ML101620437

301 Draft SRO Written Exam (Section 3)

ML101620437
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Site:	Summer
Issue date:	03/28/2010
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1.1 large LOCA AA large LOCA has has occurred.

occurred. WhichWhich ONEONE of of the following actions the following actions are are corrrect corrrect given given the the following conditions:

following conditions:

• RWST level RWST level isis 17%

17% and continues to and continues to decrease.

decrease.

• RHR sump level is 410 feet and RHR sump level is 410 feet and increasing. increasing.

• • All RCPs All RCPs were were tripped tripped (by procedure) when (by procedure) when RCSRCS pressure pressure dropped dropped below below 1400 1400 psig psig

• The crew The crew isis currently currently performing performing the the actions actions ofof EOP-2.0, EOP-2.0, LOSS LOSS OF OF REACTOR REACTOR OR OR SECONDARY COOLANT SECONDARY COOLANT The following The following EOPs EOPs are are being being considered:

considered:

• • EOP-2.2, TRANSFER EOP-2.2, TRANSFER TO TO COLD COLD LEG LEG RECIRCULATION RECIRCULATION

• EOP-2.4, LOSS EOP-2.4, LOSS OF EMERGENCY COOLANT OF EMERGENCY COOLANT RECIRCULATION RECIRCULATION Transition to:

Transition to:

A. EOP-2.4 A. EOP-2.4 fromfrom EOP-2.0.

EOP-2.0. When When RHRRHR sump sump levellevel reaches reaches the the required required level, level, transition transition to to EOP-2.2.

B. EOP-2.4 from EOP-2.0. When RHR sump level reaches the required level, return to EOP-2.0 and transition to EOP-2.2.

C. EOP-2.2 from EOP-2.0 then transition to EOP-2.4. When RHR sump level reaches the required level, return to EOP-2.0 and transition to EOP-2.2.

D D ..... EOP-2.2 from EOP-2.0 then transition to EOP-2.4. When RHR sump level reaches the required level, transition back to EOP-2.2.

Feedback Distractor analysis:

A and B. Incorrect: The transition is not made directly to EOP-2.4 from EOP-2.0 unless coolant recirculation was established and ,subsequently subsequently lost, this is not the case.

C. Incorrect: The C. The transition from EOP-2.4 EOP-2.4 is is made made backback to the the procedure procedure step in affectaffect which would would have have been been in in EOP-2.2 EOP-2.2 not not EOP-2.0.

EOP-2.0.

D. Correct.

D. Correct.

Reference:

EOP EOP 2, 2, page page 44 of of 32 32 EOP EOP 2.2, 2.2, page page 33 of of 13 13 EOP EOP 2.4, 2.4, page page 44 of of 29 29 K/A KJA CATALOGU CATALOGUE E QUESTION QUESTION DESCRIPTIDESCRIPTION: ON:

- Reactor Coolant System (RCS);

- Reactor Coolant System (RCS); Ability to (a) Ability to (a) predict the impacts predict the impacts ofof the the following following malfunctions malfunctions or operations on the RCS; or operations on the RCS; and (b) and (b) based based on on those those predictions, predictions, use use procedures procedures to to correct, correct, control, control, or or mitigate mitigate the the consequence consequences s of of those those malfunctions malfunctions or or operations:

operations: LossLoss ofof heat heat sinks.

sinks.

Categories Categories Tier:

Tier: 22 Group:

Group: 22 Key KeyWord:Word: RCS RCS Cog Level:

Cog Level: CIA (4.3/4.6)

C/A (4.3/4.6)

Source:

Source: NN Exam:

Exam: SM05301 SM05301 Test:

Test: SS Author/Revie AuthorlReviewer:

wer: RFAlSDR RFAJSDR

2.

2.

The following The following conditions conditions exist:

exist:

Reactor Power

- Reactor

- Power isis 9%.

9%.

- AA Total

- Total Loss Loss ofof All All Service Service Water Water has occurred.

has occurred.

AOP-1 17.1, "Total

- AOP-117.1,

- Total Loss Loss of of Service Service Water,"

Water, has has been been entered.

entered.

RCP temperatures are beginning

- RCP temperatures are beginning to rise.

- to rise.

Service Water

- Service

- Water can can not not be be restored.

restored.

Which ONE Which ONE of of the following describes the following describes the action(s) the the action(s) the operators operators must must take and when take and when (in(in accordance with accordance with AOP-117.1)?

AOP-117.1)?

A.oI Initiate aa reactor A. Initiate reactor plant plant shutdown shutdown perper GOP-4B, GOP-4B, POWER POWER OPERATION OPERATION (MODE (MODE 11 - -

DESCENDIN DESCENDING). G). Stop Stop ONE ONE RCP.

RCP. When When an an RCP RCP motor motor bearing bearing temperatures temperatures oror lower lower seal water bearing seal bearing temperature temperature exceeds exceeds thethe specified specified limit, limit, stop stop the the affected affected RCP.

RCP.

B. Initiate a reactor B. Initiate reactor plant plant shutdown per per GOP-4B, POWER POWER OPERATION OPERATION (MODE (MODE 11 - -

DESCENDIN DESCENDING). G). When an RCP motor bearing temperatures or lower lower seal water bearing bearing temperature exceedsexceeds the specified specified limit, stop stop the affected affected RCP RCP and and one one other other RCP.

RCP.

C. Initiate a reactor plant shutdown per GOP-4B, POWER OPERATION (MODE 11 - -

DESCENDING). Stop two RCPs. When the running RCP motor bearing temperatures or DESCENDING).

lower seal water bearing temperature exceeds the specified limit, trip the reactor and stop the affected RCP.

D. Stop ONE RCP. Initiate a reactor plant shutdown per GOP-4B, POWER OPERATION (MODE 1 1 - DESCENDING).

- DESCENDING), When an RCP motor bearing temperatures or lower seal water bearing temperature exceeds the specified limit, trip the reactor and stop the affected RCP.

Feedback Feedback Distractor Analysis:

Distractor Analysis:

A. Correct: lAW A. Correct: lAW AOP-117.1, AOP-117.1, the the reactor reactor should should be shutdown (not be shutdown (not tripped) tripped) due due to to power power being being 10% (Step

<< 10% (Step 3). Secure aa running 3). Secure running RCP RCP (Step (Step 12).

12). The The affected affected RCP should be shutdown ifif RCP should be shutdown RCP motor RCP bearing temperatures motor bearing temperatures exceeds exceeds 195195 of

°F or or lower lower seal seal water water bearing bearing temperature temperature exceeds 225°F exceeds 225°F (Step 13).

(Step 13).

B. Incorrect: Do B. Incorrect: Do not not wait until temperature wait until temperature are are exceeded exceeded to to secure secure RCPsRCPs C. Incorrect: Step C. Incorrect: Step 12 allows two 12 allows two RCPs RCPs to to be be stopped stopped ifif plant plant conditions conditions permit.

permit. Prudent Prudent action action is to is shutdown with to shutdown with 22 RCPs RCPs running running andand secure secure one one ifif necessary necessary for temperature.

for temperature.

Incorrect: Shutdown D. Incorrect: Shutdown is initiated in in step 3 and Step Step 12 12 secures secures the RCP. RCP. Reactor Reactor is is not not tripped unless above tripped unless above P-7.

P-7.

References:

GOP-4B

References:

AOP-117.1, page 8 AOP118.1, page 5 AOP-118.1, K/A CATALOGUE KIA CATALOGUE QUESTION DESCRIPTION: DESCRIPTION:

- Reactor Coolant Pump System (RCPS); Ability to (a) predict the impacts of the following malfunctions or operations on the RCPS; and (b) based on those predictions, use procedures consequences of those malfunctions or operations: Problems to correct, control, or mitigate the consequences associated with RCP motors, including faulty motors and current, and winding and bearing temperature problems.

Categories Tier:

Tier: 2 Group: 1 Key Word:

KeyWord: RCPS Cog Level: C/A(2.7/3.1)

Source: N Exam: SM05301 Test: S S Author/Revi ewer:

Author/Reviewer: RFAJSDR RFAlSDR

3.

3.

Which ONE Which ONE of of the the following following correctly correctly describes describes the the purpose purpose and and or or function function (not (not all all inclusive) inclusive) of the of the RHR RHR system system and and one one ofof its its Mode Mode 44 Technical Technical Specification Specification requirements?

requirements?

A. Hot A. Hot Leg Leg Recirculation, Recirculation, Refueling Refueling Cavity Cavity Cooling, Cooling, Alternate Alternate Water Water supply supply toto Reactor Reactor Building Building Coolers, Pressurizer Relief Coolers, Pressurizer Relief Tank Tank Cooling.

Cooling. RHR RHR cancan be be deenergized deenergized for for up up to to 22 hour2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> hour provided that provided that corecore outlet outlet temperature temperature isis maintained maintained at at least least 500F 50°F below below saturation saturation temperature.

temperature.

B. Cold B. Cold Leg Leg Recirculation, Recirculation, Hot Hot Leg Leg Recirculation, Recirculation, Simultaneous Simultaneous Cold Cold Leg Leg - Hot

- Hot Leg Leg Recirculation , Alternate Water supply to Reactor Recirculation, Alternate Water supply to Reactor Building Building Coolers.

Coolers. RHRRHR can can be be deenergized for deenergized for up to 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> up to hour provided provided that that core core outlet outlet temperature temperature isis maintained maintained at at least least 10°F below saturation temperature.

100F below saturation temperature.

C. Refueling Cavity C. Refueling Cavity Draining, Draining, Cold Cold Overpressure Overpressure Protection, Protection, Simultaneous Simultaneous Cold Cold Leg Leg - Hot

- Hot Leg Leg Recirculation , Pressurizer Recirculation, Pressurizer Relief Relief Tank Cooling.

Cooling. RHR RHR can be be deenergized for up to 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> hour provided that core core outlet outlet temperature is maintained at at least least 500F 50°F below saturation saturation temperature.

D Cold Leg Recirculation, D)I Recirculation, Refueling Cavity Draining, Cold Overpressure Protection, Cold Leg Injection. RHR can be deenergized for up to 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> provided that core outlet temperature is maintained at least 10°F below saturation temperature.

Feedback Distractor Analysis:

A. Incorrect: Hot Leg Recirculation, A. Recirculation, Alternate Water supply to Reactor Building Coolers, Pressurizer Relief Tank Cooling are all incorrect functions. RHR can be deenergized for up to Pressurizer 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> provided that core outlet temperature is maintained at least 10°F 100 F below saturation temperature.

B. Incorrect: Hot Leg Recirculation Recirculation,, Alternate Water supply to Reactor Building Coolers are incorrect functions.

C. Pressurizer Relief Tank Cooling Cooling is an incorrect function.

D. Correct D. Correct answer

References:

AB-7, AB-7, RHR RHR system, system, pagepage 99 AB-2, AB-2, RCS, RCS, page page 99 lB-i, IB-1, SW SW System, System, pagepage 1717 TS 3.4.1.3, page 237 TS 3.4.1.3, page 237 and 241 and 241 K/A KIA CATALOGU CATALOGUE E QUESTION QUESTION DESCRIPTI DESCRIPTION: ON:

- Residual Residual HeatHeat Removal Removal System; System; Knowledge Knowledge of of system system purpose purpose andand oror function.

function.

Categories Categories Tier:

Tier: 22 Group:

Group: 1 Key Word:

KeyWord: RHR RHR Cog Level:

Cog Level: M (2.8/2.9)

M (2.8/2.9)

Source:

Source: NN Exam:

Exam: SM0530l SM05301 Test:

Test: SS Author/Reviewer: RFAlSDR AuthorlReviewer: RFA/SDR

4.

4.

Plant conditions Plant conditions are are as follows:

as follows:

-- The unit The unit isis inin Cold Cold Shutdown.

Shutdown

-- The RCS The water solid RCS isis water solid with with one train of one train RHR providing of RHR providing shutdown shutdown cooling.

cooling.

-- RHR letdown RHR letdown isis inin service service with with PCV-145 PCV-145 controlling controlling RCS pressure in RCS pressure in AUTO.

AUTO.

-- Both pressurizer PORV control Both pressurizer PORV control switches are switches are in in AUTO.

AUTO.

-- RCS temperature RCS temperature isis 180 180 of.

°F.

-- PRT level PRT level isis 78%.

78%.

-- PRT pressure PRT pressure is is 66 psig.

psig.

-- PRT temperature PRT temperature is is 95 95 of

°F Assuming no Assuming operator action, no operator action, aa _____ will will result result in in aa pressure pressure increase increase in in the the PRT PRT and and the crew the crew can restore PRT can restore PRT parameters parameters by by _ _ _ _ _ __

Failure of pressurizer A. Failure pressurizer pressure pressure control channel PB-455APB-455A HIGH.HIGH.

Spraying down the PRT PRT using reactor makeup water per SOP-1 SOP-i 01, Reactor Reactor Coolant System.

System.

B.

B ..... Loss of air to HCV-142, LLTDN TON FROM RHR.

Draining the PRT to the Recycle Holdup Tanks per SOP-108, SOP-i 08, Liquid Waste Processing System.

C. Failure of pressurizer pressure control channel PB-455A HIGH.

Draining the PRT to the Recycle Holdup Tanks per SOP-108, SOP-i 08, Liquid Waste Processing System.

D. Loss of airto HCV-142, L LTDN TON FROM RHR.

Spraying down the PRT using reactor makeup water per SOP-lOl, SOP-1 01, Reactor Coolant System.

Feedback Feedback -

D ISTRACTORS:

DISTRACTORS:

AA Incorrect Incorrect failure.

failure. AA failure failure of PB-455A high of PB-455A high will will not not cause cause aa pressurizer pressurizer PORV PORV to to open open because because the the P-11 P-i 1 signal signal (2/3 (2/3 pressurizer pressurizer protection protection channels channels lessless thanthan 1985 1985 psig) psig) will will prevent automatic prevent automatic operation operation of of the pressurizer PORVs the pressurizer PORVs inin thisthis plant plant Mode.

Mode.

Plausible because Plausible because the the discharge discharge of of aa pressurizer pressurizer PORV PORV will will cause cause an an increase increase in in PRT PRT pressure.

pressure.

Incorrect corrective corrective action.

action. AtAt 180 o 180°F/6+ psig, the Incorrect F/6+ psig, the PRT PRT isis saturated saturated (no (no vapor vapor bubble).

bubble).

Spraying the Spraying the PRT PRT would would not not reduce reduce PRT pressure (but PRT pressure would increase (but would increase PRT PRT pressure pressure as as PRT level PRT level increased increased from from the addition of the addition reactor makeup of reactor makeup water).

water). Plausible Plausible because because thisthis action would action would reduce reduce PRT PRT pressure pressure following following aa relief relief or or safety safety valve valve discharge discharge at at power.

power.

BB Correct Correct failure.

failure. HCV-142 HCV-142 will will fail shut shut onon loss of air.

loss of air. A failure of A failure of HCV-142 HCV-142 in in the the closed closed position isolates position isolates the the RHRRHR system system fromfrom thethe letdown letdown system.

system. With With charging flow in charging flow in manaul, manaul, RCS pressure RCS pressure willwill increase increase until until the the RHR RHR suction suction relief relief valve(s) valve(s) lift, lift, relieving relieving to to the the PRT.

PRT.

Correct corrective action. Draining the PRT PRT will reduce PRT pressure.

Incorrect failure. See A. Correct corrective action. See B.

C Incorrect B.

D Correct failure. See B. Incorrect corrective action. See A.

REFERENCES:

1. Panel XCP-616, XCP-61 6, Annunciator Point 4-4

2. AB-2, Reactor Coolant System, Pressurizer Relief Tank

3. AB-7, Residual Heat Removal System SOP-lOl, Reactor Coolant System

4. SOP-101, KIA CATALOGUE QUESTION DESCRIPTION:

K/A CATALOGUE DESCRIPTION:

- Ability to (a) predict the impacts of the following malfunctions or operations on the P PSS (Pressurizer Relief Tank 1 / Quench Tank System); and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences consequences of those malfunctions or operations: Overpressuri Overpressurizationzation of the PZR (3.6/3.9)

Categories Tier:

Tier: 2 Group: I1 Key Word:

KeyWord: PRT PRT PRESSURE Cog Cog Level:

Level: C!A(3.6/3.9)

C/A(3.6/3.9)

Source:

Source: N Exam: 5M05301 SM05301 Test:

Test: SS Author/Revi ewer: FJE/SDR AuthorlReviewer:

5.

5.

The Unit The Unit experienced experienced aa loss loss of of BOTH BOTH Feedwater Feedwater PumpsPumps with with aa concurrent concurrent automatic automatic Reactor Reactor trip failure. The trip failure. The crewcrew has has completed completed the the immediate immediate actions actions of of EOP-1.0, EOP-1 .0, "Reactor Reactor Trip/Safety Trip/Safety Injection Actuation."

Injection Actuation.

Current plant Current plant conditions conditions are are as follows:

as follows:

The Integrated

- The

- Integrated PlantPlant Computer Computer SystemSystem has has failed.

failed.

- SG

- LO-LO Level SG LO-LO Level annunciators annunciators are are lit.

lit.

Reactor Power

- Reactor

- Power isis 6% 6% and and slowly slowly decreasing decreasing withwith aa negative negative SUR.

SUR.

All AFW Pumps failed

- All AFW Pumps failed to start.

- to start.

Which ONE Which ONE of of the the following following describes describes the the procedure procedure path path based based on on the the above above information?

information?

A. Remain A. Remain in in EOP-1.0, EOP-1 .0, untiluntil directed directed toto monitor monitor Critical Critical Safety Safety Functions Functions then then transition transition to to EOP-1 5.0, "Response EOP-15.0, Response To To Loss Loss ofof Secondary Secondary Heat Heat Sink."

Sink.

B. Directly enter EOP-15.0,EOP-1 5.0, "Response Response To Loss Loss of Secondary Heat Heat Sink."

Sink.

C. Remain in C. Remain in EOP-1.0, EOP-1 .0, untiluntil directed directed to monitor Critical Critical Safety Safety Functions Functions then transition to Response To Abnormal Nuclear Power Generation."

EOP-13.0, "Response Generation.

Dw Directly enter EOP-13.0, "Response Dy Response To Abnormal Nuclear Power Generation." Generation.

Feedback Feedback DISTRACTORS:

DISTRACTORS:

A INCORRECT INCORRECT Should transition directly to EOP-13.0.

B INCORRECT B INCORRECT Should transition directly to EOP-13.0.

INCORRECT C INCORRECT Should transition directly to EOP-13.0.

D D CORRECT Should transition directly to EOP-13.0.

REFERENC

REFERENCES:

ES:

1.

1.

KIA CATALOGU K/A CATALOGUE E QUESTION DESCRIPTI DESCRIPTION: ON:

- Reactor Trip; Ability to determine or interpret interpret the following as they apply to aa reactor reactor trip:

Decreasing Decreasing power power level, level, from available indications.

Categories Categories Tier:

Tier: 1 Group:

Group: 1 Key Word:

KeyWord: REACTOR REACTOR TRIP TRIP Cog Cog Level:

Level: CIA(4.1I4.3)

C/A(4. 1/4.3)

Source:

Source: MM Exam:

Exam: SM05301 SM05301 Test:

Test: SS Author/Reviewer:

AuthorlReviewer: MC/SDR MC/SDR

- 6.6.

The Unit The Unit isis operating operating at at 100%

100% powerpower with with all all systems systems inin normal normal lineups lineups when when the the following following annunciators actuate:

annunciators actuate:

CCW LOOP

- CCW

- LOOP AA ESSENESSEN LOAD LOAD TEMP TEMP HI HI

-CC LOOP A RM-L2A

- CC LOOP A RM-L2A HI RAD HI RAD

- CC

- CC SRG SRG TK TK VENT VENT 7096 7096 CLSD CLSD HIHI RAD RAD CCW SRG

- CCW

- SRG TK TK LVL LVL HI/LO/LO-LO HI/LO/LO-LO NO other NO other annunciators annunciators are are lit.

lit.

Which ONE Which ONE of of the following isis the the following the correct correct cause cause andand action?

action?

A. AA leak A. leak exists exists inin the Letdown HX; the Letdown verify closure HX; verify closure of PVT-8152, LTDN of PVT-8152, LTDN LINE LINE ISOL ISOL andand manually shut manually shut PW-7096, PW-7096, CC CC SURGE SURGE TK VLV per TK VLV per SOP SOP 102,102, CHEMICAL CHEMICAL AND AND VOLUME VOLUME CONTROL SYSTEM.

CONTROL SYSTEM.

BB.

..... AA leak leak exists exists in the Letdown in the Letdown HX; manually close HX; manually close PVT-8152, PVT-8152, LTDNLTDN LINELINE ISOL ISOL andand verify verify closure of PW-7096, closure of PW-7096, CC SURGE TK CC SURGE TK VLV per per SOP SOP 102, 102, CHEMICAL CHEMICAL AND VOLUME CONTROL SYSTEM.

CONTROL C. RCP C. RCP "A" A thermal barrier has been breached. Conduct a normal shutdown per GOP-4B, POWER OPERATION (MODE 1I - DESCENDING), - DESCENDING), Stop RCP A within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> per SOP-lOl, SOP-101, REACTOR COOLANT SYSTEM.

D. A D. A Phase Phase "B" B Containment Isolation has actuated due to RM-L2A&B 9 (Component Cooling) alarming. Immediately trip the reactor and trip ALL RCPs and enter EOP 1.0.

Feedback Feedback Distractor Analysis:

A. Incorrect. PVT-8152 must be manually shut and PVV-7096 A. PW-7096 should close automatically and be verified closed.

B. Correct:

C. Incorrect:

Incorrect: RCP seals have not not failed nor nor hashas the thermal barrier barrier been breached.

breached. Therefore, Stopping Stopping RCP A A within 88 hours0.00102 days <br />0.0244 hours <br />1.455026e-4 weeks <br />3.3484e-5 months <br /> hours per SOP-iSOP-1 01, 01, REACTOR COOLANT COOLANT SYSTE,SYSTE, does does notnot apply.

apply.

D.

D. Incorrect:

Incorrect: RM-L2A&B RM-L2A&B 99 will will notnot cause cause aa Phase Phase BB Containment Containment Isolation.

Isolation.

References:

AOP AOP 101, 101, Reactor Reactor Coolant Coolant Pump Pump Seal Seal Failure, Failure, page page 88 SOP 102.2, CHEMICAL SOP 102.2, CHEMICAL AND VOLUME CONTROL AND VOLUME CONTROL SYSTEM, SYSTEM, page 70, page 70, ARP-00I ARP-001-XCP-601, -XCP-601, page page 16 16 K/A KIA CATALOGU CATALOGUE E QUESTION QUESTION DESCRIPTI DESCRIPTION: ON:

- Component Component Cooling Cooling Water Water System System (CCWS);

(CCWS); Ability Ability to (a) predict to (a) predict the the impacts of the impacts of the following following malfunctions malfunctions or or operations operations on on the the CCWS, CCWS, and and (b)

(b) based based on on those those predictions, predictions, use use procedures procedures to to correct, correct, control, control, or or mitigate mitigate the the consequence consequences s of of those those malufunction malufunctions or operations:

s or operations: PRMS PRMS alarm.

alarm.

Categories Categories Tier:

Tier: 22 Group:

Group: 11 Key Word:

KeyWord: CCW CCW Cog Level:

Cog Level: CIA C/A (3.3/3.5)

(3.3/3.5)

Source:

Source: MM Exam:

Exam: SM05301 SM05301 Test:

Test: SS Author/Reviewer:

AuthorlReviewer: RFAlSDR RFAJSDR

- 7.7.

Which ONE Which ONE of of the the following following identifies identifies an event that an event that isis required required to to bebe reported reported to to the the NRC NRC within within 1 hour per EPP-002, 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per EPP-002, COMMUNICATION COMMUNICATION AND AND NOTIFICATION.

NOTIFICATION.

A. An A. An unplanned unplanned ECCS ECCS initiation initiation that that does does not not discharge discharge to to the the RCS RCS during during an an SISI surveillance surveillance test.

test.

BB. An ECS

..... An ECS discharge discharge to to the the RCS RCS inin response response to to aa small small break break LOCA.

LOCA.

C. An C. An airborne airborne release release of>of> 2X Appendix BB limits.

2X Appendix limits.

D. AA liquid D. liquid release release of> of> 2X Appendix BB limits.

2X Appendix limits.

Feedback Feedback Distractor Analysis:

Distractor Analysis:

A. Incorrect:

A. Incorrect: This This is is aa non-emergency non-emergency event event that that does does not not discharge discharge to to the the RCS RCS this this is is aa 44 hour5.092593e-4 days <br />0.0122 hours <br />7.275132e-5 weeks <br />1.6742e-5 months <br /> notification requirement.

hour notification requirement.

B. Correct: A LOCA B. Correct: LOCA is an emergency event which requires notification.

C. Incorrect:

C. Incorrect: This This is aa 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> hour notification notification requirement requirement D. Incorrect:

D. Incorrect: This This is a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> notification requirement

Reference:

EPP-002, page 27

Reference:

KIA CATALOGUE QUESTION DESCRIPTION:

K/A CATALOGUE DESCRIPTION:

Small

- Small Break

- Break LOCA; Knowledge of which events related to system operations/status operations/status should be reported to outside reported outside agencies.

Categories Categories Tier:

Tier: 1 Group: 1I Key KeyWord: Word: REPORTABILITY REPORTABILITY Cog Level: M(2.2/3.6)

M(2.2/3,6)

Source:

Source: N Exam: SM05301 5M05301 Test:

Test: SS Author/Revi AuthorlReviewer:

ewer: RFAISDR RFAlSDR

8.

8.

The plant The plant was was operating operating at at 80%

80% power power when when thethe following following annunciators annunciators (not (not all all inclusive) inclusive) came came in:

in:

- REGEN HX REGEN HX LLTDN TDN OUTOUT TEMP TEMP HI HI

- VCTLVLHI/

VCT LVL HIILO LO

- CHG LINE CHG LINE FLO FLO HIILO HI/LO

- PZR LOS PZR LCS DEV HIILODEV Hl/LO Charging pump Charging pump amps amps areare running running between between 25 25 and and 3030 amps amps Charging flow Charging flow isis between between 2525 and and 30 30 gpm gpm Charging pressure Charging pressure isis between between 2500 2500 and 2600 psig and 2600 psig Which ONEONE of of the following set of actions set of actions should should the the supervisor supervisor direct direct his his board board operators operators to to perform (These actions perform (These actions are not are all inclusive)?

not all inclusive)?

A.. Secure A:.t Secure the the operating charging pump, pump, close all letdown letdown isolation isolation valves, and close FCV-122, charging flow control valve.

B. Verify at least one charging pump is operating, verify FCV-122 FCV-122 is is open, and verify CCW COW flow to the RCP Thermal Barriers is GREATER THAN 90 gpm on FI-7273A(B), Fl-7273A(B), THERM BARR FLOW GPM.

C. Secure the operating charging pump, realign charging pump suction, and close both LCV-1 1 5B(D), RWST TO CHG PP SUCT.

LCV-115B(D),

D. Verify at least one charging pump is operating, verify FCV-122 is open, and open both LCV-1 150(E), VCT OUTLET ISOL.

LCV-115C(E),

Feedback Distractor Analysis:

A. Correct answer per AOP-1 02.2, page 4-6 AOP-102.2, B,C, and D. Charging flow is abnormal abnormal- must go to the RNO column. Closing both LCV-1 1 LCV-115B(D),5B(D), RWST TO CHG PP SUCT, is an action if charging was initially aligned to the RWST.

Reference:

AOP-1 02.2, page 4-6 AOP-102.2, KJA KIA CATALOGU CATALOGUE E QUESTION QUESTION DESCRIPTI DESCRIPTION: ON:

- Loss Loss ofof Reactor Reactor Coolant Coolant Makeup; Makeup; Ability to to perform perform without without reference to to procedures procedures those those actons actons thatthat require require immediate immediate operation operation of of system system components components andand controls.

controls.

Categories Categories Tier:

Tier: 1 Group:

Group: 11 Key Word:

KeyWord: RCS MAKEUP RCSMAKEUP Cog Cog Level:

Level: CIA (4.0/40)

C/A (4.014.0)

Source:

Source: NN Exam:

Exam: SM05301 SM05301 Test:

Test: SS Author/Revie Author/Reviewer:

wer: RFAJSDR RFAlSDR

9.

9.

Refueling operations Refueling operations are are inin progress progress when when Power Power isis suddenly suddenly lost lost to to source source range range neutron neutron flux flux monitor N31 monitor N31 and and subsequently subsequently regained regained 3030 minutes minutes later.

later.

Which ONE Which ONE of the following of the following describes describes the the action action to to be be taken taken for for this this situation?

situation?

A Suspend A.'" Suspend all all core core alterations alterations and and perform perform an analog channel an analog channel operational operational test test of of source source range neutron range neutron flux flux monitor monitor N31 N31 within within 88 hours0.00102 days <br />0.0244 hours <br />1.455026e-4 weeks <br />3.3484e-5 months <br /> hours prior prior to the initial to the initial start start of of core core alterations.

alterations.

B. Suspend B. Suspend all all core core alterations alterations and and perform perform aa neutron neutron fluxflux response response time time test test AND AND operational operational test of source test of source rangerange neutron neutron flux flux monitor monitor N31N31 within within 88 hours0.00102 days <br />0.0244 hours <br />1.455026e-4 weeks <br />3.3484e-5 months <br /> prior to hours prior to the the initial initial start of start of core core alterations.

alterations.

C. Determine boron C. Determine boron concentration concentration and and perform perform aa channel channel checkcheck of of source source range range neutron neutron flux flux monitor N31 monitor within 12 N31 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

hours.

D. Determine D. Determine boron boron concentration and perform a neutron neutron flux response time test of source range neutron flux monitor monitor N31 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Feedback DISTRACTORS:

DISTRACTORS:

A CORRECT B INCORRECT B INCORRECT Neutron detectors are exempt from response time testing.

C INCORRECT C INCORRECT measuriments are only required when both monitors Boron concentration measuriments are down.

D INCORRECT INCORRECT Boron concentration measuriments measuriments are only required when both monitors are down. Neutron detectors are exempt from response time testing.

REFERENC

REFERENCES:

ES:

1. TS 3.9.2, Instrumenta "Instrumentation." tion.

2. TS 3.9.1, Boron Concentratio "Boron Concentration." n.

3. TS Table 3.3-2, Reactor "Reactor Trip System Instrumentat Instrumentation ion Response Times. Times."

4. IC-8, IC-8, Nuclear "Nuclear Instrumentat ion, pages 24, 48, & 50.

Instrumentation,"

KIA CATALOGU K/A CATALOGUE E QUESTION DESCRIPTI DESCRIPTION: ON:

- Loss of of Source Range Nuclear Instrumentat ion; Ability to determine and interpret the following Instrumentation; as they apply to the Loss of Source Range Nuclear Instrumentat Instrumentation: ion: Testing required ifif power is is lost, lost, then restored.

Categories Categories Tier:

Tier: 1 Group:

Group: 22 Key Word:

KeyWord: SRNI SRNI Cog Cog Level:

Level: M(2.2/3.l)

M(2.2/3.1)

Source:

Source: NN Exam:

Exam: SM05301 SM05301 Test:

Test: SS Author/Revi ewer:

Author/Reviewer: MC/RFAJSD MCIRFAlSDR R

10.

10.

The SRO The SRO has just entered has just entered EOP-15.0, EDP-15.0, "Response Response to Loss of to Loss of Secondary Secondary Heat Heat Sink" Sink from from EOP EOP 12, Monitoring 12, Monitoring of of Critical Critical safety safety Functions.

Functions.

The following The following conditions conditions exist:

exist:

WR SG

- WR

- SG "A" level isis 25%

A level 25%

WR SG

- WR

- SG "8" B level level isis 12%

12%

WR SG

- WR

- SG "C" level isis 11%

C level 11%

Total Feed

- Total

- Feed Flow Flow isis 290 290 gpm gpm Which ONE Which ONE of the following of the following actions actions should should be be taken taken as directed by as directed by EOP-15.0, EOP-1 5.0, "Response Response toto Loss of Secondary Heat Loss of Secondary Heat Sink"? Sink?

Ensure all A. Ensure all EFW EFW valves are are open and establish EFW EFW flow to at least least one SG.

SG.

B. Reset SI and establish MFW flow to either the "8" B. B or "C" C Steam Generators.

C. Reset SI, dump steam to the condenser and feed using a condensate pump. pump.

D/ Trip ALL RCPs, actuate SI, Establish an RCS bleed path:

Dy Feedback NOTE: No other initial conditions are needed. The caution prior to step 4 of EOP-15 EOP-1 5 is a stand alone statement. If the SRO has entered this procedure and these conditions exist, there is no other option.

Distractor Analysis:

A, B, 8, C. Incorrect: Not allowed due to caution prior to step 4 D Correct:

Reference:

EOP-12, EOP-12, page 99 EOP-15, page 33 caution prior to step 4 KIA CATALOGU K/A CATALOGUE E QUESTION DESCRIPTI DESCRIPTION:ON:

Steam

- Steam

- Generator; Knowledge of operational of operational implications implications of EOPEOP warnings, warnings, cautions, andand notes.

notes.

Categories Categories Tier:

Tier: 22 Group:

Group: 22 Key Word:

KeyWord: SG SG Cog Level:

Cog Level: C/A CIA (3.3/3.4)

(3.3/3.4)

Source:

Source: N Exam:

Exam: SM05301 SM05301 Test:

Test: SS Author/Revie wer:

AuthorlReviewer: RFAJSDR RFAlSDR

11.

11.

The following The following conditions conditions exist:

exist:

- AA plant

- plant startup startup was was inin progress.

progress.

Power level

- Power

- level was was at 38%

at 38%

The reactor

- The

- reactor tripped tripped SG blowdown

- SG blowdown isolation

- isolation valves valves (PVG-503A(8)(C),

(PVG-503A(B)(C), A(8)(C) A(B)(C) ISOL)

ISOL) closed closed Current SG

- Current

- SG narrow narrow range range levels levels inin "A",

A, "8",

B, and and "C" C SGs SGs areare 8%,

8%, 10%,

10%, andand respectively 10% respectively 10%

Which ONE Which ONE of of the the following following correctly correctly states states the the initiating initiating event event that that caused caused the the trip trip and and the the component(s ) that failed to actuate per component(s) that failed to actuate per ARP-001-XCP-624?ARP-001-XC P-624?

A.A. The operating MFP The operating MFP tripped tripped andand ONLY ONLY the the motor motor driven driven AFW AFW pumppump should should have have started.

started.

sB.

. . . The The operating operating MFP MFP tripped tripped and BOTH turbine and 80TH turbine driven driven AND AND motor motor driven driven AFW AFW pumps pumps should have should have started.

started.

C. All SG C. SG Flow Flow control control Valves drifted drifted closed closed and and AMSAC should should have have actuated.

actuated.

D. All SG Flow control Valves drifted closed and ONLY the turbine driven AFW pump should have started.

Feedback Unless the applicant keys on the fact that SG blowdown isolation valves (PVG-503A(8)(C), (PVG-503A(B)(C),

A(B)(C) ISOL) closed, he may consider C or D.

A(8)(C)

Distractor Analysis:

A. Incorrect: LO LO level both MD AND TD TO AFW pumps will start B.

8. Correct:

C. Incorrect: All SG Flow control Valves drifting closed could cause this. However, SG blowdown isolation valves (PVG-503A( (PVG-503A(8)(C),B)(C), A(B)(C)

A(8)(C) ISOL) closed which dont don't according to ARP XCP-624. AdditionallyAdditionally,, AMSAC will not actuate since initial power was << 40%

D. Incorrect: All SG Flow Flow control Valves drifting closed closed could could cause this. However, SG SG blowdown blowdown isolation isolation valves valves (PVG-503A(

(PVG-503A(8)(C),B)(C), A(B)(C)

A(8)(C) ISOL)

ISOL) closed which dont don't according according to to ARP ARP XCP-624.

XCP-624. Additionally Additionally,, bothboth MD MD AND AND TD TO AFW AFW pumps pumps will will start.

start.

Reference:

ARP-001-XC ARP-001-XCP-624, P-624, pagepage 22 22 and and 26 26 K/A KIA CATALOGU CATALOGUE E QUESTION QUESTION DESCRIPTI DESCRIPTION: ON:

- Loss

- Loss of of Main Main Feedwater Feedwater (MFW);(MFW); Ability to determine Ability to determine and and interpret interpret the the following following as as they they apply apply to to thethe Loss Loss of of Main Main Feedwater Feedwater (MFW):

(MFW): Conditions Conditions and and reasons reasons for for AFW AFW pumppump startup.

startup.

Categories Categories Tier:

Tier: 1 Group:

Group: 1 Key KeyWord:Word: MFW MFW Cog Level:

Cog Level: CIA (4.1/4.2)

C/A (4.114.2)

Source:

Source: NN Exam:

Exam: SM05301 SM05301 Test:

Test: SS Author/Revie AuthorlReviewer: RFAlSDR wer: RFAJSDR

12.

12.

AA Liquid Liquid Radwaste Radwaste ReleaseRelease isis been been inin progress:

progress:

-- XCP-646 2-5, XCP-646 2-5, MON MON TK DISCH RM-L5 TK DISCH RM-L5 RAD,RAD, has has just actuated for just actuated for the the second second time.

time.

-- RCV00018-WL, Liquid RCV0001B-WL, Liquid Radioactive Radioactive Waste Waste ControlControl Valve, Valve, indicates indicates shut.

shut.

-- The alarm The alarm waswas verified verified by observing the by observing the reading reading on RM-L9 as on RM-L9 being just as being just above above the the alarm alarm setpoint.

setpoint.

Within 30

- Within

- 30 seconds seconds afterafter XCP-644 XCP-644 2-5 2-5 actuated, actuated, RM-L9's RM-L9s reading reading had had returned returned below below the the setpoint.

setpoint.

Which ONE Which ONE of of the following correctly the following correctly states states the the next next procedure procedure steps steps toto be be taken.

taken.

A.v The A...; The tank tank must must be sampled and be sampled and activity activity levels levels verified, verified, then then open open RCV0001B-WL RCV00018-WL and and resume the release per resume the release per SOP-1 OB.SOP-i 08.

B. Verify that B. Verify that the the RM-L9's RM-L9s reading reading isis below below the the setpoint, setpoint, then then open open RCV0001B-WL RCV00018-WL and and resume the resume release per the release SOP-i OB.

per SOP-1 08.

C. Verify that C. Verify that the RM-L9s reading the RM-L9's reading isis below below the the setpoint, setpoint, then then open open RCV0001B-WL RCV00018-WL and and resume the release per SOP-1 SOP-i OB.08. Direct Heath Physics to continue to monitor the release reduce the release rate.

and reduce D. Notify Health Physics and request a radiological survey. The release can not be reinitiated D.

under the current release permit.

under Feedback Feedback DISTRACTORS:

DISTRACTORS:

CORRECT A CORRECT As per XCP-646-2-5 XCP-646-2-5,, this is the first step of the supplementa supplementall actions.

INCORRECT BB INCORRECT This is the action if this is the first time the release has been automatically terminated.

C INCORREC INCORRECT T This is the action ifif this is the first time the release has been automatically terminated, coupled wiht the actions for aa malfunctioni malfunctioning ng RM-L5.

DD INCORREC INCORRECT T This would be plausible plausible ifif itit is is believed believed that the release can can not not be be continued.

continued.

REFERENC

REFERENCES:

ES:

1.1. XCP-646 XCP-646 2-5 2-5 && 2-6, 2-6, pages pages 12 12 && 13.

13.

2. XCP-644 2-5,

2. XCP-644 2-5, page 15. page 15.

3. XCP-643

3. XCP-643 4-1, 4-1, page page 22.

22.

K/A KIA CATALOGU CATALOGUE E QUESTION QUESTION DESCRIPTI DESCRIPTION: ON:

- Liquid Radwaste System; Ability to execute

- Liquid Radwaste System; Ability to execute procedure procedure steps. steps.

Categories Categories Tier:

Tier: 22 Group:

Group: 22 Key Word:

KeyWord: LIQUID LIQUID RADWASTE RADWASTE Cog Cog Level:

Level: C/A(4.3/4.2)

CIA(4.3!4.2)

Source:

Source: NN Exam:

Exam: SM05301 SM05301 Test:

Test: SS Author/Revie AuthorlReviewer:

wer: RFAlSDR RFA/SDR

13.

13.

Plant conditions Plant conditions are are asas follows:

follows:

The unit

- The

- unit isis currently currently inin MODE MODE 4, 4, with with temperature temperature and and pressure pressure increasing.

increasing.

All major

- All

- major work work inside inside containment containment was was completed completed two two hours hours ago ago and and there there are are NO NO personnel inside personnel inside the the Reactor Reactor Building.

Building.

- AA field

- field operator operator has has just just called called to to report report that the red that the indicating light red indicating light above above the the Personnel Personnel Escape Airlock Escape Airlock isis LIT LIT and and that that he he was was unable unable to operate atomosphere to operate atomosphere door door operating operating handle NO.4 handle No. 4 after after RPRP unlocked unlocked itit for for him.

him.

Which ONE Which ONE of of the the following following isis correct correct regarding regarding thethe status status ofof the the Personnel Personnel Escape Escape Airlock Airlock AND Containment AND Containment Integrity?Integrity?

A. The remote A.'<I remote doordoor is is OPEN.

OPEN.

Personnel Escape The Personnel Escape Airlock is INOPERABLE.

is INOPERABLE.

B. The remote door is is CLOSED.

The Personnel Escape Escape Airlock is INOPERABLE.

INOPERABLE.

C. Only the inside remote door position indicator has malfunctioned. malfunctioned.

The Personnel Escape Airlock is OPERABLE. OPERABLE.

D. The Personnel Escape Airlock is OPERABLE.

D. OPERABLE.

The Personnel Escape Airlock door interlock is INOPERABLE. INOPERABLE.

Feedback Distractor Analysis A Correct. The red bulkhead light and the inability to operate door operating handle No.4 No. 4 (after unlocking it) indicate that the remote (containment side) door is open. Per Tech Spec 3.6.1.3, Containment Air Locks, both airlock doors are required to be CLOSED in Mode 4 unless the air lock is being used for normal transit entry and exit. With NO personnel in containment for two hours, the air lock is NOT being used for normal transit entry and exit.

BB Incorrect.

Incorrect. Incorrect Incorrect equipment status, correct Tech Spec application. See A.

C. The indicator is aa positive indication indication of the status of the door. door. The door is open. The Personnel Personnel Escape Airlock is is INOPERAB INOPERABLE. LE.

D.

D. The The indicator indicator is is aa positive indication indication ofof the status of of the the door.

door. The The door door is is open.

open. The The Personnel Personnel Escape Escape Airlock Airlock isis INOPERAB INOPERABLE. LE.

Reference:

Technical Technical Specification Specification 3.6.1.3, 3.6.1.3, Containment Containment Air Air Locks Locks K/A KIA CATALOGU CATALOGUE E QUESTION QUESTION DESCRIPTI DESCRIPTION: ON:

- 103 103 Containment Containment System System

- G2.1 G2.1.30 .30 Ability Ability toto locate and operate locate and operate components, components, including including controls controls (3.9/3.4)

(3.9/3.4)

Categories Categories Tier:

Tier: 22 Group:

Group: 1I Key Word:

KeyWord: CONTAINMENTAIRLOCK CONTAINMENT AIRLOCK Cog Cog Level:

Level: MM (3.9/3.4)

(3.9/3.4)

Source:

Source: NN Exam:

Exam: SM0530 SM05301 1 Test:

Test: SS Author/Reviewer:

AuthorlReviewer: FJEIRF AlSDRR FJE/RFA/SD

14.

14.

Which ONE Which ONE ofof the the following following (as (as stated stated inin SAP SAP 200, 200, Conduct Conduct of of Operations)

Operations) has has the the final final authority, per authority, per Management Management Directive Directive 11, 11, for for aa case where an case where an individual's individuals condition condition for for work work inside the inside protected area the protected area isis inin question?

question?

A. General Manager, A. General Manager, Nuclear Nuclear PlantPlant Operations Operations BB. Shift Supervisor

..... Shift Supervisor C. Management Duty C. Management Duty Supervisor Supervisor D. Security Manager D. Security Manager Feedback Feedback Distractor Analysis:

Distractor Analysis:

Incorrect: per A. Incorrect: per SAPSAP 200, 200, Paragraph Paragraph 6.5.2 6.5.2 H, page 10 H, page 10 B. Correct:

B. Correct: per SAPSAP 200, 200, Paragraph Paragraph 6.5.2 H, H, page page 10 10 C. Incorrect: per C. Incorrect: per SAP 200, Paragraph Paragraph 6.5.26.5.2 H, H, page page 1010 D. Incorrect: per SAP 200, Paragraph 6.5.2 H, page 10

Reference:

SAP 200, Conduct of Operations, Paragraph 6.5.2 H, page 10 SAP KIA CATALOGUE QUESTION DESCRIPTION:

K/A CATALOGUE DESCRIPTION:

- Knowledge of facility requirements vital / controlled access.

for controlling vital/controlled Categories Categories Tier:

Tier: 33 Group:

Key KeyWord: Word: ADMIN Cog Level: M (2.0/2.9)

Source:

Source: N Exam: SM05301 Test:

Test: SS Author/Revi ewer: RFAJSDR AuthorlReviewer: RFAlSDR

15.

15.

The unit The unit isis undergoing undergoing aa normal normal heatup.

heatup. Plant Plant conditions conditions are are as follows:

as follows:

- Hydrazine was Hydrazine was addedadded when when RCSRCS temperature temperature waswas 185°F.

185°F.

- RCS temperature RCS temperature is is 205°F.

205° F.

AA reactor reactor coolant coolant sample sample shows shows dissolved dissolved oxygen oxygen concentrations concentrations of 0.5 ppm.

of 0.5 ppm.

Given the Given the above above conditions conditions and and InIn accordance accordance with with GOP-2,"Plant GOP-2,Plant Startup Startup and and Heatup,"

Heatup, and and Tech Spec Tech 3.4.7, "Chemistry,"

Spec 3.4.7, Chemistry, which which ONEONE ofof the the following following isis correct?

correct?

A. Plant A. Plant chemistry is is NOT NOT in in compliance compliance withwith GOP-2; GOP-2; anan LCO LCO HASHAS been been entered.

entered.

BBy Plant chemistry

..... Plant chemistry is NOT in is NOT in compliance with GOP-2; GOP-2; anan LCO LCO hashas NOT NOT been been entered.

entered.

c.

C. Plant Plant chemistry IS in compliance with GOP-2; an LCO HAS been been entered.

D. Plant chemistry IS in in compliance with GOP-2; an LCO has NOT been entered.

Feedback DISTRACTORS:

DISTRACTORS:

INCORRECT A INCORRECT Per GOP-2, RCS temperature should not be permitted to exceed 200°F until oxygen scavenging of the primary is complete and chemistry is within specification.

specification.

B CORRECT Per GOP-2, RCS temperature should not be permitted to exceed 200°F until oxygen scavenging of the primary is complete and chemistry is within specification. Although the Steady State Limit for Oxygen is 0.1 specification. ppm in 0.lppm Modes 1 1 - 4, it is not applicable with Tavg ~

- 250° F.

< 250°F.

INCORRECT C INCORRECT Plant temperature has exceeded the GOP-2 limit of 200°F but not the TS limit of 250°F.

250° F.

INCORRECT D INCORRECT Plant temperature has exceeded the GOP-2 limit of 200°F.

REFERENC

REFERENCES:

ES:

1. Tech Spec Table 1.1, Operational "Operational Modes.

Modes."

2. Tech Spec 3.4.7, Chemistry, "Chemistry," and Table 3.4-2, Chemistry "Chemistry Limits.

Limits."

2. GOP-2,Plan GOP-2,"Plantt Startup and Heatup (Mode 5 to Mode 3), 3)," Step 2.la 2.1a page 2, Step 3.1 page 5,

& the Reference Page.

KIA CATALOGU K/A CATALOGUE E QUESTION DESCRIPTIDESCRIPTION: ON:

- Ability to maintain primary and secondary plant chemistry within allowable limits.

Categories Tier:

Tier: 33 Group:

Group:

Key KeyWord: Word: CONDUCT CONDUCT OF OF OPS OPS Cog Level: C/A(2.3/2.9)

C/A(2.3/2.9)

Source:

Source: BB Exam:

Exam: SM05301 Test:

Test: SS Author/Reviewer:

AuthorlReviewer: MC/SDR MC/SDR

16. We

16. We hadhad insufficient insufficient references references to to verify verify this this question.

question. II think think wewe need either SAP-0210 need either SAP-0210 or SAP or SAP 0300.

0300.

The following The following question question was was modified modified fromfrom facility facility exam exam bank bank (closed) question 1891, (closed) question 1891, which referenced SAP-300.

which referenced SAP-300. The The facility facility submittal submittal diddid not include SAP-300.

not include SAP-300. Need Need facility facility toto verify verify all all answers/distractors.

answers/distractors.

Which ONE Which ONE of of the the following following isis aa VIOLATION VIOLATION of administrative procedures of administrative procedures whenwhen troubleshooti ng an INOPERABL E system troubleshooting an INOPERABLE system or component, the or component, the condition condition ofof which which isis specified specified by by aa Technical Technical Specification Specification Action Action Statement.

Statement.

A.. AA Temporary Ay Temporary Restoration Restoration to Service isis used to Service used even even though though anan alternative alternative method method of of completing the completing the work work that that will will meet meet thethe action action statement statement requirement requirement was was identified.

identified.

B. The troubleshooting B. troubleshooting requires requires posting posting a plant plant operator to to immediately immediately restore restore an an affected affected component.

component.

C. The Temporary Inoperable Inoperable Status Change required required to perform perform the troubleshooting troubleshooting was NOT approved NOT approved by the the Manager, Operations.

Operations.

D. The Work Document also includes an approved Bypass Authorization Authorization Request to install electrical jumpers.

Feedback Feedback DISTRACTORS:

DISTRACTORS:

A Correct per SAP-205, 6.7.2.B B Incorrect. Acceptable per 6. 6.7.3.A.1.

7.3.A.1. and 6.7.3.A.2. Plausible if applicant believes that the need to "immediately immediately restore" restore would prevent aa troubleshoot troubleshooting ing activity.

C Incorrect. SAP-205, Attachment V, Temporary Inoperable Status Change, requires approval C

by the Duty Shift Supervisor. Plausible because the Manager, Operations, approves some plant activities (e.g. extending the time an invalid nuisance annunciator may be removed from service).

D D Incorrect. Allowed per SAP-0148 section 2.2. Plausible if applicant believes aa Bypass Authorizatio Authorization n Request is not used to authorize installation of electrical jumpers or that administrativ administrative e procedures procedures prohibit prohibit the use use ofof electrical electrical jumers during during troubleshoot troubleshooting.

ing.

REFERENC

REFERENCES:

ES:

1.

1. SAP-0205, SAP-0205, Status Control and and Removal and Restoration

2. SAP-0148, Temporary Bypass,

2. SAP-0148, Temporary Bypass, Jumper, Jumper, and and Lifted Lifted Lead Lead Control Control KIA CATALOGU K/A CATALOGUE E QUESTION QUESTION DESCRIPTI DESCRIPTION: ON:

- Knowledge Knowledge of of the the process process for for managing managing troubleshoot troubleshootinging activities activities (2.2/3.3)

(2.2/3.3)

Categories Categories Tier:

Tier: 33 Group:

Group:

Key Word:

KeyWord: TROUBLESHOOTING TROUBLESHOOTING Cog Cog Level:

Level: MEM2.2/3.3 MEM2.2/3.3 Source:

Source: MM Exam:

Exam: SM05301 SM05301 Test:

Test: SS Author/Reviewer:

AuthorlReviewer: FJE/SDR FJE/SDR

17.

17.

AA bypass bypass authorization authorization request, request, prepared prepared per per SAP-148, SAP-i 48, "Temporary Temporary Bypass, Bypass, Jumper, Jumper, and and Lifted Lead Lifted Lead Control,"

Control, requires requires prior prior PSRC PSRC and and NSRC NSRC review review for for which ONE of which ONE of the the following following conditions?

conditions?

A. AA review A. review indicates indicates that that system system operability operability will will be be affected.

affected.

B.B. AA review review indicates indicates that that 10 10 CFR CFR 5050 Appendix Appendix RR fire fire protection protection criteria criteria are are impacted.

impacted.

C. AA review C. review indicates indicates that that Seismic Seismic or or blowout blowout provisions provisions areare being being diminished.

diminished.

DY' review indicates D AA review indicates that that aa full full safety safety evaluation evaluation isis required required per per 10 10 CFR CFR 50.59.

50.59.

Feedback Feedback DISTRACTORS:

DISTRACTORS:

A INCORRECT INCORRECT B INCORRECT B INCORRECT C INCORRECT C INCORRECT D CORRECT

REFERENCES:

SAP-i 48, "Temporary

1. SAP-148, Temporary Bypass, Jumper, and Lifted Lead Control." Control. Attachment 1, page 14 of 20.

K/A CATALOGUE KIA CATALOGUE QUESTION DESCRIPTION: DESCRIPTION:

- Knowledge of the process for conducting tests or experiments not described in the safety analysis report.

Categories Tier:

Tier: 33 Group:

Key Word:

KeyWord: EQUIPMEN EQUIPMENT T CONTROL Cog Level: M(2.0/3.2)

M(2.O/3.2)

Source:

Source: BB Exam: SM05301 SM05301 Test:

Test: SS Author/Revi AuthorlReviewer: MC/SDR ewer: MC/SDR

18.

18.

Which ONE Which ONE of the following of the following isis correct correct per HPP- 709, per HPP- 709, Sampling Sampling andand Release Release of of Radioactive Radioactive Gaseous Effluents:

Gaseous Effluents:

A.oI Discharges from A. Discharges from the the Waste Waste GasGas Decay Decay Tank Tank or or other high activity other high activity gaseous gaseous releases releases should should be avoided be avoided whenwhen the the wind wind isis from from the the East-Southeast.

East-Southeast. This This will prevent the released activity will prevent the released activity from being from being drawn drawn intointo the the Auxiliary Auxiliary Building Building ventilation.

ventilation.

B. Discharges from B. Discharges from the the Waste Waste GasGas Decay Decay Tank Tank or or other high activity other high activity gaseous gaseous releases releases should should be avoided be avoided whenwhen the the wind wind isis from from the the South-Southeast.

South-Southeast. ThisThis will will prevent prevent the the released released activity from activity from being being drawn drawn into into the the Auxiliary Auxiliary Building Building ventilation.

ventilation.

C.C. Discharges Discharges from the Waste from the Waste Gas Gas Decay Decay Tank Tank or or other other high high activity activity gaseous gaseous releases releases should should be avoided when be avoided when the the wind wind isis from from the the East-Southeast.

East-Southeast. This This will will prevent prevent the the released released activity activity from being from drawn into being drawn into the the Control Control Building Building ventilation.

ventilation.

D. Discharges D. Discharges from the Waste Gas Decay Tank Gas Decay Tank or or other other high high activity activity gaseous gaseous releases releases should should be avoided be avoided when the wind is is from the South-Southeast.

South-Southeast. ThisThis will prevent the released will prevent the released activity from being activity being drawn drawn into into the Control Control Building Building ventilation.

ventilation.

Feedback Distractor Analysis:

A: Correct: Discharges from the Waste Gas Decay Tank or other high activity gaseous releases should be avoided when the wind is from the gaseous East-Southeast. This will prevent the released activity from being East-Southeast.

drawn into the Auxiliary Building ventilation.

B, C, D Incorrect

Reference:

HPP-HPP- 709, Sampling Sampling and Release of Radioactive Gaseous Effluents, page 12 12 KIA CATALOGU CATALOGUE E QUESTION QUESTION DESCRIPTI DESCRIPTION: ON:

- Knowledge of of facility facility ALARA program.

program.

Categories Categories Tier:

Tier: 33 Group:

Group:

Key Word:

KeyWord: Cog Level:

Cog Level: M(2.5/2.9)

M(2.5/2.9)

Source:

Source: NN Exam:

Exam: SM05301 SM05301 Test:

Test: SS Author/Revie AuthorlReviewer: RF AlSDR wer: RFAJSDR

19. This question

19. This question was was taken taken directly directly from from the the facility facility exam exam bank bank (closed reference ##3544).

(closed reference 3544). TheThe question references question references OAP-110.i.

OAP-11O.1. The The facility facility submittal submittal did did not include OAP-110.1.

not include OAP-11O.1. Need Need facility to facility to verify verify allall answers/distractors.

answersldistractors.

Which ONE Which ONE of of the the following following individual's individuals approval approval isis required required to extend the to extend the time time limit limit an an invalid invalid nuisance annunciator nuisance annunciator may may be be removed removed fromfrom service service for for troubleshooting?

troubleshooting?

A. Duty Shift A. Duty Shift Engineeer Engineeer B. Duty Shift B. Duty Shift Supervisor Supervisor Manager, Operations C. Manager, C)oI' Operations D. General Manager, D. General Manager, Nuclear Nuclear Plant Plant Operations Operations Feedback Feedback DISTRACTORS:

DISTRACTORS:

A A

B C Correct per C Correct per OAP-11 OAP-11O.1, 0.1, Section 6.1 D

D

REFERENCES:

1.

K/A CATALOGUE KIA CATALOGUE QUESTION DESCRIPTION: DESCRIPTION:

- Knowledge of the process used to track inoperable alarms.

Categories Categories Tier: 33 Group:

Key Word:

KeyWord: INOPERABLE ALARM Cog Level: MEM2.4/2,8 MEM2.4/2.8 Source: B Exam: SM05301 Test:

Test: SS Author/Reviewer:

AuthorlReviewer: FJE/SDR

20.

20.

Plant conditions Plant conditions are are as follows:

as follows:

• An event An event hashas occurred occurred resulting resulting inin substantial substantial core core degradation degradation with with potential potential loss of loss of containment containment integrity.

integrity.

• AA General General Emergency Emergency has has been been declared.

declared.

• The prevailing wind is blowing The prevailing wind is blowing from from the the south.

south.

Which ONE Which ONE of the following of the following must must assume assume the the dities dities of of Interim Interim Emergency Emergency Director, Director, and and to to which area which area should should he direct non-essential he direct non-essential personnel personnel be be evacuated?

evacuated?

A. Shift A. Supervisor; Evacuate Shift Supervisor; Evacuate to to their their personal personal residence.

residence.

BB.v Shift Supervisor;

..... Shift Supervisor; Evacuate Evacuate to to the the Southern Southern Offsite Offsite Holding Holding Area.

C. Manager, Operations; C. Manager, Operations; Evacuate Evacuate to their personal to their personal residence.

residence.

D. Manager, Operations: Evacuate to the Southern Southern Offsite Holding Area.

Feedback DISTRACTORS:

DISTRACTORS:

A INCORRECT INCORRECT B CORRECT INCORRECT C INCORRECT D INCORRECT INCORRECT

REFERENCES:

SAP-i 09, "Management

1. SAP-109, Management Duty Supervisor."

Supervisor.

2. EPP-0i2, EPP-012, Onsite "Onsite Personnel Accountabili Accountability ty and Evacuation, Evacuation," pages 55 and 9.

K/A KIA CATALOGU CATALOGUE E QUESTION DESCRIPTI DESCRIPTION: ON:

- Ability to take actions called for in the facility emergency plan, including (if required) supporting or acting as emergency coordinator.

Categories Tier:

Tier: 33 Group:

Group:

Key KeyWord: Word: EMERGENC EMERGENCY Y PROCEDUR PROCEDURES ES Cog Cog Level:

Level: M(2.2/4.0)

M(2.2/4.O)

Source:

Source: M Exam:

Exam: SM05301 Test:

Test: SS Author/Revi MC/SDR ewer: MC/SDR AuthorlReviewer:

21.

21.

Plant conditions Plant conditions are are as follows:

as follows:

- AA reactor

- reactor trip trip and and SI have occurred SI have occurred due due to to aa steam steam break.

break.

- ALL

- ALL Main Steam Isolation Main Steam Isolation Valves Valves initially initially failed failed to to close.

close.

EOP-3. 1, Uncontrolled

- EOP-3.1,

- Uncontrolled Depressurization Depressurization of of All All Steam Steam Generators, Generators, isis in in progress progress at at Step Step 17, 17, Establish Normal Establish Normal Charging.Charging.

- PZR

- PZR level level isis 58%.

58%.

- EFW

- EFW flowrate flowrate isis 5050 gpm gpm to to each each Steam Steam Generator Generator due due to to required required operator operator action.

action.

- All

- All Steam Steam Generator Generator NarrowNarrow Range Range levels levels are are 4%.

4%.

Reactor Building

- Reactor

- Building pressure pressure hashas remained remained belowbelow 11 psig.

psig.

RCS pressure is 1750 psig

- RCS pressure is 1750 psig and going UP.

- and going UP.

CETCs are

- CETCs

- 435 OF are 435 °F and and going going DOWN.

DOWN.

The "C" Main Steam C Main Isolation Valve closed 30 Steam Isolation 30 seconds seconds ago ago and C Steam and "C" Steam Generator Generator pressure pressure has changed from 80 has changed from 80 to 130 psig. to 130 psig.

Which ONE of the following correctly describes the actions the crew should take? take?

A. Remain A. Remain in in EOP-3.1 EOP-3.1 until the Critical Safety Function Status Trees direct entering an orange or red path Emergency Operating Procedure.

IMMEDIATELY transition to EOP-3.0, Faulted B. IMMEDIATELY Faulted Steam Generator Isolation, Step 1. 1.

C C . . . Complete EOP-3.1 through Step 20, verify SI Flow is NOT required, and then transition to EOP-3.0, Faulted Steam Generator Isolation, Step 1.

D. Complete all steps of EOP-3.1 and then transition to EOP-1.2, Safety Injection Termination, Step 1.

Feedback Feedback DISTRACTORS:

DISTRACTORS:

Incorrect. The AA Incorrect. The CC SG pressure has SG pressure has increased.

increased. Per Per EOP-3.1 EOP-3.1 Reference Reference Page Page item item 2,2, Secondary Integrity Transition Criteria, the Secondary Integrity Transition Criteria, the crew should crew should go go toto EOP-3.0, EOP-3.0, Faulted Faulted Steam Steam Generator Isolation, Generator Isolation, Step Step 1,1, after after completing completing EOP-3.0 EOP-3.0 SI SI Termination Termination steps steps 15 15 through through 20.

20.

Plausible ifif applicant Plausible applicant does does not not recognize recognize secondary secondary integrity integrity transition transition criteria.

criteria.

Incorrect. Per BB Incorrect. Per EOP-3.1, EOP-3.1, Reference Reference Page Page item item 2,2, the the crew crew should should go go to to EOP-3.0 EOP-3.0 ifif any any SG SG pressure pressure increases increases at at any any time time EXCEPT EXCEPT while while performing performing SI SI Termination inin steps Termination steps 15 through 20. Plausilbe if applicant does not 15 through 20. Plausilbe if applicant does not recognize step recognize step number number or or step step description description as an as an SI Termination step SI Termination or does step or does not not remember remember an an exception exception to to Secondary Secondary Integrigy Integrigy Transition Critierion.

Transition Critierion.

C Correct per C Correct per EOP-3.1, EOP-3.1, Reference Reference Page,Page, item item 2,2, Secondary Secondary Integrity Integrity Transition Transition Criterion.

Criterion.

D Incorrect. Per D Incorrect. Per EOP-3.1 EOP-3.1 Reference Reference Page,Page, item item 2,2, the the crew crew should should transition transition toto EOP-3.0 EOP-3.0 after completing SI Termination after completing SI Termination in in Steps Steps 15 15 through through 20.20. Plausible Plausible because because the the last last step step of of EOP-3.0, Faulted EOP-3.0, Faulted Steam Steam Generator Generator Isolation, Isolation, directs directs aa transition transition to to EOP-1.2.

EOP-1 .2.

REFERENCES:

1. EOP-3.1, Uncontrolled Depressurization

1. EOP-3.1, Depressurization of All Steam Generators

2. EOP-3.1LP,

2. EOP-3.1 LP, Uncontrolled Depressurization of All Steam Generators Depressurization Generators Lesson Plan K/A CATALOGUE KIA CATALOGUE QUESTION DESCRIPTION: DESCRIPTION:

W/E02 SI

- W/E02

- Termination SI Termination Knowledge symptom based EOP mitigation strategies (3.1/4.0).

- Knowledge Categories Categories Tier:

Tier: 1 Group: 2 Key KeyWord:Word: SI TERMINAT TERMINATION ION Cog Level: CIA(3.1/4.0)

C/A(3. 1/4.0.)

Source:

Source: N N Exam: SM05301 Test:

Test: SS Author/Revi AuthorlReviewer:

ewer: FJE/SDR

22.

22.

The Crew The Crew hashas entered entered EOP-16.0 EOP-16.0 "ResponseResponse to Pressurized Thermal to Pressurized Thermal Shock" Shock duedue toto an an Orange Orange path onpath on the the integrity integrity CSF CSF status status tree.

tree. The The Crew Crew isis atat the step for the step for Checking Checking RCS RCS Tcold Tcold Stable or Stable or Increasing.

Increasing.

While checking While checking EFW EFW flowflow itit isis determined determined thatthat aa Red Red path path condition condition exists exists on on the the Heat Heat Sink Sink CSF status tree.

CSF status tree.

Which ONE Which ONE of the following of the following correctly correctly describes describes the the action action that that should should bebe taken taken byby the the crew?

crew?

A. Remain A. Remain inin EOP-16.0 EOP-16.0 until until itit isis completed, completed, thenthen transition transition to EOP-15.0, Response to EOP-1S.0, Response to to Loss Loss of of Secondary Heat Secondary Heat Sink.

Sink.

B. Remain in B. Remain in EOP-16.0 EOP-16.0 until until the the Orange Orange pathpath isis cleared, cleared, then then tranistion tranistion to to EOP-1S.0.

EOP-15.0.

ClI IMMEDIATELY transition C,, IMMEDIATELY transition to EOP-1 5.0.

to EOP-1S.0.

D. The D. The transition transition to to EOP-1S.0 EOP-15.O is is NOT NOT required required since since EOP EOP 16.0 16.0 provides provides actions actions for for adjusting adjusting EFW.

EFW.

Feedback Feedback DISTRACTOR5:

DISTRACTORS:

A Incorrect, a red path exists for heat sink and it has priorty over integrity, the operator should tranistion immediately.

tranistion immediately.

B Incorrect, B Incorrect, a red path exists for heat sink and it has priorty over integrity, the operator should tranistion immediately.

tranistion immediately.

C Correct, the operator should transition to EOP-1S.0 EOP-15.0 immediately.

immediately.

D D Incorrect, a red path exists for heat sink and it has priorty over integrity, the operator should tranistion immediately immediately.. EOP-15.0 EOP-1S.0 has a caution that states:

If total EFW flow is LESS THAN 450 4S0 gpm due to operator action, this procedure should NOT be be performed, since these actions are NOT appropriate if 450 4S0 gpm EFW flow is available.

The stem does The stem does not not support this and and EOP-1 EOP-1S.05.0 mustmust be transitioned to for this CAUTION to apply.

apply.

REFERENC

REFERENCES:

ES:

1.1. EOP- 15.0, 16.0, EOP-1S.0, 16.0, 12.0.

12.0. Summer Summer Exam Exam bank bank question question EOPSEOPS 385. 38S.

K/A KIA CATALOGU CATALOGUE E QUESTION QUESTION DESCRIPTI DESCRIPTION: ON:

WEO5EA2.1 WEOSEA2.1 Ability Ability to to operate operate and and /1oror monitor monitor the the folowing folowing as as they they apply apply toto the the (Loss (Loss of of Secondary Heat Sink) Facility Secondary Heat Sink) Facility conditions conditions andand selection selection of of appropriate appropriate procedures procedures during during abnormal abnormal and and emergency emergency operations.

operations. (3.4/4.4)(3.4/4.4)

Categories Categories Tier:

Tier: I Group:

Group: 1I Key Word:

KeyWord: HEAT SINK HEAT SINK Cog Level:

Cog Level: CIA C/A (3.4/4.4)

(3.4/4.4)

Source:

Source: BB Exam:

Exam: SM0530l SM05301 Test:

Test: SS Author/Reviewer:

AuthorlReviewer: GWLIRF GWL/RFA/SA/SDRDR

23.

23.

AA Reactor Reactor Trip with aa loss Trip with loss ofof Off-site Off-site power power hashas occurred.

occurred. Power Power will will not not bebe restored restored for for at at least eight least eight hours, hours, andand aa cooldown cooldown isis desired.

desired.

RCS temperature

- RCS

- temperature isis currently currently 557557 of°F Only one

- Only

- CRDM fan one CRDM fan isis operable.

operable.

Which ONE Which ONE of of the the following following correctly correctly describes describes the the actions actions to to be be taken taken inin accordance accordance withwith EOP-1 .3 Natural Circulation EOP-1.3 "Natural Circulation Cooldown"? Cooldown?

A. Reduce A. Reduce RCSRCS pressure pressure to below 1925 to below 1925 psig, psig, maintain maintain RCSRCS subcooing subcooing greater greater than than 80 80 of,

°F, cooldown shall not exceed cooldown shall not exceed 50 of/hr. 50 °FIhr.

B.

B Maintain RCS

..... Maintain pressure above RCS pressure above 1925 1925 psig, psig, maintain maintain RCS RCS subcooling subcooling greater greater than than 130 130°F of and cooldown shall not and cooldown shall not exceed 50 exceed 50 0F/hr:

F/hr; 0

C. Reduce RCS pressure to below below 1925 1925 psig, maintain RCS RCS subcooing greater than 130 130 of,°F, cooldown shall not exceed 25 of/hr. F/hr.

0 D. Maintain RCS pressure above 1925 1925 psig, maintain RCS subcooling greater than 80 of °F and cooldown shall not exceed 25 of/hr. F/hr.

0 Feedback DISTRACTORS:

DISTRACTORS:

A Incorrect, RCS pressure should not be reduced, subcooling must be greater than 130 0 F.

130°F.

B Correct, RCS pressure should be maintained above 1925, subcooling must be greater than B

130 0 F, and cooldown is limited to 50 130°F, 0 F/hr.

F/hr.

0 50 C Incorrect, RCS pressure should not be reduced, subcooling must be greater than 130 °F, C of, and the cooldown is limited to 50 °F/hr. of/hr.

D D Incorrect, the cooldown is limited to 50 °F/hr. of/hr.

REFERENC

REFERENCES:

ES:

1. EOP-1.3 Natrual

1. Natrual Circulation Circulation Cooldown.

Cooldown.

K/A KIA CATALOGU CATALOGUE E QUESTION QUESTION DESCRIPTI DESCRIPTION: ON:

WEO9EA2.2 WE09EA2.2 Ability Ability toto operate operate andand I/ or or monitor the following as monitor the as they they apply apply to to the the (Natural (Natural Circulation Circulation Operations)

Operations) Adherence Adherence to to appropriate appropriate procedures procedures andand operation operation within within the the limits in limits in the the facilityss facilitys's license license and and amendments amendments.. (3.4/3.8)

(3.4/3.8)

Categories Categories Tier:

Tier: I Group:

Group: 22 Key KeyWord: Word: NATURAL NATURAL CIRC CIRC Cog Cog Level:

Level: CI A(3 04/3 .8)

CIA(3.4/3.8)

Source:

Source: MM Exam:

Exam: SM05301 SM05301 Test:

Test: SS Author/Revie AuthorlReviewer:

wer: GWLlSDR GWL/SDR

24.

24.

Plant conditions Plant conditions areare as as follows:

follows:

The Unit

- The

- experienced aa Steam Unit experienced Steam Generator Generator Tube Tube Rupture Rupture (SGTR)

(SGTR) on the "8" on the B Steam Steam Generator (SG).

Generator (SG).

The crew

- The

- currently performing crew isis currently performing EOP-4.0, EOP-4.0, Steam Steam Generator Generator Tube Tube Rupture, Rupture, Step Step 3, 3,

Isolate flow from each RUPTURED Isolate flow from each RUPTURED SG. SG.

When the When the crew crew transitioned transitioned from from EOP-1.0 EOP-1 .0 to EOP-4.0, FOUR to EOP-4.0, FOUR (4)

(4) minutes minutes ago, ago, plant plant parameters were parameters were as listed below:

as listed below:

Loop AA Loop Loop 8B Loop Loop C Loop C SG Pressure SG Pressure 800 psig 800 psig 1200 psig 1200 psig 800 psig 800 psig SG NR SG NR Level Level 40%

40% 80%

80% 45%

45%

SGPORV SG PORV SHUT SHUT OPEN OPEN SHUT SHUT RCS Temperature RCS Temperature 557 of°F 556 of

°F 557 of°F RCS Pressure:

RCS Pressure: 13501350 psig psig NOTE: ALL plant parameters were stable, with the exception of 8B SG NR NR Level, which was going UP.

CURRENT plant CURRENT plant parameters are as follows:

Loop A Loop 8 B Loop C SG Pressure 500 psig 1050 psig 750 psig SG NR SG NR Level Level 20% 85% 45%

SGPORV SG PORV SHUT SHUT SHUT RCS Temperature 520 °Fof of 550 °F of 550 °F RCS Pressure: 1000 psig ALL above parameters are all decreasing (going DOWN), with Loop A parameters decreasing decreasing faster than Loops B 8 and C.

Which ONE of the following correctly describes the NEXT action the crew should take in accordance with Emergency Operating Operating Procedures?

A.

A. IMMEDIAT IMMEDIATELY ELY go to EOP-2.0, go to EOP-2.0, Loss of Reactor or Secondary Coolant. Coolant.

B.

B."" IMMEDIAT IMMEDIATELY ELY go go to to EOP-3.0, EOP-3.0, Faulted Faulted Steam Steam Generator Generator Isolation.

Isolation.

C. RETURN to C. to EOP-4.0, EOP-4.0, Steam Steam Generator Generator Tube Tube Rupture, Step 1.

Rupture, Step 1.

D. COMPLETE D. COMPLETE EOP-4.0, EOP-4.0, Step and THEN Step 33 and THEN gogo to to EOP-3.0, EOP-3.0, Faulted Faulted Steam Steam Generator Generator Isolation.

Isolation.

Feedback Feedback DISTRACTORS:

OISTRACTORS:

AA Incorrect.

Incorrect. Plausible Plausible ifif applicant applicant believes believes aa LOCALOCA isis now now inin progress.

progress. AA LOCA LOCA would would bebe indicated by decreasing RCS pressure indicated by decreasing RCS pressure and and Loop Loop BB SG pressure ONLY, SG pressure ONLY, NOTNOT aa large large decrease inin Loop decrease Loop AA SG pressure, level, SG pressure, level, and and RCSRCS temperature.

temperature.

BB Correct Correct per per EOP-4.0, EOP-4.0, Reference Reference Page, Page, Secondary Secondary Integrity Integrity Transition Transition Criteria Criteria CC Incorrect.

Incorrect. Plausible Plausible because because thisthis isis item item 44 (Multiple (Multiple Tube Tube Rupture Rupture Criteria)

Criteria) on on the the EOP-4.0 reference EOP-4.0 reference page. page.

oD Incorrect. EOP Incorrect. EOP rules rules of of usage usage require require immediate immediate transition transition after after performing performing applicable applicable immediate actions.

immediate actions. EOP-4.0 EOP-4.0 doesdoes not not contain contain anyany immediate immediate actions. Plausible ifif actions. Plausible applicant believes applicant believes that that completely completely isolating isolating the ruptured SG the ruptured SC isis aa higher higher priority priority than than isolating the isolating the ruptured ruptured SG. SC.

REFERENCES:

1. EOP-4.0,

1. EOP-4.O, Steam Generator Generator Tube Rupture,Rupture, Reference Reference Page, Page, item item 2, Secondary Secondary Integrity Integrity Transition Criteria.

2. EO-2, Usage of of Emergency Operating Operating Procedures.

K/A CATALOGUE KIA CATALOGUE QUESTION DESCRIPTION: DESCRIPTION:

- W/E12 Steam Line Rupture - Excessive Heat Transfer

- G2.4.4 Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures (4.0/4.3).

Categories Categories Tier:

Tier: I Group: 11 Key Word:

KeyWord: STEAM LINE RUPTURE Cog Level: C/A(4.0/4.3)

C/A(4.O/4.3)

Source:

Source: N Exam: SM05301 Test:

Test: SS Author/Revi AuthorlReviewer:

ewer: FJE/SDR

25.

25.

Which ONE Which ONE of of the following describes the following describes thethe basis basis forfor reducing reducing the the Power Power Range Range Neutron Neutron Flux Flux High Trip Setpoint, in accordance High Trip Setpoint, in accordance with with Summer Summer Technical Technical Specification Specification Table Table 3.7-1, 3.7-1, ifif one one oror more main more main steam steam line code safety line code safety valves valves areare inoperable inoperable for for more more thanthan 44 hours5.092593e-4 days <br />0.0122 hours <br />7.275132e-5 weeks <br />1.6742e-5 months <br />?

hours?

A To A:<I To ensure ensure that that sufficient sufficient relieving relieving capacity capacity isis available available to limit secondary to limit secondary system system pressure pressure to within 110%

to within 110% of of design design pressure.

pressure.

B.B. ToTo minimize minimize the the positive positive reactivity reactivity effects effects of the Reactor of the Reactor Coolant Coolant System System cooldown cooldown associated associated with with the the blowdown blowdown of of the INOPERABLE safety the INOPERABLE safety valve(s).

valve(s).

c.

C. To limit the To limit pressure rise the pressure rise within within the the reactor reactor building building to within the to within the values values assumed assumed in in the the accident analysis accident analysis in in the the event event ofof aa steam steam line line rupture rupture within within the the reactor reactor building.

building.

D. To ensure that pressure induced D. induced stresses in in the steam generator with the INOPERABLE INOPERABLE safety safety valve(s) do not exceed do not exceed thethe maximum maximum allowable allowable fracture fracture toughness toughness stress stress limits.

limits.

Feedback D ISTRACTORS:

DISTRACTORS:

A Correct per Summer Technical Specification Bases 3/4.7.1.1, page B 3/4 7-1, paragraph 2.

B Incorrect. Plausible because this is part of the basis for the operability of MSIVs and FWIVs.

C Incorrect. Plausible because this is part of the basis for the operability of the MSIVs and FWIVs.

D Incorrect. Plausible because this is the basis for the Steam Generator Pressure /

Temperature limitiation (3.7.2). Fracture toughness (brittle fracture) is not aa concern at NOP/NOT.

REFERENC

REFERENCES:

ES:

1. Summer Technical Specification Bases 3/4.7.1.1, 3/4.7.1.5, 3/4.7.1.6, 3/4.7.2 3/4.7.1.1,3/4.7.1.5,3/4.7.1.6,3/4.7.2 K/A KIA CATALOGU CATALOGUE E QUESTION QUESTION DESCRIPTIDESCRIPTION: ON:

- W/E 13 13 Steam Generator Over-pressur Over-pressure. e.

G2.2.25 G2.2.25 Knowledge of bases in in technical specification specifications s for limiting limiting conditions conditions for operations and and safety safety limits (2.5/3.7).

(2.5/3.7).

Categories Categories Tier:

Tier: 11 Group:

Group: 22 Key Word:

KeyWord: S/G S/G OVERPRES OVERPRESSURE SURE Cog Cog Level:

Level: MEM2.5/3.7 MEM2.5/3.7 Source:

Source: NN Exam:

Exam: SM05301 SM05301 Test:

Test: SS Author/Revi Author/Reviewer:

ewer: FJE/SDR FJE/SDR