-EOP-FR-C.2, Steps 13 and 15 13 and 15 Cog Level:

Cog Level: Recall 1I Recall New Question Analysis:

Response Analysis:

A. Incorrect because RCS pressure is reduced by dumping steam from intact SIGs. Plausible because opening a PORV is a method often used during S/Gs.

implementation to depressurize the RCS.

EOP implementation B. Incorrect because RCS pressure is reduced by dumping steam from intact S/Gs. Plausible because opening pressurizer spray valves is a method often implementation to depressurize the RCS.

used during EOP implementation C. Incorrect because the parameter used to judge when to stop dumping steam is S/G pressure, the stopping criteria in ECA-0.0 ECA-O.O is S/G Pressure at l8opsig.

180psig.

Plausible because reducing subcooling implies reducing RCS pressure also D.

D. Correct Correct perper the reference 48 48

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q #25 Q#25 In accordance In accordance with with 3-EOP-ES-1.1, 3-EOP-ES-1 .1, "SI SI Termination,"

Termination, which which ONE ONE ofof the the following following describes why describes why seal seal return return isis restored restored toto the the VCT VCT AND AND why why RCS RCS pressure pressure must must be be greater than 100 psi above VCT greater than 100 psi above VCT pressure pressure before before establishing establishing seal seal return return flow?

flow?

Seal return Seal return isis restored restored to to the the VCT VCT to:

to:

A.

A. stop ## 1I sealleakoff stop seal leakoff flow flow from from flowing flowing to the PRT.

to the PRT.

RCS pressure RCS pressure must must be higher than be higher than VCT VCT pressure pressure to to prevent prevent Hydrogen Hydrogen intrusion from the VCT into the the RCS.

RCS.

B.

B. stop ## 1I sealleakoff seal leakoff flow from flowing to the PRT. PRT.

RCS pressure must be higher than VCT pressure to prevent prevent reverse flow from the VCT into the RCS.

C. reinitiate # 11 seal leakoff flow.

RCS pressure must be higher than VCT pressure to prevent Hydrogen intrusion from the VCT into the RCS.

D. reinitiate # 1I sealleakoff seal leakoff flow.

RCS pressure must be higher than VCT pressure to prevent reverse flow from the VCT into the RCS RCS..

49 49

NRC DRAFT 07124/07 07/24/07 Q #25 Q#25 ANSWER:

ANSWER: BB KA:

KA: W/EO2EK3.l W/E02EK3.1 Knowledge for the reasons Knowledge reasons for the following responses as they they apply to the SI termination: Facility operating characteristics termination: characteristics during transient conditions, including coolant chemistry coolant chemistry and and the effects effects of of temperature, pressure, pressure, and and reactivity reactivity changes changes and operating and operating limitations limitations and reasons reasons for these operating characteristics.

characteristics. 3.3/3.6 3.3/3.6 10CFR55:

10CFR55: 41.b.2, 41.b.3, 41.b.10

Reference:

3-EOP-ES-1 .1, Step 20 BO 3-EOP-ES-1.1, BD 5613-M-3047, 5613-M-3047,Sheet3 Sheet 3 Cog Level: 11 Recall New Question Response Analysis:

A. Incorrect because the stated reason for the required 100 psi differential in the Basis document is to prevent backflow from VCT to RCS, not to prevent Hydrogen intrusion from the VCT into the RCS. Plausible because stopping seal return flow to the PRT is the reason for restoring normal seal return.

B. Correct per the references C. Incorrect because stopping seal return flow to the PRT is the reason for restoring normal seal return. Note that even though seal return was isolated,

1. 1 seal leakoff still existed to the PRT. Plausible because Hydrogen is sealleakoff present in the VCT which can find its way to the RCS if aa flow path is established.

D.

O. Incorrect because stopping seal return flow to the PRT is the reason for restoring normal seal return. Note Note that even though seal return was isolated,

1. 1 seal leakoff still existed to the PRT. Plausible because the stated reason sealleakoff for the required 100 100 psi differential in the Basis document document isis to prevent backf low from VCT to RCS, backflow 50 50

NRC DRAFT NRC DRAFT 07124/07 07/24/07 Q #26 Q#26 AA RCS RCS leak leak has has occurred occurred that required aa manual that required manual reactor reactor trip trip based based on on the the inability inability to maintain Pressurizer to maintain Pressurizer level.

level.

Operators are Operators are performing performing 4-EOP-ES-1.2, 4-EOP-ES-1 .2, "Post Post LOCA LOCA Cooldown Cooldown and and Depressurization.

Depressurization."

The US The US directs directs the RO to the RO depressurize the to "depressurize the RCS RCS to to refill refill the the pressurizer."

pressurizer.

ONE of Which ONE of the the following identifies identifies the preferred preferred order order of of methods methods toto depressurize the the RCS RCS asas directed directed by 4-EOP-ES-1 .2?

by 4-EOP-ES-1.2?

A. 1) Normal Spray

1) Spray PRZPORV

2) PRZ PORV Spray

3) Aux Spray B. 1) Normal Spray 2) Aux Spray 3) PRZ PORV C. 1) Aux Spray PRZPORV

2) PRZ PORV 3) Steam Dump D. 1) Aux Spray 2) Normal Spray PRZPORV

3) PRZ PORV 51 51

NRC DRAFT NRC DRAFT 07124/07 07/24/07 Q#26 Q#26 ANSWER:

ANSWER: AA KA:

KA: W/EO3EK1 .3 W/E03EK1.3 Knowledge of Knowledge of the the operational operational implications implications of of the the following following concepts concepts asas they they apply apply to to LOCA Cooldown and Depressurization: annunciators LOCA Cooldown and Depressurization: annunciators andand conditions, conditions, indicating indicating signals and signals and remedial remedial actions actions associated associated with with the the (LOCA (LOCA cooldown cooldown and and depressurization. 3.5/3.8 depressurization. 3.5/3.8 10CFR55:

10CFR55: 41.b.1O 41.b.3, 41.b.7, 41.b.10

Reference:

4-EOP-ES-1.2, Step 10 10 Cog Level: 1I Recall Bank Question Response Analysis:

A. Correct per the reference B. Incorrect because a pressurizer PORV is preferred over Aux Spray Spray....

Plausible because normal spray is the preferred first method to reduce pressure.

C. Incorrect because steam dump is not a method directed by ES-i ES-1.2.2 and aa pressurizer PORV is preferred over Aux Spray. Plausible because all three methods listed are effective methods of RCS pressure reduction under these conditions.

D. Incorrect because Normal spray is the first choice directed by ES-i ES-1.2.

.2.

Plausible because all three methods listed are effective methods of RCS pressure reduction under these conditions and all are methods directed by ES-I .2.

ES-1.2.

52 52

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q #27 0#27 In accordance with In accordance 4-EOP-FR-P.1, "Response with 4-EOP-FR-P.1, Response to Imminent Pressurized to Imminent Pressurized Thermal Thermal Shock Condition, which Shock Condition", which ONE ONE of of the the following following describes describes thethe purpose of starting purpose of starting an an RCP while responding RCP while responding to to aa pressurized pressurized thermal thermal shock shock condition?

condition?

An RCP An RCP is is started started to:

to:

A.

A. minimize the minimize time to the time reach Mode to reach Mode 55 by by allowing allowing aa faster faster cooldown cooldown rate rate with with forced cooling forced cooling than than with with natural natural circulation.

circulation.

B.

B. restore normal restore pressurizer spray normal pressurizer spray capability to subsequently subsequently reduce reduce RCSRCS pressure to the right of the 60°/hr pressure the right of the 60° Ihr cooldown cooldown curve.

curve.

C. mix the cold SI water with warm RCS water and decrease the likelihood of a PTS likelihood PTS condition.

D. mix the water in the vessel and loops to ensure boron concentration is equal throughout the reactor coolant system. system 53 53

NRC DRAFT NRC DRAFT 07124/07 07/24/07 Q #27 Q#27 ANSWER:

ANSWER: CC KA:

KA: WW/E08G2.1 .28 IE08G2.1 .28 RCS overcooling - PTS, RCS overcooling PTS, As As itit relates relates to to the the PTS PTS event:

event: Knowledge Knowledge ofof the the purpose purpose and function of major and function of major system system components components and and controls.

controls. 3.2/3.3 3.2/3.3 100FR55:

10CFR55: 41.b.2, 41.b.3, 41.b.2, 41.b.3, 41.b.7, 41.b.7, 41.b.10 41.b.10

Reference:

3-EOP-FR-P.1, Step 3-EOP-FR-P.1, Step 27 BDBD Cog Level: 1I Recall New Question New Response Analysis:

A. Incorrect because starting an RCP does not allow a faster cooldown rate in FR-Ri. Plausible because the normal cooldown rate limit with RCPs is FR-P.1.

1100°F/hr OO°F/hr and without RCPs is 25°F/hr.

B. Incorrect because RCS pressure will be subsequently maintained within a band between the minimum subcooling curve and the 200°F 200° F subcooling curve. Plausible because even though EOP-FR-P.1 does not specify which RCP should be started, operators will normally start an RCP with pressurizer spray capability.

C. Correct per the reference D. Incorrect because mixing of boron in the loops is not aa basis described in the EOP-FR-P.1 basis document. Plausible because running aa RCP provides this desirable benefit.

54 54

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q #28 0#28 Operators are Operators are cooling cooling down down the the plant plant in in accordance accordance with with 3-GOP-305, 3-GOP-305, "HotHot Standby Standby to Cold to Cold Shutdown".

Shutdown. 3B 3B RCP RCP pump bearing temperature pump bearing temperature has has been been slowly slowly increasing increasing and has and has just just reached reached the the alarm alarm setpoint setpoint value.

value.

The present The present plant plant conditions conditions are are as as follows:

follows:

• • RCS pressure RCS pressure isis 600 600 psig.

psig.

• • 3B RCP #1 seal AP is 3B RCP #1 seal llP is >> 400 400 psid.

psid.

• 3B RCP 3B RCP seal seal injection flow is 10 10 gpm.

gpm.

• • 3B RCP 3B RCP #1 sealleakoff seal leakoff flow is is 0.9 0.9 gpm.

gpm.

• • 3B RCP RCP # 11 sealleakoff seal leakoff isol isol valve, CV-3-303B, CV-3-303B, isis open.

Which ONE of the following describes the correct operator response?

A. Increase seal injection flow to the 3B RCP to greater than 13 gpm. gprn.

B. Open the RCP Seal Bypass Valve, CV-3-307.

C. Close the 3B RCP #1 seal leakoff isol valve, CV-3-303B.

D. Increase CCW flow through the 3B RCP thermal barrier.

55 55

NRC DRAFT NRC DRAFT 07124/07 07/24/07 Q#28 Q#28 ANSWER:

ANSWER: BB KA:

KA: 003A4.07 003A4.07 Ability to Ability manually operate to manually operate and/or and/or monitor monitor in in the control room the control room RCP RCP seal seal bypass.

bypass.

2.6/2.6 2.6/2.6 100FR55:

10CFR55: 41.b.5, 41.b.1O 41.b.5,41.b.10

Reference:

3-GOP-305, Step 3-GOP-305, Step 5.3.5.9.d 5.3.5.9.d 3-ONOP-041 3-0NOP-041.1 Step 35

.1,, Step 35 Level:

Cog Level: 2 Comprehension Comprehension Level 2 because Level because the operators mustmust evaluate plant plant conditions and determine that opening the bypass valve would improve the RCP conditions. Many plant conditions must be met in order to use the bypass valve and the operator must analyze the current conditions to determine that it is appropriate and desired in this situation.

New Question Response Analysis:

A. Incorrect because the required procedural response is to open the RCP Seal Bypass Valve, CV-3-307. Plausible because the RCP sealleakoff seal leakoff flow rate is low and the RCP bearing temperature is increasing.

B. Correct per the reference.

C. Incorrect because the required procedural response is to open the RCP Seal Bypass Valve, CV-3-307. Plausible because CV-303B will be closed in aa subsequent step in the same procedure (GOP-305, (GOP-305, Step 5.19.14,9.b) and would terminate the flow of hot hot water to the VCT D. Incorrect Incorrect because the required procedural response is to open the RCP Seal Bypass Valve, CV-3-307.

Bypass Valve, CV-3-307. Plausible Plausible because increasing increasing CCW CCW through through the thermal thermal barrier barrier would would be be beneficial to to pump pump bearing bearing cooling ifif seal seal injection injection flow was was lost.

lost.

56 56

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q #29 0#29 Unit 33 is Unit is at at 100% power when 100% power when VCT VCT level level transmitter, transmitter, LLT-3-1 T-3-115, 15, fails fails high.

high.

Which ONE ONE of following describes the effect of the following effect on the plant plant assuming assuming NO NO operator action?

action?

level will:

VCT level A. decrease.

Auto-makeup will NOT occur.

Auto-swap to the RWST will occur.

B:

B. decrease.

Auto-makeup will NOT occur.

Auto-swap to the RWST will not occur.

C. increase.

automatically.

Auto-makeup will start and stop automatically.

LCV-1 ISA will auto-divert to the CVCS HUT.

LCV-115A D. increase.

automatically.

Auto-makeup will start but NOT stop automatically.

LCV-1 ISA will auto-divert to the CVCS HUT.

LCV-115A 57 57

DRAFT NRC DRAFT 07/24/07 07/24/07 Q #29 Q#29 ANSWER:

ANSWER: BB KA:

KA: 004K11.23 004K .23 Knowledge of Knowledge of the physical physical connection and/or cause-effect relationships between the CVCS and the RWST. 3.4/3.7 IOCFR55:

10CFR55: 41.b.6, 41.b.7 41.b.6,41.b.7

Reference:

3-ONOP-046.4, Step 28, CAUTION and NOTE prior to Step 29 3-0NOP-046.4, Cog Level: 1I Recall New Question Response Analysis:

A. Incorrect because auto-swap to the RWST will not occur (2 of 2 low levels required). Plausible because VCT level will decrease and auto-makeup will not occur.

B. Correct per the reference.

C. Incorrect because VCT level will decrease and auto-makeup will not occur.

LCV-1 1 5A will auto-divert to the CVCS HUT.

Plausible because LCV-115A D. Incorrect because VCT level will decrease and auto-makeup will not occur.

Plausible because LCV-I 1 5A will auto-divert to the CVCS HUT.

LCV-115A 58 58

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q #30 Q#30 Unit 33 isis operating Unit operating at at 75% power when 75% power when an Instrument Air an Instrument Air System System leak leak reduces reduces the the IA pressure to IA pressure to 60 psig on 60 psig on both both units.

units.

Operator actions Operator actions are unsuccessful in are unsuccessful in restoring restoring IA IA pressure.

pressure.

Which ONE Which ONE of of the the following following describes describes the the effect effect of this event of this event on on Unit Unit 33 pressurizer pressurizer level and the correct operator level and the correct operator response?response?

Pressurizer level Pressurizer level will:

A. decrease.

decrease.

Trip the reactor and perform EOP-E-O,EOP-E-0, "Reactor Reactor Trip or Safety Injection."

Injection.

B decrease.

Start additional charging pumps and increase speed using 3-0P-047, 3-OP-047, "cvcs CVCS Charging and Letdown."

Letdown.

C increase.

Trip the reactor and perform EOP-E-O,EOP-E-0, "Reactor Reactor Trip or Safety Injection."

Injection.

D. increase.

Open additional letdown orifice isolation valves using 3-0P-047, 3-OP-047, "cvcs CVCS Letdown.

Charging and Letdown."

59 59

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q#30 Q#30 ANSWER:

ANSWER: C C

KA:

KA: 004A2.11 004A2.11 Ability to Ability to (a)

(a) predict predict the the impacts impacts of of the the following following malfunctions malfunctions or operations on or operations on the the CVCS; and CVCS; and (b)

(b) based based onon those those predictions, predictions, useuse procedures procedures to to correct, control, or correct, control, or mitigate the consequences mitigate the consequences of of those those malfunctions malfunctions oror operations:

operations: loss loss of of lAS.

lAS.

3.6/4.2 3.6/4.2 10CFR55:

10CFR55: 41.b.4, 41.b.5, 41.b.1 41.bA, 41.b.1O 0

Reference:

O-ONOP-013, FO 0-ONOP-013, FO Page Page Cog Level:

Cog Comprehension 2 Comprehension Level 2 because the operator must recognize that the loss of IA will result in the running charging pump(s) going to full speed and the letdown valves closing resulting in increasing pressurizer level. The operator must also relate the plant conditions and system responses to the need for a reactor must be tripped when IA pressure drops to <65 psig.

New Question Response Analysis:

A. Incorrect because pressurizer level will increase. Plausible because the correct response to IA pressure at 60 psig is to trip the reactor and enter EOP-E-O.

B. Incorrect because pressurizer level will increase. Plausible because if level were to decrease, starting additional charging pumps would be the appropriate operator response.

resp~mse.

C. Correct per the reference D. Incorrect because opening additional orifice valves is not possible due to the loss of loss of IA.

IA. Plausible because because pressurizer level level will increase.

increase.

60 60

NRC DRAFTDRAFT 07/24/07 07/24/07

1. 31 Q #31 Q

Unit 44 is Unit is inin Mode Mode 44 with with RHR RHR cooling cooling inin service.

service.

The automatic The automatic controller controller circuit circuit for for RHR RHR HeatHeat Exchanger Exchanger Bypass Bypass Flow Flow control control valve, valve, FCV-4-605 has FCV-4-605 failed resulting has failed resulting in in the the FCV FCV going going closed.

closed.

Which ONE Which ONE of of the the following following describes describes the the correct correct operator operator response?

response?

Place FCV-4-605 controller in Manual Place Manual and raise flow to:

A. between 3000 and 3750 gpm.

between IfIf manual control is is NOT NOT possible, possible, direct the NSONSO to locally locally control FCV-4-605 to raise flow to between 3000 and 3750 gpm.

B. >3750gpm.

> 3750 gpm.

If manual control is NOT possible, direct the NSO to locally control FCV-4-605 to raise flow to > > 3750 gpm.

C. between 3000 and 3750 gpm.

If manual control is NOT possible, open RHR Heat Exchanger Outlet Flow HCV4-758 to raise flow to between 3000 and 3750 gpm.

control valve, HCV-4-758 D. >3750gpm.

> 3750 gpm.

If manual control is NOT possible, open RHR Heat Exchanger Outlet Flow control valve, HCV-4-758 to raise flow to > > 3750 gpm.

61 61

NRC DRAFT NRC DRAFT 07124/07 07/24/07 Q#31 Q#31 ANSWER:

ANSWER: AA KA:

KA: 005G2.1.30 005G2.1.30 As itit relates As relates to RHR, ability to RHR, ability to to locate locate and and operate operate components, components, including including local local controls. 3.9/3.4 controls. 3.9/304 IOCFR55:

10CFR55: 41.b.4, 41.b.7, 41.bo4, 41.b.7, 41.b.8, 41.b.8, 41.b.10 41.b.10

Reference:

4-ONOP-050, Step 77 4-0NOP-050, Cog Level:

Cog Level: 1I memory memory New Question Response Analysis:

A. Correct per the reference B. Incorrect because flow should be increased to between 3000 and 3750 gpm.

Plausible because if control room control is not possible, the NSO will be directed to locally control FCV-605.

C. Incorrect because operators are directed to use FCV-605, not HCV-758 to locally control flow. Plausible because flow should be increased to between 3000 and 3750 gpm.

D. Incorrect because flow should be increased to between 3000 and 3750 gpm and operators are directed to use FCV-605, not HCV-758 to locally control flow. Plausible because aa previous revision of ONOP-050 had operators increase flow using HCV-758.

HCV-758.

62 62

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q #32 0#32 The RO The RD manually manually tripped tripped the reactor due the reactor due to decreasing pressurizer to decreasing pressurizer pressure.

pressure. An An automatic SI automatic SI occurred occurred on on the the trip trip depressurization.

depressurization.

RCS pressure RCS pressure isis currently currently 1700 1700 psig psig and and slowly slowly lowering.

lowering.

One minute after One minute after the the automatic automatic SI SI signal signal actuated, actuated, the the RO RD depressed depressed both both SI SI reset reset pushbuttons on VPB.

pushbuttons on VPB.

ONE of the following describes the response Which ONE response of the safety injection injection system?

A. SI immediately SI immediately reset reset when the the reset pushbuttons were depressed.

reset pushbuttons depressed.

B. SI reset occurs one minute after the reset pushbuttons were depressed.

C. SI reset occurs two minutes after the reset pushbuttons were depressed.

D. SI did NOT reset but will reset if the operators push the reset buttons after the 2 minute timer has timed out.

63 63

NRC DRAFT DRAFT 07124/07 07/24/07 Q #32 Q#32 ANSWER:

ANSWER: BB KA:

KA: 006A4.08 006A4.0B ECCS - Ability to manually ECCS - manually operate and/or monitor monitor in the control room, room, 4.2/4.3 4.2/4.3 10CFR55:

10CFR55: 41.b.7, 41.b.8 41.b.7,41.b.B

Reference:

561 O-T-L1, 5610-T-L 1, Sheet 11 Level:

Cog Level: Comprehension 2 Comprehension Level 2 because the operator must recognize that the SI reset logic is different if the initiating event was SI due to automatic actuation or manual actuation. The SI signal automatically actuated, therefore the system "remembers" remembers the reset attempt and SI will reset after an additional minute (2 minutes total). The operator must relate that even though RCS pressure is below the automatic SI setpoint, the system will allow manual reset in two minutes. If the SI signal was manually actuated, the system does not remember the reset attempt within the first 2 minutes and SI will not reset until another reset attempt is made after the 2 minute timer times out.

New Question Response Analysis:

A. Incorrect because SI did not reset in this situation. Plausible because SI normally resets immediately when operators push the manual reset pushbuttons as it is normally more than two minutes after the initiation signal.

SI will reset after one more minute, B. Correct. There is aa two minute delay so SI will reset within one minute.

C. Incorrect Incorrect because SI was already reset. ItIt reset one minute minute earlier as the 22 minute minute timer is from initiation signal and not the reset signal. Plausible because the reset logic does useuse aa 22 minute timer and this would be aa correct response if the RO attempted to reset immediately.

D.

D. Incorrect. The 22 minutes Incorrect. The minutes must must be be over over before before the reset will work from aa manual manual actuation. Plausible Plausible because because this this would apply SI was apply ifif SI was manually manually initiated.

initiated.

64 64

DRAFT NRC DRAFT 07/24/07 07/24/07 Q #33 Q#33 Operators are Operators are preparing preparing to to reduce reduce PRT PRT pressure pressure which which has has approached approached itsits upper upper limit of limit of 10 psig.

10 psig.

Which ONE of the following describes the processprocess for reducing reducing PRT PRT pressure pressure under these conditions?

Verify the PRTPRT nitrogen regulator, PCV-3-473, nitrogen regulator, PCV-3-473, is:

is:

A. aligned to the PRT.

Start a waste gas compressor. Open the PRT vent valve, CV-3-549.

When PRT pressure reaches 6 psig to 8 psig, then close CV-3-549.

B. aligned to the PRT.

Start a waste gas compressor. Open the PRT vent valve, CV-3-549.

When PRT pressure reaches vent header pressure, then close CV-3-549.

C. isolated from the PRT.

Start a waste gas compressor. Open the PRT vent valve, CV-3-549.

CV3-549.

When PRT pressure reaches 6 psig to 8 psig, then close CV-3-549.

D. isolated from the PRT.

Start a waste gas compressor. Open the PRT vent valve, CV-3-549.

When PRT pressure reaches vent header pressure, then close CV-3-549.

65 65

NRC DRAFT 07/24/07 07/24/07 Q #33 Q#33 ANSWER:

ANSWER: AA KA:

KA: 007A1.02 predict and/or monitor changes in Ability to predict in parameters parameters (to prevent prevent exceeding design limits) associated with operating the PRTPRT controls controls including maintaining maintaining PRT PRT pressure. 2.7/2.9 pressure. 2.7/2.9 IOCFR55:

10CFR55: 41.b.1O 41.b.3, 41.b.4, 41.b.10

Reference:

3-OP-041.3, Section 7.3.2 3-0P-041.3, Cog Level: 1I Recall New Question Response Analysis:

A. Correct per the reference B. Incorrect because PRT pressure must reach 6 to 8 psig before closing CV-549. Plausible because the PRT nitrogen regulator, PCV-3-473, is aligned to the PRT.

C. Incorrect because the PRT nitrogen regulator, PCV-3-473, is aligned to the PRT. Plausible because when PRT pressure reaches 6 psig to 88 psig, then CV-3-549 is closed.

D. Incorrect because the PRT nitrogen regulator, PCV-3-473, is aligned to the PRT and because PRT pressure must reach 6 to 8 8 psig before closing CV549.

CV-549. Plausible because vent header pressure is lower than 66 to 88 psig and would represent aa greater pressure reduction than that provided by the procedure instructions.

66 66

NRC DRAFT NRC DRAFT 07124/07 07/24/07 Q #34 0#34 Unit 33 operators Unit operators areare responding responding to to aa Loss Loss ofofAll All AC AC Power Power (LOAAC).

(LOAAC).

• • The The BOP BOP isis using using 3-0NOP-004.2, 3-ONOP-004.2, "Loss Loss of of 3A 3A 4KV 4KV Bus,"

Bus, toto restore restore the the 3A3A 4KV 4KV Bus which Bus which failed failed to load onto to load onto its its EDG EDG because because of failure of of aa failure the 3A sequencer.

of the 3A sequencer.

• • AsAs the the BOP BOP verifies verifies 3A3A 4KV 4KV busbus stripping, stripping, he he notes notes that that the the 3A 3A Bus Bus loads loads that that were running before were running before the the LOMC LOAAC stillstill show show breaker breaker closed closed indication indication (red (red light).

light).

• • The The BOP BOP places places each each ofof the the 3A 3A Bus Bus components' components control switches inin the control switches the STOP STOP position.

position.

Which ONE Which ONE of the following of the following describes describes the the response response of of the the 3A 3A CCWCCW pump pump breaker breaker light indication on VPB after light indication on VPB after the the BOP BOP places places its its control control switch switch in in STOP?

STOP?

The 3A The 3A CCW CCW pump green light will:

A.

A. remain on. Its red light will remain off.

B. immediately go off. Its red light will energize and remain on.

C. remain on for 10 seconds at which time it will go out and the red light will go on.

D. remain on for 30 seconds at which time it will go out and the red light will go on.

67 67

NRC DRAFT 07124/07 07/24/07 Q #34 Q#34 ANSWER:

ANSWER: C C

KA:

KA: 008A4.08 OOBA4.0B manually operate and/or monitor Ability to manually monitor in in the control room: CCW pump control 3.1/3.8 switch. 3.1/3.B 10CFR55:

10CFR55: 41.b.4, 41.b.7 41.b.4,41.b.7

Reference:

561 0-T-L1, 5610-T-L 1, Sheet 24D Cog Level: 3 Analysis/Application Level 3 because the operator must recognize that the 3A sequencer failure includes the bus stripping portion of the sequencer as evidenced by the operator's operators observation that the 3A Bus loads that were running before the LOAAC still have red breaker light indication. Bus stripping failed to work and bus stripping is the signal that blocks the timed low pressure auto-start of CCW pumps. When the operator takes the 3A CCW pump to off, the breaker opens but 10 seconds later it closes in because bus stripping did not block the low pressure auto-start.

New Question Response Analysis:

A. Incorrect because its green light will remain on for only 10 seconds at which time it will go out and the red light will come on. Plausible because this is the way the system would respond if the sequencer/bus stripping had not failed.

B. Incorrect because its green light will remain on for only 10 seconds at which time it will go out and the red light will come on. Plausible because more than ten seconds has elapsed and aa common misconception is that the breaker will immediately close.

C. Correct per the reference D. Incorrect because its green light will remain on for only only 10 10 seconds at which time it will go out and the red red light light will come on. Plausible because this is the way 3C CCW pump indication would respond under these conditions and this is is the same same train pump.

pump.

68 68

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q #35 Q#35 Unit 33 is Unit is at at 70% power with 70% power all systems with all systems inin normal normal operation.

operation.

The control group The control group ofof pressurizer pressurizer heaters heaters malfunctions malfunctions and and goes goes to to minimum minimum output.

output.

Which ONE Which ONE ofof the the following following describes describes the effect on the effect on the pressurizer pressure the pressurizer pressure control control system AND system AND the the operator operator response response required required by by 3-0NOP-041.5, 3-ONOP-041 .5, "Pressurizer Pressurizer Pressure Control Pressure Control Malfunction"?

Malfunction?

Both groups Both groups of of backup backup heaters heaters will automatically automatically operate:

operate:

A. immediately.

immediately.

Dispatch an operator to locally verify the control group heater breakers are closed.

closed.

B. immediately.

immediately.

Manually cycle backup heaters as needed to maintain pressure at 2235 psig.

C. when pressurizer pressure drops to 2210 psig.

Dispatch an operator to locally verify the control group heater breakers are closed.

D. when pressurizer pressure drops to 2210 psig.

Man ually cycle backup heaters as needed to maintain pressure at 2235 psig.

Manually 69 69

NRC DRAFT 07/24/07 07/24/07 Q #35 Q#35 ANSWER:

ANSWER: C C

KA: 01 KA: 010A2.01- (a) predict OA2.01- Ability to (a) predict the impacts impacts of the following malfunctions malfunctions or operations on the PRZ PCS; and (b)

PRZ PCS; based on those predictions, (b) based predictions, use procedures procedures to correct, control, or mitigate the consequences consequences of of those malfunctions or operations:

Heater failures. 3.3/3.6 Heater 3.3/3.6 10CFR55:

10CFR55: 41.b.4, 41.b.7 41.b.3, 41.bA,

Reference:

3-ONOP-041 .5, Step 12 3-0NOP-041.5, 12 5610T-D-16B, Sheet 11 5610-T-D-16B, Comprehension Cog Level: 2 Comprehension

.Level 2 because the operator must realize that the Control Group going to

.Level2 minimum will result in a decrease in pressurizer pressure. The operator must then recall that the backup groups will both energize at 2210 psig and the correct response is to check the control group heater status.

New Question Response Analysis:

A. Incorrect because the backup heaters will not energize until pressure drops to 2210 psig. Plausible because an operator should be dispatched to locally verify the control group heater breakers are closed.

B. Incorrect because the backup heaters will not energize until pressure drops to 2210 psig and operators are not directed to use the backup heaters to control pressure at 2235 psig. Plausible because normal pressure is 2235 psig and controlling pressure at that value is easily done using the backup heaters.

C. Correct per the reference D. Incorrect because operators are not not directed directed to use the backup heaters to control pressure at 2235 psig. Plausible because the backup heaters will not not energize until pressure drops to 2210 psig.

70 70

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q #36 Q#36 Operators are Operators are performing performing aa shutdown shutdown of Unit 44 reactor.

of Unit reactor.

• • Power level Power level isis currently currently 50%.

50%.

• • First stage pressure transmitter, First stage pressure transmitter, PT-4-447,PT-4-447, fails fails high.

high.

Which ONE Which ONE of of the the following following describes describes the the effect effect of of this this failure failure on on the the normal normal operation of operation of the the reactor reactor protection protection system system during during aa plant plant shutdown?

shutdown?

At the current current power power level, level, aa turbine turbine trip signal can:

can:

A. cause aa reactor cause reactor trip.

When power is is less than 10%,

10%, turbine trip will be able to cause reactor trip.

B. cause a reactor trip.

When power is less than 10%, turbine trip will NOT be able to cause reactor trip.

c.

C. NOT cause a reactor trip.

When power is less than 10%, turbine trip will be able to cause reactor trip.

D. NOT cause a reactor trip.

When power is less than 10%, turbine trip will NOT be able to cause reactor trip.

71 71

NRC DRAFT NRC 07124/07 07/24/07 Q #36 Q#36 ANSWER:

ANSWER: A A

KA:

KA: 012K4.06 012K4.06 Knowledge of Knowledge the RPS of the RPS design design feature(

feature(s) s) and/or and/or interlock( s) which interlock(s) which provide provide forfor automatic automatic or manual enable/disable manual enable/disable of of RPS RPS trips.

trips. 3.2/3.5 3.2/3.5 100FR55:

10CFR55: 41.b.7

Reference:

0-T-L1, 561 O-T-L Sheet 17 1, Sheet 2, Sheet Cog Level: 2 Comprehension Level 2 because the operator must recognize that PT-447 failing high has no immediate affect on the RPS system but results in the inability to clear permissive P-7. Normally when turbine power reduces below 10%, the "At-Power"At-Power trips which include the turbine tripping the reactor are cleared. The clearing logic requires both PT-447 and PT-446 to be below 10%. With PT-447 failed high it cannot clear and At-Power trips remain instated at all power levels.

the "At-Power" New Question Response Analysis:

A. Correct per the reference B. Incorrect because when power is <10%, turbine trip will be able to cause a reactor trip. Plausible because a turbine trip signal can presently cause a reactor trip C. Incorrect because a turbine trip signal can presently cause aa reactor trip.

Plausible because when power is <10%, turbine trip will be able to cause aa reactor trip.

D. Incorrect because aa turbine trip signal can presently cause aa reactor trip and because when power is <10%, turbine trip will be able to cause aa reactor trip.

Plausible because the turbine trip is not normally able to cause aa reactor trip below 10%

10% power.

72 72

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q#37 0#37 Unit 33 reactor Unit reactor power power isis at at 40%

40% with with all all systems systems in in normal normal alignment alignment except except forfor NIS NIS power range power range channel channel N-41N-41 which which isis OOS DOS withwith bistables bistables tripped.

tripped.

Subsequently power Subsequently power range range channel channel N-42N-42 fails fails low.

low.

Which ONE Which ONE of of the the following following describes describes the the immediate immediate effecteffect of of the the N-42 N-42 failure failure onon the reactor the reactor trip trip logic?

logic?

A.

A. The reactor The reactor trip trip logic logic is is NOT NOT affected affected by by the the N-42 N-42 failure.

failure.

B.

B. The RCS The RCS Loop Loop Low Low Flow Flow reactor reactor trip logic is trip logic is disabled disabled byby the the N-42 N-42 failure failure C.

C. RCS Loop The RCS Loop Low Low Flow Flow reactor reactor trip logic logic changed changed to 22 of of 33 flow flow channels channels to trip on 1I of 3 loops.

loops.

D.

D. reactor trip logic The reactor logic disables the at-power reactor trips with 2 of 4 channels

<<10%

10% power.

73 73

NRC DRAFT 07/24/07 Q#37 ANSWER: A KA: 012K6.02 Knowledge of the effect of a loss or malfunction of the following will have on the RPS: Redundant Channels. 2.9/3.1 IOCFR55:

10CFR55: 41.b.7

Reference:

5610-T-L1, 561 O-T-L 1, Sheet 2, Sheet 17, Sheet 20 Cog Level: 2 Comprehension Level 2 because the operator must recognize that the throwing of N-41 bistables inserted a "power power above P-8"P-8 signal to the logic. This effectively changed the trip logic from 2 of 4 channels on 2 of 3 loops to 11 of 3 channels on 2 of 3 loops. When power above P-8" N-42 failed low it could not generate a "power P-8 signal, effectively disabling its input to the logic. However the logic still recognizes inputs from N-43 and N-44 at 40% power and the loop trip logic remains the same even though N-42 input has been disabled.

New Question Response Analysis:

A. Correct per the reference B. Incorrect because the RCS Loop Low Flow reactor trip logic was not affected by this N-42 failure. Plausible because the N-42 input to the RCS Loop Low Flow reactor trip logic is disabled.

C. Incorrect because the RCS Loop Low Flow reactor trip logic was not affected by this N-42 failure. Plausible because the trip logic was initially changed to I of 3 NIS channels to trip when the N-41 bistables were originally thrown.

1 D. Incorrect because the at-power trips require 3 of 4 power range channels be below 10% to be disabled. Plausible because the reactor trip logic does disable the at-power reactor trips when < < 10% power.

74 74

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q #38 0#38 Operators are Operators are responding responding toto aa main main steam steam line line break break outside outside containment.

containment.

• • All safety All safety systems systems functioned functioned asas designed.

designed.

• • SI has been reset.

S I has been reset.

• • The BOP The BOP goes goes behind behind VPB VPB to to reset reset Containment Containment Isolation Isolation Signals.

Signals.

The RO The RO continues continues toto monitor monitor the control boards the control boards and and notes notes the the status status of of annunciator H annunciator H 5/2, 5/2, CNTMT CNTMT ISOLATION ISOLATION ACTIVATED.

ACTIVATED.

Which ONE ONE ofof the following following correctly correctly describes describes the the status status ofof annunciator annunciator H H 5/2?

5/2?

Before the BOP begins to reset Containment Isolation relays, H 5/2 is:

A. in alarm, because Phase A and Containment Ventilation Isolation relays are tripped. After the BOP resets relays, H 5/2 is NOT in alarm because Phase A relays are reset.

B. in alarm, because Phase A and Containment Ventilation Isolation relays are tripped. After the BOP resets relays, H 5/2 is still in alarm because Containment Ventilation Isolation relays are still tripped.

C. not in alarm, because Phase B B relays have not tripped.

After the BOP resets relays, H H 5/2 is NOT in alarm because Phase B B relays have NOT tripped and Phase A relays are reset.

D. NOT in alarm, because Containment Ventilation Isolation relays have NOT tripped. After the BOP resets relays, H H 5/2 is still in alarm because Phase A relays cannot be reset under these conditions.

75 75

NRC DRAFT DRAFT 07/24/07 07/24/07 Q #38 Q#38 ANSWER:

ANSWER: BB KA:

KA: 013A4.02 013A4.02 Ability to Ability manually operate to manually operate and/or and/or monitor monitor in in the the control control room room reset reset of of ESFAS.

ESFAS.

channels. 4.3/4.4 channels. 4.3/4.4 IOCFR55:

10CFR55: 41.b.7, 41.b.9 41.b.7,41.b.9

Reference:

4-EOP-E-1, Step 7 4-ARP-097.CR, H H 5/2 Sht. 11 5610-T-L1, Sht.11 Cog Level: 2 Comprehension Level 2 because the operator must recognize that a steamline break outside containment will trigger Phase A and Containment Ventilation Isolation, but not Phase B. Additionally the operator must recognize that the alarm is active when any of the 3 signals have not been reset. It takes the reset of all 3 signals to clear the alarm.

New Question Response Analysis:

A. Incorrect because after the BOP resets relays, H H 5/2 is still in alarm because Containment Ventilation Isolation relays are still tripped. Plausible because before the BOP begins to reset Containment Isolation relays, H H 5/2 is in alarm, because Phase A and Containment Ventilation Isolation relays are tripped.

B. Correct per the reference C. Incorrect because before the BOP begins to reset Containment Isolation relays, HH 5/2 is in alarm, because Phase A and Containment Ventilation Isolation relays are tripped. After the BOP resets relays, H H 5/2 is still in alarm because Containment Ventilation Isolation relays are still tripped.

Plausible because Phase B B relays have not tripped and after the BOP resets relays, Phase A relays are reset.

D. Incorrect because before the BOP begins to reset Containment Isolation Isolation relays, HH 5/2 is in alarm, because Phase A and Containment Containment Ventilation Isolation relays are tripped.

tripped. After the BOP resets relays, H H 5/2 5/2 is is still in in alarm because alarm because Containment Ventilation Isolation relays are Containment Ventilation Isolation are still still tripped.

tripped.

Plausible because after Plausible because after the the BOP BOP resets resets relays, H H 5/2 5/2 is is still still in in alarm.

alarm.

76 76

NRC DRAFT NRC DRAFT 07124/07 07/24/07 Q#39 Q#39 Operators are Operators are responding responding to to aa simultaneous simultaneous LOOP/LOCA LOOP/LOCA event.

event.

3A EDG 3A EDG failed failed to to start.

start.

Which ONE Which ONE ofof the following describes the following describes the the status of the status of the Emergency Emergency Containment Containment Coolers (ECC5) after sequencing Coolers (ECCs) after sequencing isis complete?

complete?

3A ECC 3AECC 3B ECC 3B ECC ECC 3C ECC 3C A.

A. de-energized running running running running B. de-energized stopped running C. running running stopped de-energized D. running running de-energized 77 77

NRC DRAFT 07124/07 07/24/07 Q #39 Q#39 ANSWER:

ANSWER: CC KA: 022K2.01 Knowledge of the power supplies to the containment cooling fans. 3.0/3.1 Knowledge IOCFR55:

10CFR55: 41.b.8, 41.b.10 41.b.8,41.b.10

Reference:

SD-029, Page 15 15 5610-T-E-1591, 561 0-T-E-1591, Sheet 1I 5613-T-L1, 5613-T-L 12B 1, Sheet 128 Cog Level: 2 Comprehension Level 2 because the operator must recognize that the sequencers will auto-start their respective ECCs if power to the bus is available. 3A ECC is powered from the B train (38 "8" (3B MCC, bkr 30650). 3C ECC is powered from the "A" A train 3C MCC, bkr 30729). 38 3B ECC is powered from either train (swing bus) but does not get an auto start by the sequencer even though the bus will energize.

New Question Response Analysis:

A. Incorrect because 3C ECC is de-energized and 38 does not auto-start.

Plausible because 3A safeguards equipment is normally powered from 3A Train which is de-energized.

B. Incorrect because 3C ECC is de-energized. Plausible because 3A safeguards equipment is normally powered from 3A Train which is de de-energized.

C. Correct per the references D. Incorrect because 3B38 ECC ECC does notnot auto-start. Plausible because 3A 3A ECC ECC is is running and 3C 3C ECC ECC isis de-energized.

78 78

NRC DRAFT NRC DRAFT 07124/07 07/24/07 Q #40 0#40 Following aa large Following large break break LOCA, LOCA, operators operators have have transitioned transitioned toto 3-EOP-ES-1.3, 3-EOP-ES-1 .3, Transfer to "Transfer Cold Leg to Cold Leg Recirculation,"

Recirculation, andand are are determining determining ifif "piggy-back" piggy-back recirculation will recirculation will be be required.

required.

The RO The RO reports reports the the following following information:

information:

• • RHR flow RHR flow on on FI-3-605 F 1-3-605 isis 2800 2800 gpm gpm

• • Containment pressure Containment pressure isis 1212 psig.

psig.

• • Containment temperature Containment temperature is is 178°F.

178°F.

• • All ECF All ECF spray spray valves valves are are closed.

closed.

ONE of Which ONE of the following is is correct regarding regarding subsequent subsequent Containment Containment Spray Spray Pump (CSP) operation?

Pump (CSP) operation?

Operators will run:

A. No CSPs.

CSP5.

B. One CSP with suction provided directly from the RWST.

C. One CSP with suction provided from the discharge of the running RHR pump(s).

D. Two CSPs with suction provided from the discharge of the running RHR pump(s).

79 79

NRC DRAFT 07/24/07 07/24/07 Q #40 Q#40 ANSWER: C KA: 026K4.0l 026K4.01 Knowledge of the CSS design feature( feature(s) interlock(s) s) and/or interlock( s) which provide for:

source of water for CSS, including recirculation phase after LOCA 4.2/4.3 IOCFR55:

10CFR55: *41.b.7, 41.b.8 41.b.7,41.b.8

Reference:

3-EOP-ES-1.3, Steps 18, 21, 23, 25, 26 Cog Level: 2 Comprehension Level 2 because the operator must recognize that one of the four criteria to discontinue CSP operation is not satisfied. Additionally the operator must recall pull-to-lock in Step 2 of EOP-ES-1.3 that one CSP was put in pull-to-Iock EOP-ES-1 .3 and must remain in pull-to-lock pull-to-Iock subsequently. Finally the operator must recognize that subsequent procedure steps change the CSP suction source from the RWST to the discharge of the RHR pumps.

New Question Response Analysis:

A. Incorrect because 1 I CSP must be run under these conditions. Plausible because 3 of the 4 listed parameters support not starting a CSP.

B. Incorrect because when a CSP is subsequently started, cold leg recirculation will have been aligned. Plausible because up to this time the running CSP has been aligned to the RWST.

C. Correct per the reference D. Incorrect because one CSP was put in pull-to-lock pull-to-Iock earlier in EOP-ES-1 EOP-ES-1.3 .3 and it will remain in pull-to-lock.

pull-to-Iock. Plausible because the running CSP will have its suction provided from the discharge of the running RHR pump(s).

80 80

NRCDRAFT NRC DRAFT 07124/07 07/24/07 Q#41 0#41 Operators are Operators are performing performing 3-EOP-E-1, 3-EOP-E-1, "LossLoss of of Reactor Reactoror orSecondary Secondary Coolant" Coolant and and thefollowing the following plant plant conditions conditions exist:

exist:

• • RCS Pressure RCS Pressure isis 1000 1000 psig psig

• • All RCPs are All RCPs are OffOff

• • Contai nment Tempe Containment Temperature rature isis 220°F 220°F

• • Containment Pressure Containment Pressure isis 19 19 psig psig and and rising rising

• • Two ECCs are Two ECCs are running running

• • All Available Charging All Available Charging Pumps Pumps areare running running

• • The RCS The RCS isis saturated saturated

• • RWST level RWST level isis 220,000 220,000 gallons gallons Containment Pressure Containment Pressure has has just just increased increased to to 2121 psig.

psig. The The operators operators entered entered 3-EOP-FR-Z.1, "Response 3-EOP-FR-Z.1, Response to to High High Containment Containment Pressure" Pressure and are assessing and are assessing Containment Spray Containment Spray pumps pumps (CSPs)

(CSP5) status.

status.

Which one of the following describes Which describes the correct plant plant and operator operator response?

response?

A.

A. Neither CSP auto-started.

auto-started.

Manually Manually start both CSPs.

B.

B. Neither CSP auto-started.

auto-started.

Manually start one CSP and place the other CSP in Pull-To-Lock Manually Pull-To-Lock..

C. Both CSPs auto-st arted.

auto-started.

Verify both CSPs auto-st arted.

auto-started.

D.

D. Both CSPs auto-st arted.

auto-started.

Manually Manually stop stop one one CSP CSP and and place place itit in in Standb Standby.y.

8181

NRC DRAFT DRAFT 07124/07 07/24/07 Q #41 Q#41 ANSWER:

ANSWER: A A

KA:

KA: 026A1.O1 026A 1.01 Ability to predict and/or to predict and/or monitor monitor changes changes inin parameters parameters (to (to prevent prevent exceeding exceeding design limits) associated design limits) associated with operating the CSS operating the CSS controls controls including including containment containment pressure 3.9/4.2 pressure 3.9/4.2 10CFR55:

10CFR55: 41.b.7, 41.b.8 41.b.7,41.b.8

Reference:

5610-T-L1, 5610-T-L 11 1, Sheet 11 5613-T-L1, 5613-T-L 12A 1, Sheet 12A 3OEOP-E-O, Attachment 3, Step 12 30EOP-E-0, 3-EOP-FR-Z.1,, Step 8 3-EOP-FR-Z.1 Cog Level: 2 Comprehension Level 2 because the operator must analyze plant conditions and determine that both CSPs are needed but neither auto-started based on the sequencers having been reset when SI was reset in EOP-E-O.

New Question Response Analysis:

A. Correct because neither CSP auto started because the sequencer was reset when the operators reset SI in E-O and both CSPs are needed lAW 3-EOP-FR-Z.1, Step 8 guidance.

B. Incorrect because both CSPs are needed lAW 3-EOP-FR-Z.1, Step 8 guidance. Plausible because neither CSP auto-started because the sequencer was reset when the operators reset SI in E-O.

C. Incorrect because neither CSP auto-started. Plausible because operators are directed to verify both CSPs are running lAW 3-EOP-FR-Z.1, Step 88 guidance.

D. Incorrect because neither CSP auto-started. Plausible because operators are directed to manually stop one CSP and place it in Standby if containment pressure is << 1414 psig.

82 82

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q #42 0#42 Operators have Operators have responded responded to to aa small small break break LOCA LOCA on on Unit Unit 33 and and are are performing performing 3-EOP-ES-1 .2, Post-LOCA 3-EOP-ES-1.2, Post-LOCA Cooldown Cooldown and and Depressurization."

Depressurization.

The RO The RD isis preparing preparing to to initiate initiate an an RCS RCS cooldown cooldown to Cold Shutdown to Cold Shutdown by by dumping dumping steam from intact steam generators.

steam from intact steam generators. .

Which ONE Which ONE of of the the following following describes describes why the RO why the RO must must limit limit steam steam flow flow rate rate to to maintain the maintain the allowable allowable coolcool down down rate rate below below 100°F/hr?

100°F/hr?

Excessive steam Excessive steam flow rate may flow rate may result result in:

in:

A. termination of RCS natural circulation flow.

B. challenging the integrity status tree for pressurized pressurized thermal shock limits.

C. automatic closure of the MSIVs which isolates the condenser steam dumps.

D. exceeding the capability of the AFW system to maintain S/G SIG levels above 6% which will require stopping the cooldown.

83 83

NRC DRAFT DRAFT 07124/07 07/24/07 Q #42 Q#42 ANSWER:

ANSWER: BB KA:

KA: 039K5.05 039K5.05 Knowledge of Knowledge of the the operational operational implications implications of the following of the following concept concept as as itit applies applies to to the MRSS: Basis the MRSS: Basis for the RCS cooldown the RCS cooldown limits limits 2.7/3.1 2.7/3.1 IOCFR55:

10CFR55: 41.b.4, 41.b.5, 41.b.10 41.b.3, 41.bA, 41.b.1O

Reference:

3-EOP-ES-1 .2, Step 6, BD 3-EOP-ES-1.2, Cog Level: 1I Recall New Question Response Analysis:

A. Incorrect because excessive steam flow will not prevent RCS NC flow.

Plausible because excessive steam flow may temporarily retard NC flow.

B. Correct per the reference C. Incorrect because excessive steam flow will not occur under these conditions. Only possible when you cooldown at maximum rate rate....

D. Incorrect only ECA-O.O requires stopping the cooldown rate if SG level is less than 6% in all SGs.

84 84

NRC DRAFT NRC DRAFT 07124/07 07/24/07 Q #43 Q#43 Unit 44 is Unit is at at 80%

80% power power with all systems with all systems in in auto auto when when the the 4A 4A S/G SIG pressure pressure transmitter associated transmitter associated with with the the controlling controlling S/G S/G steam steam flow flow transmitter transmitter fails fails LOW.

LOW.

Which ONE Which ONE of of the the following following describes describes thethe immediate immediate effect effect on on 4A:

4A:

1)

1) S/G steam S/G steam flow signal to flow signal to the feed reg the feed valve controller reg valve controller 2)

2) feed reg feed reg valve valve 3)

3) SIG level S/G level A.

A. 1) steam

1) steam flow flow signal signal decreases decreases

2) feed

2) feed regreg valve valve opens.

opens.

SIG level increases.

3) S/G B. 1) steam flow signal decreases 1)

2) feed reg valve closes.

SIG level decreases.

3) S/G C. 1) steam flow signal increases

2) feed reg valve opens.

SIG level increases.

3) S/G D. 1) steam flow signal increases

2) feed reg valve closes.

3) S/C S/G level decreases.

85 85

DRAFT NRC DRAFT 07/24/07 07/24/07 Q #43 Q#43 ANSWER:

ANSWER: B B

KA:

KA: 059K1.03 059K1.03 Knowledge of Knowledge the physical of the physical connection connection and/or and/or cause-effect cause-effect relationships relationships between between the main feedwater and the SIGs.

the main feedwater and the S/Gs. 3.1/3.3 3.1/3.3 IOCFR55:

10CFR55: 41.b.4, 41.b.7

Reference:

5610-T-D-17, 561 O-T-0-17, Sheet 11 5610-T-D-18B, Sheet 1 5610-T-0-18B,Sheet1 SD-li, Page SO-11, Page 32 Cog Level: 2 Comprehension Level 2 because the operator must realize that when the pressure density compensation input to the steam flow signal fails low, the result is the steam flow signal to the feed reg valve controller also goes low. Steam flow is compared to feed flow and the resulting imbalance causes the feed reg valve to go closed with a resulting drop in S/G level.

New Question Response Analysis:

A. Incorrect because for this failure the steam flow signal decreases, the feed reg valve closes and the S/G level decreases. Plausible because the steam flow signal will decrease.

B. Correct per the references C. Incorrect because for this failure the steam flow signal decreases, the feed reg valve closes and the S/G level decreases. Plausible because this response provides an accurate description of the effect of the pressure input failing high.

high.

D.

O. Incorrect because for this failure the steam flow signal decreases, the feed reg valve closes and the S/G level decreases. Plausible because the feed reg valve will close and the S/G level will decrease.

decrease.

86 86

NRC DRAFT NRC DRAFT 07124/07 07/24/07 Q#44 Q#44 Unit 44 is Unit is operating operating atat 40%

40% power power with with all all systems systems inin automatic automatic operation.

operation.

• • The sensing The sensing line line for for first first stage stage pressure pressure transmitter, transmitter, PT-4-446, PT-4-446, which which is is selected selected for control on for control on VPA, VPA, shears shears offoff at at the the connection connection toto the the pressure pressure transmitter.

transmitter.

• • Several minutes Several minutes later, later, the BOP selects the BOP selects PT-4-447 PT-4-447 as as the the controlling controlling channel channel as as directed by directed by the the procedure.

procedure.

Which ONE ONE ofof the following following describes describes the response response ofof S/G SIG levels levels assuming assuming they they left in are left in automatic automatic throughout the entire entire evolution?

evolution?

SIG levels will:

S/G A. remain stable at 60%.

remain B. lower from 60% and stabilize at 50% and then return to 60%.

c.

C. lower from 60% and remain stable at 50%.

D. lower from 60% continuously until PT-4-447 is selected and then rise to 50%

87 87

NRC DRAFT 07/24/07 Q #44 Q#44 ANSWER: B KA: 059A3.02 Ability to monitor automatic operation of the MFW, including programmed levels of SIG. 2.9/3.1 the S/G.

IOCFR55:

10CFR55: 41.b.4, 41.b.7 41.bA,41.b.7

Reference:

5610-T-D-17 561 0-T-D-17 Sheet 11 5610-T-D-18A Sheet 11 Cog Level: 3 Analysis Level 3 because the operator must recognize that when PT-446 is selected for control, it is providing programmed level input to the S/G level control program. A sheared sensing line will cause the pressure transmitter to call for a 0% power S/G level of 50%. At 40% power, the desired programmed level has just increased to 60%. When PT -446 fails low, the programmed level input changes to 50% and not PT-446 o0 %. Feed reg valves respond and level drops to 50% on all S/Gs. Operator must know that even though failed low, the control loop is limited at 50% level or the level would continue to decrease. They then must realize that when PT-4-447 is selected, the SG level control system will return level back to 60%.

New Question Response Analysis:

A. Incorrect because S/G levels will lower from 60% and will stabilize stabIlize at 50%

and then return to 60% when PT PT-4-447 447 is selected. Plausible because at 40% power the level program has just increased from 50% to 60%.

B. Correct per the reference.

C. Incorrect because S/G levels will lower from 60% and will stabilize at 50%

and then return to 60% when PT-4-447 is selected. Plausible because other SIG levels to rise continuously until a instrument failures will cause S/G a turbine trip occurs.

D. Incorrect because S/C S/G levels will lower from 60% and will stabilize at 50%

and then return to 60% when PT-4-447 is selected. Plausible because other instrument failures will cause SIG S/G levels to lower continuously until aa reactor trip occurs.

88 88

NRC DRAFT NRC DRAFT 07124/07 07/24/07 Q #45 Q#45 With Unit With Unit 44 at at 30% power during 30% power during aa plant plant startup, startup, the the RO RO discovers discovers the the running running Steam Generator Steam Generator Feed Feed Pump Pump (SGFP)

(SGFP) start/stop start/stop hand hand switch switch inin the the green-flagged green-flagged position.

position.

Which ONE Which ONE of of the the following following describes describes thethe consequences consequences of of this this discovery?

discovery?

A.

A. An AFW system An AFW system auto-start auto-start signal signal hashas been been disabled.

disabled.

B.

B. A condensate condensate pump pump auto-start auto-start signal has has been been disabled.

disabled.

C.

C. The running SGFP The running SGFP can NOT trip can NOT as aa result trip as result of of bus stripping.

bus stripping.

D. The turbine can can NOT run back as a result of a SGFP trip.

89 89

DRAFT NRC DRAFT 07124/07 07/24/07 Q #45 Q#45 ANSWER:

ANSWER: A A KA:

KA: 061 K4.02 061 K4.02 Knowledge of Knowledge the AFW of the AFW design design feature(

feature(s) and/or interlock(

s) and/or interlock(s) s) which which provide provide for:

for: AFW AFW automatic start upon loss of MEW pump, automatic start upon loss of MFW pump, S/G level, blackout S/G level, blackout or or SI.

SI. 4.5/4.6 4.5/4.6 IOCFR55:

10CFR55: 41.b.4, 41.b.7 41.bA,

Reference:

Sheet 15, Notes 1I and 5610-T-L1, Sheet and 55 Cog Level: 11 Recall Recall New Question Response Analysis:

A. Correct per the reference B. Incorrect because the Condensate pump auto-start feature is unaffected by this event. Plausible because Condensate pumps do have auto-start features but they are affected by the status of other Condensate pumps, not SGFPs.

C. Incorrect because the S/G feed pump trip signal from bus stripping is unaffected. Plausible because green flag indication implies to the AEW AFW start logic that the SGFP has been manually stopped but it does not input to the bus stripping logic in the same manner.

D. Incorrect because the S/G feed pump trip signal into the turbine runback run back logic is unaffected. Plausible because green flag indication implies to the AFW start logic that the SGFP has been manually stopped but it does not input to the turbine runback logic in the same manner.

90 90

NRC DRAFT NRC DRAFT 07124/07 07/24/07 Q #46 Q#46 Unit 33 isis at Unit at 100%

100% power power with with all all systems systems inin normal normal alignment.

alignment.

The 3C The 30 main main steam steam line line non-return non-return check check valve valve body body ruptures resulting inin aa large ruptures resulting large Main Steam Line Main Steam Line Break Break (MSLB)

(MSLB) at at the the 3C 3C non-return non-return check check valve.

valve.

Which ONE Which ONE of of the following describes the following describes the the automatic automatic response response ofof the the AFW AFW system?

system?

A.

A. Only 3A Only 3A andand 3B3B AFW AFW pumps pumps startstart and and deliver deliver flow.

flow.

390 gpm 390 gpm total total AFW AFW flow flow will will be delivered to be delivered to all all S/Gs.

SIGs.

B.

B. Only 3A Only 3A andand 3C3C AFW AFW pumps pumps startstart and and deliver deliver flow.

flow.

780 gpm total AFW flow 780 gpm total AFW flow will be will be delivered delivered to to all all S/Gs.

S/Gs.

C.

C. Only 3B Only 3B andand 3C 3C AFW AFW pumps pumps startstart and and deliver deliver flow.

flow.

390 gpm 390 gpm total total AFW flowflow will will be be delivered delivered to to all S/Gs.

SIG5.

D.

D. All AFW pumps start and deliver flow.

780 gpm total AFW flow will be delivered to all S/Gs.

9191

NRC DRAFT DRAFT 07/24/07 07/24/07 Q #46 Q#46 ANSWER:

ANSWER: D D

KA:

KA: 061A3.O1 061A3.01 Ability to Ability to monitor monitor automatic automatic operation operation of of the the AFW, AFW, including:

including: AFW AFW startup startup and and flows. 4.2/4.2 flows. 4.2/4.2 IOCFR55:

10CFR55: 41.b.4, 41.b.7, 41.b.8 41.bA,

Reference:

5613-M-3072, Sheet 1I 5613-M-3072, 5610-T-L11 Sheet 5610-T-L Sheet 11 11 5610-T-L11 Sheet 15 5610-T-L 15 Cog Level: 3 Analysis/Application Level 3 because the operator must analyze the following to come to the correct conclusion. A steam line break at the 3C non-return valve will not cause the 3C S/C to blow dry because the 3C S/G 30 MSIV will close. SI actuates due to Hi steamline flow with low Tavg/ low SG SC pressure when all 3 S/Gs feed the break at the 3C non-MSIV5. Both trains of AFW get a start return valve. This SI signal closes all 3 MSIVs.

signal due to SI. With all 3 S/Gs pressurized, all AFW pumps auto start and provide S/Cs. The AFW flow controllers are preset at 130 gpm each. 130 gpm X flow to all S/Gs.

6 AFW reg valves = = 780 gpm.

New Question Response Analysis:

A. Incorrect because all AFW pumps start and deliver flow. 780 gpm total AFW flow will be delivered to all S/Gs. Plausible if the operator assumes the faulted 30 3C S/G blows down and 30 3C S/G is providing steam supply to the 30 3C AFW pump.

B. Incorrect because all AFW pumps start and deliver flow. Plausible if the operator recognizes 3A and 30 3C AFW pumps are in different trains. In In that case 780 gpm total AFW flow will be delivered to all S/Cs.

S/Gs.

C. Incorrect because all AFW pumps start and deliver flow. 780 gpm total AFW flow will be delivered to all S/Cs.

S/Gs. Plausible if the operator assumes the faulted 30 3C S/G blows down. 3A AFW pump would lose its its steam supply and 390 gpm gpm total AFW flow would be delivered to all S/Cs.

S/Gs.

D. Correct per the references 92 92

NRC DRAFT DRAFT 07/24/07 07/24/07 Q #47 Q#47 Tech Spec Tech Spec 3.8.1.1, 3.8.1 .1, AC AC Power Power Sources, Sources, allows allows aa unit unit to to continue continue power power operation operation at at less than less than 30% power for 30% power for up up to to 30 30 days days ifif its its Startup Startup Transformer Transformer becomes becomes inoperable.

inoperable.

Which ONE Which ONE ofof the the following following describes describes the the basis basis for for allowing allowing continued continued operation operation at at less than less than 30% power?

30% power?

At 30% power:

A. the two loop low flow / two RCPRCP breaker breaker open reactor reactor trip logic logic has has been been instated providing instated providing additional reactor reactor protection protection in in the event of a LOOP.

LOOP.

B. SIG pressure is greater than full power S/G pressure providing additional S/G motive force to the steam driven AFW pumps in the event of AFW actuation.

C. fewer components are loaded onto the 4KV Buses and Load Centers resulting in lower bus and load center operating temperatures.

D. decay heat has been reduced, automatic feedwater control can be maintained and the RCPs continue to run.

93 93

NRC DRAFT 07/24/07 07/24/07 Q #47 Q#47 ANSWER:

ANSWER: DD KA:

KA: 062G2.2.25 062G2.2.25 As itit relates As relates to the AC to the AC Electrical Electrical Distribution:

Distribution: Knowledge Knowledge of of the the bases bases in in Tech Tech Specs for Specs for LCOs LCOs and and safety limits. 2.5/3.7 safety limits. 2.5/3.7 10CFR55:

10CFR55: 41.b.1, 41.b.5, 41.b.7, 41.b.8 41.b.1,41.b.5,41.b.7,41.b.8

Reference:

0-ADM-536, Page 94; Section 3/4.8.1 Cog Level: 11 Recall Recall Bank Question Response Analysis:

A. Incorrect because the basis for allowing continued operation at 30% power is decay heat has been reduced, automatic feedwater control can be maintained and natural circulation conditions are avoided by staying at power and not shutting down. Plausible because at 30% power, the two loop low flow / two RCP breaker open reactor trip logic has been instated.

B. Incorrect because the basis for allowing continued operation at 30% power is decay heat has been reduced, automatic feedwater control can be maintained and natural circulation conditions are avoided by staying at power and not shutting down. Plausible because at 30% power, S/G S/C pressure is greater than full power S/G pressure.

C. Incorrect because the basis for allowing continued operation at 30% power is decay heat has been reduced, automatic feedwater control can be maintained and natural circulation conditions are avoided by staying at power and not shutting down. Plausible because at 30% power, fewer components are loaded onto the 4KV Buses and Load Centers.

D. Correct per the reference 94 94

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q #48 0#48 Both Units Both Units are are at at 100%

100% power power with with normal normal system system alignments alignments except for 40 except for 4D MCC MCC which isis out which of service.

out of service.

Subsequently the Subsequently the feeder feeder breaker breaker to 3C MCC to 3C MCC trips trips open, open, de-energizing de-energizing 3C 3C MCC.

MCC.

Which ONE Which ONE ofof the the following following describes describes the effect on the effect the Vital on the Vital DC DC electrical electrical system?

system?

A.

A. 3A DC 3A DC Bus Bus can can only only be be expected expected to maintain voltage to maintain voltage to to shutdown shutdown loads loads above 120 above 120 volts for for four hours.

hours.

B.

B. 3A DC 3A DC Bus Bus can can only only be expected to be expected maintain voltage to maintain voltage to shutdown loads to shutdown loads above 105105 volts for two hours.

C. 3B DC Bus Bus can only be expected to maintain voltage to shutdown loads above 120 volts for four hours.

D. 3B DC Bus can only be expected to maintain voltage to shutdown loads above 105 volts for two hours.

95 95

NRC DRAFT DRAFT 07124/07 07/24/07 Q #48 Q#48 ANSWER:

ANSWER: B B

KA:

KA: 063K1 .03 063K1.03 Knowledge of the physical Knowledge physical connection and/or cause-effect relationships relationships between between DC Electrical the DC Electrical Distribution and the battery charger and battery. 2.9/3.5 100FR55:

10CFR55: 41.b.4, 41.b.7, 41.b.8

Reference:

5610-T-E-I 592 Sheet 1I 5610-T-E-1592 SD-I 44, Page 9 SD-144, Cog Level: 2 Comprehension Comprehension Level 2 because the operator must recognize that 4D MCC is the power supply to the 3A2 battery charger and 3C MCC is the power supply to the 3A 3A11 battery charger. Loss of both results in no battery chargers for the 3A DC Bus. The operator must then recall that the 3A battery is sized to maintain voltage to shutdown loads above 105 volts for two hours.

New Question Response Analysis:

A. Incorrect because 3A DC Bus can only be expected to maintain voltage to shutdown loads only above 105 volts for only two hours. Plausible because it is the 3A DC Bus which is affected.

B. Correct per the reference C. Incorrect because the 3A DC Bus is the affected bus. Plausible because 120 120 volts is the approximate normal voltage for all DC buses.

D. Incorrect because the 3A DC Bus is the affected bus. Plausible because 3A DC Bus can only be expected to maintain voltage to shutdown shutdown loads above 105 volts for two hours.

105 96 96

NRC DRAFT NRC DRAFT 07124/07 07/24/07 Q #49 0#49 Unit 33 isis in Unit in Mode Mode 33 when when the input breakers the input breakers to to vital vital DC DC buses buses 3D23 3D23 and and 3D23A 3D23A trip trip open deenergizing open deenergizing the the DCDC buses.

buses.

Which ONE Which ONE of of the the following following describes describes thethe effect effect on the Unit on the Unit 33 EDG(s)?

EDG(s)?

A.

A. 3A EDG 3A EDG has lost control has lost control and field flashing and field flashing power.

power.

3A3A EDGEDG does does NOT NOT have have black black start start capability.

capability.

B.

B. 3B EDG 3B EDG hashas lost lost control control and and field flashing power.

power.

3B EDG does NOT have black start 3B EDG does NOT have black start capability. capability.

C. 3A EDG has lost control and field flashing power.

3A EDG is is still black start capable.

D. 3B EDG has lost control and field flashing power.

3B EDG is still black start capable.

97 97

DRAFT NRC DRAFT 07/24/07 07/24/07 Q #49 Q#49 ANSWER:

ANSWER: 8B KA:

KA: 064K2.03 064K2.03 EDGs - Knowledge EDGs - Knowledge of of the the power power supplies supplies to to the the control control power.

power. 2.9/3.3 2.9/3.3 10CFR55:

10CFR55: 41.b.4, 41.b.7, 41.b.8 41.bA,

Reference:

3-ONOP-003.5, Step 3-0NOP-003.5, Step 3.5 &

& Attachment 3, 8kr Bkr 3D23A-28 Cog Level:

Level: 11 Recall Recall New Question Response Analysis:

A. Incorrect because 38 3B EDG has lost control and field flashing power.

Plausible because 3A EDG does not have black start capability.

B.

8. Correct per the reference C. Incorrect because 38 3B EDG has lost control and field flashing power and because 3A EDG does not have black start capability. Plausible because both Unit 4 EDGs have black start capability.

D. Incorrect because 38 3B EDG does not have black start capability. Plausible because 3B38 EDG has lost control and field flashing power.

98 98

NRC DRAFT 07/24/07 07/24/07 Q #50 0#50 Operators are Operators are performing performing the the monthly monthly test test run of the run of the 3A 3A EDG EDG using using 3-0SP-023.1 3-OSP-023.1,,

Diesel Generator "Diesel Generator Operability Operability Test."

Test.

BOP is attempting to verify 3A EDG The BOP EDG isis in in LAG.

LAG.

He momentarily He momentarily positions positions the diesel diesel generator generator voltage regulator regulator in in RAISE.

RAISE.

Assuming the 3A EDG is in the LAG, which ONE of the following describes the EDG response and subsequent operator actions required to verify the EDG is in LAG?

3A EDG amps:

A. increased.

Slowly lower EDG voltage until amps stop decreasing and start to increase.

Then slowly raise EDG voltage until amps increase.

B. increased.

Slowly raise EDG voltage until amps stop increasing and start to decrease.

Then slowly lower EDG voltage until amps increase.

c.

C. decreased.

Slowly lower EDG voltage until amps stop decreasing and start to increase.

Then slowly raise EDG voltage until amps decrease.

D. decreased.

Slowly raise EDG voltage until amps stop decreasing and start to increase.

Then slowly lower EDG voltage until amps decrease.

99 99

NRC DRAFT 07/24/07 07124/07 Q #50 Q#50 ANSWER: A KA: 064G2.1.23 As it relates to the EDG, ability to perform specific system and integrated plant procedures during all modes of plant operation. 3.9/4.0 IOCFR55:

10CFR55: 41.b.4, 41b.7 41.bA,41.b.7

Reference:

3-OSP-023.1, Step 7.1.2.29.k 3-0SP-023.1, Cog Level: 1I Recall New Question Response Analysis:

A. Correct per the reference B. Incorrect because the operator should subsequently slowly lower EDG voltage until amps stop decreasing. Plausible because 3A EDG amps increased.

C. Incorrect because 3A EDG amps increased. Plausible because the operator should slowly lower EDG voltage until amps stops decreasing.

D. Incorrect because 3A EDG amps increased and because the operator should slowly lower EDG voltage until amps stop decreasing. Plausible because if the EDG is in the LEAD, the subsequent operator action would be to subsequently raise the EDG voltage.

100 100

NRC DRAFT NRC 07/24/07 07/24/07 Q #51 Q #51 Unit 33 is Unit is at at 100%

100% power power with with all all systems systems in normal alignment in normal alignment wherJ when the the following following occur; occur;

• • Annunciator H Annunciator H 1/6, 1/6, PRMS PRMS CHANNEL CHANNEL FAILURE, FAILURE, alarms.

alarms.

• • Steam Generator Steam Generator Liquid Liquid Sample Sample Monitor, Monitor, R3-19, R3-19, fail lamp lamp on on the the PRMS PRMS drawer drawer is illuminated is illuminated

• • R3-19 display and recorder reading are failed LOW

• R3-19 warning and high alarm lamps are off.

Which ONE of the following describes the plant plant response and the correct initial initial response?

operator response?

A. S/G blowdown does NOT automatically isolate.

Manually secure Blowdown.

B. S/G blowdown does NOT automatically isolate.

Maintain blowdown in operation but re-align the discharge to the main condenser.

C. S/G blowdown has automatically isolated.

Verify S/G blowdown flow control valves, FCV-6278 A, B, & C and blowdown tank to canal level control valve, LCV-3-6265B are closed.

D. S/G blowdown has automatically isolated.

Verify S/G blowdown isolation valves, MOV-6275 A, B, & C and S/G liquid MOV-1 425/1 426/1 427 are closed.

sample valves MOV-1425/1426/1427 101 101

NRC DRAFTDRAFT 07/24/07 07/24/07

1. 51 Q #51 Q

ANSWER:

ANSWER: AA KA:

KA: 073A2.02 073A2.02 to (a)

Ability to predict the (a) predict the impacts impacts ofof the the following following malfunctions malfunctions oror operations operations on on the the PRMS and (b) based on those predictions, use PRMS and (b) based on those predictions, use procedures procedures toto correct, correct, control, control, oror mitigate the mitigate the consequences consequences of those malfunctions of those malfunctions oror operations:

operations: detector detector failure.

failure.

2.7/3.2 2.7/3.2 IOCFR55:

10CFR55: 41 .b.1O, 41.b.11, 41.b.10, 41 .b.1 1, 41.b.12, 41 .b.12, 41.b.13 41 .b.13

Reference:

3-ONOP-071 .2, Step 3 RNO 3-0NOP-071.2, 3-ARP-097.CR, H1/6, Step 2f.

Cog Level: 1I Recall New Question Response Analysis:

A. Correct per the references B. Incorrect because blowdown needs to be manually secured. Plausible because blowdown is still in service and operator may think that with it aligned to the condenser (recent plant modification does not allow flow to condenser) continued operation is acceptable.

C. Incorrect because S/G SIG blowdown has not automatically isolated. Plausible because verifying the blowdown flow control valves are closed is an expected response if blowdown automatically isolates due to high radiation as stated on the meter.

D. Incorrect because S/G blowdown has not automatically isolated. Plausible because verifying the blowdown flow control valves are closed is an expected response if blowdown automatically isolates due to Phase A.

102 102

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q#52 Q#52 Unit 44 operators Unit operators are are responding responding to loss of to aa loss Intake Cooling of Intake Cooling Water Water (ICW).

(ICW).

Which ONE Which ONE of of the following identifies the following identifies plant plant conditions conditions that that will will require require operators operators to to trip Unit trip Unit 44 reactor reactor and and turbine?

turbine?

A.

A. Exciter hot Exciter hot air temperature increases air temperature increases to:to: 80°C B.

B. Turbine bearing Turbine bearing temperature temperature increases increases to: to: 160°F C.

C. CCW temperature CCW temperature increases increases to:

to: 130°F D.

D. TPCW temperature increases increases to: 105°F 103 103

NRC DRAFT 07/24/07 07124/07 Q #52 Q#52 ANSWER: C KA: 076A1.02 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the Service Water controls including reactor and turbine building closed cooling water temperatures. 2.6/2.6 10CFR55: 41.b.4, 41.b.5, 41.b.8 41.bA,

Reference:

4-ONOP-019 FO 4-0NOP-019 ED Page Cog Level: I Recall 1

New Question Response Analysis:

A. Incorrect because reactor trip is not required until exciter air temperatures increase beyond 90°C. Plausible because exciter air temperatures should increase during this event.

B. Incorrect because reactor trip is not required until turbine bearing temperatures increase beyond 180°F. Plausible because turbine bearing temperatures should increase during this event.

C. Correct per the references.

D. Incorrect because removing load/reactor trip is not required until TPCW temperatures increase beyond 110°F. Plausible because TPCW temperatures should increase during this event.

104

NRC DRAFT NRC DRAFT 07124/07 07/24/07 Q #53 0#53 Unit 33 operators Unit operators are are responding responding to to decreasing decreasing Instrument Instrument AirAir (IA)

(IA) Pressure.

Pressure.

Which ONE Which ONE of of the the following following describes describes the the use use of Service Air of Service Air as as backup backup to to the the IA IA System?

System?

Service Air Service Air valves valves may may be opened:

be opened:

A.

A. regardless of regardless IA pressure of IA pressure but only after but only after all all available available instrument instrument air air compressors have have been been started.

started.

B.

B. ifif IA IA pressure pressure drops drops below below 95 95 psig psig regardless regardless of of the the number number of of available available instrument air compressors started.

c.

C. ifif IA IA pressure pressure drops below below 95 psig psig and after after all available instrument instrument air compressors have been started.

D. as backup to IA without restrictions associated with IA pressure or starting of available IA compressors.

105 105

NRC DRAFT 07/24/07 07/24/07 Q #53 Q#53 ANSWER:

ANSWER: CC KA:

KA: 078K1 .02 078K1.02 Knowledge of the physical connection and/or cause-effect Knowledge causeeffect relationships relationships between between Instrument air and the the Instrument the service air. 2.7/2.8 IOCFR55:

10CFR55: 41.b.4, 41.b.10 41.b.4,41.b.10

Reference:

O-ONOP-013, Steps 3 and 4 Cog Level: 1I Recall New Question Response Analysis:

A. Incorrect because service air valves may be opened only if IA pressure drops below 95 psig and after any available instrument air compressors have been started. Plausible because service air valves may be opened after any available instrument air compressors have been started B. Incorrect because service air valves may be opened only if IA pressure drops below 95 psig and after any available instrument air compressors have been started. Plausible because service air valves may be opened if IA pressure drops below 95 psig.

C. Correct per the references.

D. Incorrect because service air valves may be opened only if IA pressure drops below 95 psig and after any available instrument air compressors have been started. Plausible because service air valves are opened as backup to instrument air.

106 106

NRC NRC DRAFT 07/24/07 07/24/07 Q #54 0#54 The plant The plant was was operating operating at at 100%

100% power power when:

when:

• • A small A small break break LOCA LOCA has has occurred.

occurred.

• • SI SI was manually actuated due to decreasing manually actuated due decreasing pressurizer pressurizer level.

level.

• • Phase A Phase was NOT A was NOT manually manually actuated actuated following following the the manual manual SI SI actuation.

actuation.

• • Containment pressure Containment pressure has has risen risen to 17 17 psig.

psig.

• The RCS is is saturated.

• Two ECCs and 3 ECFs are operating.

performing EOP-E-O, While performing EOP-E-0, containment isolation signals were reset as directed by .

All Attachment 3 actions were completed before transitioning from EOP-E-O.EOP-E-0.

After the transition to EOP-E-1, the LOCA break size increased and containment pressure increased to 24 psig.

Based upon the above conditions which ONE of the following describes the status of the containment isolation signals?

A. Only Phase A containment isolation has occurred and has been reset.

B. Only Phase B containment isolation has occurred and has been reset.

C. Both Phase A and Phase B B containment isolations have automatically actuated but neither Phase A or Phase B B containment isolations have been reset.

D. Both Phase A and Phase B B containment isolations have automatically actuated and only Phase A has been reset.

107 107

NRC DRAFT 07/24/07 07/24/07 Q #54 Q#54 ANSWER:

ANSWER: D D

KA:

KA: 103K4.06 103K4.06 Knowledge of the Ctmt Knowledge Ctmt design feature(s) and/or interlock(s) which provide for isolation system 3.1/3.7 containment isolation IOCFR55:

10CFR55: 41.b.7, 41.b.9 41.b.7,41.b.9

Reference:

5610-T-L11 Sheet 11 5610-T-L 3-EOP-E-0, Attachment 3, Step 12 Cog Level: 3 Analysis Level 3 because the operator must recognize that a manual SI does not actuate Phase A. He then must analyze the plant condition to determine that an automatic SI has occurred and that this will actuate a Phase A. He then must remember that E-0 attachment 3 resets both SI and Phase A & B if actuated (Phase B was not the E-O at the time of attachment 3). If containment pressure increases above 20 psig, a Phase B isolation signal will still be generated even with the Phase A reset.

New Question Response Analysis:

A. Incorrect because the pressure increasing above 20 psig 9 will cause aa Phase psi B even after the SI and other actuation signals were reset in E-O.

B E-0. Plausible because the Phase A signal was reset in attachment 3.

B. Incorrect because the plant conditions would result in an automatic SI signal even after the manual SI was actuated. This would result in aa Phase A signal as well. Plausible because the attch 33 does reset Phase BB if it had actuated at that time.

C.

C. Incorrect Incorrect because both phase phase A and BB have have actuated. Plausible because because the operator could assume that another signal above 20 psig would actuate Phase A again therefore it would not be reset.

D.

D. Correct per the reference Correct 108 108

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q#55 0#55 AA S/G SIC tube tube rupture rupture occurred occurred on on Unit Unit 3.

3.

All safety All safety systems systems functioned functioned as as designed designed including including Phase Phase AA Containment Containment Isolation.

Isolation.

Which ONE Which ONE ofof the the following following describes describes an an effect effect of of Phase Phase AA on on the the containment containment and and actions operators actions operators will will take take to respond to to respond to the the Phase Phase AA signal?

signal?

A.

A. Instrument Air Instrument Air to to Containment Containment has has been been isolated.

isolated.

Operators will Operators will reset reset Phase Phase AA when when directed directed by by 3-EOP-E-O, Attachment 3, 3-EOP-E-O, Attachment 3, Prompt Action "Prompt Action Verifications".

Verifications.

B.

B. CVCS letdown CVCS letdown from containment containment has has been been isolated.

isolated.

Operators will reset Operators reset Phase Phase A A when directed directed by by 3-EOP-E-O, 3-EOP-E-O, Attachment Attachment 3, Prompt "Prompt Action Verifications .

Verifications".

C. CCW valves to the RCPs in containment have been closed.

Operators will reset Phase A after initiating a controlled cooldown while performing 3-EOP-E-3.

D. Normal Containment Coolers have been tripped.

Operators will reset Phase A after initiating a controlled cooldown while 3.-EOP-E-3.

performing 3-EOP-E-3.

109 109

NRC DRAFT 07/24/07 Q #55 Q#55 ANSWER: B KA: 103A2.03 Ability to (a) predict the impacts of the following malfunctions or operations on the Ctmt; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Phase A & &B Isolation. 3.5/3.8 IOCFR55:

10CFR55: 41.b.7

Reference:

3-EOP-E-O, Attachment 3, Step 13 3-EOP-E-3, Steps 13 and 19 5613-M-3047, Sheet I 5613-M-3047,Sheet1 Cog Level: 1 Recall 1

New Question Response Analysis:

A. Incorrect because Instrument Air has not been isolated. Plausible because operators will reset Phase A when directed by 3-EOP-E-O, Attachment 3.

B. Correct per the references. Letdown isolates and operators will reset Phase A when directed by 3-EOP-E-O, Attachment 3 C. Incorrect because CCW valves to the RCPs in containment have not been closed and operators will reset Phase A when directed by 3-EOP-E-O, Attachment 3. Plausible because CCW valves are closed upon Phase Band B and E-3 does contain a step to reset Phase A.

D. Incorrect because operators will reset Phase A when directed by 3-EOP-E-O, Attachment 3. Plausible because Normal Containment Coolers have been tripped 110 110

NRC DRAFT 07/24/07 Q #56 0#56 Unit 4 is at 100% power at the beginning of core life with:

• D-230.

Control Rods are at 0-230.

• Rod control is in automatic Control Rod H-8 drops into the core:

core

• All automatic control systems responded as designed

• Tavg stabilizes rF7°F below Tref.

Which ONE of the following describes the effect of this event on the CVCS system after RCS parameters have stabilized?

A. Low Pressure Letdown Control valve, PCV-3-145, is throttled closed resulting in lower VCT level B. Low Pressure Letdown Control valve, PCV-3-145, is throttled open resulting in higher VCT level.

C. The CVCS demineralizers have absorbed boron resulting in a positive reactivity insertion.

D.

O. The CVCS demineralizers have released boron resulting in a negative reactivity insertion.

III 111

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q #56 Q#56 ANSWER:

ANSWER: CC KA:

KA: 001 K3.01 001 K3.01 Knowledge of Knowledge the effect of the effect that that aa loss loss or or malfunction malfunction of of the the CROS CRDS will will have have onon the the CVCS. 2.9/3.0 CVCS. 2.9/3.0 IOCFR55:

10CFR55: 41.b.1, 41.b.5

Reference:

3-OP-047, Step 4.10 3-0P-047, SD 013, Page 10 SO 10 Cog Level: 2 Comprehension Level 2 because the operator will have to analyze that the change in Tavg will result in lowering letdown temperatures. Cooler water through the CVCS demineralizers will result in increased absorption of boron in the demineralizers, resulting in lower boron concentration in the VCT and a subsequent positive reactivity insertion.

New Question Response Analysis:

A. Incorrect because PCV-145 responds to letdown header pressure downstream of the letdown orifices. While RCS pressure and letdown header pressure may temporarily respond to this RCS temperature change

. the control systems will soon restore these pressures to their normal values.

Plausible because if PCV-3-145 throttled closed, it would result in lower VCT level.

B. Incorrect because PCV-145 responds to letdown header pressure downstream of the letdown orifices. While RCS pressure and letdown header pressure may temporarily respond to this RCS temperature change the control systems will soon restore these pressures to their normal values.

Plausible because if PCV-3-1 PCV-3-145 45 throttled open, it would result in higher VCT level.

C. Correct per the reference D.

O. Incorrect Incorrect because the CVCS demineralizers will absorb more boron resulting in aa positive reactivity insertion. Plausible because ifif the CVCS demineralizers released boron itit would result in resulting in aa negative reactivity insertion.

insertion.

112 112

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q #57 0#57 Unit 44 reactor Unit reactor is is at at 100%

100% power power when when 4A4A RCP RCP rotor rotor seizes.

seizes. The The 4A 4A RCP RCP stops stops rotating instantly.

rotating instantly.

Which ONEONE ofof the the following following describes describes the initial effect the initial effect of of this this event event on on the the Reactor Reactor Coolant System?

Coolant System?

A.

A. Pressurizer level Pressurizer level and pressure will decrease.

DNBR will decrease and Clad Temperature Limits will NOT DNBR NOT be exceeded.

Fuel rod failure will not occur.

B. Pressurizer level and pressure will decrease.

The DNBR will decrease and Clad Temperature Limits will be exceeded.

Fuel rod failure may occur.

C. Pressurizer level and pressure will increase.

DNBR will decrease and Clad Temperature Limits will be exceeded.

Fuel rod failure may occur.

D. Pressurizer level and pressure will increase.

DNBR will decrease and Clad Temperature Limits will NOT be exceeded.

Fuel rod failure will NOT occur.

113 113

NRC DRAFT 07124/07 07/24/07 Q #57 Q#57 ANSWER:

ANSWER: C C

KA:

KA: 002K6.02 002K6.02 Knowledge of Knowledge the effect of the effect of of aa loss loss or or malfunction malfunction of of the the following following RCS RCS components:

components:

RCP, 3.6/3.8 RCP, 3.6/3.8 IOCFR55:

10CFR55: 41.b.14 41.b.2, 41.b.3, 41.b.14

Reference:

14.1.9 FSAR Section 14.1.9 Cog Level: 2 Comprehension Level 2 because the operator must relate the type of RCP failure to the effects on the RCS parameters. He then must analyze how the changing parameters relate to DNBR and determine that even though RCS pressure is increasing, the reduction in core flow causes DNB to occur and then understand the affect of DNB on the fuel rods.

New Question Response Analysis:

A. Incorrect because pressurizer level and pressure will increase. Plausible because Total core cooling flow will decrease and the DNB Ratio will decrease and core damage will occur.

B. Incorrect because pressurizer level and pressure will increase. Total core cooling flow will decrease and core damage will occur.

C. Correct per the references D. Incorrect because DNB limits will be exceeded and core damage will occur.

114 114

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q #58 Q#58 Operators are Operators are performing performing aa startup startup on on Unit Unit 33 and and power power isis 5%5% with with all all pressurizer pressurizer controls in automatic controls in automatic whenwhen the the controlling controlling pressurizer pressurizer levellevel transmitter, transmitter, LLT-3-459A, T 459A, fails LOW.

fails LOW.

Which ONE Which ONE of of the the following following describes describes the the effect effect ofof this this failure assuming NO failure assuming NO operator action?

operator action?

Pressurizer level Pressurizer level will will continuously:

continuously:

A. decrease.

decrease.

Letdown isolation Letdown isolation will occur occur pressurizer pressurizer level level reaches reaches setpoint.

B. decrease.

The reactor will trip on low pressurizer pressure when setpoint is reached.

c.

C. increase.

The reactor will trip on high pressurizer level when setpoint is reached.

D. increase.

Pressurizer PORV(s) will open when setpoint is reached.

115 115

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q#58 Q#58 ANSWER:

ANSWER: 0D KA:

KA: OIIA1.O1 011A1.01 to predict Ability to and/or monitor predict and/or monitor changes changes inin parameters parameters (to (to prevent prevent exceeding exceeding design limits) design limits) associated associated with with operating operating the the PRZ PRZ LCS LCS controls controls including including PRZ PRZ level level and pressure.

and pressure. 3.5/3.6 100FR55:

10CFR55: 41.b.3, 41.b.5

Reference:

5610-T-D -15 15 Sheet 1I 5610-T-D-16B Sheet 5610-T-D-16B Sheet 11 Cognitive Level: 3 Application / Analysis Level 3 because the operator must first recognize that the LLT-459A T-459A signal feeds back to the control loop. When LLT-459A T-459A indicates level is too low, the control loop will send a signal to charging pumps to speed up. Additionally the L T-459A failure LT-459A causes letdown isolation. This combination results in rising pressurizer level. If power were above P-7 (10%), the reactor would trip at 92% level. At 5% power, the 92% level trip is not enabled. Level will continue to rise, eventually covering the spray nozzles and taking the RCS water solid. Pressure will rise and PORVs will open at 2335 psig.

New Question Response Analysis:

A. Incorrect because pressurizer level will continuously increase. Plausible because pressurizer level would decrease if L T-459A failed high instead of LT-459A low and letdown isolation does normally occur at 14%.

B. Incorrect because pressurizer level will continuously increase. Plausible because pressurizer level would decrease if L T-459A failed high instead of LT-459A low and .the the reactor would normally trip on low pressurizer pressure when the pressurizer empties.

C. Incorrect because the reactor will not trip on high pressurizer level at this power level. Plausible because pressurizer level will continuously increase.

increase.

D. Correct per the references 116 116

NRC DRAFT NRC DRAFT 07124/07 07/24/07 Q #59 0#59 Operators are Operators performing aa plant are performing plant start start up up on on Unit Unit 3.3.

Reactor power Reactor power is is 15%.

15%.

Which ONE Which ONE ofof the following describes the following describes thethe direct direct effect effect of of depressing depressing the the Source Range Less "Source Range Less than than P-6 Push to P-6 Push to Reinstate" Reinstate pushbutton?

pushbutton?

The NIS source The NIS source ranges ranges will:

will:

A. reinstate causing reinstate causing aa SR SR Hi Flux reactor Hi Flux reactor trip.

trip.

B. reinstate but a SR Hi Flux reactor trip will NOT occur.

c.

C. NOT reinstate and a SR Hi Flux reactor trip will NOT occur.

D. NOT reinstate until power is reduced below 10% when the SRs will automatically trip the reactor.

117 117

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q#59 Q#59 ANSWER:

ANSWER: CC KA:

KA: 015A4.03 015A4.03 Ability to Ability to manually manually operate operate and/or and/or monitor monitor in in the the control control room:

room: trip trip bypasses.

bypasses.

3.8/3.9 3.8/3.9 10CFR55:

10CFR55: 41.b.7 41.b.7

Reference:

5610-T-L1 5610-T Sheet 16

-L 1 Sheet 16 Cog Level:

Cog Level: Comprehension 2 Comprehension Level 2 because the operator must recognize that when power is >10%, the P-10 P-i 0 permissive is enabled and sends a block signal to both the reinstatement reinstatement of the source ranges and to the source range trip signal. Also, pushing the re-instate pushbuttons does not affect the future automatic operation of the detectors as there is no seal in for these pushbuttons.

New Question Response Analysis:

A. Incorrect because the NIS source ranges will not reinstate and reactor trip will not occur. Plausible because if power was below P-1 P-i 0, this is the action that would occur.

B. Incorrect because the NIS source ranges will not reinstate. Plausible because reactor trip will not occur.

C. Correct per the references D.

D. Incorrect because the source source ranges will notnot automatically reinstate and trip the reactor when when power drops drops below 10%.

10%. Plausible Plausible because the SRs will not not reinstate immediately but but will reinstate (without trip) when power subsequently drops drops below below P-6.

P-6.

118 118

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q #60 Q#60 Unit 33 core Unit core off-load off-load isis in in progress progress when when the the refueling refueling SROSRO inside inside containment containment reports aa spent reports spent fuel element has fuel element has dropped dropped andand aa large large amount amount ofof gas gas bubbles bubbles areare originating from the damaged originating from the damaged element. element.

Which ONE Which ONE ofof the the following following describes describes anan expected expected plant response and plant response and the the required operator required operator response?

response?

A.

A. Only Containment Only Containment Ventilation Ventilation Isolation Isolation should should automatically automatically occur.

occur.

Manually initiate Control Manually initiate Control Room Room Ventilation Isolation Isolation and verify the isolation isolation alignments as alignments directed by as directed by 3-0NOP-033.3, 3-ONOP-033.3, "Accidents Accidents Involving Involving NewNew oror Spent FueL" Spent Fuel.

B. Control Room Only Control Room Ventilation Isolation should automatically occur.

Manually initiate Containment Ventilation Isolation Isolation and verify the isolation 3-ONOP-033.3, "Accidents alignments as directed by 3-0NOP-033.3, Accidents Involving New or Spent FueL" Fuel. .

C. Neither Containment nor Control Room Ventilation Isolation should automatically occur.

Manually initiate both and verify the isolation alignments as directed by 3-ONOP-033.3, "Accidents ONOP-033.3, Accidents Involving New or Spent FueL" Fuel.

D. Both Containment and Control Room Ventilation Isolation should automatically occur.

Verify the isolation alignments as directed by 3-0NOP-033.3, 3-ONOP-033.3, "Accidents Accidents Involving New or Spent FueL" Fuel. .

119 119

NRC DRAFT 07/24/07 07/24/07 Q #60 Q#60 ANSWER:

ANSWER: 0D KA:

KA: 034A2.01 034A2.01 Ability to Ability to (a) predict the (a) predict the impacts impacts of of the the following following malfunctions malfunctions or or operations operations on on the the fuel handling handling system; system; andand (b)

(b) based based on on those those predictions, predictions, use use procedures procedures to to correct, control, correct, control, or or mitigate mitigate the the consequences consequences of of those malfunctions malfunctions or or operations:

operations:

dropped fuel element.

dropped element. 3.6/4.4 3.6/4.4 IOCFR55:

10CFR55: 41.b.9, 41.b.10, 41.b.11, 41.b.12

Reference:

561 0-T-L11 Sheet 11 5610-T-L 11 3-ONOP-033.3, Steps 2.2, 4.3, 5.1.1.1 3-0NOP-033.3, 5.1 .1.1 Cog Level: 2 Comprehension The SRO should recognize that bubbles from a dropped assembly are an indication the cladding has been breached. Along with the nitrogen gas bubbles will be gaseous fission products so that when detected by the containment gas monitor, an automatic isolation signal will be generated. He then must recognize that when moving fuel, containment integrity is set and that both the control room and the containment ventilation system isolate on high PRMS signals.

New Question Response Analysis:

A. Incorrect because both containment and control room ventilation Isolation has automatically occurred. Plausible because containment ventilation Isolation should automatically occur and control room ventilation isolation can be manually initiated.

B. Incorrect because both containment and control room ventilation Isolation has automatically occurred. Plausible because control room ventilation Isolation should automatically occur and containment ventilation isolation can be manually initiated.

C. Incorrect because both containment and control room ventilation Isolation has automatically occurred. Plausible because control room ventilation Isolation and containment ventilation isolation can be manually initiated.

D. Correct perper the references 120 120

NRC DRAFT NRC DRAFT 07124/07 07/24/07 QQ#61

1. 61 Unit in Mode Unit 44 isis in Mode 33 with with the MSIVs closed the MSIVs closed as as operators operators commence commence aa reactor reactor start start up.

up.

4A main 4A main steamsteam line line safety safety valve, valve, "RV-4-1400",

RV-4-1 400, fails fails open open and and the the 4A 4A S/G S/G rapidly rapidly depressurizes depressurizes. .

Which ONE Which ONE of of the following describes the following describes the the response response of of the safeguards system the safeguards system to to this failure?

this failure?

Safety injection Safety injection will:

A. NOT actuate with the MSIVs NOT MSIV5 closed.

B.

B. actuate when Tavg decreases to 543°F. 543°F.

c.

C. actuate when the 4A S/G SIG pressure decreases to 485 psig.

D. actuate when the 4A S/G SIG pressure decreases to 900 psig.

121 121

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q #61 Q #61 ANSWER:

ANSWER: C C

KA:

KA: 035K1.14 035K1.14 Knowledge of Knowledge the physical of the physical connection connection and/or and/or cause-effect cause-effect relationships relationships between between the SIG and the ESF.

the S/G and the ESF. 3.9/4.1 3.9/4.1 10CFR55:

10CFR55: 41.b.7, 41.b.8 41.b.7,41.b.8

Reference:

5610-T-L11 Sheet 19 5610-T-L 5610-T-D-18B 561 0-T-O-18B Sheet 1I Cog Level: 3 Analysis Level 3 because the operator must recognize that when a S/G depressurizes, SI usually results due to high steam line ~P.AP. However with the MSIVs closed the 100 psid differential pressure that normally triggers this SI signal can't cant be generated because the main steam lines would be depressurized. That's Thats why the main steam header pressure inputs have been nulled at 585 psig so that even with the MSIVs closed, when any S/G'sSIGs pressure drops to 485 psig, the 100 psid SI actuation logic is made up.

New Question Response Analysis:

A. Incorrect because SI will actuate when the 4A S/G pressure decreases to 485 psig. Plausible because with the MSIVs closed, the header differential pressure cannot reach the 100 psid normally needed to actuate SI.

B. Incorrect because SI will actuate when the 4A S/C S/G pressure decreases to 485 psig. Plausible because 543°543°FF is an SI setpoint that when reached will make up part of SI logic.

C. Correct per the references D.

O. Incorrect because SI will actuate when the 4A S/G pressure decreases to 485 psig. Plausible because 900 psig would result in 100 100 psid at hot zero power that is an actuation signal if the MSIVs MSIVs were open.

open.

122 122

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q #62 0#62 3-EOP-E-3, "Steam 3-EOP-E-3, Steam Generator Generator Tube Tube Rupture,"

Rupture, directs directs operators operators to to use use the the Steam Steam Dump to Dump Condenser system to Condenser system to initiate aa cooldown to initiate cooldown atat maximum maximum rate rate prior to RCS prior to RCS depressurizat ion.

depressurization.

Which ONE Which ONE of of the the following following describes describes how how the the Reactor Reactor Operator Operator will will accomplish accomplish this cooldown this cooldown using using the the Steam Steam Dump Dump to to Condenser Condenser system?

system?

Place the

. Place the Mode Selector Switch Mode Selector Switch in:

in:

A. Bypass the AUTO. Bypass the low low Tavg interlock.

interlock. Place Place the Hagan Hagan controller in in MANUAL and MANUAL and use use the the UP UP arrow arrow to to open the steam open the steam dump valves.

dump valves.

B. AUTO. Place the Hagan controller in AUTO and adjust the pot setting setting to the desired setpoint to open the steam dump valves.

C. MANUAL. Bypass the low Tavg interlock. Place the Hagan controller in MANUAL and use the UP arrow to open the steam dump valves.

D. MANUAL. Place the Hagan controller in AUTO and adjust the pot setting to the desired setpoint to open the steam dump valves.

123 123

NRC DRAFT 07/24/07 07/24/07 Q #62 Q#62 ANSWER:

ANSWER: CC KA:

KA: 041G2.I .28 041G2.1 .28 As it relates to the SO SD Sys: Knowledge of the purpose and function of major major system components and components and controls.

controls. 3.2/3.3 3.2/3.3 IOCFR55:

10CFR55: 41.b.4, 41.b.7 41.bA,41.b.7

Reference:

3-EOP-E-3, Step 19 19 SD-I 05 Page 17 SO-105 17 Cog Level: Comprehension 2 Comprehension Level 2 because the operator must understand all the operating modes of the Hagan controller and EOP-E-3, Step 19 does not provide specific guidance regarding how to use the SOTCSDTC system to achieve the desired results. As stated in the correct response, this is a several step process and requires the operator to determine how the controller responds in various modes of operation, this particular evolution requires the controller to be in both the manual mode and manual control (manual-manual mode). The operator must also of the hagan process output (manual-manual understand that this action would result in the SOTC SDTC valves closing if he did not also bypass the low Tavg interlock.

New Question Response Analysis:

A. Incorrect because the Mode Selector Switch will be placed in MANUAL.

Plausible because the Hagan controller will be placed in MANUAL and the UP arrow will be used to open the steam dump valves.

B. Incorrect because the Mode Selector Switch will be placed in MANUAL and the Hagan controller will be place in MANUAL. Plausible because placing the Hagan controller in AUTO and adjusting the pot setting would open the steam dump valves if the Mode Selector Switch were placed in MANUAL.

MANUAL.

C. Correct per the references D.

O. Incorrect Incorrect because the Hagan Hagan controller will be place in be place in MANUAL.

MANUAL. Plausible Plausible because the Mode Mode Selector Switch be placed Switch will be in MANUAL placed in MANUAL 124 124

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q #63 0#63 Unit 33 isis at Unit at 100%

100% power power when when thethe steam steam jet jet air air ejector ejector common common steam steam supply supply valve, valve, 3-30-020, isis inadvertently 3-30-020, inadvertently closed.

closed.

Which ONE Which ONE ofof the the following following describes describes the the effect of closing effect of closing valve valve 3-30-020?

3-30-020?

Assume no Assume no other other operator operator action action occurs.

occurs.

A.

A. Condenser vacuum Condenser vacuum willwill decrease.

decrease.

The turbine will trip The trip when condenser condenser vacuum reaches reaches 25" 25 Hg.

Hg.

B.

B. Condenser vacuum Condenser vacuum willwill decrease.

decrease.

The turbine will trip when condenser vacuum reaches 20" 20 Hg.

C. Main generator megawatts Main megawatts will decrease.

The reactor will trip when the OP~T OPAT setpoint is reached.

D. Main generator megawatts will decrease.

The reactor will trip when the turbine trips due to high vibration.

125 125

NRC DRAFTDRAFT 07124/07 07/24/07 Q #63 Q#63 ANSWER:

ANSWER: BB KA:

KA: 055K3.O1 055K3.01 Knowledge of Knowledge of the effect effect that aa loss loss or or malfunction malfunction of of the the CARS CARS will will have have onon the the main condenser.

main condenser. 2.5/2.7 2.5/2.7 IOCFR55:

10CFR55: 41.b.5, 41.b.7 41.b.5,41.b.7

Reference:

5613-M-3014, Sheet 3 3-ONOP-014, Step 3.1, 5.5.2 3-0NOP-014, Cog Level: 1I fundamental knowledge New Question Response Analysis:

A. Incorrect because the turbine will trip when condenser vacuum reaches 20" 20 Hg. Plausible because condenser vacuum will decrease B. Correct per the references C. Incorrect because turbine efficiency will decrease if the operator assumes reactor power would have to increase to maintain the same output.

D. Incorrect because there is no high vibration trip on the turbine.

126 126

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q #64 0#64 Unit 33 isis at Unit at 75% power when 75% power when the the following following occurs; occurs;

• • annunciator D annunciator D 5/3, 5/3, SGFP SGFP AA SUCTION SUCTION LO LO PRESS, PRESS, alarms alarms

• • annunciator D 7/4, LP HEATER annunciator D 7/4, LP HEATER BYPASS OPEN BYPASS OPEN alarms alarms

• • CV-3-201 1 indicates CV-3-2011 indicates open open

• • aa turbine turbine runback runback isis NOT NOT in in progress progress Which ONE Which ONE of the following of the following correctly correctly describes describes the the first first operator operator response?

response?

A.

A. Close CV-3-2011 Close CV-3-201 1 ifif SGFP SGFP suction suction pressure pressure is is greater greater than 220 220 psig.

psig.

B.

B. Reduce turbine load to restore SGFP suction pressure pressure to greater than psig.

220 psig.

C. Start th'e the standby Condensate Pump to restore SGFP suction pressure to greater than 220 psig.

D. Stop the 3A SGFP to start the runback as it should have tripped when the SGFP A SUCTION LO PRESS annunciator actuated.

127 127

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q #64 Q#64 ANSWER:

ANSWER: CC KA:

KA: 056G2.4.50 056G2.4.50 As itit relates As relates to to the condensate system:

the condensate system: Ability Ability to verify system to verify system alarm alarm setpoints setpoints and and operate controls identified in the alarm response manual.

operate cont.rols identified in the alarm response manual. 3.3/3.3 3.3/3.3 IOCFR55:

10CFR55: 41.b.4 41.b.4

Reference:

3-ARP-097.CR, D 3-ARP-097.CR, D 7/4 7/4 Step Step 11 &

& 3.b.

3.b.

3-ARP097.CR, D 3-ARP-097.CR, D 5/3 Step Step 2 && 3.a.

3.a.

Cog Level: 1I Recall New Question New Response Analysis:

A. Incorrect because the ARP directs operators to start the standby Condensate Pump to restore SGFP suction pressure to > > 220 psig.

CV-201 1 would help to restore SGFP suction Plausible because closing CV-2011 pressure.

B. Incorrect because the ARP directs operators to start the standby Condensate Pump to restore SGFP suction pressure to > 220 psig.

Plausible because reducing turbine load would help to restore SGFP suction pressure.

C. Correct per the references D. Incorrect because the ARP directs operators to start the standby Condensate Pump to restore SGFP suction pressure to to>

> 220 psig.

Plausible because stopping the 3A SGFP would help to restore 3B SGFP suction pressure.

128 128

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q #65 0#65 Chemistry has Chemistry has reported reported that that the concentration of the concentration of oxygen oxygen in in the the in-service in-service gas gas decay decay tank isis 4.2%

tank and the 4.2% and the hydrogen hydrogen concentration concentration is is 4.8%.

4.8%.

Which ONE Which ONE of of the following describes the following describes the correct operator the correct operator response?

response?

Stop addition of Stop addition waste gas of waste gas to the gas to the decay tank gas decay tank and and reduce reduce the:

the:

A.

A. oxygen concentration oxygen concentration to to << 4%

4% as as soon soon as as possible.

possible.

B. hydrogen concentration to <<4% possible.

4% as soon as possible.

C. oxygen concentration to << 4% within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

D. hydrogen concentration to <<4% 4% within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

129 129

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q#65 Q#65 ANSWER:

ANSWER: A A KA:

KA: 071 K5.04 071 K5.04 Knowledge of Knowledge of the the operational operational implications implications of of the the following following concept concept as as itit applies applies to to the WGD system: relationship the WGD system: relationship of of H2/02 H2/02 concentrations concentrations to to flammability.

flammability. 2.5/3.1 2.5/3.1 10CFR55:

10CFR55: 41.b.10, 13 41.b.10,13

Reference:

0-ONOP-061, NOTE 0-ONOP-061, NOTE prior prior to to Step Step 55 Cog Level:

Cog Level: 1I Recall Recall New Question New Response Analysis:

A. Correct per the reference.

B. Incorrect because ONOP-061 directs operators to reduce the oxygen concentration to < < 4% as soon as possible. Plausible because with concentrations of both gases>

concentrations gases > 4%, ONOP-061 directs operators to stop addition of waste gas to the gas decay tank.

C. Incorrect because ONOP-061 directs operators to reduce the oxygen concentration to << 4% as soon as possible. Plausible because with oxygen concentration > 2%, ONOP-061 directs operators to reduce the oxygen concentration>

concentration within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

D. Incorrect because ONOP-061 directs operators to reduce the oxygen concentration to << 4% as soon as possible. Plausible because with concentration concentrations s of both gases gases> > 4%, ONOP-061 directs operators to stop addition of waste gas to the gas decay tank.

130 130

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q #66 0#66

• • Unit 33 isis at Unit at 90% power.

90% power.

• • Tavg 630°F Tavg = 630°F

• • RCS pressure RCS pressure is is 2235 2235 psig psig Which ONE Which ONE of of the the following following describes describes the the required required operator operator response?

response?

A.

A. Place the Place the unit unit in Mode 33 within in Mode within 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />.

hour.

B. Reduce Tavg to less than 625°F within 15 Reduce 15 minutes.

C.

C. Reduce power Reduce power to less less than 75%

75% within 1515 minutes minutes D. Reduce RCS pressure pressure to less than 2235 psig within 5 minutes.

REFERENCE PROVIDED PROVIDED 131 131

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q #66 Q#66 ANSWER:

ANSWER: AA KA:

KA: G.2.1.11 G.2.1.11 Knowledge of Knowledge of less than one less than one hour hour technical technical specification specification action action statements statements for for systems. 3.0/3.8 systems. 3.0/3.8 10CFR55:

10CFR55: 41.b.5 41.b.5

Reference:

TS 2.1.1 TS 2.1.1 TS Figure TS Figure 2.1-1 2.1-1 Provide as reference:

Provide reference: Tech Spec Figure Figure 2.1-1 Cog Level: 11 Recall New Question Response Analysis:

A. Correct per the reference.

B. Incorrect because the TS required response is to shutdown within 1 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

Plausible because reducing Tavg to less than 625°F 625° F would restore conditions to within the acceptable operating region and because there are other short term Tech Specs that require aa 15 15 minute response.

C. Incorrect because the TS required response is is to shutdown shutdown within 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />.hour.

Plausible because reducing power to less than 75% would restore conditions to within the acceptable operating region and because there are other short term term Tech Tech Specs Specs that that require require aa 15 15 minute minute response.

response.

D.

D. Incorrect Incorrect because because the the TS TS required required response response isis to to shutdown shutdown within within 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />.

hour.

Plausible Plausible because because reducing reducing pressure pressure within 55 minutes minutes is is aa required action action ifif the the other other PTN PTN Safety Safety Limit Limit (press (press >2735

>2735 psig) psig) isis violated.

violated.

132 132

NRC DRAFT NRC DRAFT 07124/07 07/24/07 Q #67 Q#67 Operators have Operators have evacuated evacuated the Control Room.

the Control Room.

The Unit The Unit 33 RORO isis performing performing Attachment Attachment 33 ofof 0-ONOP-1 0-ONOP-1 05, 05, "Control Control Room Room Evacuation and Evacuation" and has determined that has determined that RCS RCS boration boration isis required.

required.

Which ONE Which ONE of of the following describes the following describes the the correct correct orders orders the the RO RO should should give give the the SNPO to SNPO to successfully successfully borate borate the the RCS?

RCS?

Locally open "Locally open the:

the:

A.

A. Emergency Boration Emergency Boration Valve, Valve, MOV-3-350.

MOV-3-350. After After II start start the the 3C 3C Charging Charging pump, II will direct youyou to increase the 3C Charging pump pump speed controller setpoint to setpoint to 66 psig."

psig.

B. Emergency Boration Valve, MOV-3-350. After I start the 3B Charging pump, I will direct you to increase the 3B Charging pump speed controller setpoint psig.

to 12 psig."

C. Manual Boration Valve, 3-356. After II start the 3B Charging pump, II will direct you to increase the 3B Charging pump speed controller setpoint to 6 psig.

psig."

D. Manual Boration Valve, 3-356. After II start the 3C Charging pump, II will direct you to increase the 3C Charging pump speed controller setpointto setpoint to 12 psig.

psig."

133 133

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q #67 Q#67 ANSWER:

ANSWER: BB KA:

KA: G.2.1.8 G.2.1.8 Conduct of Conduct of Operations:

Operations: Ability Ability to coordinate personnel to coordinate personnel activities activities outside outside the the control control room. 3.8/3.6 room. 3.8/3.6 IOCFR55:

10CFR55: 41.b.7, 41.b.10 41.b.7, 41.b.1O

Reference:

O-ONOP-105, Attachment 0-ONOP-105, Attachment 3, 3, Page Page 65,65, Step Step 23 23 Cognitive Level:

Level: 1I Recall Recall New Question Response Analysis:

A. Incorrect because the 3C Charging pump is the wrong pump (it will have no power) and the SNPO should increase the Charging pump speed controller setpoint to 12 psig. Plausible because MOV-350 is the correct valve to open and 6 psig is the initial charging pump controller setting.

B. Correct per the references C. Incorrect because valve 3-356 is the wrong valve and the SNPO should increase the Charging pump speed controller setpoint to 12 12 psig.. Plausible because 3-356 is aa manual emergency boration valve used for boration under different circumstance circumstances s and 66 psig is the initial charging pump controller setting and 3B Charging pump is the correct pump. pump.

D.

D. Incorrect Incorrect because valve 3-356 is is the wrong valve and and the 3C3C Charging pump pump is is the wrong pump pump (it (it will have have no no power) Plausible Plausible because because 3-356 3-356 isis aa manual manual emergency emergency boration boration valve valve used used for boration boration under under different different circumstance circumstances s and and because because 12 12 psig psig isis the the correct correct charging charging pump pump controller controller setting.

setting.

134 134

NRCDRAFT NRC DRAFT 07/24/07 07/24/07 Q #68 0#68 WhichONE Which ONEof ofthe thefollowing followingisisan anaccurate accuratecomparison comparisonofofthe theUnitUnit33SFPSFP radiolo gical monitoring radiological monitoring system system totothe the Unit Unit44SFP SEP radiological radiological monitoring monitoring system?

system?

AAgaseous gaseous radioactive radioactive release releasefrom:

from:

A.

A. both SFPs both SEPs areare monitored monitored by bytheir theirown own separate separate Unit Unit 33 and and Unit Unit 44 SFP SEP SPING detecto rs located in each SEP SPING detectors located in each SFP vent duct. vent duct.

B.

B. both SFPs both SEPs areare monitored monitored by by aa common common SFPSEP SPING SPING located located inin the the SFP SEP comm on vent common vent duct. duct.

C.

C. Unit 33 SFP Unit SEP isis monitored monitored by by the the plant plant vent vent monitor monitor while while Unit Unit 44 SFP SFP isis monitored by monitored by aa separate separate U4U4 SFP SEP SPING.

SPING.

D.

D. Unit 44 SFP Unit SFP is monitored by is monitored the plant by the plant vent vent monitor monitor while while thethe Unit Unit 33 SFP SEP isis monito red by a separa te U3 SEP monitored by a separate U3 SFP SPING.. SPING 135 135

NRC DRAFT NRC DRAFT 07124/07 07/24/07 Q #68 Q#68 ANSWER:

ANSWER: D D

KA:

KA: G.2.2.4 G.2.2.4 Ability to Ability to explain explain the the variations variations in in control control board board layouts, layouts, systems, systems, instrumentation instrumentation and procedural actions between units and procedural actions between units at at aa facility. 2.8/3.0 2.8/3.0 100FR55:

10CFR55: 41.b.11

Reference:

SD-041 Page 20, SD-068 Page 33, 5614-M-3034, Sheet 1, 1, 5610-M-3060 Sheet 1, 1, 5613-M-3034 Sheet 1, 1, Cog Level: 11 Recall New Question Response Analysis:

A. Incorrect because a gaseous radioactive release from both SFPs is monitored differently. Plausible because only unit 4 is vented to the plant vent while unit 3 has a SPING detector in its vent duct..

B. Incorrect because a gaseous radioactive release from both SFPs SFP5 is monitored differently. Plausible because only unit 4 is vented to the plant S PING detector in its vent duct..

vent while unit 3 has a SPING C. Incorrect because aa gaseous radioactive release from both SFP5 SFPs is monitored differently. Plausible because only unit 4 is vented to the plant vent while unit 3 has a SPING detector in its vent duct..

D. Correct per the references 136 136

NRCDRAFT NRC DRAFT 07/24/07 07/24/07 Q #69 0#69 WhichONE Which ONEofofthe thefollowing followingtemporary temporaryalterations alterationswouldwould require requireaa"prior priorPNSC PNSC approv ed Tempo approved Temporary rarySystem SystemAlteration Alteration (TSA),,?

(TSA)?

A.

A. lifting of lifting ofaa wire wiretoto perform perform aa troubleshooting troubleshooting procedure procedure on on aa circuit circuit associated with associated with turbine turbine runback runback logic.

logic.

B.

B. addition of addition ofaa jumper jumper inin the the start start circuit circuit of ofthe the 3A 3A HHSI HHSI Pump Pump which which will will remain QOS on an remain OOS on an ECO while ECO while the the jumper jumper isis inin place.

place.

C.

C. addition of addition of aa temporary temporary power power supply supply forfor aa Phase Phase AA Containment Containment Isolation Isolation actuati actuation on circuit circuit until until aa permanent permanent powerpower supply supply can can be be obtained.

obtained.

D.

D. installation of installation of drain drain rigs rigs on on the the pressurizer pressurizer in in preparation preparation for for fill fill and and vent vent following refueli following refueling. ng.

137 137

NRCDRAFT NRC DRAFT 07124/07 07/24/07 Q #69 Q#69 ANSWER:

ANSWER: CC KA:

KA: G.2.2.11 G.2.2.11 Knowledge Knowledge of ofthe the process process for for controlling controlling temporary temporary changes.

changes. 2.5/3.4 2.5/3.4 10CFR55:

10CFR55: 41.b.1O 41.b.10

Reference:

ADM-503, Step ADM-503, Step 5.1.4, 5.1.4, Step Step 5.6.1.1 5.6.1.1 ADM-503, Att.

ADM-503, Att. 1, 1, Page Page 11 Cog Level:

Cog Level: 1I Recall Recall New Question New Question Response Analysis:

Response Analysis:

A.

A. Incorrect because Incorrect because lifting of a wire to perform troubleshooting troubleshooting on a circuit isis specifically excluded from requiring a TSA by ADM-503 ADM5O3 (Ref. Step 4.1.2.5).

4.1.2.5).

because lifting a wire is a temporary alteration.

Plausible because B.

B. because addition of a jumper in a circuit of a component which will Incorrect because will remain OOS on an ECO while the jumper is in place is specifically excluded from requiring a TSA by byADM-503 ADM-503 (Ref. Step 4.1.5.9). Plausible because adding aa jumper to aa circuit is aa temporary alteration.

C. Correct per the references.

D.

D. Incorrect Incorrect becaus becausee installation installation of of drain drain rigs connected to floor drains drains isis specifically excluded specifically excluded from requiring aa TSA TSA by by ADM-503 ADM-503 (Ref.

(Ref. Step Step 4.1.2.1).

4.1.2.1 ).

Plausible Plausible becaus becausee installing installing aa drain drain rig rig is is aa temporary temporary alteration.

alteration.

138 138

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q #70 Q#70 Refueling core Refueling core off-load off-load isis being being conducted conducted onon Unit Unit 3.

3.

The following The following off-load off-load data data has been recorded:

has been recorded:

Time Cumulative ## of Cumulative of fuel fuel elements elements off-loaded off-loaded SFP SEP temperature temperature 0800 0800 o0 138°F 138°F 0900 0900 33 138°F 138°F 1000 1000 99 139°F 139°F 1100 1100 15 15 139°F 139°F 1200 1200 22 22 141°F 141°F 1300 1300 30 142°F 142°F 1400 1400 37 37 14rF 147°F 1500 47 151°F 151°F Which ONE of the following identifies the first time at which the core off-load should have been stopped as required by 3-0P-040.2, 3-OP-040.2, "Refueling Refueling Core Shuffle"?

Shuffle?

A. 1200 B. 1300 C. 1400 D. 1500 1500 139 139

NRC DRAFT NRC DRAFT 07124/07 07/24/07 Q #70 Q#70 ANSWER:

ANSWER: AA KA:

KA: G.2.2.28 G.2.2.28 Knowledge of Knowledge of new new and and spent spent fuel fuel movement movement procedures.

procedures. 2.6/3.5 2.6/3.5 IOCFR55:

10CFR55: 41.b.1, 41.b.11, 41.b.1, 41.b.11, 41.b.13 41.b.13

Reference:

3-OP-040.2, Steps 3-0P-040.2, Steps 4.5 4.5 and and 4.6 4.6 Cog Level:

Cog Level: 11 recall recall New Question New Question Response Analysis:

A. Correct because Correct because the SFP SEP temperature increased to 141°F 141°E at 1200. This exceeds the OP-040.2 limit of 140°F. 140°E.

B. Incorrect because the off-load should have been stopped at 1200. Plausible because the cumulative off-load limit and the instantaneous instantaneous off-load limits have been reached at 1300.

C. Incorrect because the off-load should have been stopped at 1200. Plausible because the cumulative off-load limit has been exceeded at 1400.

D. Incorrect because the off-load should have been stopped at 1200. 1200. Plausible because the instantaneou instantaneous s off-load limit has been exceeded at 1500.

1500.

140 140

NRC DRAFT NRC DRAFT 07/24/07 07/24/07

1. 71 QQ #71 AA plant plant worker worker isis assigned assigned toto work work inin aa radiation radiation field field under under the the following following conditions:

conditions:

• • TheThe job job isis located located 22 meters meters from from aa 1" valve that 1 valve that isis reading reading 60 60 mr/hr mr/hr atat 11 meter meter distance.

distance.

• • Additionally, Additionally, the the job job location location general general area area dose dose rate rate from from other other radiation radiation sources sources is equal is equal to to the the 10CFR20 IOCFR2O minimum minimum dose dose rate rate that that defines defines aa Radiation Radiation Area.

Area.

• • The operator's The operators cumulative cumulative documented documented dose dose for for the the year year is is 940 940 mrem.

mrem.

• • An extension An extension of of the the exposure exposure guidelines guidelines has has NOT NOT been been granted.

granted.

Determine the Determine the number number of hours he of hours he may may work work without without receiving receiving aa dose dose extension?

extension?

A. 1lhr hr B. 22hrs hrs C. 33hrs hrs D. 4hrs 4 hrs 141 141

NRC DRAFT NRC DRAFT 07124/07 07/24/07 Q#71 Q#71 ANSWER:

ANSWER: C C KA:

KA: G.2.3.1 G.2.3.1 Knowledge of Knowledge of 10CFR20 10CFR2O andand related related facility facility radiation radiation control requirements. 2.6/3.0 control requirements. 2.6/3.0 10CFR55:

10CFR55: 41.b.12 41.b.12

Reference:

0-ADM-600, Section 0-ADM-600, Section 5.7.1.4 5.7.1.4 11 OCFR20 OCFR2O - Radiation Radiation Area Definition Definition Cog Level:

Cog Level: 33 Analysis Level 33 because the operator operator must recall the administrative administrative limits limits and then calculate the remaining stay time by by determining the total dose rate. The operator must recognize to use the inverse square law to calculate that the valve reading 60 mr/hr at 11 meter will cause a 15 mr/hr dose rate at the 2 meter work location.

However, the operator must recognize that the general area dose (10CFR20 (10CFR2O dose rate =

= 5 mr/hr minimum for Rad Area) needs to be added as well as the worker is also exposed to this. This will allow 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of stay time before exceeding the 1000 Administrative Limit is 1000 mr/yr without an extension. Operator has mr guideline. Administrative 60 mr remaining exposure.

New Question Response Analysis:

A. Incorrect-pla usible if you improperly calculate the 60 mr/hr at 1 Incorrect-plausible 1 meter remains constant out to 2 meters (plane source calculation).

B. Incorrect-pla usible if you do not account for the inverse square law and only Incorrect-plausible reduce the dose by Y  % (30 mr/hr) instead of 1/4 2  % (a common mistake)

C. Correct Correct - the 15

- 15 mr/hr mr/hr from the valve valve is added to the 55 mr/hr mr/hr general area dose dose rate to have 20 mr/hr mr/hr total resulting inin 33 hours3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br /> of stay time.

D.

D. Incorrect Incorrect because because the dose from the dose the valve from the valve atat 22 meters meters isis 15 15 mr/hr mr/hr but but the the general general area area dose dose rate rate must must bebe added added to it.

to it.

142 142

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q #72 Q#72 Given the Given the following following conditions conditions at work site:

at aa work site:

• • Radiation level Radiation level isis 40 40 mrem/hr mrem/hr

• • Radiation level with shielding Radiation level with shielding isis 10 10 mrem/hr mrem/hr

• • Time for Time for one one worker worker to to place place shielding shielding isis 15 15 minutes minutes

• • Time to conduct the task Time to conduct the task with one with one worker worker isis 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />.

hour.

• • Time to Time to conduct conduct the the task task with with 22 workers workers isis 20 20 minutes.

minutes.

Assumptions:

Assumptions:

• • IfIf shielding shielding is is used, used, itit is is to to be installed by be installed by one one worker worker only.

only.

• • The worker The worker placing placing shielding shielding willwill be be exposed exposed to to aa dose rate of dose rate of 40 40 mr/hr.

mr/hr.

Which ONE of the following would would result in in the lowest lowest total whole body dose?

A. Conduct the task with two workers with shielding.

B. Conduct the task with two workers without shielding C. Conduct the task with one worker with shielding.

D. Conduct the task with one worker without shielding.

143 143

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q #72 Q#72 ANSWER:

ANSWER: AA KA:

KA: G.2.3.2 G.2.3.2 Knowledge of Knowledge offacility facility ALARA ALARA program.

program. 2.5/2.9 2.5/2.9 IOCFR55:

10CFR55: 41 .b.9, 41.b.12, 41.b.9, 41 .b.12, 41.b.13 41 .b.13

Reference:

0-ADM-600, Step 0-ADM-600, Step 5.1.1.2 5.1.1.2 Cognitive Level:

Cognitive Level: 33 Application Application // Analysis Analysis Level 33 because Level because the the operator operator must must recall recall the the ALARA ALARA rulerule which which calls calls for for the the total total collective exposure collective exposure to to be minimized. Then be minimized. Then the the operator operator must must calculate the calculate the collective exposure collective exposure for each each option option and and choose choose thethe alternative alternative with with the the lowest lowest total total collective exposure.

collective exposure.

Bank Question Bank Response Analysis:

A.

A. correct because the total dose would be 10 mr to the worker placing the shielding plus 3.3 mr to each worker resulting in 16.6 total mr.

B. incorrect because each worker receives 13.3 mrfor mr for aa total dose of approximatel approximately y 26.6 mr.

C. incorrect because the worker would receive 20 mrem. (10 mrem while placing the shielding and 10 10 mrwhile mr while performing the work).

D.

D. Incorrect Incorrect because because thisthis would would result inin one one worker worker receiving 40 40 mr.

mr.

144 144

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q #73 0#73 An operator An operator has has volunteered volunteered to to be be aa member member of of an an Emergency Emergency Response Response Team Team that will that will enter enter aa high high radiation radiation area area to rescue aa person to rescue person from from aa non-life non-life threatening threatening situation.

situation.

• • TheThe operator operator has has already already received received 22 REM REM Total Total Effective Effective Dose Dose Equivalent Equivalent (TEDE)

(TEDE) this this year.

year.

• • The dose The dose projection projection forfor each each team team member member forfor this this rescue rescue isis 44 REM REM TEDE.

TEDE.

Which ONE Which ONE of the following of the following isis correct correct regarding regarding this this situation?

situation?

The operator The operator may:may:

A.

A. NOT be NOT be part part of of the rescue rescue team.

IfIf the operator participated, the the operator the additional additional 44 REM REM would exceed the annual I10CFR20 OCFR2O limit but would NOT NOT exceed the allowable allowable exposure exposure limitlimit of Enclosure 11 of O-EPIP-20111, O-EPIP-201 II, "Re-Entry" Re-Entry...

B. NOT be part of the rescue team.

If the operator participated, the additional 4 REM would exceed the annual 100FR2O limit and would exceed the allowable exposure limit of Enclosure 1I 10CFR20 O-EPIP-201 11, "Re-Entry".

of O-EPIP-20111, Re-Entry.

C. be part of the rescue team.

The additional 4 REM will NOT exceed the annual 10CFR20 IOCFR2O limit and will NOT exceed the allowable exposure limit of Enclosure I1 of O-EPIP-201 O-EPIP-20111, 11, Re-Entry.

"Re-Entry" .

D. be part of the rescue team.

The The additional additional 44 REM will will exceed exceed thethe annual 110CFR20 limit but OCFR2O limit but will NOT NOT exceed exceed the allowable exposure exposure limit limit of of Enclosure Enclosure 11 of of O-EPIP-201 O-EPIP-20111, 11, Re-Entry.

"Re-Entry" .

145 145

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q #73 Q#73 ANSWER:

ANSWER: DD KA:

KA: G.2.3.4 G.2.3.4 Knowledge of Knowledge radiation exposure of radiation exposure limits limits and and contamination contamination control, control, including including permis sible levels inin excess permissible levels excess ofof those those authorized.

authorized. 2.5/3.1 2.5/3.1 IOCFR55:

10CFR55: 41.b.12 41.b.12

Reference:

0-EPIP-20111, Step O-EPIP-20111, Step 5.1.1.1, 5.1.1.1, 5.1.1.4, 5.1.1.4, 5.1.1.8, 5.1.1.8, Enclosure Enclosure 11 I OCFR2O.1201 10CFR20.1201 Cog Level:

Cog Level: 1I Recall Recall New Question New Question Response Analysis:

Response

A.

A. Incorrect because Incorrect because the operator operator may be a membermember of the team in spite of 10CFR2O limits. Plausible violating the 10CFR20 Plausible because because the annual 10CFR20 10CFR2O limit will be exceeded exceeded and the EPIP-20111 EPIP-201 11 limit of 10 REM will not be exceeded. exceeded.

B.

B. Incorrect because because the operator operator may be a member member of the team and the additional 4 REM would not violate the EPIP limit of 10 additional 10 REM. Plausible Plausible becaus because e the annual IOCFR2O 10CFR20 limit will be exceedexceeded.

ed.

C.

C. Incorrect becaus because e the 10CFR2O 10CFR20 limits limits will be violated. Plausib Plausible because le becaus e the operato operatorr maymay bebe aa membe member r of of the the team and and the EPIP-201 EPIP-20111 limit of 11 limit of 10 10 REM REM will not not be be violated.

D.

D. Correc Correctt becaus because e the the operato operator r may may bebe aa membe member of the r of the team team inin spite spite of of violating the I OCFR2O violating the 10CFR20 limits. limits. The The EPIP-201 EPIP-20111 limit of 11 limit of 10 10 REM REM will will not not be be violated.

violated.

146 146

NRCDRAFT NRC DRAFT 07/24/07 07/24/07 Q #74 Q#74 Unit44tripped Unit trippedfromfrom 100%100%power.

power.

Thefollowing The following conditions conditions are areobserved observed by bythe the control control room room operators operators upon upon compl etion of 4-EOP-E-0:

completion of 4-EOP-E-O:

• • Steam Generator Steam Generatornarrow narrow range range levels:

levels: off-scale off-scale low low

• • Steam Genera tor Steam Generator pressures: pressu res: 800 psig 800 psig

• • 3A S/G 3A S/G AFWAFW max.max. flowflow rate:

rate: 100 gpm 100 gpm

• 3B S/G S/G AFWAFW max.max. flowflow rate:

rate: 125 125 gpm

• 3B gpm

• • 3C S/G 3C S/G AFWAFW max.max. flow flow rate:

rate: 125 gpm 125 gpm a Pressurizer level:

Pressurizer level: off-scale off-scale low low

• RCS pressu re: 600 600 psig

• RCS pressure: psig

• RCS ColdCold Leg Leg temperatures:

temperatures: 330°F 330° F

• RCS Which ONE Which ONE of of the the following following identifies identifies the the correct correct procedure procedure the the operators operators should should transit ion to when 4-EOP -E-0 transition to when 4-EOP-E-0 is complete? is compl ete?

A.

A. 4-EOP-E-1, "Loss 4-EOP-E-1, Loss of Reactor Reactor or Secondary Secondary Coolant" Coolant B.

B. 4-EOP-E-2, "Faulted 4-EOP-E-2, Faulted Steam Generator Generator Isolation" Isolation C.

C. 4-EOP-FR-P.1, "Response 4-EOP-FR-P.1, Response to Imminent Imminent Pressurized Pressurized Thermal Thermal Shock Condit ion Condition" D.

D. 4-EOP -FR-H.1, Respo 4-EOP-FR-H.1, "Responsense to Loss of Second Secondaryary Heat Sink Sink" 147 147

NRC DRA DRAF FTT 07/24/07 07/2410 7 Q #74 Q#74 ANSWER: A KA: G.2.4.4 G.2.4 .4 Ability to recog recogn ize abnor nize abnorm al indica mal indicattions ions for system opera operati ng param ting parame ters which are eters entry level conditions for emerg emergeency ncy and abnor abnorm al opera mal operati ng proce ting proced ures.. 4.0/4.

dures 4.0/4.33 IOCFR 10CF 55:

R55: 41.b.10 41.b.1 0 Refere Refer nce:

ence: 4-EOP-E-O, 4-EOP -E-0, Step 15 4-EOP-F-O, 4-EOP -F-0, Enclo Enclos ures 3 and 4 sures Cog Level: Comprrehen 2 Comp ehensi on sion Level 2 becau becaus see the opera operatotorr must recog recogn ize that a LOCA exists and a secon nize seconddary ary break does not. The Opera Operattor or must then apply the criteri criteria a of EOP-F EOP-F-O -0 to determine that a red or orang orange e path does not exist for heat sink or integr integriity.

ty.

New Quest Questiion on Response Analy Analyssis:

is:

A. Correcctt per the refere Corre referen ces nces B. Incorre Incorr ect ct becau becaus see a LOCA exists and the correc correctt transi transittion ion is to EOP-EOP-E -1, E-1, not EOP-EOP-E E-2.

-2. Plaus Plausibible le becau becaus e S/G press se pressu res are lower than expec ures expectted ed for the post-t post-trrip ip condition and conta contain mentt press inmen pressu re is at a value that can be ure caused caused by a MSLB.

c.

C. Incorre Incorr ect ct becau becaus see a LOCA exists and the correccorrectt transi transittion ion is to EOP-E-1, not EOP-EOP-F FR-P.

R-P.1.1. Plaus Plausib le becau ible becaus see RCS cold leg tempetemperrature atures s are above the thresh threshooldld value of 320°F 320° F that would force transi transiti on tion to FR-P.

FR-P.1 1..

D. Incorre Incorr ct becau ect becaus e a LOCA exists and the correc se correctt transi transiti on is to tion to EOP-E-1,,

not EOP-EOP-F R-H.1.

FR-H. 1. Plaus Plausib le becau ible becaus e se S/G NR levels are off-sc off-sca le low and ale AFW flow rates are barely above the thresh threshoold ld value of 345 psig that would force transi transiti on to FR-H.1.

tion 148

NRC DRA FT 07/24/07 07/24/0 7 Q #75 Q#75 Opera Operattors ors are perfor perform ming ing 3-EOP-FR-C.2, "Resp Respo nse to Degra onse Degrad ed Core Cooling ded g" and are currently depre depresssuriz surizin g all intact S/Gs.

ing SIGs.

The STA updat updateess the Shift Mana Manag er that prese ger presenntly tly the CSF status trees for Contaiinmen Conta nmentt (due to high contacontain mentt press inmen pressuure) re) is Orang Orange e and Integr Integriity ty is Red. All other CSF status trees are green or yellow.

Which ONE of the follow ing descr describ es the correc ibes correctt opera operato torr respo respon se?

nse?

A. Imme Immed diatel iatelyy transi transittion ion to 3-EOP-FR-Z.1, "RespRespo nse to High Conta onse Contaiinmen nmentt Pressu Pressure."

re.

B. Imme Immed diatel iatelyy transi transittion ion to 3-EOP-FR-P

-FR-P..1, 1, "Resp Respo nse to Immin onse Imminent ent Press Pressuurized rized Thermal Shock Condi Condittion."

ion.

C. Continue in 3-EOP-FR-C.2 until comp compllete.

ete. Then transi transittion ion to 3-EOP-FR-Z-FR-Z..11,,

Respo "Resp nse to High Conta onse Contaiinmen nmentt Press Pressuure."

re.

D. Continue in 3-EOP-FR-C.2 until comp compllete.

ete. Then transi transittion ion to 3-EOP-FR-P

-FR-P..11,,

"Resp Respo onse nse to Immin Imminent Press Pressuurized rized Thermal Shock Condi Condittion."

ion.

149

NRCDRAFT NRC DRAFT 07/24/07 07/24/07 Q #75 Q#75 ANSWER:

ANSWER: DD KA:

KA: G.2.4.5 G.2.4.5 Knowl edge Knowledge of theof theorganization organization of ofthe theoperating operating procedures proceduresnetwork networkfor fornormal, normal, abnorm al and emerge ncy evolut abnormal and emergency evolutions. 2.9/3.6 ions. 2.9/3.6 100FR55:

10CFR55: 41.b.1O 41.b.10

Reference:

0-ADM-211, Step 0-ADM-211, Step 5.10.6 5.10.6 3-EOP -FR-C 3-EOP-FR-C.2 .2 Caution Caution prior prior to to Step Step 1313 Cognitive Level:

Cognitive Level: 22 Comprehension Comprehension Level Level 22 because because the the operator operator mustmust recall recall the the Caution Caution inin FR-C.2 FR-C.2 that that directs directs that that FR-FR-0.2 be compl eted prior to transit C.2 be completed prior to transitioning ioning to to the the Red Red Path Path onon Integrity.

Integrity. The The caution caution states that states that you you must must complete complete FR-C.2 FR-C.2 priorprior toto transitioning transition ing to to FR-P.1.

FR-P.1. This This isis contrar y to the rules of usage and contrary to the rules of usage and require the require the operator operator to to analyze analyze and and evaluate evaluate that that the completion the completion of of C2 C2 isis higher higher importance importance than than the the P1P1 transition transition for the given plant given plant conditions. Additionally conditions. Additionally this exception exception to the rule rule is is identified identified in in 0-ADM-211.

0-ADM-21 1.

New Question New Question Response Analys Response is:

Analysis:

A.

A. Incorrect becaus Incorrect because e the operato operators rs should contin continue 3-EOP-FR-C.2 ue in 3-EOP until

-FR-C.2 until compl ete.

complete. Then transit ion transition to 3-EOP -FR-P.1. Plausib 3-EOP-FR-P.1. Plausible because le becaus e an Red pathpath exists exists on on Integri ty.

Integrity.

B.

B. Incorre Incorrectct becaus because e the the operato operators rs should should contin continueue inin 3-EOP 3-EOP-FR-C.2 until

-FR-C.2 until compl ete. Then complete. Then transit ion to transition to 3-EOP -FR-P.1. Plausib 3-EOP-FR-P.1. Plausible because an le because an Red Red exists associa ted with exists associated with vessel vessel integri ty.

integrity.

C.

C. Incorre Incorrectct becaus because e the the operato operators rs should should transit transition ion toto 3-EOP 3-EOP-FR-P.1 following

-FR-P.1 follow ing comple tion of completion of 3-EOP -FR-C.2. Plausib 3-EOP-FR-C.2. Plausible le becaus because e anan orange orange path path exists exists due due to to contain ment high containment high pressu re.

pressure.

D.

D. Correc Correct t per perthe the referen referencece 150 150

NRC DRA FT 07124/0 07/24/07 7

Q #76 0#76 Operators Opera tors are perfor perform ing 3-EOP-ES-1 .2, ming .2, "Post Post LOCA CooldCooldo wn and own Depressu Depre rizat ssuriz ion," and are prepa ation, preparing ring to start an RCP.

Primarryy system Prima system param paramete rs are:

eters

• PRZ Level: 73%

• RVLMSS Plenu RVLM Plenum m Level: Full Full

• RVLM S Head RVLMS Head Level: NOT Full Which ONE of the follow following ing descr describes ibes the effect on pressurizeurizerr level when an RCP started is starte under these condit d under condition ionss and the correc correctt opera operator tor respo response?

nse?

Pressuriz Press er level will:

urizer A. drop when an RCP is starte started.

d.

Transiition Trans tion to 3-EOP 3-EOP-FR-FR-1-l.3, Respons

.3, "Resp onsee to Voids in React Reactor or Vesse Vessell."

B. NOT be affect affecteded when an RCP is starte started.d.

Transiition Trans tion to 3-EOP 3-EOP-FR-FR-1-l.3, Respons

.3, "Resp onse e to Voids in React Reactor or Vesse Vessell."

C. drop when an RCP is starte started.d.

Continue Contin implem ue to imple ent 3-EOP-ES-1 ment -ES-1.2.

.2.

D. NOT be affect affecteded when an RCP is starte started.d.

Continue Contin ue to impl impleemen mentt 3-EOP 3-EOP-ES -ES-1 1 .2.

.2.

151 151

Draft Submittal (Pink Paper)

Senior Reactor Operator Written Exam

Xerox WorkCentre Network Scanning Network Scanning Confirmation Confirmation Report Report XEROX XE ROX Job Details:

Job Details: Job Status:

Job Status:

11 out out of of 11 filed filed successfully.

successfully.

Job Information Job Information Destination 1:

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Copyright Copyright(c)(c) 1993-2007 XeroxCorporation.

1993-2007Xerox Corporation. ?Jl All Rights RightsReserved.

ReselVed.

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q #76 Q#76 ANSWER:

ANSWER: CC KA:

KA: 000009EA2.04 000009EA2.04 Able to Able determine and to determine and interpret interpret the the following following as as they they apply apply to to Small Small Break Break LOCA:

LOCA:

PRZ Level.

PRZ Level. 3.8/4.0 3.8/4.0 IOCFR55:

10CFR55: 43.b.5 43.b.5

Reference:

3-EOP-ES-1 .2, Step 3-EOP-ES-1.2, Step 2525 and and BD BD 3EOP-F-O, Enclosure 66 3-EOP-F-0, Enclosure 3-EOP-FR-l.3, CAUTION 3-EOP-FR-1.3, CAUTION prior prior to to Step Step 11 Cog Level: 2 Analysis Level 2 because the operator must determine that the RVLMS RVLMS and pressurizer level indications indicate a void in the vessel head and predict that starting an RCP will collapse the void, lowering the pressurizer level. The operator must recall that starting an RCP is desirable in these circumstances circumstances to provide forced cooling and normal pressure control during the cooldown. Finally these conditions are to be expected and there is no need to transition to the identified yellow path procedures.

FR-l.3 should not be implemented when SI pumps are operating.

Additionally FR-1.3 New Question Response Analysis:

A. Incorrect because FR-1.3 FR-I.3 should not be implemented when SI pumps are operating. Plausible because pressurizer level will drop when an RCP is started as coolant flow to the head region collapses the void, lowering the pressurizer level.

B. Incorrect because pressurizer level will drop when an RCP is started as coolant flow to the head region collapses the void, lowering the pressurizer level. Plausible because aa transition to FR-l-3 FR-I-3 would address the head head void.

Additionally the operator operator must recognize FR-l.3 FR-1.3 should not not be implemented when SI SI pumps are operating.

operating.

C.

C. Correct Correct per the reference per the D.

D. Incorrect Incorrect because because pressurizer pressurizer level level will will drop drop when when anan RCP RCP isis started started asas coolant coolant flowflow to to the the head head region region collapses collapses the the void, void, lowering lowering the the pressurizer pressurizer level.

level. Plausible Plausible because because thethe operators operators should should continue continue to to implement implement 3-EOP-3-EOP-ES-i ES-1.2..2.

152 152

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q #77 0#77 3EOPECA-2.1, "Uncontrolled 3-EOP-ECA-2.1, Uncontrolled Depressurization Depressurization of ofAll All Steam Steam Generators,"

Generators, directs directs operators to operators control feed to control feed flow flowto minimize RCS to minimize RCS cooldown.

cooldown.

RCS cold RCS cold reg leg temperatures temperatures have have decreased decreased from from 54rF 547°F toto 340°F 340°F inin the the past past 60 60 minutes.

minutes.

Which ONE Which ONE of the following of the following describes describes the the correct correct operator operator response?

response?

A.

A. Decrease feed Decrease feed flow flow to to 345 345 gpm.

gpm.

Transition to 3-EOP-FR-P Transition to 3-EOP-FR-P.1, .1, "Response Response to to Imminent Imminent Pressurized Pressurized Thermal Thermal Shock Condition."

Shock Condition.

B.

B. Decrease feed Decrease feed flow flow to 25 gpm to 25 gpm toto each each S/G.

S/G.

Transition to and complete 3-EOP-FR-H Transition to and complete 3-EOP-FR-H.1, .1, "Response Response to Loss of to Loss of Secondary Secondary Heat Sink."

Heat Sink.

C. Continue to implement Continue implement 3-EOP-ECA-2.1.

3-EOP-ECA-2.1. Decrease feed flow to 25 gpm to each S/G.

D. 3-EOP-ECA-2.1. Decrease total feed flow to 345 Continue to implement 3-EOP-ECA-2.1.

gpm.

153 153

NRC DRAFT NRC DRAFT 07/24/07 07/24/07 Q #77 Q#77 ANSWER:

ANSWER: CC KA:

KA: W/EI2EA2.2 W/E12EA2.2 Able to determine Able to determine and and interpret interpret thethe following following asas they they apply apply toto Uncontrolled Uncontrolled Depressuriza tion of all S/Gs: Adherence to appropriate Depressurization of all S/Gs: Adherence to appropriate procedures procedures and and operation operation within the within the limitations limitations inin the the facility's facilitys license license and and amendments.

amendments. 3.4/3.9 3.4/3.9 10CFR55:

10CFR55: 43.b.1 && b.5 43.b.1 b.5

Reference:

3-EOP-ECA-2.1, Step 3-EOP-ECA-2.1, Step 33 3-EOP-F-0, Enclosure 3-EOP-F-0, Enclosure 44 3-EOP-FR-H.1, CAUTION 3-EOP-FR-H.1, CAUTION prior prior to to Step Step 11 Cog Level:

Cog Level: Comprehension 22 Comprehension Level 22 because Level because the operator must must recognize recognize that withwith aa cool down> 100°F/hour, 100°F/hour, ECA-2.1 ECA-2.1 will require feed flow to be reduced to 25 gpm per S/G. This reduction in feed flow feed flow will result in a red red path on heat sink, but because because the reduction of feed flow was procedurally driven, performance of FR-H.1 is not desirable.

New Question Response Analysis:

A.

A. Incorrect because RCS temperatures have not dropped far enough to trigger an orange path on Integrity and feed flow should be reduced to 345 gpm.. gpm ..

Plausible because RCS temperatures have dropped 227°F 22rF in the past 60 minutes.

B.

B. Incorrect Incorrect because transition to to FR-Hi FR-H.1 is is not required because feed flow has has been reduced due due to procedural requirements requirements.. Plausible Plausible because because operators operators will will decrease decrease feed feed flowflow to 2525 gpm gpm toto each each S/G.

S/G.

C.

C. Correct Correct perper the the reference reference D.

D. Incorrect Incorrect because because feedfeed flow flow needs needs to to be be reduced reduced toto 25 25 gpm gpm to to each each S/G S/G as as directed directed by by EOP-ECA-1 EOP-ECA-1.2. .2. Plausible Plausible because because operators operators will will continue continue to to implement implement 3-EOP-ECA 3-EOP-ECA-2. -2.

154 154

NRCDRAFT NRC DRAFT 07/24/07 07/24/07 Q #78 0#78 Unit44 isisatat 100%

Unit 100% power powerwith with all all systems systemsinin normal normal alignment.

alignment.

• • The The 4A 4A CCWCOW pumppump isis being being removed removed from from service.

service.

• • The The 4A 4A CCWCOW pumppump CS CS has has been been placed placed inin Pull-to-Lock Pull-to-Lock but but its its breaker breaker isis still still racked in.

racked in.

The switchyard The switchyard subsequently subsequently de-energizes.

de-energizes.

Which ONE Which ONE of of the the following following correctly correctly describes describes UnitUnit 44 sequencer(s) sequencer(s) response response and and the first procedure operators the first procedure operators will use will use to verify correct to verify correct CCW COW system system alignment?

alignment?

A.

A. 4A sequencer 4A sequencer will will close close thethe 4C 40 CCW COW pump pump breaker.

breaker.

4B sequencer 4B sequencer will close the will close the 4B 4B CCW COW pump pump breaker.

breaker.

4-EOP-ES-0.1, "Reactor 4-EOP-ES-O.1, Reactor TripTrip Response."

Response.

B.

B. sequencer will close 4A sequencer close the 4C 40 CCW COW pump pump breaker.

breaker.

4B sequencer sequencer will close the 4B CCW COW pump breaker.

4-ONOP-004, "Loss 4-0NOP-004, Loss of Offsite Power."

Power.

0.

C. sequencer will attempt to close the 4A CCW 4A sequencer COW pump breaker.

4B sequencer sequencer will close the 4B CCW COW pump breaker.

4-EOP-ES-0.1, "Reactor 4-EOP-ES-0.1, Reactor Trip Response."

Response.

D. 4A sequencer will attempt to close the 4A COW CCW pump breaker.

4B sequen sequencer cer will close the 40 COW 4C CCW pump breaker.

4-ONOP-004 4-0NOP-004,, Loss "Loss of Offsite Power.

Power."

155 155

NRCDRAFT NRC DRAFT 07124/07 07/24/07 Q #78 Q#78 ANSWER:

ANSWER: CC KA: 000056AA2.47 KA: 000056AA2.47 - Able - Abletoto determine determine and and interpret interpret the the following following as as they they apply apply to Loss of Off-site Power: Proper to Loss of Off-site Power: Proper operation operation of ofthe the EOGEDG load load sequencer.

sequencer. 3.8/3.9 3.8/3.9 10CFR55:

10CFR55: 43.b.5 43.b.5

Reference:

4-EOP-ES-0.1, Step 4-EOP-ES-0.1, Step 17 17 4-ONOP-004 4-0NOP-004,, First First NOTE NOTE prior prior toto Step Step 1I 5614-T-L1, 5614-T-L Sheet 12A 1, Sheet 12A && 128, 12B, 5610-T-L1, 5610-T-L Sheet 1240 1, Sheet 124D 5610-T-L1, 5610-T Sheet 152A

-L 1, Sheet 152A Cog Level:

Cog Level: 22 Comprehension Comprehension Level 22 because Level because the the operator operator mustmust recognize recognize that that ifif the the 4A 4A CCW CCW pumppump is is in in PTL PTL itit cannot start. If the cannot start. If the 4A CCW 4A CCW pump breake breakerr hashas not not been been racked out, the 4A sequencer will still try to close its sequencer its breaker breaker inin the event of of a LOOP.

LOOP. 4C CCW pump pump can be can be started by either sequencersequencer depending depending on the alignment alignment of 40 4D bus.

However if both 4A and 48 However 4B CCW pumps are racked in, 4C CCW pump will not get get aa start signal start signal from a sequencer.

sequencer. Operators Operators will transition from EOP-E-O to EOP-E-0 EOP-ES EOP-ES-0.1 in response 0.1 response to the reactor trip caused by the LOOP. ES-0.1, Step 17 is the first first procedural opportunity to verify proper CCW operation.

procedural operation. Note that it is checked checked a a second time in ONOP-004 second ONOP-004 after operatorsoperators complete complete ES-0.1.

New New Questi Question on Respo Response nse Analysis:

A.

A. Incorrect Incorrect becaus because e 4A 4A sequen sequencer cer will attemp attemptt to close the 4A 4A CCW CCW pump pump breake breaker.r. Plausib Plausible le becaus because e 4B 48 sequen sequencer will close cer will close the the 4B48 CCW CCW pump pump breake breaker r and and operato operators rs will will verify verify the the CCW CCW alignm alignment first using ent first using 4-EOP 4-EOP-ES- -ES-0.1, React 0.1, "Reactor Trip or Trip Respon Response." se.

B.

8. Incorrect Incorrect becaus because e 4A4A sequen sequencer cer will will attemp attempt t toto close close thethe 4A 4A CCW CCW pump pump breake breaker r and and operato operators rs will will verify verify the the CCW CCW alignment alignment first first using using 4-EOP 4-EOP-ES- -ES-0.1, 0.1, React "Reactor or Trip Trip Respon Response."se. Plausib Plausible le becaus because 48 sequen e 4B sequencer will close cer will close the the 4B48 CCW CCW pump pump breake breaker r C.

C. Correc Correct t per perthe the referen referencece D.

O. Incorrect Incorrect becaus because e 4B 48 sequen sequencer cer will will close close thethe 4B 48 CCW CCW pump pump breake breaker and r and operato operators rs will will verify verify the the CCW CCW alignment alignmentfirst first using using 4-EOP 4-EOP-ES-0.1, "Reactor

-ES-0.1, Reactor Trip Trip Respon Response."se. Plausib le becaus Plausible because e 4A 4A sequen sequencer will attemp cer will attemptt toto close close thethe 4A 4A CCW CCW pump pump breake breaker.r.

156 156

NRCDRAFT NRC DRAFT 07/24/07 07/24/07 Q #79 0#79 Unit33 isis atat 75%

Unit 75% power powerwhenwhen the thefollowing following occur; occur;

• • Automatic VCT Automatic VCT makeup makeup STARTS STARTS withwith VCT VCT level level atat 50%

50% on on LT-112.

LT-1 12.

• • 3B main feedwater flow control valve 3B main feedwater flow control valve transfers transfers toto MANUAL MANUAL mode. mode.

• • QSPDS channel OSPDS channel "A" A isis DEENERGIZED DEENERGIZED

• • Train 1I AFW Train AFW flow flow control control valves valves fail fail CLOSED CLOSED After completion After completion of of any any immediate immediate operator operator actions actions andand with with the the plant plant stable, stable, the the US should; US should; A.

A. Restore 3A Restore 3A EDG EDG to to service service within within 7272 hours0.0842 days <br />2.02 hours <br />0.012 weeks <br />0.00277 months <br /> hours or or initiate initiate aa plant plant shutdown shutdown to to reach Mode 3 within the following reach Mode 3 within the following 66 hours7.638889e-4 days <br />0.0183 hours <br />1.09127e-4 weeks <br />2.5113e-5 months <br /> hours because because 3A 3A EDG EDG auto-start auto-start capability has capability has been been lost.

lost.

B.

B. Restore 3P07 Restore 3P07 toto service service within within 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> hour or or initiate initiate aa plant plant shutdown shutdown to to reach reach Mode 33 within the following 66 hours7.638889e-4 days <br />0.0183 hours <br />1.09127e-4 weeks <br />2.5113e-5 months <br /> Mode hours because because AFW actuation actuation logic has been logic has been degraded.

degraded.

C. Verify that all Train B emergency equipment is operable within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or or initiate a plant shutdown to reach Mode 3 within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> because 3A EDG auto-start capability has been lost.

because D. Place 3A 4kv bus and 3A/3C 3A13C 480V load center bus stripping logic in the tripped condition within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> because AFW actuation logic has been degraded.

157 157

NRCDRAFT NRC DRAFT 07/24/07 07/24/07 Q #79 Q#79 ANSWER: BB ANSWER:

KA:

KA: 000057G2.1.33 000057G2.1.33 As it relates As it relates to Lossto Lossof ofVital Vital AC AC Inst.

Inst. Bus:Bus: Ability Abilitytoto recognize recognize indications indicationsfor forsystem system operati ng parame operating parameters ters which which areare entry-level entry-level conditions conditions for fortechnical technical specifications.

specifications.

((3.4 3.4 1/4.0) 4.0 )

10CFR55:

10CFR55: 43.b.2 43.b.2

Reference:

3-ONOP-003.7 Enclosure 3-0NOP-003.7 Enclosure 1, 1, NOTE NOTE 11 Tech Specs. 3.0.3 Tech Specs. 3.0.3 - Page - Page 3/40-1 3/4 0-1 Cog Level:

Cog Level: 22 Comprehension Comprehension Level 2 becaus Level 2 becausee the the operator operator mustmust analyzeanalyze indications, indications, determine determine that that they they are are caused by a loss of 3P07 and caused by a loss of 3P07 and relate that the relate that the most most limiting limiting impact impact results results in in aa loss loss of of the bus the bus stripping stripping relays.

relays. He He must must then then relate relate that that the the loss loss of of bus bus stripping stripping results in results in loss of aa loss of anan auto auto start start signal signal toto the the AFW actuation actuation as as well well as as the the EDG EDG output output breaker auto breaker auto closure closure failure. He He then must must determine determine that the TS actions actions of 3.0.33.0.3 are required are required based based on AFW availability.

New Question New Question Response Analysis:

Response Analysis:

A.

A. Incorrect, indications are for a loss of 3P07 therefo Incorrect, therefore re operators operators must take take action action within 1 1 hour to restore the Vital AC panel or initiate aa plant shutdown to to reach reach Mode 33 within the following 66 hours7.638889e-4 days <br />0.0183 hours <br />1.09127e-4 weeks <br />2.5113e-5 months <br /> becaus because actuation e AFW actuati on logic has been degrad ed. Plausib has been degraded. Plausible because le becaus 3A EDG e 3A EDG auto-st auto-start capability has art capability has been been degrad degraded ed andand 3A3A EDGEDG tech tech specs specs areare also also applica applicable (but less ble (but less restrictive).

restrictive ).

B.

B. Correc Correctt perper the the referen reference ce C.

C. Incorrect, Incorrect, indications indications are are for for aa loss of 3P07 loss of 3P07 therefo therefore operators re operato must take rs must take action within 1 hour to restore action within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to restore the the Vital Vital AC AC panel panel or or initiate initiate aa plant plant shutdo shutdown wn to to reach reach Mode Mode 33 within within the the following following 66 hours7.638889e-4 days <br />0.0183 hours <br />1.09127e-4 weeks <br />2.5113e-5 months <br /> hours becaus because AFW actuati e AFW actuation logic on logic has has been been degrad degraded. ed. Plausib Plausible le becaus because all Train e all Train BB emerge emergency equipment ncy equipm ent needs needs to to be be verified verified operab operable le within within 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br />.

hours.

D.

D. Incorrect, Incorrect, indications indications are are for for aa lossloss of of3P07 3P07 therefo therefore operators re operato musttake rs must take action action within within 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> hourto to restore restore the the Vital Vital AC AC panel panel or orinitiate initiate aa plant plantshutdo shutdownwn toto reach reach Mode Mode 33withinwithin the thefollowing following 66 hours7.638889e-4 days <br />0.0183 hours <br />1.09127e-4 weeks <br />2.5113e-5 months <br /> hours becaus because AFW actuati e AFW actuation logic on logic has has been been degrad degraded. ed. Plausib Plausible le becaus because operators e operato will need rs will needtoto place place3A 3A4kv4kv bus and 3A/3C 480V load center bus and 3A/3C 480V load center busstripping bus stripping logic logicininthe thetripped tripped condition.

condition.

158 158

NRCDRAFT NRC DRAFT 07/24/07 07/24/07 Q #80 0#80 Unit44isisatat100%

Unit 100%powerpowerwithwith all all systems systems inin normal normalalignment alignmentwhen whenthethe4A4AICW ICW pump breakertrips pump breaker tripsopen open on on over-current.

over-current.

The 4A The 4A ICW ICW pump pump isis declared declared inoperable inoperable and and removed removed from from service.

service.

Which ONE Which ONE of ofthe the following following describes describes the the Technical Technical Specification Specification limits limits associated associated with the with the 4A 4A ICWICW pumppump being being out out ofof service?

service?

Unit 44 isis inin a:

Unit a:

A.

A. 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 72 hour action action statement.

statement. The The action action statement statement time time can can be be extended extended toto seven days if 4D 4KV Bus seven days if 40 4KV Bus is realigned is realign ed to to 4A 4A 4KV 4KV Bus.

Bus.

B.

B. 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 72 hour action action statement.

statement. The The action action statement statement time time can can NOT NOT bebe extended extended by realigning by realigning 40 4D 4KV 4KV Bus.

Bus.

C.

C. seven day seven day action statement.

statement. The action action statement statement time cancan be be extended extended toto thirty days thirty days if 40 4D 4KV Bus is is realigned to 4A 4KV Bus.

D.

O. seven day seven day action statement.

statement. The action statementstatement time can NOT be extend extended ed by realigning 4D 40 4KV Bus.

159 159

NRCDRAFT NRC DRAFT 07/24/07 07/24/07 Q #80 Q#80 ANSWER:

ANSWER: AA KA:

KA: 000062G2.2.22 000062G2.2.22 As it relates to As it relates to Loss Loss of ofNuclear NuclearSvc SvcWater:Water: Knowledge Knowledge of of limiting limiting conditions conditions for for operations && safety operations safety limits.

limits. 3.4/4.1 3.4/4.1 IOCFR55:

10CFR55: 43.b.2 43.b.2

Reference:

Tech Spec Tech Spec 3.7.33.7.3 Actions Actions aa and and bb 5610-T-E-15 91, 561 0-T-E-1591, Sheet 1 Sheet 1 Cog Level:

Cog Level: 22 Comprehension Comprehension Level 22 because Level because the the operator operator must must recognize recognize that that the the 4A4A ICW ICW pump pump is is powered powered from 4A 4KV Bus. If plant from 4A 4KV Bus. If plant components compo nents are are inin normal normal alignment, alignment, 4B 4B and and 4C 40 ICW ICW pumps share pumps share thethe same same traintrain power power supplysupply resulting resulting in in aa 72 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> action statement.

hour action statement.

Swapping 40 Swapping 4D Bus Bus to 4 A Bus Bus places places 4C ICW ICW pump pump on on the "A"A Train increasing increasing the the Action Time Action Time to to 77 days.

days.

New Question New Question Response Analysis:

Response Analysis:

A.

A. Correc Correctt per the referen reference ce B.

B. Incorrect Incorrect becaus because e the action statem statement ent time can be extend extendeded to seven days ifif 4D 40 4KV 4KV BusBus is is realign realigneded toto 4A 4A 4KV 4KV Bus. PlausibPlausible because le because Unit Unit 44 is is in in aa 72 hour action statem 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> action statement. ent.

C.

C. Incorrect Incorrect becaus because e Unit Unit 44 is is inin aa 72 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> hour action action statem statement. Plausible ent. Plausib because le becaus e 77 days days isis the the correct correct action action statem statement ent time time for for aa 00W CCW pumppump andand thethe action action statem statement ent time time cancan be be extend extended ed to to 3030 days days (for (for aa CCW CCW pump) 40 4KV pump) ifif 4D 4KV BusBus isis realign ed to realigned to 4A4A 4KV4KV Bus.

Bus.

o.

D. Incorrect Incorrect becaus because e Unit Unit 44 isis inin aa 72 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> hour action action statem statement and the ent and the action action statem statement ent time time cancan be be extend extended ed ifif 4D 40 4KV 4KV Bus Bus isis realign realigned to 4A ed to 4A 4KV 4KV Bus.

Bus.

Plausib le becaus Plausible because e 77 days days isis the the correct correct action action statem statement time for ent time for aa 00W CCW pump.

pump.

160 160

NRC DRA D k

1 FTR FT 07/24/077 07/24/0

1. 81 Q#81 Q

Unit 3 is at 100% powepowerr when a loss of all aN feedw feedwa ter event occurs.

ater As the crew transi transittions ions from 3-EOP-E-0, the STA informs them a red path exists on Heat Sink.

The opera operato rs succe tors successsfully sfully initiate bleed and feed.

Which ONE of the following descr describ es the report ibes reportaability bility of this event event?  ?

The event must be report reporteedd to the:

A. NRCOC within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> hours..

B. NRC Resid Reside ent nt within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> hours..

C. State of Florid Florida a within 15 minut minuteess and to the NRC immeimmed iatelyy following diatel State notific notification.

ation.

D. State of Florid Floridaa within 1 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and to the NRC imme immed iatelyy follow ing State diatel notific notification.

ation.

REFE REFER RENC ENCE E PROVIDED 161

NRCDRAFT NRC DRAFT 07/24/07 07/24/07

1. 81 QQ#81 ANSWER:

ANSWER: CC KA:

KA: WW/E05 G2.4.30

/E05G2.4.30 As it relates As it relates toto Loss Lossof ofsecondary secondaryHeat HeatSink:Sink: Knowledge Knowledgeof ofwhich whichevents eventsrelated related toto system operati ons/sta tus system operations/status should be should be reported reported toto outside outside agencies.

agencies. 2.2/3.6 2.2/3.6 10CFR55:

10CFR55: 43.b.5 43.b.5

Reference:

0-EPIP-20101, 0-EPIP-201 01, Enclosure Enclosure 1,1, Category Category 5,5, Item Item C.3 C.3 0-EPIP -20101 0-EPIP-201 01,, CAUTIONS CAUTIONS before before Step Step 5.6.1.11 5.6.1.11 Cog Level:

Cog Level: 1I Recall Recall New Question New Question Provide EPIP-20101 Provide EPJP-20101 Enclosure Enclosure 1I as as aa reference reference Response Analysis:

Response Analysis:

A.

A. Incorrect because Incorrect because the event must be reported reported to the State of Florida within within 15 minute s and 15 minutes and to to the NRC immediately immediately following following State notification notification inin accordance with accordance with 0-EPIP-201 0-EPIP-201 01, "Duties Duties of the Emergency Emergency Coordinator."

Coordinator.

Plausible becaus Plausible because e notification notification to the NRCOCNRCOC lAW ADM-115 required ADM-1 15 is require d in in the the event event of of the the occurr ence of signifi occurrence cant events as defined in 10CFR significant 10CFR50. 72.

5O.72.

B.

B. Incorre ct becaus Incorrect because e the event event must be reportereported d to the State State of of Florida Florida within within 15 minute s 15 minutes and and to the NRC NRC immed iately follow immediately following State notific ing State notification ation inin accord ance with accordance with 0-EPIP -20101, Dutie 0-EPIP-20101, "Duties s of of the the Emerg Emergency Coordinator."

ency Coord inator.

Plausib le becaus Plausible because e notific ation to notification to the the NRC NRC Reside Resident lAW ADM-nt lAW ADM-115 1 15 isis require d in required in the the event event ofof the the occurr ence of occurrence of signifi significant events..

cant events C.

C. Correc Correctt per per the the referen referencece D.

D. Incorre ct becaus Incorrect because e the the event event must must be be reporte reportedd toto the the State State of of Florida Florida within within 15 15 minute minutes s and and to to the the NRC NRC immed iately follow immediately following State notification ing State notification in in accord ance with accordance with 0-EPIP 201 01, 0-EPIP-201 01, Dutie "Duties s of ofthe the Emerg Emergency Coordinator."

ency Coordi nator.

Plausib le becaus Plausible because e the the 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> hourtime timeframe frame applies applies to to NRC NRC notific notification and ation and certain other notific ations describ ed certain other notifications described inin 0-ADM 0-ADM-115.

1 15.

162 162

NRC DRA FT 07/24/077 07/24/0 Q #82 0#82 Unit 3 is at 50% power with control Bank "0" D at 180 steps as I&C invest investiigates gates a powerr cabin powe cabineett non-u non-urrgent gent failure alarm alarm..

A momentary powe powerr interruption in the 2BO2BD power cabin cabine ett control power circuitry causess all 3 of the Bank "0" cause D group 2 rods to drop 140 steps into the core where they are gripped and held norma normallylly by the statio station ary grippers being re-ene nary re-enerrgized gized..

The US should direct the opera operato rs to; tors A. Verify rod control is in AUTOMATIC and reduc reduce e turbin turbine e load using 3-0NO 3-ONOP-100, "Fast Fast Load Reduc Reduction, tion", to lower Tref to within 3°F of Tavg.

B. Verify rod control is in MANUAL and reduc reduce turbine e turbin e load using 3-0NO 3-ONOP-100P-100,,

Fast Load Reduc "Fast Reduction, tion", until all Bank "0" D rods are aligne aligned d within 12 steps C. Manuaally Manu lly trip the reacto reactorr,, verify the reacto reactorr is trippe trippedd,, perfor performm 3-EOP-E-0 and stabili stabiliz zee the plant using 3-EOP-ES-0-ES-0..1.

1.

D.

O. Manuaally Manu lly trip the reacto reactorr,, verify the reacto reactorr is trippe trippedd and Emergency Borate per 3-0NO 3-ONOP-046 P-046..1.

1.

163

NRC DRA NRC DRAFT 07/24/0 07/24/077 Q #82 Q#82 ANSWER ANSW ER:: CC KA:

KA: 000003G 00000 3G.2..2.4.

4.66 As itit relate As relates to the s to the dropp dropped controll rod ed contro rod event:

event: Know Knowledledge ge of of sympt symptom om based based EOPEOP mitigation mitiga strategies tion strate gies.. 3.1/4.

3.1/4.0 0 IOCFR5 10CF R55: 5: 43.b.5 43.b.5 Referenc Refer ence: e: 3- ONOP ONOP-02 -028.38.3,, Step 1I 3-EQ P-E-3-EOP -E-0,0, Step Step 1, 3-EOP-ES 3-EOP -ES-0 -0.1,

.1, Step 5 Level: 2 Comp Cog Level: Compreh rehenensio sionn The SRO must must recogrecogniz nizee that even thoug though h the dropp dropped ed rods did not fully insert reactorr trip is requir insert a reacto required.ed. He then must must analyz analyze e that the contro controll rods that were dropped dropp ed initially wouldwould still be trippa trippable ble as they were re-grip re-grippepedd by the statio nary stationar y grippers grippe rs and should should be free to fall on the trip. He then must must under understan stand d that the EOP netwonetwork rk only addre addresses sses rods that do not fully insert insert on a trip by emerg borating emer ency genc y borati using ONOP ng using QNQP-46 -46.1,

.1, dropp dropped ed rods are not addre addressed ssed unless unless they fail to insert.

insert.

Question New Quest ion

Response

Respo Analysis:

nse Analy sis:

A. Incorrect Incorr because ect becau se the reacto reactorr would be manu manually ally tripp trippeed.

d. Plaus Plausible ible becau because se Tavg is restor restoreded to Tref by borati borating ng and reduc reducinging turbin turbine e load in ONOP ONOP-28 -28.3.3 which is used for dropp which dropped ed rod recove recovery ry.. ONOP ONQP-02 -028.3 8.3 requir requireses the Rod Control Contr Selector ol Selec Switch to be placed tor Switch placed in MANUAL.

B. Incorrect Incorr because ect becau se the react reacto orr would be manu manually ally tripp trippeed.

d. Plaus Plausible ible beca becau usese Tavg is restorestorred ed to Tref by bora borati ting ng and redureduc cing ing turbi turbinnee load in ONQONOP -28.3 P-28.3 whic which h is used for drop dropp ped ed rod recorecove very ry..

C. Corr Corre ectct as the eveneventt desc descrribed ibed was multiple drop dropp ed rods that were ped relat relatch cheded by the norm norma all oper opera ation tion of the stati statioonar naryy gripp grippe rs, they shou ers, shouldld still be tripp trippa able ble and fully inserinsertt when the man manu ual al trip is orde ordere d. The EOP red. EOPs s only addr addre ess ss rods that are stuck out of the core core..

D. Inco Incorr rrect ect beca becau use se the EOP EOPs s only addr addre essss stuck rods and these rods shou should ld still inser insertt on the reactreacto orr trip. Plau Plaus sible ible beca becauusese the step in ES-0.1 ES-0.1 direc directtss the oper opera ator tor to Eme Emerg rgenency cy Bora Borate te usin usingg 3-ON 3-0NO OP-0 P-046 .1 to com 46.1 comp ensat pens atee for any stuck rods rods..

164 164

NRC DRAFT 07/24/07 07/24/0 7 Q #83 Q#83 Operators Opera tors are increa increasing sing Unit 3 power to 100% 100%..

• powerr at 95% power With powe power,, annun annunciat or B 9/3, SHUTDOWN ciator DOWN ROD OFF TOP /

DEVIATION, DEVIA TION, alarm alarms.s:

• The RO report reportss that control rod rod H-8 H8 (0(D Bank) has stopp stopped ed moving and is now 14 steps lower than other other 0D Bank control rods.

• Subseque Subse nt invest quent investiigation gation revea revealsls H-8 isstuck and untrip untripp able..

pable Which ONE of the follow following descr describes ibes the Tech Spec requirrequire d opera ed operator tor response and the basis for the action action??

A. Place Unit 3 in Mode 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Place hours to ensur ensure adequate e adequ ate Shutd Shutdowown n Margi Margin n

requirem requir emenents ts are met.

B. Place Unit 3 in Mode 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Place hours to reduc reducee the effect of the stuck rod on subseque the subse quent nt Xenon Oscill Oscilla tion.

ation.

c.

C. Declare Decla inoperab re H-8 inope le and reduc rable reduce powerr to <

e powe < 75% within 1 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, confir confirm m all Bank "0" D rod positio positions are within 2:.+/- 12 steps of each other other to ensur ensure e adequate adequ Shutdow ate Shutd own Margin n Margi requirem n requir emenents ts are met.

D. Declare Decla inoperab re H-8 inope le and reduc rable reduce powerr to <

e powe < 75% within 1 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, confir confirm m all D rod positio Bank "0" positions ns are within 2:.+/- 18 steps of each other to reduc other reducee the affect of the stuck rod on the subse subsequequent nt Xenon Oscill Oscilla tion.

ation.

165 165

NRC DRA NRC DRAFT 07/24/0 07/24/07 7

Q#83 Q#83 ANSWER ANSW ER:: AA KA:

KA: 000005G 00000 .2.2.

5G.2. 22 2.22 As itit relate As relates to the s to the Inope Inoperab le/St rable/ uck Contr Stuck Controlol Rod:

Rod: knowl knowledg edgee ofof limitin limitingg condit ionss condition for opera for operationtionss andand safety safety limits.

Nmits. 3.4/4.1 3.4/4.1 IOCFR5 10CF R55:5: 43.b.2 43.b.2 Referenc Refer ence:e: 3-ONOP-0 3-0NO P-02828,, Step 5.1.4.

5.1.4.22 Tech Spec 3.1.3.1 3.1.3.1 Action Action a.

O-ADM-536, 0-ADM -536, Sectio Section n %.1.3

%.1.3 Level:

Cog Level: Recalll 1I Recal New QuestQuestionion

Response

Respo Analysis:

nse Analy sis:

A. Correct Corre ct per the referereference nce..

B. Incorrect Incorr because ect becau Xenon Oscill se Xenon Oscillatio ations ns are not the basis for the requir requirem emenentt to MODE 3 in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> be in MODE hours.. Plaus Plausible ible becau because se the reacto reactorr must must be placed placed in MODE 3 with MODE within in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> hours.. Misali Misaligne gned d rods could could be an initiati initiating ng event event for Xe oscillatio oscilla tionsns which which do challe challenge nge the powe powerr distrib distributi ution on limits.

C. Incorrect Incorr because ect becau se the unit must must be placed placed in ModeMode 3 with within in 66 hour7.638889e-4 days <br />0.0183 hours <br />1.09127e-4 weeks <br />2.5113e-5 months <br /> hourss..

Plau Plaus sible because ible becau se the rod musmustt be declar declareded inope inoperab rable le and reduc reducing ing power power to <75% wou would ld be a correc correctt response if the rod was tripp trippaable.

ble. Reduc Reducinging powerr using powe using bora boratition on wou wouldld increa increasese shut shutddow own n margi margin.n.

D. Incorrect Incorr ect beca becau use se the unit musmustt be place placed d in Mod Mode e 3 with within in 66 hour7.638889e-4 days <br />0.0183 hours <br />1.09127e-4 weeks <br />2.5113e-5 months <br /> hourss and Xeno Xenon n oscil oscilla latio tions ns are not the basis basis.. Plau Plaus ible beca sible becau se redu use reduc ing pow cing power er to

<75% and conf confir irmi ming ng all rods in the bank are within 18 18 steps wou would reduc ld redu cee peak peakiningg facto factorrss and wou wouldld be aa corre correc ctt response if the rod were not untri untripppab pable le..

166 166

NRC DRA NRC DRAF FT T 07/24/0 07/24/07 7 Q#84 0#84 Unit 44 isis at Unit at 80%

80% powepowerr during during endend of of life life (EOL)

(EOL) powepowerr coast coast downdown opera tion..

operation The auto The auto functi functionon ofof the the maste masterr charg charginging pump pump contro controllellerr fails fails causin causing g Charg Charging ing pump speed pump speed to to go go toto minim minimumum..

• • Operators Opera respond tors respo nd and and take take manu manual controll of al contro of Charg Charging ing pump pump speedspeed..

• • Tavg is Tavg is being being allowe allowed to "droop d to droop" to to maint maintain ain the reacto reactorr critica criticall and and isis prese prese ntly 3°F BELO 3°F BELOW W Tref as as direct directed by ed by React Reactor or Engin Engineereering ing..

Which ONE of Which of the follow following identifies ing identif ies the press pressurize urizerr level level that should should be be maintaine maint ained d and the basis basis for maint maintaini ainingng that level.

level.

Pressuriz Press urizer er level should should be:

A. 44%.

44%.

Pressuriz Press er level progra urizer program determine m is determ ined d by reacto reactorr power power to ensur ensure e that the steam volumvolume e in the pressurize urizerr is smalle smallerr at highe higherr powe powerr to preve prevent nt a high level reacto reactorr trip follow followinging a 100% load rejecti rejection.

on.

B. 44%.

44%.

Pressuriz Press er level progra urizer program m is determ determine inedd by Tavg to ensur ensuree that the water water volu volum mee in the press pressurize urizerr is highe higherr at highe higherr tempe temperatu ratureress to preve prev nt the ent pressurize press urizerr heaters from uncov uncoverin ering g durin during g a 10% step increa increase se in turbi turbinnee load.

load.

C. 47%

47%..

Pressuriz Press er level prog urizer prograramm is deter determ mine ined d by react reacto orr pow powe err to ensu ensurree that the steam volu volum mee in the press pressurize urizerr is high enou enoug ghh at anyany powpowe r er level to prevpreve nt ent wate waterr relie relieff throu throug ghh the safet safetiieses on aa 50% load rejec rejecti on.

tion.

D. 47%

47%..

Pres Press suriz er level prog urizer prograram m isis deter determ mine ined d by Tavg to ensu ensurree that the wate waterr volu volum mee in in the press pressurize urizer r at at any any powpowe err level level is is high enouenoug ghh to prev preve nt ent requ requir iring ing aa safet safety y injec tion injecti on follo wing follow ing aa react reacto orr trip.

trip.

167 167

NRC DRA NRC DRAFT 07/24/0 07/24/077 Q #84 Q#84 ANSWER:

ANSW ER: B B

KA:

KA: 000028AA2.

8AA2.08 08 Able to determ Able determine and interp ine and interpret the follow ret the following ing asas they they apply apply to to Press Pressuriz urizer er Level Level Malfun Malfu ction:: PRZ nction PRZ level level as as aa functio functionn of power power level.

level. 3.1/3.

3.1/3.55 IOCFR 10CF 55:

R55: 43.b.5 43.b.5 Referenc Refer ence: e: 4-ONOP-041 4-0NO P-041.6,.6, Step Step 4.2 & & Enclo Enclosur suree 1, SD-009 pages SO-00 pages 8&9 Cog Level: 3 Applic Application ation / Analy Analys sisis Level 3 becau because se the SRO must must recog recogniz nizee that the autom automati aticc pressurize urizerr level control system system would have been been maint maintaaining ining level lower based based on the lower than normal Tavg for the present powe powerr level. He must must calcul calculate ate the progra programmmmed ed pressurize urizerr level for the given plant conditions and relate relate that Tavg is being maintaine maint ained d at 3°F below Tref and that prz Prz level refere reference nce signal is genergenerated ated from Tavg and not from power power.. Tref at 80% power power would norma normally lly be 568.6 568.6°F°F which demand would dema nd 47% press pressurize urizerr level but since Tavg is 3°F low, the requir require edd pressurize urizer r level would be 44%. Calcu Calcullation:

ation: 22% to 53% level. 80% X 31 %

program progra m level span = = 25%. 25% + + 22% = = 47% for 80% power power but Tavg is not on program progra m so the press pressurize urizerr level must must be maintmaintaine ained d at 44% to equat equate e to the 565.6°F 565.6 °F Tavg.

New Quest Question ion

Response

Respo Analyssis:

nse Analy is:

A. Incorre Incorrect ct beca becau use se prz Prz level is aa function of Tavg and aa high level react reacto orr trip will be gene generrated ated from a com comp plete lete load rejecti rejectio on.

n. Plaus Plausible ible beca becau se the use level is base based d on Tavg and is corre correc ctt for the curre curren ntt Tavg.

B. Correc Correct. t.

C. Incorre Incorrect ct beca becau use se press pressurize urizerr level level is is aa function of of Tavg and aa high steam volume would be aa caus cause e of the heaters uncove uncovering.

ring. A high level react reacto orr trip will will be genegenerrated ated befo beforere wate waterr relief throu throug ghh the safet safety y valves. Plau Plaus ible sible beca becau use se the level is correcorrecctt for the curre curren ntt react reacto orr pow powe err and wate waterr will not not be relea releassed ed throu throug ghh the safet safety y valv valves es..

D.

O. Incorre Incorrect ct beca becau use se press pressurize urizerr level should should be 44%. 44%. PlauPlaus ible beca sible becau se the use level level is is corre correc ctt for the curre curren ntt react reacto orr pow powerer and thethe level is is main mainttaine ained high d high enou enoug ghh to notnot require require aa SI SI following aa reactreactoorr trip.

trip.

168 168

NRC DRA NRC DRAF FT T 07/24/0 07/24/07 7

Q#85 0#85 With reacto With reactorr powe powerr at at 80%,

80%, PRMS PRMS-R- 1 5 alarm

-R-15 alarmss and and count count-rate

-rate increa increases ses rapidl rapidly y

and stabili and stabilizes at 5,000 zes at 5,000 cpm.

cpm.

Operators Opera enter 3-0NO tors enter 3-ONOP-0 71.2, P-071 .2, "Steam Steam Gene Generator Tube Tube Leaka Leakage, ge," and and attem attempt to quan tify quantify thethe leakag leakage using the e using the R-15 R-1 5 Prima Primary to Secon ry to Secondardary y Leak Leak Rate Rate Graph Grap h in the in the Plant Plant Curve Curve Book.

Book.

Unit 33 Cond Unit Condens enserer air air in-lea in-leakag kagee is consta constant at 7 scfm.

nt at scfm.

All of the S/G All S/G tube leaka leakage is comin coming g from the 3B S/G.

Which ONE of the follow Which following describes ing descr Technical ibes Techn ical Speci Specifica ficatio tionn implic implicati ations ons..

The RCS prima primary secondar ry to secon daryy leakage has:

A. NOT excee exceeded Tech. Spec.

ded the Tech. Spec. limit.

B. exceeded NOT excee Tech. Spec.

ded the Tech. Spec. limit. Howe However ver,, be in Mode Mode 3 in:s; in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> hours..

C. exceeded excee Tech. Spec.

ded the Tech. Spec. limit. Be in ModeMode 3 in :s; 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />.

hour.

D. exceeded excee Tech. Spec.

ded the Tech. Spec. limit. Be in ModeMode 3 in :s; 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> hours..

REFERE REFE RENCNCE PROVID E PROV IDEDED 169 169

NRC DRA NRC DRAF FTT 07/24/0 07/24/07 7 Q #85 Q#85 ANSWER ANSW ER:: CC KA: 00003 KA: 000037G 7G2.12.1.33.33 As itit relate As relates s toto Steam Steam Gene Generator rator Tube Tube Leak: Leak: Ability Ability to to reco gniz e recognize indica indication tionss forfor system system opera operatingting param parameteeters rs which whic h are are entry-entry level

-leve l condition condit ionss forfor techn technicalical specif specifica icationtions s.. 3.4/4.

3.4/4.0 0 10CFR5 10CF R55: 5: 43.b.2 43.b.2 Refe renc

Reference:

e: 3-ON 3-0NOOP-0 P-071 71.2,

.2, Step Step 7, 7, 9A 9A TS 3.4.6.

TS 3.4.6.2.c2.c PCB Sectio PCB Section 5, Figure n 5, Figure 15, 15, Unit Unit 33 R-15 R-1 5 Prima Primary ry to to Secon Secondar daryy LeakLeak Cog Level:

Cog Level: 33 Applic Applicat ion 1/ Analy ation Analysis sis Level 33 becau Level becaus see the the opera operator must locate tor must locate the correccorrectt point point on on the R-15 R-1 5 curve, curve, read read the value value from the the curve curve (which (which is is less less than the TS TS limit) limit) and and then then relate relat e the air in-in-leakage leakag e to the needneed to multipmultiply ly the valuevalue by by 7. Then the opera the multip oper tor must ator mus t comp com are pare multiplieliedd value value to the TS limit limit of 500 gpd and determ determine ine the TS limit limit has been exceeded excee ded.. The opera operator mus tor mustt then recall recall the guidaguidance nce of ONOP ONOP-07 -071.2 1 .2 to be in Mode 3 within Mode within 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> which which is more restric restrictiv tivee than the TS limit of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> hours..

Question New Quest ion Examiner note: note: ONOPONOP 71.2 and TS have been frozen frozen earlie earlierr revisio revision. n.

5000 cpm = = 122 gpd from graph graph.. Multip Multiply ly 122 X 7 scfm = = 854 gpd which TS limit of 500 gpd from one S/G. whic h excee exceeds ds Prov Proviide de PCB Sectio Section Figuree 15 as a refere n 5, Figur referen nce ce Respon Respo nsese Anal Analyysis:sis:

A. Inco Incorr rrect ect bec becau ausse e S/G tube leaka leakag gee has exceexcee ded the Tech eded Tech.. Spec Spec.. limit and the unit mus mustt be in Mod Mode e 33 in s; 11 hourhour.. PlauPlaus ible bec sible becauausse e ifif the curv curve e is read direcdirecttly ly with withou outt mult multipiplyi ng by 7, lying 7, the S/G tube leaka leakag gee will not not have have exce excee eded ded the Tech Tech.. SpecSpec.. limit limit..

B.

B. Inco Incorr rrect ect bec becauausse e S/G tube leaka leakag gee has has exce excee ded the eded the Tech Tech.. Spec Spec.. limit limit andand the the unit unit musmustt be be inin Mod Mode e 33 in in s; 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> hour.. PlauPlaus ible bec sible becau aussee ifif the the curv curve e isis read read direc direct tly ly with withou outt mult multipiplyi lyingng byby 7, 7, the the S/G S/G tube tube leaka leakag gee will will not not havehave exce excee ededded the the Tech Tech.. SpecSpec.. limit limit and and 66 hour7.638889e-4 days <br />0.0183 hours <br />1.09127e-4 weeks <br />2.5113e-5 months <br /> hours s isis the the time time iden identif tifiedied byby Tech Tech..

Spe Specs cs to to go go from from Mod e Mode I1 to to ModMode e 3.3.

C.

C. Corr Corre ect ct per per the the refer refere ence nce D.

D. Inco Incorr rrect ect bec becau ausse e the the unit unit mus must t be be in in Mod Mode e 33 inin s; 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> hour.. Plau Plaus ible bec sible becau ausse e S/G tube S/G tube leakageleaka ge has has exce excee eded ded the the Tech Tech.. Spec Spec. . limit limit whic which allows h allow s 66 hrs hrs to to HSB HSB..

170 170

NRC DRA NRC DRAF FTT 07124/0 7 07/24/07 Q #86 Q#86 Unit 33 isis at Unit at 100%

100% powepower with the r with the 3A 3A Norm Normal al Conta Contain inmen mentt Coole Cooler r (NCC (NCC) ) out out of of service servic e on on aa cleara clearan ce (ECO nce (ECO).). The The 3B 3B NCC NCC subse subseq quent uentlyly trips.

trips.

Which ONE Which ONE of ofthe the follow following describ ing descr ibeses the the effect effect on on RCP RCP opera operati tion on and and thethe correc correctt operato opera r resp tor response? ons e?

A.

A. RCPRCP stator stator tempe temper atures rature will start s will start to to rise.

rise.

If stator tempe If stator temper atures rature exceed s excee 248°F,, trip d 248°F trip the the reacto reactor,r, transi tion to transition to 3-EOP-E-O, 3-EOP -E-0, "Reac Reacto torr Trip Trip or or Safety Safety Injecti Injection, on," and and stop stop allall RCPs RCPs..

B.

B. RCP stator RCP stator tempe temper atures rature will start s will start to to rise.

rise.

If stat If stator or tempe temper atures rature exceed s excee 248°F,, conta d 248°F contact ct the the Electr Electrica icall Maint Mainte enanc nancee Superv Super isor as visor as direct directed ed byby 3-0NO 3-ONOP-0 P-0-4-411.1,

.1, "Reac Reacto torr Coola Coolant nt Pump Pump Off-Off-Normal,"

Norm al, for for autho authoriz ationn to rizatio to contin continuuee RCP RCP opera operati tions ons above above 248°F248° F..

C.

C. RCP pump RCP pump bearin bearing temperrature g tempe atures s will start start to rise.

rise.

IfIf bearin bearing temperrature g tempe atures exc s excee eed 225°F,, trip the reacto d 225°F reactor, r, transi tion to transition 3-EOP-E-0, 3-EOP -E-0, "Reac Reacto torr Trip or Safety Safety Injecti Injection, on," and stop all RCPs RCP5..

D. RCP pump pump bearin bearing temperrature g tempe aturess will start start to rise.

bearing If bearin temperrature g tempe atures exceed s excee d 225°F 225°F,, conta contact ct the Electr Electricaicall Maint Mainte enanc nancee Supervvisor Super isor as direct directed 3-ONOP-0 ed by 3-0NO P-0-4-411.1,

.1, "Reac Reacto torr Coola Coolant nt Pump Pum p Off-Off Normal, authoriz al," for autho ation to contin rizatio continu uee RCP operaoperati tions ons above above 225°F225°F..

171 71

NRC DRA NRC DRAF FTT 07/24/0 07/24/07 7 Q #86 Q#86 ANSWER ANSW ER:: AA KA: 003A2 KA: 003A2. .0303 Ability Ability toto (a)

(a) predic predictt the the impac impacts ts ofofthe the follow followinging malfu malfun nction ctions s oror ope operarati ons on tions on the the RCP; RCP; and and (b)(b) based based on on those those predic predicttions, ion s, use use proce pro ced dures ure s to to correctt,, contro correc control, or mitiga l, or mitigat tee the the conse conseq uences quenc es of of those those malfu malfun nction ctions s or or opera operati tions:

ons:

Pro blem Proble mss assoc associat ed with iated with RCPRCP motor motorss,, includ includinging faulty faulty motor mo s tors and and curren cur ren t, t, and and winding windin and bearin g and bearing temper g tempe ature proble rature problem ms. s. 2.7/3.1 2.7/3.1 100FR5 10CF R55: 5: 43.b.5 43.b.5 Referen Refer ence: ce: 3-ONOP-041 3-0NO P-041..1, 1, Step Step 44, 44, FO ED pagepage StepStep 11 && 55 SD-29,, Page SD-29 Page 10 10 and and Fig.

Fig. 11 Cog Level:

Cog Level: 22 comp compre hension rehen sion - LevelLevel 22 becau becaus see the the SRO SRO must must recog recogni nizeze that that NC NCCs Cs provid providee coolin cooling to the g to the RCP RCP motormotor comp compar artme tmentsnts thereb ther eby y coolin cool ing g the stator stator and not and not thethe pump pump bearin bearing gs.s. HeHe then then must must underunderst stand and that that two two NCCs NC Cs canno cannott maintai maint ainn the contacontain ment ambie inmen ambient temperrature nt tempe ature const constan antt at full power power,, and that an an increas increa see inin conta contain ment tempe inmen temperratureature will cause cause an an increa increas see in the stator stat or temperrature tempe atures s of the RCPs RCPs,, he then must must recall recall the thresh thresho old ld tempe tem per rature atur e to take take action and the correc action correctt action action to take,take, New Quest New Questio ionn Respon Respo nsese Analy Analysi s:

sis:

A. Correct Corre ct per the refere referen ce.

nce.

B.

B. Incorreect Incorr ct becau becausse e If stat statoror tem tempeperrature aturess exc exceeeedd 248° 248°F F,, ope opera ratotorsrs shoshould uld trip the reac tor, reactor, tran sitio transi tionn to 3-E 3-EOP OP-E-

-E-0,0, Re "Reac actotorr Trip or Saf Safetyety Injecti Injec on,"

tion, and..

and stop all RC RCPs Ps.. Pla Plaususib le bec ible becau ausse e RCRCP P stat statoror tem tempe perrature atur ess will startt to rise star and 248 248°F°F is the tem tempe perrature ature requ requiriring ing ope opera tors rato rs to take acti action on. . Also the the Ele Electrctriical cal Sup Super ervvisor isor maymay authautho oriz rizee ope operaratition on inin exc exces esss of of limit limits s for stator stat or tem tempe perrature ature ifif the auth autho oriz ationn is rizatio is giv givenen bef before startin ore star tingg the the RC RCP. P.

C.

C. Inc orreect Incorr ct bec becau aussee RCRCP P pum pump p bea ringg tem bearin tempe perrature aturess areare depdepen enddent ent upo upon n COW CCW con conditditiions, ons, not not thethe run ningg of runnin of NCC NCCs s.. Pla Plaus ible usib becau le bec aus see if if the the pump pum p bea ringg tem bearin tempe perrature aturess incrincreaeassee to to >> 225 225°F°F,, the the ope operaratotors rs should sho uld trip trip the the reac reactotor,r, got got toto EO P-E-0 EOP-E -O andand stop stop RO RCPs Ps..

D.

D. Inc Incorrorreect ct bec becauaussee RORCP P pum pump p bea bearin ringg temtempe perrature aturess are are depdepenenddent ent upo upon n COW CCW con ditiions, condit ons, notnot the the run ningg of runnin of NOO NCCs s.. Pla Plaus usibible becau le bec aus se e if if the the pump pum p bea bearinringg tem tempe perrature aturess incrincreaeasse, e, 225 225°F°F isis the the tem tempeperrature ature requ requir ing ope iring opera ratotors rs to to take take acti on..

action 172 172

NRCDRA NRC DRAF FTT 07/24/0 07/24/077 Q #87 Q#87 Operato Opera torsrsareareperfor perform ming ing3-EOP 3-EOP-ECA--ECA-1 1.1, .1,"Loss LossofofEmer Emerg gency encyCoola Coolant nt Rec Recircircu lation, ulation in resp ons e

," in response totoaaLOCA LOCAand andfailure failureofofbothboth RHR RHRpump pumps. s.

Asdirect As directed ed by by3-EOP 3-EOP-ECA- -ECA-1 .1, both both Conta 1.1, Contain ment tSpray inmen Spraypump pumps s (CSPs ) have stop ped stopped. . (CSP5) have been been The STA The STAsubsesubseq uently quent reports ly report an Orang s an Orange e path path onon Conta Con inmen tainmentt pressu pressure. re.

Which ONE Which ONE of ofthe the follow followi ng descr describ es the ing ibes the correc correctt opera operato torr respo respons nsee and for the acti for the action? on? and thethe basis basis A.

A. Continu Contin uee perfor perform ing ECA-1 ming ECA-1.1. .1.

Mainta Maint in CSP s ain CSPs stopped instop ped in accor accord ance with dance with thethe guida guidan ncece ofof ECA-1 ECA-1.1.

Maximizes Maxim izes availa availabbility ility of of the the RWST .1.

RWST invent invento oryry for for injecti injectio onn flow.

flow.

B.

B. Continu Contin uee perfor perform ing ECA-1 ming ECA-1 .1. .1.

Sta Start rt CSPs CSPs in in accor accord anc e dance with with the the guida guidan nce ce ofof FR-Z.

FR-Z.1 1..

Contain Conta ment barrie inmen barrierr protec protecttionion isis aa highe higherr priorit priority y than injecti injectioonn flow flow as as long as RWST as RWST level level is >> 60,0060,000 gallons long 0 gallon s..

C.

C. Transitition Trans ion to to FR-Z.

FR-Z.1 1,, "Resp Respo nse to High onse High Conta Contain inmen ment Press Pressuure." re.

Sta rt CSP s in Start CSPs accordance acc ord ance withwith the guidaguidan nce ce of FR-Z.

FR- 1.

Z.1 .

Contain Conta ment barrie inmen barrierr protec protecttion ion is aa highe higherr priorit priorityy than injecti injectioon flow as n flow long as lon g as RW ST leve as RWST level > 60,0 l is 60,00 000 gall gallononss..

D.

D. Tra nsitition Trans ion to FR- FR-Z. Z.11,, Re spo nse to Hig "Resp onse High h Con Conta inmen tain ment Pre Press ssuure."

re.

Ma inta in Maintain CSPs CSP s stop stoppepedd in acc accorord anc dance e wit with the gui h the guidadannce ce of ECA-1 of ECA-1 .1. .1.

Ma ximizes Maxim izes ava ilabbility availa ility ofof the the RWRWST ST inv inven ento tory for inje ry for injecti ctioon flow..

n flow 173 173

NRC DRA NRC DRAF FT T 07/24/0 07/24/077 Q#87 Q#87 ANSWER ANSW ER:: 0D KA:

KA: 006G2.4.6 006G 2.4.6 As itit relate As relates to Emer s to Emergen gency cy Core Core CoolinCooling: Knowled g: Know ledge ge of of sympt symptom om based based EOP EOP mitig ation mitigation strate strategies gies.. 3.1/4.

3.1/4.0 0 IOCFR5 10CF R55: 5: 43.b.5 43.b.5 Referenc Refer ence: e: 3-EOP-EC 3-EOP -ECA- A-1 .1, Step 1.1, Step 88 3-EOP-FR 3-EOP -FR-Z -Z.1

.1,, CAUT CAUTION ION PriorPrior to Step 8 Cog Level:

Cog Level: 33 Analy Analysis sis Level 3 becau Level because se the situation situati require on will requir e the SRO to analyz analyze e comp competin etingg priorit ies priorities for the remai remaining RWST injecti ning RWST injection water and determ on water determine ine that even thoug thou ghh a highe higherr priority priorit procedur y proce duree (FR-Z (FR-Z-1) would start the CSPs

-1) would CSPs the EOP mitiga mitigating ting strate strat gy egy to follow is to conse follow conserve rve the RWST RWST inven inventorytory to protec protectt the core.

core. The SRO must mus t understan under stand d that a transi transition FR-Z.1 is requir tion to FR-Z.1 requireded but that a cautio caution n in FR-Z.1 FR-Z .1 states states that the CSPs CSPs shouldshould be opera operated ted iaw the requir requirem emen ents ts of ECA-1 ECA-1 .1. .1. The SRO must relate must relate the plantplant condit conditionionss and determdetermine ine that maint maintaini aining ng the reducreduced ed injec tion injection flow estab lishe lished d in ECA-1 ECA-1 .1 .1 is more of a priorit priorityy than runnin runn ingg the CSPs CSPs under these condit under conditionionss even thoug though h an Orang Orange e path on the conta containm inmen entt exists exists..

New QuestQuestion ion

Response

Respo Analysis:

nse Analy sis:

A. Incorrect Incorr because ect becau se the Oran Orang gee path on cont conta ainm inmenentt integr integrityity mus mustt be addressed addre ssed but the EOP mitiga mitigating ting strat strateegy gy will not run aa CSP CSPs recircculat s if recir ulation ion is not avail availa able ble in orde orderr to main mainttain ain injec injectition on flow for as long as poss possib le.

ible.

B. Inco Incorrrrect ect beca becau usese the OranOrang gee path on cont conta ainm inmen entt integ integr ity mus rity mustt be addr addre essed ssed but the CSP CSPs s will not be run if recir recirc culat ulation ion is not availavaila ble in able in orde orderr to mainmainttain ain injec injectition on flow for as long as poss possibible.

le.

C. Inco Incorrrrect ect beca becau usese the OranOrang gee path on on cont conta ainm inmenentt integ integr ity mus rity mustt be be addr addre essed ssed butbut the CSP CSPs s will not not be be run run ifif recir recirc culat ulation ion isis not not avail availa ble in able in orde order r to to main mainttainain injec injectitionon flow flow forfor as as long long as as poss possib ible.

le. Plau Plaus ible beca sible becau usese trans transiition tion will will be be mad made e toto FR-Z FR-Z.1 .1 whic which h will will direc directt that that the the CSPCSPs to be s to be start starte edd unle unless ss the the RWS RWST T isis need neede edd for for injec injecti tion on flow flow..

D.

D. Corr Corre ect ct per per the the refer refere ence nce 174 174

NRC NR C DR DRA AFFT T 07/2 4/07 07/24/ 07 Q #88 Q# 88 Opera Op erators tors are are resrespon pondin dingg to to aa red reduceuced Intake d Inta ke Co Coolin oling Intake Inta ke Co Coolin oling W g Wa Wate terr (IC (ICW)

W) flow flow due due to g Waate terr Sys Syste tem m lea leakag kage e.. to WhWhich ich ON ONEE of of the the foll folowlowing ing des descrcribibeess the the effe effect ct (if(if any any)) on Co ole rs Coolers (NC (N CC Cs5)) abiability lity to on the the No Norma rmall Co Conta ntainm inment ent to remremoveove hea he at t fro from m the the Co Co nta tha thatt effe effect ct,, and and the the cor nta inm inm ent ent ,

, the the con co seq ns eq uen ue ces nc of correcrectt opeoperaratotorr res respon pons es of se?

e?

The NC The NCCs Cs abiability lity toto rem remove ove hea heatt is:

is:

A.

A. degra deg radde d. Co ed. Contantainminment ent tem temperperatatuureress will will INCINCR RE EA 125°F and 125 and equ equip ASSE E tow towardard the the TSTS limlimit of me ipment nt env environ ironm meentnta all qua qua lifi lific of Initiat e cat atio ion ns s WI LL LL be be cha cha llen llen ged ged .

Init Co iate Conta ntainm inment ent Pur Purgege in in acc acco Purge ordrdaanc nce with with O-OO-OP P-0

-0553, 3, "Co Cont ntaain inm Pu rge SysSyste temm.." meent nt B.

B. degra deg radde d. Co ed. Conta ntainminment ent tem temper perat atuureress will will INC INCR RE EA AS SE 125°F and equ 125 equip E tow towardard the TS limit of ipmme nt environ ent ironm ent menta all qualifi lificcat Isolate the affe atio ionnss WI LL be challenged.

affect cteed d portion tion of the ICW lOW opera sy sys ste tem m and est abl ab ish lis h at least one ope rabble le ICW hea head derer.. one C. unaffeffeccte tedd.. Containment temper peratatuureress will will NOT CHANGE and equ enviro nm ironmeent ntaall qualifi lificcat ion atio s equip ipmmeentnt will NOT be cha ns will chall llen en ged ge d.. Init Ini iate Purge in acc acco rda nc ordance with tiat e Co nta inm ent with O-OO-OP -05 P-0 3, "Co 53, Cont ntaain inmmeent nt Purge Sys Syste tem m.."

D. im impprorovveded.. Containment temper peratatuureress wil willl DECREASE and equipm enviroiron nmme ent ntaall qua qualifilificcat ion ipment atio nss wil willl NOT be challenged. Isolate portio tion n of the ICW sy sys ste m and est the affeect aff cte edd tem estababllisish h at least on one e opope rab era le ICW he ble hea adder er..

175 175

NRCDRA NRC DRAF FTT 07/24/0 07/24/07 7 Q #88 Q#88 ANSWER:

ANSW ER: BB KA:

KA: 022A2.

022A2 .0404 Abi lity Ability toto (a) (a) predic predict the t the impacimpacts ofthe thefollow ts of foHowi ingng malfu malfun nction ctions s ororopera operati tions onson CC S; and CCS; and (b) based (b) bas ed on on those those predic predict on the the ion s, tions, use use proce pro ced dures ure s to to correc cor t, rect , contro con l, or mit igat mitigatee the the conse conseq uences ofthose trol , or quenc es of those malfu malfun ctions nction s ororopera operati tions:

ons: Loss Loss of wat er. 2.9 water. 2.9/3.2 /3.2 ofservic service e 100FR5 10CF R55: 5: 43.b.5 43.b.5 Referen Refer ence: ce: 3-ONOP-019 3-0NO P-019,, StepStep 55 RNO,RNO, SD-02 SD-029, 9, Page Page 8, 8, SD-04 SD-040, 0, Page Page 77 Tech Specs Tech Specs 3.6.1.

3.6.1.5 & Basis 5 & Basis Cog Level:

Cog Level: 22 comp compre hension rehen sion Lev el 22 becau Level becaus see the the opera operato torr must must recog recogni nizeze that that thethe ICWICW systemsystem provid provides es heat heat rem ova l for removal for the CCW the CC W system system whichwhich provid provides es heat heat remov rem ova al l for for conta con inmen tain men t via via the Nor mal Normal Conta Contain ment cooler inmen coolers and the the s and the Contr Control ol Rod Rod DriveDri ve Mech Me chaanism nism cooler coo s. The actions action s ofof sever several ONOPss will reduc lers . The al ONOP reduce heat loads e heat loads on the system sys tem but but ultima tely the CC W CCW tempetem perrature atures ulti mat ely the s will rise causin causing g the conta contain inmen ment tempetemperrature ature to rise.

rise.

New Quest New Questio ion n Respon Respo se Analy nse Analysi s:

sis:

A.

A. Incorreect Incorr ct bec becau ausse e ther there e is no proce procedduralural diredirectctio ionn to init initiate iate aa Con Conta taininmen mentt Pur Purge ge.. PlausPlausib le bec ible becau ausse e the NC NCCs Cs abil ability ity to remremov ove e hea heatt is deg degra rad ded ed and and Con Conta tain mentt tem inmen tempe perrature aturess will incr increa eassee tow towar ardd the TS limit limit of 125125°F °F and and equ equip ipm mentent env enviroironnmen mental tal qua lific qualif ationss wiN ication will be be chachallellen nged ged and bec and becau ausse e init iating initiati ng aa conconta tain mentt pur inmen purgege wou would ld red reduc ucee con conta taininmen mentt tem tempeperrature atures. s.

B.

B. Cor Corre rectct perper the the referefererennce ce C.

C. Inc Incorr orreect ct bec ausse becau e the the NCNCCs Cs abil ity to ability to rem remov ovee heaheat t isis deg degraradded.

ed.

Con Conta tain mentt tem inmen tempe perrature aturess will will incr increa eassee and and equ eqUip ipm ment ent enviro environnmenmental tal qua qualif lific ationss will ication will bebe cha llennged challe ged and and becbecauausse e there isis no there no pro proce ced dural ura l direct dire ctioionn to to init iate aa Con initiate Conta tain mentt Pur inmen ge.. Pla Purge Plaususibible le becbecauausse e initiati init iati ng aa con ng conta tain inmen men tt pur purge ge wouwould ld red reduc ucee concontatain mentt tem inmen tempeperrature aturess D.

D. Inc orreect Incorr ct becbecauausse e the the NCNCCs Cs abil ity to ability to rem remov ovee hea heat t isis deg degraradded.

ed. Con Conta inmen tem tempe perrature aturess will will incr eassee and tain mentt increa and equequip ipm ent env ment enviro ironnmen men tal qua tal qualif ication lific s will be be cha llennged.

ged. Pla atio ns will challe usibible Plaus le bec ausse becau e ope operaratotors rs will will Isol Isolateate the affe the affect ed portio of ofthe the ICW ICW sys tem and cted por tionn system and esta estab blis h atat leas lish leastt one one ope operarabble le ICWICW hea heade der.r.

176 176

NRC NR C DR DRAF AFTT 0712 4/07 07/24/ 07 Q#89 Q# 89 Both Bo th uni units ts are are at at 100 100%  % powpower er wit withh all all sys syste tem ms s inin nor norma mall alig alignm nment ent..

• • 0-O0-OSP SP-07

-075.11,1, "AuAuxixilialiarryy Fee Feed wa dw ateterr Ins Inserv ervice ice Tes Test,t," isis bei being ng per the A the "A" AF AFW W pum pump. p. perform forme edd to to tes testt

• • The Sh The Shift ift MaManag nager er isis not notifie ifiedd tha thatt the the "A" A AFAFW W pum pumpp dev develo eloped ped 300 maxim ma ximum um obt obtain ainabl ablee spespee 300 gpmgpm atat aa edd ofof 580 58000 RP RPM.M.

Which Wh ich ON ONEE of of the the foll follow owing ing desdescr ibe crib ess the the corcorrec rectt ope opera rattor Sp ec . im Spec. implica pli cattion ionss of or resrespon pons see and and thethe Tec Tech.h.

of this this eveevent?

Decla De clarere the the "A" A AFAFW W pum pump:

A.

A. operable and ope and retu return rn it toto ser servic vice.

e.

Align Alig A AF W pum n "A" pump to Tra Train 11 to restore tore full fuN com compliaplianc ncee with the TS LCO.

B.

B. inoper ino perable but available and ret retuurn rn it to servic vicee..

Align Alig A AFW pump to Train 2 to n "A" restor toree full complia pliancncee with the TS LCO. D.

C. inoper ino perabl e and remove it from from service.

Align Alig n "c" C AF W pump to Train 1I to extend the AFW TS action time hours to 30 days. from from 72 D. inoperable and remove it fro ino fromm servic vice e..

Align Alig n B "B" AFW pump to Train 2 to ext hours to 30 days. end the AFW TS action ion time frofrom m 72 177 177

NRCDRA NRC DRAF FTT 07/24/0 07/24/077 Q#89 Q#89 ANSWER:

ANSW ER: CC KA:

KA: 061G2.

061G 2.22 2.2.22 As As ititrelate relates to the s to the AFW AF W system system:: knowl knowle dge of edge oflimitin limitingg condit conditiions onsfor foropera tions safe ty lim its.

safety limits. 3.4/4.1 3.4 /4.1 operati ons andand IOCFR5 10CF R55: 5: 43.b.2 43.b.2 Referen Refer ence: ce: 3-OP-0 3-0P- 075,75, Sectio Section 7.1 n 7.1 0-OSP-0-OSP 075 .11 , Ste

-075.11, Stepp 7.1.6.1 7.1.6.1 TS 3.7.1.

TS 3.7.1.2 Actionss 1I and 2 Action and 33 Cog: Level:

Cog: Level: 22 comp compre hension rehen sion Lev el 2 bec Level 2 becausee the aus the opera operato torr must must recogrecogni nizeze that that 58005800 RPMRPM and and 300 300 gpmgpm do do not meet the meet the criteri criteria for a a for a SAT SA T test.

test. and and the not the pump pump must mu st be be declar dec lareedd inope ino perrable.

able Then the opera the operato torr must must recog recogni ze that that even . Then nize even thoug though h either either "8" B or or "c" C AFW AF W pump pum can be alig ned aligned to to Train Train 1, 1, OP-07 OP-0755 direct p can be directs that "c" s that C AFW AFW pump pum p be be aligne alig nedd to to Train Tra 1 and finally itit is finally is this this action action that will restor in 1 and restore e 2 indep indepe ndentt AFW enden AFW trains trai ns and increa see the Act ion Action TimeTime to to 30 days.days. incr eas the New Quest New Questio ionn Respon Respo nsese Analy Analysi s:

sis:

A.

A. Incorre Incorr ct becau ect becausse e the "A"A AF W pump AFW pump fail failed ed to dev devel op eno elop enoug ughh flow or RPM RPMss and and mu mustst be dec lare declared d ino inopeperrable able and take taken n OO OOS.S. PlaPlaus usibiblele becau bec aus se the e the A

"A" AF AFW W pumpump p was DO OOS S dur ing the Inse during Inservrvicice Testt and wou e Tes would ld norma nor mal lly ly bebe retu return rneedd to servservicicee and alig alignenedd to TraTrainin I1 ifif the test hadhad bee been n SASAT.T.

B.

8. Inc orreect Incorr ct bec becau aussee the the A "A" AF W pum AFW pump p fail failed ed to to dev devel op eno elop enougughh flowflow or or RPM RPMs and mu st and must be dec be lareed declar d ino inopeperrable able and s and take taken n DO OOS. S. PlaPlaus usib ible le becau bec aus see the A

"A" AF AFW W pumpump p nea rly deli the nearly verred delive ed the the req requir uireed flow and d flow and mig might be con consid (err one ous (erroneously) av ly) ailable ht be sideered red "availa ble" for for serv servicice.

e.

C.

C. Cor Corre rectct per per thethe refe refererennce ce D.

D. Inc Incorrorreect ct bec becau ausse e ope rato exte nd opera rs nee tors needd to to alig align "c" AF n C AFW pump W pum p toto TraTrain in I1to to extend the AFthe AFW W TS TS acti actionon tim time e from from 72 72 hou hours rs toto 30 30 day days.

alre s. "8" B AFW pump AFW pump isis alreadadyy alig nedd to aligne to Tra in 22 but Train but unt il C until "C" pum pump p isis alig aligne d to ned to Tra Train in 1,1, the the TS TS Act ion Tim Action Time e isis still still 72 72 hou hoursrs. . Pla usibible Plaus le becbecau ausse "8" AF e B AFWW pump pum p is norma is normally lly alig alignenedd toto Tra Trainin 2..

2 ..

178 178

NRNRC C DR DRA AFFT T 0712 4/07 07/24/ 07 0#Q #9 900 UnUnitit 44 isis inin Mo Mode de 1I witwithh all all sys systetemms opera s ope rabble le,, wh whenen CoConta ntainm gas mo gas monitonitors ,

rs, PR PRMS MS- 11/12

/12,, Sa inmentent par parti ticu culate late and and

-11 Samp mple le Inle Inlett Tem Temp perera atutur ree swi switch tch,, TS TS-36

-3640, 40, fail faisls HIG HIGH H..

Which Wh ich ON ONEE of ofthe the foll folow lowing ing des descr ibe crib ess the the Tec Techh SpSpec ec imp impli lica cat tion ionss of of this this fail faiure lure??

Th Thee TS TS-36 -3640 40 fail faiure lure::

A.

A. did NO did NOTT affe affec ctt ope operarabbil ity of ility of R-1 R-111 or or R-1 R-12. 2.

Th e The apppliap cable lica ble TecTech h SpSpecec LCLCD D isis sat satisfi isfied ed..

B.

B. disabl dis abled ed R-1 R-111 onl only.

y.

Verify Ve rify R-1 R-122 isis ope operarabble and the le and the ass associ ociat ateedd Tec Tech h SpSpec ec LCLCDD will will be be sat satisfi ed..

isfied C.

C. disabl dis ableded R-1R-122 onl only.

y.

Verify R-1 Ve R-111 is is ope operarab ble and the le and the ass assoc ociiat ateedd Tec Tech h Sp Spec LC LCD will will be be sat isfiied satisf ed..

D.

D. disabl dis abled bot ed bot R-1 h R11 and and R-1 R-12.2.

Until ope Un operarab bilility ity of of R-1 R-111 andand R-1 R1 22 isis res restore tored d,, comply wit with the app Tech Tec h Sp Spec Act Actioionn Sta State temme nt.. appli lica cable ent 179 179

NRCDRA NRC DRAF FTT 07/24/0 07/24/077 Q #90 Q#90 ANSWER:

ANSW ER: 0D KA:

KA: 073G2.

073G 1.33 2.1.33 As As ititrelate relates to Pro ces s to Processs Radia Radiati on Monit Monito tion ring: Ability oring: Abilitytoto recog recogninizeze indica indicat tions ions for sys tem ope rati system operating paramng parame terswhich which are for eters are entry-entry-le level vel condit con ions diti ons for for techn tech ical spe cifi cations nica l specification s.. 3.4/4.

3.4/4.0 0 10CFR5 10CF R55: 5: 43.b.2 43.b.2 Referen Refer ce:

ence: SD-068, SD-06 8, Page Page 27 27 and and Figure Figuress 1919 and and 20 20 TS 3.4 TS 3.4.6.1 .6.1 Cog Level:

Cog Level: 22 comp compre hension rehen sion Lev el 2 Level 2 becaubec aussee the the opera operato torr must must recog recogni ze that nize that TS-36 TS-364 400 failing failing high high trigge trigger rss the high tempe high temperrature ature alarm alarm at at 125°F 125°F andand closes the closes the the inlet inle t and and outlet out let valves valv es and and stops the samp the sample pumps.

le pump Becaus stops

s. Becau see the the samp sample flows throug le flows through h both bot h R-11 R-1 1 and R12 in series bot h R-1 I and both R-11 and R-12 R-12 havehave lostlost samp sample and RI 2 in series,,

flow. The le flow. The TS TS Action Act ion Statem Sta tem ent applie app liess ifif both R-I1 and R-11 and R-12 R-12 areare inope inoperrable.

able. IfIf either either R-11 both R-11 oror R-12 R-1 2 are satisfi sati ed, sfie d, the LCO LC D is is sati sfie satisfied. d.

New Quest New Questio ionn Respon Respo se Analy nse Analysisis:s:

A.

A. Incorre Incorr ct becau ect becausse e the tempe temperrature ature swi switch tch fail failure disabl ure disa ed bot bled both R-111 and h R-l and R R-

12. Plausib

12. Plaus le bec aus e ible because if the swi switch tch fail failure ure had not disa disabl ed R-1 bled R-111 and R-12, R-12, the app licaable applic ble Tec Tech h Spe Spec c LC LCO D wou wouldld be sati satisfi sfieed.

d.

B.

B. Inc orreect Incorr ct bec becau ausse e the the tem tempe perrature ature swi switch tch fail failure disabl ure disa ed bot bled both R-111 and h R-1 and R R-12.

12. Pla usib Plaus le bec ible becauausse e ifif R-1 R-122 rem remaiaine nedd ope opera rabble, the app le, the applic licaable Tech ble Tec Spec h Spe c LC LCO O wou wouldld be be sati sfieed.

satisfi d.

C.

C. Inc orreect Incorr ct bec becau ausse e the the temtempe perrature ature swi switch tch fail failure disabl ure disa ed bot bled both R-111 and h R-1 and R R-12.

12. Pla usib Plaus le bec ible becau ausse e ifif R-1 R-111 rem remaiaine ned d ope operarabble, the app le, the applic able licable Tec Tech h SpeSpec c LC LCO D wou wouldld be be sati sfieed.

satisfi d.

D.

D. Cor Correrect ct per per thethe refe refererennce ce 180 180

NRC NR C DRDRAF AFT T 07/2 07/24/

4/07 07 Q#91 Q# 91 Unitit 33 isis at Un at 100 100% pow power er wit withh all all sys syste ms tem in nor s in norma mall alig alignm nmentent and withdr wit hdraw awn. n. and con control trol rod rodss full y fully

• • An Annun nuncia ciatortor FF 4/64/6,, RP RPIS IS PO POWE WER R TR TROU OUBLBLE,E, ala alarmsrms..

• • TheThe fiel field op era d ope rattor reports or rep orts tha thatt the the 300 3D01 1 sup sup ply ply bre bre ake akerr to to thethe RP tripped trip ped ope open. n. RPI inv inverte erterr has has Predict the Pre the imp impacactt of of this this fail failur uree on on the the rod rod pos positio ition indindica ication tion (RP action act ionss req require uired. d. (RPI) sys system and and thethe RPls RP Is will will be be powpowere eredd from from the the GV CVT:

A.

A. automatically.

aut RPls RP Is ind indication tion mamay hav e cha chan ged.

nge Initial Init iallly imple y imp lem me nt 3-0 ent 3-ONONOP-0 P-028.

28.11,, "RG RCC G Mis Misal alig ignnm me ent nt.."

Then The transi n tran sititio onn to 3-03-ONO NOP-0 P-028.28.2, "RG RCC G Pos Positiitioonn Ind Indication tion Malfun lfunct ctio ionn."

B. automatically.

RPIs ls indicatio tionn will will NOT change.

Initial Init iallly Imple y Imp me lem ent nt 3-0 3-ONO NOP-0P-028.

28.2, "RGRCC G Pos Positiitio onn Indicatio tion n Malfun lfunct ctio ionn."

C.

G. afterr manual tran afte transf sfe er.

r.

RPIs ls indicatio tion n may hav e cha chan ngegedd..

Initial Init ialllyy imp imple lem me nt 3-0 ent 3-ONO NOP-0P-028.1, "RG RCC G Mis Misal aligignnm meentnt.."

Thenn tran The transi tio siti onn to 3-0 3-ONO NOP-0 P-028.

28.2, "RGRCC G Position Indicatio tionn Malfu lfun ctio nct ionn."

o.

D. afterr manua afte nuall tratrannsf sfeer.

r.

RPls indicatio tion n wil l will NOT change.

Initial Init ialllyy Im Impplelem meent nt 3-O 3-0 NONOP-0 P-028.2, R "RG CCG Po Pos siti itio onn Indicatio tionn Malfu lfun ctio nct ionn."

181 181

NRC DRAFT 07/24/07 Q# 91 ANSW AN SWER : A KA::

KA 014A2.

A2 .02 02 Abiility Ab lity to (a) predict dict the imp impactactss of the foll follow owiing ng mamallfun functio ctions or operat ratiion RPIIS; RP S; and (b) based on tho those se predict onss on the ions, use pro diction pro ced ced ure s to cor rectt,, control, or rec mitiga mit igattee the con conseqsequences of tho thosese ma mallfun functio ctions or operations: los the RPRPIls. s. 3.1/3.6 losss of pow er to IOCFR 10C FR5 5:

55: 43.b.5 Refere ferenc nce e:: SD-006 Pa SO Paggee 11 and Fig Figure 5, 3-ONO 3-0 NOP-0 P-028.

28.1, Step 1.1, 5.6 3-ONO 3-0 NOP-0 P-028.

28.2, Step 1.1, 5.3 3-ARP 3-A RP--09 097 .CR 7.C R,, F 4/6 416 Cog Co g Level: 11 Re Reccal alll New Ne w Qu Que stio est ion n Respo Re sponse An Ana alylysi siss::

A. Corrre Co rect ct per the refe refere ren nce ce B. Incorr Inc orre ct because ON ect ONOP OP-028.2 is not a direct ent OE has demonstrat entrry y pro procedure and sta stattion ion trated ed tha thatt the out put vol voltag tage e of the CV inverte inv erter res C\I T is diff diff eren ere t nt than tha n the resuulti ltin ngg in all RP RPIlss indica icatting ing diff differe erenntly mu st first perform act tly afte r tran sfer sfe .

r. Op erator torss actiiononss of ONONOPOP-028.1 and the then n wh whe enn directe cted tran sitio siti onn to ON ON OP OP -028.2 d.. Plausibusible le because The RP RPII pow er supply has aut transf tran sfe err rreedd from the inv inverte auto o--

erter to the CV T.

C. Incorrorre ct because the RP ect RPII pow er supply has auto-t inv inverte erter to the CVT. Plausi o-trran anssfe rre ferr edd from the usib le because the RP ble RPIlss will indicaicattee low er tha before the pow er interrup rruptio tion than n n and operato rators rs will Initially impimp 028.1, "RC RCC Mis Misalig lem ent 3-ONO 3-0 NOP-alignment ent,," the thenn transitio sition n to 3-0 3-O NO NO Indicaicattion ion Malfunction. P-0 P-0 28.2

28. 2,, RC "RC C Pos Pos itio ition n."

O.

D. Incorr orre ectct because the RP RPII pow er supply has auto-tr inv inverte erter to the CV T and because ON o-tran anssfe rre ferr edd from the ONOP OP-028.2 is not a direct ent entrry y pro procedure. Op Operator torss will Initially impimplem lement 3-03-O NO NO P-0 P-0 28.1

28. 1,, RC "RC C Mis Misaligalignment ent,," the then n transitio sition n to 3-0 3-ONONOP-0P-028.

28.22,, RC "RC C Pos Pos itio itio n Indica Malfunction. n." Plausi usib le because the primary procedure ble icattion ion respond to this event is ON ope rat rato orsrs will use to ONOP OP-028.2 182

NRC NR C DRDRA AFFT T 0712 07/24/

4/07 07 0#Q #92 92 AA req require uired continu d con tinuououss fire fire wa watch tch has has bee the 3C been establ n est ablish isheded in in the the Au Auxilia xiliarryy Bui the 3C MCMCC. C. Build ldin g at ing at

• • AR ARMSMS Ch Chann annel el 15, 15, AuAuxx Bld Bldgg No North rth N/S N/S CoCorrid rridor, or, ala alarms rms and and its increa inc reases ses toto 80 80 mr/mr/hr hr.. its dig digital dis display

• • The RO The RO depdepreresssesess the the ChCh.15

.15 HIG HIGH H alaalarm PB PB on on the the AR ARMS MS con control no tes notes tha thatt the the dis display rea reads ds 55 mr/ trol pan panel andand mr/hr hr,, the the sam sam e val val ue ue as as the the shown In sho In Att Attach achme ment nt 11 (AR hig highh ala ala rm val val ue ue (ARM MSS SeSettpo poiint nt Lis List and and LocLocat High "Hi Area gh Are a RaRadiation atioion ns) s) of of 0-O 0-ONO NOP-0P-066, tion MoMonito nitori ng Sys ring Syste temm Ala Alarm.

rm."

Which Wh ich ONONE E of of the foll follow owinging des descr ibe crib ess the the validit idityy of of this this reading and the correct op era ope rattor respon or res pons se?e?

The alarm is:

The A. valid.

Evacu Eva cuaate perso te per son nss in the affe affect cteed d area.

Do NOT includ lude the fire watch person in the evacuatio tion n..

B. valid.

Evacu Eva cuaate perso te per son nss in the affeaffect cteedd area.

Inc lude the fire watch person in the evacuacuatiotion n..

C. NOT valid.

Silenc Sile nce e the alarm rm..

Notify Radiatio tionn Protec tectio n to survey the area.

tion D. NOT valid.

Sil Sileenc ncee the alarm rm..

No Notify tify Radiatio tionn Protec tectio tionn to ins install tall aa portable rad radiati iation monit nito or.r.

183 183

NRC DRAFT 07/24/07 Q #92 Q# 92 ANSW AN SWER : B KA::

KA 072G2 G2..1.1 1.14 As it rela relatetess to AreArea Ra Rad iati dia on Mo tion Monito nitoring: Kn Kno ow wle leddgege of system status crit whiich wh ch require the notific ation of pla ificatio criteria plan ntt personnel.

nel. 2.5/3.3 IOCFR 10C FR5 5:

55: 43.b.4 bA , 43.b.5 Refere ferencnce e:: O-ONO NOP-066, Step 2 and CA UTION prior to Step 3 Cog Co g Level: 2 com compre prehension Level 2 bec because the operator mu st rec recoogngniize ze tha thatt the ala alarrm m is valvaliidd and tha continu tinuous fire wa wattch ch loc loca tion atio n at the 3C MCC is adjacent to thatt the loca loc tion atio n and that respon the AR MS Cha Ch nneell 15 ann ponse se to an AR MS ala alarrm m tak takeses priority over a continu wattch wa ch.. tinuous fire New Ne w Qu Que stio est ionn Respo Re sponse An Ana lysi aly siss::

A. Incorr Inc orre ct bec ect because fire wa wattch ch personnel should be inc incllud ude d in the evacuation.

ed usib Plausi le bec ble becaus e the ala alarrmm is val valiidd and a loc locaall area evacuation tion is required.

B. Corrre Co rectct per the refe refererenncecess..

C. Incorr Inc orre ct because the ala ect alarrmm is val valiid.

d. Plausiusib le because the ala ble silenced if the ala alarrm alarrm m ma mayy be m is det deteermrmiine nedd to not be val vali d id and Protectecttion ion will subseq bec aus e Rad Ra iati dia on tion sequen uentlytly be cal callled ed to sur surv ey the area.

vey D. Incorr Inc orre ect ct because the ala alarrm m is val valiid.

d. Plausib usiblele because the ala silenced if the ala alarrm alarrm m mamayy be m is detdeteermrmiine nedd to not be val vali idd and Protec tecttion ion will subseq bec aus Raddia e Ra iati on tion sequenuentlytly be cal callled ed to ins insttall all a portab tabllee radiation monitor.

184

NRC NR C DRDRAF AFTT 07/2 07/24/

4/07 07 Q #93 Q# 93 Opera Op erators tors are are res respon pondin dingg to to aa larg large break e bre ak LOLOCA CA whwhenen thethe ST folow foll lowing ing QSQSPD PDSS Co Corere Exi Exitt The STA A rep reports orts the the Therm rmoococouupl plee rea readin dings:

gs:

QuQuad ad 1I Quad Qu ad 22 Quad Qu ad 33 Qu Quad ad 44 CETT Tem CE Temp p CETT Tem CE Temp p CETT Tem CE Tempp CE CETT TemTemp p R7 R7 660 660 K5 K5 1250 125 H8 H8 415 415 P8 P8 590 590 K3 K11 Ku 666 666 K3  ???

??? F9 F9 835 835 N6 N6 604 604 J2 N1 N155 680 680 J2 2300 230 E8 E8 7??

???

N4 N4 625 625 G6 H1 H133 602 602 G6 675 675 BlO B1 0 905 905 Mu1 M1  ???

??? G1 H9 H9 615 615 G1 1560 156 B5 B5 660 660 M9 M9  ??

???? F5 E1 E14 622 622 F5 230 2300 L8 L8 670 670 F3 F3 E12 E12 688 1780 178 Which ON ONE of the foll follow ing des owing descrcribibeess the cor coree condit ditiion Manag Ma nager should giv givee to the Unit Supervis on and the dire ctio direct n the Shift ion or?

CETs J2 and F5: F5:

A. should be included in the core con dit ditiion on evaluatio tion n..

A Red Path exists sts.

Transitio n to 3-EOP-FR-C.1, "Re tion Respspoons nsee to Inadequate Core Cooli olin g."

ng.

B. should be included in the core con dit ditiion on eva evalua luatio tion n..

An Ora Orang ngee Path exists.

Transitio tionn to 3-EOP-FR-C.2, R "Reesp spoons nse e to Degraded Core Co Cooli olin g."

ng.

C. sho shoulduld NOT T be included in the core con A Re conditditiion on eva evalualuatiotion n..

Red d Path exists.

Transi nsitio tionn to 3-EOP-FR-C.1, R "Reespspoons nse e toto Inade deq quuat atee Core re Co Cooli olin g."

ng.

D.

D. sho uld should NO NOTT bebe included ed in in the the coree concondit ditiion on eva evalualuatiotion An An OrOraang ngee Pat Pathh exists n..

sts..

Tra Transi nsitio tion n to to 3-EOPOP-FR-FR-C. -C.2, 2, R"Reesp spoons nsee toto Degraded ded Core re Co Cooli olin g."

ng.

185 185

NRCDRA NRC DRAF FTT 07/24/0 07/24/07 7 Q #93 Q#93 ANSWER:

ANSW ER: AA KA:

KA: 017A2.02 017 A2.02 Abi lity to Ability to (a) (a)predic predict theimpac t the impacts ts ofofthe thefollow followiingng malfu malfun nction ctionss ororopera tions ITM sys tem  ; and ITM system; and (b) based (b) bas ed on onthose operati onson on the the those predic predict ion tions, s, use use proce pro dures ced ure s to correc t, contro or mit igat or mitigate the e theconse conseq uences quenc es of ofthose those malfu to cor rect , con troll,,

malfunnction ctio s ns or or opera ope tions:

rations: Core Core Dama ge 3.6/4.1 3.6/4.1 Damage 10CFR5 10CF R55: 5: 43.b.5 43.b.5 Referen Refer ence: ce: 3-EOP-F-0, 3-EOP -F-0, EncloEnclosu re 22 and sure and Basis Basis Page Page 20 20 Cog Level:

Cog Level: 33 Analy Analysi siss Lev el 3 bec aus Level 3 because the opera e the operato torr must must analyz analyze e all all of of the the core core tempe temperratureature data then recall then recall that that thethe evalua evaluattion ion is data and and is based based on on the the five five highe hig hesst t CETs CE Ts includ ing the failed CETS and and that that thresh thresho incl udi ng the failed CETS ld for old for Red Red Path Path is is 1200° 1200°F F (Oran (Or ang ge Path =

the QS PD S e Pat h = 700°F 700 °F) ).

. Revie Rev ieww of of the QSPDS readin reading gss revea reveals that includ ls that includiing ng the the failed Conditi fail ed CETs CE Ts revea rev ls eals a Red Red Path Pat h Condi on and tion and FR-C.

FR-C.1 needs to be 1 needs be implem implementedented.. This tho ugh This must must be determdete rmi ined ned even eve n that though that if the if the failed failed CETsCETs are not includ include and ed, d, five CETsCE T5 are are greate gre ater r than than 700°F 700 and thethe opera operato torr will conclu conclud °F dee errone erroneo usly that only ously only an OrangOrange e Path Path exists exists..

New Quest New Questio ionn Respon Respo se Ana nse Analy lysi s:

sis:

A.

A. Cor Corre rect ct per per the refe refere ren ces nces B.

B. Inc orreect Incorr ct bec becau ausse e aa Red Red Pat h exis Path ts and exists and tran transi tion sitio should n sho uld bebe mad made to e to 3-E OP -FR 3-EOP-FR-C.1, Re-C.1 , "Resp spo nse to onse to Ina Inadedeqquate uate Cor Core e Coolin Coo lingg."

. Plaus Pla usib ible becau le becausse the the con conditditiions ons for for anan OraOrang ngee Pat e Pathh also also exis existt and and EO EOP- P-F FR-C.

R-C 2

.2 is is the the correc t pro proceceddure ure to to tran sitio n for cor rect transi tion for an an Ora Orangngee Pat Path.h.

C.

C. Inc orreect Incorr ct bec becauausse e the the failfaileded CE Ts sho CETs should uld be be incl includ udeed d inin the the eva evalua luationtion.

Pla usib le Plausible becau bec ausse e aa Red .

Red Pat Pathh exis exists ts and and opeopera ratotors rs should sho uld transi tran sitiotion to 3-EO P-FFR-C.

R-C.1, n to 3-EOP- 1, Re "Resp spoonsense to to Ina deqquate Inade uate Cor Core Coolin e Coo g."

ling.

D.

D. Inc orreect Incorr ct bec becauausse e the the fail ed CE failed CETsTs sho should uld be be incl includ udeedd inin the the evaevalua luation tion.

Pla usib le bec Plausible because aus e the .

the con ditiions condit ons forforan an Ora Orangngee Pat Pathh also exis also existt and and EOP-FR- C.22 isisthe EOP FR-C. the cor rectt pro correc proce ceddure ure toto tran transi sitio tion n forforanan Ora Orangngee Pat Path.

h.

186 186

NRC NR C DRDRA AFFT T 07/24/

07/2 4/07 07 Q #94 0# 94 With Wit h Un Unitit 33 at at 80%

80% pow power,er, ope opera tor rato rss are are res respondindingg to to aa Xe Xenon non osc RO rep RO reportsorts the the foll follow owinging val values ues of oscilla illation tion.. TheThe of Axi Axial al Flu Fluxx Dif Differe ferenc ncee (AF (AFD D):):

• • N-41:

N-4 1: +13

+1

• • N-42:

N-4 2: +122

+1

• • N-43:

N-4 3: +1

+1 6

• • N44:

N-4 +16

+1 Which Wh ich ON ONE E of of the the foll follow owinging des descr ibe crib ess the the con conditi dition on ofof the the rea eff ect effect (if (if any any) ofof allo allowin wingg con reactors r's AFD andand the continu tinued ed opeoperati ration on wit withh the thesese con conditi dition onss??

The rea The reactor AF AFD is: is:

A. within wit hin the operati ration ona all spa spac e.

ce.

Operatio Op n tion at thisthis pow power level may continu tinue e indefin efinit itel elyy..

B. within wit hin the operat ratiion onaall spa spac e.

ce.

Wi th With the positiv itive AFD, Hot channel factors transsie tors may be exc exce eed eded if a short term tran ien ntt occurs. term c.

C. outside the operat ratiion ona all spa spacce.

e.

Hot channel factors tors may be exc exce eed eded as a result of contin tinu ed operat ued this pow er level.

this ratiion on at D,

D. outside the operat ratiion onaall spa spacce.

e.

Hot channe l nnel factors tors wil willl not be excexce eded as a res eed result ult of contin tinu ed operat ued at thithiss pow er level but mayy be ex ratiion on excceeed eded if a short rt ter termm tratran sie nsi nt occurs.

ent REFERENCE PR PROVOVID IDE ED D 187 187

NRC NR C DRDRAF AFT T 0712 07/24/

4/07 07 Q #94 Q# 94 ANSW AN SWER ER:: CC KA::

KA G2.1.7 G2 .1.7 Ability Ab ility to to eva evaluluaate plant te pla nt per perform forma nce anc and ma e and make ke ope operati ration onaall jud operati ope rating ng chacharacteri teristi judgemgeme ent ntss bas ed on based on sticcs, reactorr beh s, rea behavi avior, andand ins instrum trume entnt inte interp rprret etaatio tionn.. 4.4 4.4 IOCF 10C FR R5 5: 43.

55: 43.b.5 Refere Re ferenc ncee:: PCB Se PC Secctio tion 5, 5, Fig Figure ure 1A1A O-AD O-A M-DM-53 5366,, Att Attach achme ment nt 1, 1, Se Secctio tion 3/4 3/4.2 PCB Se PC Secctio tion 7, 7, Fig Figureure 11 Cog Lev Co Levelel:: 2 com compre prehensio n Le vel Level 2 bec beca use the ope aus opera rattor will have to plot the giv or will givenen AFD val refere refe rennce provid ce pro vided.

ed. The Then valuesues on the n the ope opera rattor or wil willl hav e to rec ognize that 2 val outside the operat out ratiion ona all spa spac values ues are

e. 2 of the 4 val ce. values ues out sid e imp the operat ratiion ona all spa spac e. The im pli lies es tha t AF D is out of ce. The ope opera rattor will then have to rela or will the operat ratiion ona all spa spac rel ate te tha t bei ng out side of e me ce meansans Hot channel factors tor s continu tinued ma y be exc ex ceeed ed ed as a result of ed operat ratiion on at thisthis pow er lev el.

New Question Prov Pro vidide e PCB Secti ctio onn 5, Fig Figuurere 1AIA and and Secti ctio onn 7, FigFigu urere 1 1 as reference nces s Respo spon nsese An Anaalylyssis is::

A. Incorrect bec beca use the AFD is outside the.op aus be ca ope erarati tioona nall sp spa acce.

e. Plausible bec use 2 of the four AFD values are aus AFD was within the operat wit hin the ope ratiion rat ona all sp spa accee and if ratiion ona all sp spaacce, e, operat rati ion on at this thi contintinuuee indefiefinnititel elyy.. s pow er level ma mayy B. Incorrectect bebec caaus use the AFD D is outside the ope operat ratiion ona all sp spa be bec caaus use 22 of the four AFD values are acce.

e. Plausi usible ble AFD was within the ope wit hin the ope ope rati rat ona ion al l spa sp ac ce and ifif e and operatratiion onaall sp spa acce, e, hot hot chachanne nnell factor ex exc ceeed ededed as tors s wo uld uld not not be be as aa resresultult ofof contin tinu ued ed ope operatratiion on at at thi thiss power er level. el.

C.

C. Correct ct per thethe refrefe ere ren ncces es..

D.

D. Incorrect ect be bec caaususee hothot cha channennell fac factor tors s ma mayy be be ex exc ceeed eded con contintinuued ed opeoperat ed as as aa resresult ult of of ratiion on at at thi thiss power er level.

el. Pla Pla usi usi out outsidee the ble ble bec be ca aus us e e the the AF AFD D isis the ope operat ratiion ona all sp spaacce.

e.

188 188

NRC NR C DR DRA AFFT T 07/2 07/24/

4/07 07 Q#95 0# 95

• • Unitit 33 RC Un RCSS temtemper perat atuure re isis 400 400°F.°F.

• • Unitit 44 RC Un RCSS temtemper perat atuure re isis 310 31 0°F

°F..

Which Wh ich ONONEE of of the the foll foNow owing ing ide identif ntifie iess the the min minim imuumm req require Co nd en sat Co nde nsa tee Sto Stora uiredd wa water ter inv invent entory ory in in the ragge Ta nk e Tan k sys systetemm and and de des scr ibe crib ess the inv entory invent ory?? the the ba bassis is for for tha thatt req require uiredd A.

A. 210,0 210 ,0000 gallon 0 gal lons.

s.

En su Ensurres suffici es suf ficien entt wa water ter to to ma mainta intain Unit 33 at in Un at Ho Hot Sta Stan ndb dby con minim min imuum m of of 2323 hou hours.

rs. conditi dition on for for aa B.

B. 210,0 210 ,00 00 gallon 0 gal lons.

s.

Ensur En sures suf es sufficificien entt wa water to mainta intain Unit 4 at Hot Sta in Un Stanndb dby condit minim min imuum m of 23 hours2.662037e-4 days <br />0.00639 hours <br />3.80291e-5 weeks <br />8.7515e-6 months <br />. ditiion on for a C. 420,0 420 ,00 000 gallonlons.

Thiss is suffic Thi ficiien entt wa ter to maint intaain in both Units at these condit ditiion mi nim minimuum m of 15 hou rs and then cool dow onss for a Mode de 4. n bot h rea cto r coo lan t sys syste tem Mo mss to D. 420,0 420 ,00 000 gallons.

Th is is This suffic ficiien entt wa ter to maint ain inta in both units at these condit ditiion onss for a minim min imu um m of 23 hours2.662037e-4 days <br />0.00639 hours <br />3.80291e-5 weeks <br />8.7515e-6 months <br />.

189 189

NRC NR C DR DRAF AFT T 07/2 4/07 07/24/ 07 Q#95 Q# 95 ANSW AN SWER ER:: AA KA KA,; G2.1.3 G2 .1.322 Ability Ab ility to to exp explain lain and and app apply ly all all sys system tem lim limits its and and preprecau caution tions.s. 3.8 3.8 1OCF 10C FR R5 5:

55: 43.b.2

43. b.2 Refere Re ferenc ncee:: 3-OP-0 3-0 P-018.

18.1, 1, Ste Step 4.24.2 Tech Tec h SpSpecs ecs 3.7 3.7.1.3 O-AD 0-A DM M- 536

-53 6,, SeSecctio tion 3/43/4.7.1

.7.1.3 Cogg Lev Co Levelel:: 22 Co Comp mpreh rehens ension Level Lev el 2 bec beca aususe the ope opera rato torr must evaluate the RCS provid vided ed and determine that Unit 3 S tem temper peratatuureress is in MoMo de de 3 and Un it 4 is in Mo

4. Only afte afterr this this determinatio tionn is made can the operat Mode de correct Tec Tech.

h. Specs rato orr app ly the ecs..

New Question Respo spon se An nse Analy alysis sis:

A. Correct per the refe refere nce ren ce B. Incorrect bec beca use there is suffic aus ficiien entt water to maint intaainin only Unitit 3 at these condit ion ditionss for a min minim imu umm of 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br />. Un Unitit 4 would be on RHR at this temperperatatu ure re and its AFW system valved out this gallons is the requir . Plausible be bec caaus us e 210 ,000 uireedd amount of water inventory in the CSTs.

C. Incorrect bec beca use only 210,000 gallons is the aus inv entory in the CSTs and Un requir uire edd amoun ountt of wa ter Unitit 33 is the onl y unitt tha tha tt wo be becca use Un aus Unitit 44 would be on RHR at thi uld needd CS nee CST T water valved out. Plausible be thiss tem per pe atu rat urere and and itsits AFW sys sys bec caaus use the numberss sho tem tem by the Te sho wn wn are are the num ber s s provided ed Tec chh Spec Basis sis document ent..

D. Incorrect ect bebeccaaususee onl onlyy 210,000 gallonss is invent is the the req requiruireedd amamoun ountt of of water ter entoryory inin the CS CSTsTs andand UnUnitit 33 isis the the onlonl y y uni uni tt tha tha tt wo wo uld uld nee nee d CS be beccaaus usee Un Unitit 44 wo would uld be be on on RH d T CST water ter RHR R atat thi thiss tem tem per pe ratatu re ure and and its valved ved outout.. Pla Plausi usible ble be its AF AF WW sys sys tem tem bec caaus usee thethe numberss sho shownwn areare the by by the the Te Tecchh Spec the numberss pro provid vided ed ec Basissis doc docum ument ent..

190 190

NRC NR C DR DRA AFFT T 07/2 07/24/

4/07 07 Q #9 Q# 966 BoBothth Un Units its are are atat 100 100% powe

% pow er.r.

The 3A The 3A ED EDGG isis outout of of ser servic vicee and and aa 1414 day day Tec Techh SpSpec ec Act for Un for Unitit 3.3. Actio ionn Sta tem State me ent nt isis inin effe effecctt ECO EC O req reques uests have ts hav been e bee subm n sub mititt ed by ted by Ma Main inteten nanancece to eq uip equipment me nt from from serservic vice: to rem remove ove the the foll owing follow ing e:

• • 3A 3A Co Contantainm inmentent Sp Spray ray Pu Pumpmp

• • 3A 3A EmEmerg ergenc ency Conta y Co ntainm inment ent Filt Filter er

• • 3A 3A ReResid sidual ual HeHeatat Re Remomoval val PuPumpmp

• • Pre Press ssu uri zerr He rize Heate ater Co Contro ntroll Gro Grou upp IfIf tak taken en outout of of ser servic vice, e, wh which ich ON ONE E of of the wo uld red the foll follow owing ing com comp pon onent ents s from would reduce uce the the UnUnit 33 effe effec tivee Tec from the the list list abo abov vee ctiv Te ch h Sp Sp ec Ac Acttio ionn Ti Tim mee from to 2 ho to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />?? urs fro m the cur cu ren t rrent 14 14 daydays s A.

A. 3A Co Conta ntainm inment ent Spray Pump B.

B. 3A Em Emergergencencyy Co ntainment ent Filt Filter er C. 3A Residua uall Heat Remova vall Pump D. Press Pre ssu uri zer Heaterr Contr rize oll Gro ntro Grouup p 191 191

NRC NR C DR DRA AFFT T 0712 07/24/

4/0707 Q#96 Q# 96 ANSW AN SWER ER:: BB KA::

KA G2G2.2.2

.2.24 4 Ability Ab ility toto ana analy lyzze the effe e the effect ct ofof ma mainteintennan ancece actactivit ivities ies on on LC LCO D stastatus tus.. 3.83.8 1OCF 10C FRR5 55:5: 43. 43.b.b.22 Refere Re feren ncece:: TS 3.8 TS 3.8.1.1

.1.1,, Act Actio ionn d.1d.1 O-OS O-O SP P-0 23. 3,

-023.3, Ste Step p 6.16.1.2.2 andand Att Attac achhm meen ntt 22 Ste Step p 88 Cogg Lev Co Level el:: 22 com comp reh pre ensio hen sionn Le vel Level 22 bec beca usee the aus the opeopera ratotorr mu must st rec recogn ogniz izee that the 3A EC comp com pononentent and and the then detdeter ECF is is a Train B B safety erm miinene thethe imp im pac act t of of tha tha t pie pie ce ce ser vic servicee dur during the the ma mainte of equ eq ipm uip ent ment being out of inten nanance ce act activi ty.. The ivity The SR SRO mu the Act the Actio n tim e ion time to 2 hou mu st st ana an lyz aly ze e that thisthis reduce uced d hours rs ifif the the opeopera torrss pla rato placedced a Train B while the 3A ED EDG is is OOS. B saf ety com co mp pon onent ent OOS S S.

New Question spon Respo nsese Analy alysissis:

A. Incorrect bec beca use 3A Containment aus ent Spray Pump is Train A equ equip ipm being out of service will will not sho short meentnt and rten en the TS Act Ac ion tio n tim e from fro m ass oc associiat ate ed with the EDG to 2 hou d with the 14 day dayss hours rs.. Pla Pl auusi sibble le bec be caaus us e ing DOS wi" OO will intr introd oduucece an add additio tak the 3A CSP itional TS Ac Acttio ionn time to comply wit 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, not 2 hou hours with h but willl be it wil rs..

B. Correct per per the ref refeere ren ncce e C. Incorrect ect be bec caaus use 3A Residua uall Heat Re Remo movalval Pu Pump mp is is Tra Train in A eq an d and being out of ser servicvicee wil equ ipm uip meentnt wi"l not not sh sho ortrten en the TS TS Act Ac ion tio n ass assoc ociiat ateedd witwith h the EDG tim e e from fro m the 14 14 day da yss G to 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br />. rs. Pl Pla auusi sib ble le bec be ca aus RHRP RP DO OOS S wil us e e tak tak ing ing the the 3A 3A wi"l int intrrod odu uce ce an an addadditioitional nal TS TS Ac ACtio wil wi"l be tionn timee to to com com ply ply with wit but itit h but be 77 da ys ,

days, not not 22 hou hours. rs.

D.

D. Incorrect ect be bec caaus usee thethe pressu ssuriz rizeerr con controtroll gro groupup he hea eq equ uip me ipment nt an d bei ate ters rs areare TraTrain in AA and being ng out out of of serservicvicee wil wi" l not not the the 14 sho sh rten ort en the the TS TS Act Ac ion tio timee fro n tim from 14 daday yss assassoc ociiat edd wit ate withh thethe ED EDG G m the to to 22 hou hou rs.

rs. Pla Pl auusi sib ble le bec be caaus e wh the con contro l trol grogroupup he heaate rs do ters do not not ha us e wh ile ile hav vee aa Te Tecchh SpSpec ec LC LCO, O, the the BU BU he hea ate rs wh ters which ich are are alsalsoo Tra Gro Gr oupup "A" A

Train in A "A" eqequ uipipm meent nt dodo and and tak takinging he hea ate rs OD ters OOSS wil wi"l int the the BU BU Gro Gr oupup "A" A

intrrod odu uccee anan add additioitional nal TS TS Ac Act ion tio wil l be will be 72 72 ho urs n tim tim ee to to com com ply ply with wit but h but itit hou rs,, not not 22 ho hou ursrs..

192 192

NRC NR C DR DRA AFFT T 07/2 4/07 07/24/ 07 Q #9 Q# 977 WhWhic ichh ON ONEEof ofthe thefoll folow lowing ing actactiv ivititi ieses req require uiress dire direc ctt sup Senio Se niorrRe React actor Opera erator? supeerv rviisio sionn by by aa lice nse licen d sed or Op tor?

A.

A. Under Un derw waateterrTV TV camcameerara sur surve veiill ance llan ce inin the the refu refueelin lingg cav cavit ityy B.

B. React Re actor vesse or ves sell irra irrad diaiattion ion spe spec imen cim en rem removaovall C.

C. Lowe Low err inte intern rnaals remova ls rem ovall D.

D. Contro Co ntroll rod rod unl unlat atcch ing hin g 193 193

NRC NR C DRDRAF AFT T 07/2 4/07 07/24/ 07 Q#97 Q# 97 ANSW AN SWER ER:: 0D KA::

KA G2G2.2.2

.2.277 Know Kn owled ledge ge of of the the refu refuel ing elin proces g pro cess. s. 3.5 3.5 IOCF 10C FRR5 5:

55: 43.b.61b.

43. /b.77 Refere Re ferenc ncee:: 4-OP-0 4-0 P-038. 38.1, Ste Step 4.14.1 & & SeSecctio tion 4.64.6 Cog Lev Co Levelel:: 11 rec recall Bank Qu Ba Quest estion Respo Re spon nsese Ana Analy lyssis is::

A. Incorr Inc orrect ect bec beca aususe und erw erwater TV camera surveillan is not considered a Core Alte ce in the refu refuel elin ingg cavity Altera tio rati onn and as such doe doess not requir supervision by an SRO. uire dire e directct Plausible bec beca aususe this this act activi ivittyy typica direct dire ctlyly over the core while the ically lly occurs upp er inte internrnaals ls are removed and irradiated fuel in place.

B. Incorrect bec beca use reactor vessel irradiatio aus tionn specimcimen removal is not consid ered a Core Alt Alteera tio rati onn and as such doe by an SRO. Plausible bec do es s not requiruire e dir dire ct superv ect ervision beca use thi aus thiss act act ivi ivit tyy occ urs dire dir while the reactor head is rem ectctly ly ove rr the reactoctor oved.

C. Incorrect be beccaaususe lower inteintern rnaals ls remova ovall is not consideredd aa Co Alt Alteera tio n ration and as suchh do doe ess not requir re Plausible be uire e dir direect ct sup superv ervisio isio n by an SR bec caaus use thi s act this activi ivittyy occurs dir O.

reacto direect ctly ly overr the reareacto ctorr while the ctorr headd and upper int inteern rna als ls are removed.

D. Correct per the ref ere refe nce ren ce 194 194

NRC NR C DR DRA AFFT T 07/2 07/24/

4/07 07 Q#98 Q# 98 Core Co re off-off-lo loaadd isis inin pro progre gress ss on on UnUnitit 3.

3.

• • OnOnee fue fuell ass assembly bly isis latc latch heded on on the

• the mamanip nipula ulator tor cra crane.

ne.

An oth

• An oth er fueer fuell ass assembly bly isis ver vertica ticall in in the the upe upennde derr on on the the SpSpent ent Fue Fuell Pit Pit sid side.e.

AA refu refuel ing cav eling cavity ity sea seall fail failur uree occ occu rs and urs and cav cavity ity lev level el beg begininss dec decre reaasi sinng g raprapidly idly..

Which Wh ich ONONEE of of the the foll follow ing des owing descr ibe crib ess the the cor corre recctt ope operarato torrs' s res respon pons seses??

A.

A. Insert Ins ert the the assassembly bly onon the the ma manip nipula ulator into into the the cor Lay the Lay the ass assembly core e and and lea leave ve itit latc latched hed.

in bly in thethe upe upennde derr dow downn and and lea leave itit in in the the tran transsfe ferr car cart.

B.

B. Insert Ins ert the the assassembly on on the the ma manip nipulator into into thethe cor Relatc Re latch the ass h the assembly in core e and and unl unlatc atch it.it.

in the the upe upen ndeder and and momove it to a fue fuel rac rack.

k.

C.

C. Do NO Do NOT Ins Insert the assembly bly on the manipulator into into the cor the edg edge e of of the corcore coree but move it to e and leave it sus su sppen en ded de d..

Lay the assem Lay embly bly in the upe upenndeder down and leave it in the tra nsf er cart.

nsfer D. Do NOT Ins ert the ass assememblybly on the manipulator into into the cor nsfer transf canaal.

er can l. coree but move it to Relatc latch h the ass assem embly bly in the upeupen der and move it to a fuel rac nde k.

195 195

NRC NR C DR DRA AFFT T 07/2 07/24/

4/07 07 Q #9 Q# 988 ANSW AN SWER ER:: AA KA::

KA G2G2.3.1

.3.1O 0 Ability Ab ility toto per perform form pro proced cedu res ure s toto red reduce uce excexce ess ssiive ve lev levels again aga insstt per perso sonnn el exp expo els of of rad radiati iation on andand gua guard rd nel su osure.re. 3.3 3.3 I OCFR 10C FR55:55: 43.b.41b.

43. /b.77 Refere Re feren ce::

nce 3ONOP-0 3-0 P-O3 3.2

33. 2,, Ste Step 5.1.2, p 5.1 .2, 5.1 5.1.3.3 &

& NONOTE TE Pri Prior or to to Ste Step p 5.2 5.2.4

.4 Cogg Lev Co Level el:: 1I Re Recalll New Qu Ne Quest estion Respo Re spon se An nse Analy alysis sis:

A. Corre ct per per the referefererennc e.

ce.

B. Incorrect Inc ect bec beca aususe the ope opera torr sho rato shouuldld lay the ass assememblybly in the upe an andd leave it in the tran transsfe ferr cart. Pla upen nde der down Plau usi sibble le bec be caaus us e ope op erarato torrs sho assem the ass bly embly on the manipulator into s sh ouuld ld insert into the cor coree but shoshouuldld leave it latc latch hed ed.

C. Incorrectect bec beca use ope aus opera torrss sho rato shouuldld insert the ass assemembly bly on the manipulator into the cor into core and leave it latc e and latch ed. Pla hed Plauusisibble le bec be aus ca us e the ope the assassememblybly in the upe upen opera rato torr sh shoouuld ld lay der down and nde and leave it in the trans nsffer er cart.

D. Incorrect ect bebecca use op aus era ope torrss sh rato shoouuld ld insert the ass assemembly int intoo the co corree an d leave it lat bly on the ma manip nipula ulator tor and latcchhed ed an and d bec be ca aus us ass assem embly e the ope op rato era tor r sho sh uld ould lay the bly in the up upe ennde derr do dow wnn an and d leave itit in be bec ca use un in the tra trannssfe fer r car car t.

t. Pla Pl auusi sibble aus unllat atcchh the assassemembly bly heldd by the ma le ass assem ma nip nip ula ula tor tor and an d rela rel tch atc ing hin emblybly in the up upe ennde derr an andd move ve itit to aa fue g the op enn to the op fuell rac rackk are are bot bothh workable ble opopttio ion ope ope era torrs rato s but but neneiith theerr is nss is dir direeccte tedd by by ONOP-03 -033.2 3.2..

196 196

NRC NR C DR DRA AFFT T 0712 4/07 07/24/ 07 0#Q #9 999 UnUnitit 33 has has exp expe rience erie nced d aa loslosss of of offs offsite ite powpower er(LO (LOOP OP).).

• • The The 38 3B ED EDGG has has eneenerg rgizize edd the the 38 3B 4K4KVV bus bus asas des desig ignne ed.

• • 3A 3A ED EDGG loc locked ked out out andand can can NONO T be d.

• SI wa T be res res tar tart ted ed. .

• SI was NO s NOTT req require uiredd and and did did NONOTT occoccur. ur.

Which Wh ich ON ONEE of ofthethe foll folow lowinging desdescr ibe crib ess the the mit mitig igaatio tionn stra strate 3-E 3-EOP OP-ES -ES--O. 0.2 , N 2, "Naturaatu rall Cir teggie iess pro provid videded by by Circulculatio ationn Co Coold oldow own,"

n, for for the the pre presen sentt pla plant nt con cond diti itions ons??

Limitit the Lim the RCRCSS coo cooldo ldown wn rate rate to:

to:

A.

A. 25°F 25° F/h /hrr and and ma mainta intainin RCRCSS sub subcoolin lingg ~ 80° 80°FF toto avo the rm thermaall sho shoc kin avoid the the pos possibilit ilityy of of cki ngg the the reareactorr ves vessesell..

B.

8. 25°F 25° F/h /hrr and and ma mainta intain RCSS sub in RC subcoolin lingg ~ 226226°F to to avo reactorr ves rea vesse avoid the the pos sibilit possib ilityy of of sell hea head d voivoidd form forma tion.

atio n.

C.

C. 60°F 60° F/h/hrr and and ma mainta intain in RCRCS S subcoolin lingg ~ 80°F to avoid the pos the rmall sho therma shocckikin ngg the sibilit possib ilityy of reactor vesvessesell....

D. 60°F 60° F/h/hrr and and mainta intain in RCS subcoo coolin ling g ~ 226°F to avoid the pos reactor ves vessesell hea head d voi d formforma possib sibilit ility y of tion.

atio 197 197

NRC NR C DR DRA AFFT T 07/2 07/24/4/0707 Q #9 Q# 999 ANSW AN SWER ER:: BB KA KA G2G2.4.7.4.7 Know Kn owledledgege of of the the eveeven ntt basbaseded EO EOP P mitmitig igaatio tionn stra strate teggie iess.. 3.8 3.8 IOCF 10C FR R5 5:

55: 43.b.

43. b.55 Refere Re feren ce::

nce 3-EOP 3-E OP-ES-ES--0. O.2,2, Ste Step p 1010,,1717,,18 18 Cogg Lev Co Levelel:: 22 Co Comp mpreh rehensensiv Le ivee vel 2 be Lev el 2 becca aus usee the the SRSRO O mumust st rela relate the los te the losss ofof the the 3A plant pla nt con cond itions diti ons and and det deter 3A 4K 4KV V busbus to to the the pre presensentt erm miinene tha tha t t onl onl y y on one e CR CR DM DM the n mu st rel the n mu st relaate this kno co coo oli ling ng fan fan is is ava av ilab ailab le. He te this know wleled dge ge toto the the effe effec ctsts the He natur nat uraall circ circu lattion ion coo the CR CRDM coo co ling oli ng fan fan s s hav ha e on ula cooldldoow wnn andand det deter erm miinene thathatt the ve on aa higher hig her sub subccoo oolin the low low er er coo co ldo old ow wn n rate rat s and es and mu lingg num numb berers must s mu st be be appappli ed for lied for the giv much ch remova rem ovall fro fromm thethe rea reactor hea givenen plapla nt con co ndditi iti ons on s as as hea t head d isis dim diminis inishheded wit withh onl y one he at one CRDM fan ..

New Ne w QuQuestestion Respo Re spon se Ana nse Analy lyssisis::

A.

A. Incorr Inc orrect ect becbeca use ope opera aus rattor orss sho shouuld ld maint intaainin RCS sub av oid avoid the possi pos bilility ity of reactor ves subccoo oolinling g ;::: 226°°F F toto sib vesse sel l he hea add voi be becca use ope aus opera d form for ma atio tio n. Pla usi Plausibble le rattor orss shoshouuld ld limit the RC S coo coold ldoow wnn rate rate to 25 25°°F F/h/hrr..

B.

B. Correct per Co per the refe refere renncce e C. Incorrec ectt be bec caaus use op ope era ratotorrss sh sho ouuld ld limit the RCS co an d maint coo ldo old ow wn n ratrate e to 25 25° °FF/h and ain inta in RCS su sub bccoo oolin g 2 22 ling 2266° F /hrr ve sse °F to to av avo oid id the the pos po ssisib bilility ity of rea ves sell he hea add void for form maatio tion. Pl Plaauusi of reacto ctorr 80 sibble le be bec caaus usee ma maintintaaininin ing g sub coo 80° °FF is an is an app ap pro roppri atee str riat ate su bc oo ling lin g>>

stra gyy ifif bo teg botthh CRCRDM DM co coo olelers rs are 60 °F 60° F/h /hoourur is is an an attattaain abble are in in ope op rati eration anon and d ina le cocoooldldoowwnn rat rate e tha thatt mi mig ght ht be be viewe co con nssid ideerin ringg the the off we d d as as app ap proroppririat atee off--no norrm ma all ev eve ennt.

t.

D.

D. Incorrec ectt be bec caaususee op ope era torrs rato s sh sho ouuld ld lim limitit the the RC RCSS co Pl au sibble coooldldoow wnn rat ratee to to 2525° °FF/h Pla usi le be bec caaususee op ope era rat tor s sh ors shoouuld ld /hrr avo ma ma int inta ainin RC RC S S sub su bc coo oo ling lin g 226 avoid id the the po ssi pos sib bilility ity of of rea reacto ctorr ve 2 22 6° °F F to to an ves sse sell he hea add voi voidd for formmaatio tionn an and 60° an att ain atta inaabblele co coooldldoow n wn ratrate e tha d 60 °F F/h

/ho our ur isis thatt mimigghtht bebe vieviewewedd as as apapp rop the the off off--no nor rm al ma l eveev ennt.t. pro pri riat ate e con co ns sid ide erin rin gg 198 198

NRNRC C DR DRA AFFT T 07/2 07/24/

4/07 07 QQ #10

1. 100 0 UnUnitit 44 has has exp expe rience erie ncedd aa larg large break e bre ak LOLOCA CA andand con contatain at 28 at 28 psipsig.

g. inmmeen ntt pre pressu ssurere has has pea peak ked ed The Em The Emergergencencyy Co Coord ordina inator tor (EC (EC)) has has NO NOTT yetyet rec receiv eiveded any rad ioa radioactivvecti relea e rele ase ses fro m any ind indica ication tion ofof pot enttia poten iall s from Co Contantainm inment ent..

Which Wh ich ON ONEE of of the the foll folow lowing ing des descr ibe crib ess the the ProProte teccti tive ve Act Actio (P

(PA ARR)) thethe ECEC sho shou ld ma ionn Re Recom comm meen nda dation tion uld makeke dur durin ingg init initial conta ial con tacctt wit withh the the Sta St te?

ate?

A.

A. No PA No PAR R sho shou ld be uld be ma madede unt untilil con confi rmatio firm ation n of of aa rad radioa ioactiv ctive e rele rel ase ease isis ma made.

de.

B.

B. Shelte Sh elterr all all per perso sonns within s wit hin aa 22 mil mile radius e rad ius ofof the the site ou t to out to 55 milmiles in the site and and she shelt lter er all all per sonns perso s es in the dow down nwwiind nd secsectors tors..

C.

C. Evac Eva cuauate allall per perso sonns within s wit hin aa 22 milmile e rad radius of of the site ou outt to to 55 mil miles in the dow site and and she sheltlter er all all per persosonns s es in down nwwiind nd secsectors tors..

D.

D. Evac Eva uate all cua all per persosonns within s wit hin a 2 mil milee radius of the site perso per sonns ou t to s out 5 mil miles site and and eva evac cuauate all es in the dowdown nwwiind nd sectortorss..

REFERENCE PROVIDED IDED 199 199

NRC DR NR DRAFT 07/24/

0712 4/07 07 Q#10 Q# 1000 ANSW AN SWER ER:: BB KA::

KA G2.4.4 G2 .4.44 Know Kn owledledge ge ofof em emergergency pla plan pro protec tective tive actaction recrecomomme mendandationtions.s. 4.0

4.0 100FR55

10C 43.b.5 43.

Refere Re ferencncee:: 3-EPIP 3-E PIP-20

-201101 01,, En Enclo closur sure 1, 1, Category 11 (Ge (Gene 3EPlP nerralal Em Emergergency) 3-E PIP-20-20101, Step 5.1 5.1.4 3-EPIP 3-E PIR-202O101IOI,, Att Attach achment 3, 3, Pa Paggee 11 of 6 Cog LevLevelel:: compre 2 com prehension Level Lev becaus el 2 bec ause the operator mu st det erm with 28 psig inside con tainme ine that the combination of a larg large LO CA wit e break Th nt as cla ssifia fiabble le as a Ge ner al en The n the ope rator mu must recall that the min Em Em erg ency.

withou minim imuumm classific ficaatio tionn for a GE wit hout a rele releas e ase is "Sh Shelter all persons within , eve n persons out to 5 mil all per mile a 2 mil e radius of the site and shelter miles es in the downwind sector torss.

Provide EPIP-20101, En Encloclosur sure e1 I as a Refer ferenc ence New Qu estion Respo nse An Analyalysis sis:

A. Inc orrect because the EC should issue the PAR to she shelterlter all persons within milee radius of the site and she a 2 mil lter lter all persons out to 5 mil mileses in the downwind sector torss.. Plausible because there is radioactive rele no indicatio tionn of potent ential ial releasase ess fro fromm Containment.

B. Correct per the refe refererennce ce C. Incorrect because the EC sho should uld issue the PAR to she shelte lterr all persons within a 2 mil milee radius of the site and she sheltelterr all persons out to 55 mi milles es in the downwind sec sectortorss.. Plausible because evacua conser cua tio tion n cou cou ld ld be con sideredd more servat vative ive than she shelter ltering ing in the event re nt of aa Gener neral al Emergenc ency.y.

D. Incorrect because the EC sho should uld issue the PAR R to she shelterlter all aa 22 mi millee radius of the site and all personss wit with in hin and she sheltelterr all personss out to to 5 downwind ind sec sector torss.. Plausible becausee eva 5 mi milles es in in the the conser evacua cuatio n cou tion could ld bebe consideredd more servatvative ive thann she shelter ltering ing in in the the eve re event nt of aa Gener neralal Emergenc ency. y.

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