ML101620366

301 Final SRO Written Exam (Section 9)

ML101620366
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Site:	Summer
Issue date:	03/28/2010
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76. 002A2.04

76. 002A2.04 OO1l212/RCS/C/A 00 l/2/2/RCS/C/A (4.3/4.6)lN/SM05301lSIRFAlSDR (4.3/4. 6)/N/SM0530 l/S/RFAJSDR AA large large LOCA LOCA has has occurred.

occurred. Which Which ONE ONE of of the the following following actions actions are are corrrect corrrect given given the the following conditions:

following conditions:

• RWST level RWST level isis 17%

17% andand continues continues to to decrease.

decrease.

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

increasing.

• All RCPs All RCPs werewere tripped tripped (by (by procedure) procedure) when when RCS RCS 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 REACTOR OR OF REACTOR OR SECONDARY COOLANT SECONDARY COOLANT The following The following EOPs EOPs areare being being considered:

considered:

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

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

EOP-2.4 from A. EOP-2.4 from EOP-2.0.

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

Feedback 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 lost, this is not the case.

C. Incorrect:

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

D.

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 2.4, page EOP 2.4, page 4 of 4 29 of 29 KIA CATALOGU K/A CATALOGUE E QUESTION QUESTION DESCRIPTI DESCRIPTION: ON:

- Reactor Reactor Coolant Coolant System System (RCS);(RCS); Ability to (a)

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

operations: Loss Loss ofof heat heat sinks.

sinks.

Categories Categories Tier:

Tier: 22 Group:

Group: 22 Key Word:

KeyWord: RCS RCS Cog Level:

Cog Level: C/A CIA (4.3/4.6)

(4.3/4.6)

Source:

Source: NN Exam:

Exam: SM05301 SM05301 Test:

Test: SS Author/Reviewer:

Author/Reviewer: RFAJSDR RFAlSDR

77. 003A2.03

77. 003A2.03 002/211IRCPS/CIA 002/2/1/RCPS/C/A(2.7!3. 1 )/N/SM0530 1/S/RFAJSDR 2.7/3.1INISM0530IlSIRFAlSDR This Question This Question DELETED DELETED The following The following conditions conditions exist:

exist:

Reactor Power

- Reactor

- Power isis 9%.9%.

- AA Total

- Loss of Total Loss of All All Service Service WaterWater has has occurred.

occurred.

AOP-1 17.1, Total Loss of Service

- AOP-117.1, "Total Loss of Service Water," has

- Water, has been been entered.

entered.

RCP temperatures are

- RCP temperatures are beginning to

- beginning to rise.

rise.

Service Water

- Service

- Water can can not not be be restored.

restored.

Which ONE Which ONE of of the the following following describes describes the the action(s) action(s) the the operators operators must must take and .the take and the sequence sequence of those actions (in accordance of those actions (in accordance with AOP-117.1)?with AOP-1 17.1)?

A.v Initiate aa reactor A Initiate reactor plant plant shutdown shutdown per per GOP-4B, GOP-4B, POWERPOWER OPERATION OPERATION (MODE(MODE 11 - -

DESCENDING). Stop DESCENDING). Stop upup to TWO RCPs.

to TWO RCPs. Isolate Isolate unnecessary unnecessary CCW COW loads, loads, and and ensure ensure FS FS

• is is aligned to the DIGs. D/Gs. When an an RCP RCP motor motor bearing bearing temperatures or lower seal water or lower bearing temperature exceeds the specified limit, bearing limit, stop the affected RCP.

RCP.

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

DESCEN DING).

DESCENDING). Isolate unnecessary CCW loads, and ensure FS is aligned to the DIGs.

Secure an RCP only if motor bearing temperatures or lower seal water bearing temperature exceeds the specified limit.

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

DESCENDING). Stop at least TWO RCPs. Isolate unnecessary CCW loads, and ensure DESCENDING).

ES is aligned to the DIGs.

FS D/Gs. When the running RCP motor bearing temperatures or lower seal water bearing temperature exceeds the specified limit, increase monitoring and continue pump operation until the unit is shutdown then stop the affected pump.

D. Stop ONE RCP. Initiate aa reactor plant shutdown per GOP-4B, POWER OPERATION (MODE 11 - 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:

A. Correct: lAW AOP-1 17.1, the lAW AOP-117.1, the reactor reactor should should be be shutdown shutdown (not (not tripped).

tripped). Secure Secure upup to to TWO TWO RCPs (Step RCPs (Step 12).

12). TheThe affected affected RCPRCP should should bebe shutdown shutdown ifif RCP RCP motor motor bearing temperatures bearing temperatures exceeds 195 exceeds 195 of°F oror lower lower seal seal water water bearing bearing temperature temperature exceeds exceeds 2250F 225°F (Step (Step 13).

13).

B. Incorrect:

B. Incorrect: Do Do not not wait wait until until temperature temperature are are exceeded exceeded to secure RCPs to secure RCPs C. Incorrect:

C. Incorrect: Step Step 12 12 allows allows two 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 and secure one and secure one ifif necessary necessary for for temperature.

temperature.

D. Incorrect:

D. Incorrect: Shutdown Shutdown isis initiated initiated inin step step 33 and and Step Step 12 12 secures secures the the RCP.

RCP. Reactor Reactor isis not not tripped unless unless above above P-7.P-7.

References:

GOP-4B

References:

GOP-4B AOP-117.1, page 8 AOP-118.1, page page 55 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.

Facility POST EXAM comment resulted in this question being DELETED from the exam. The correct sequence is not contained in any of the distractors, so there is no correct answer.

The question was originally constructed and proposed by the NRC to contain only a list of the actions taken in the AOP without regard to sequence. The NRC agreed to the addition of the sequence "sequence" requirement and the inclusion of more of the sequence at the request of V. C.

Summer.

Categories Categories Tier:

Tier: 22 Group: 1I Key Word:

KeyWord: RCPS Cog Level:

Level: C/A(2.7/3.l)

C/A(2.7/3.1)

Source:

Source: N Exam: SM05301 SM05301 Test: SS Author/Revi ewer: RFAISDR Author/Reviewer: RFAlSDR

78. 005G2.1.27

78. 005G2. 1.27 OOII2/l/RHRIM 001/2/1 /RHRJM (2.812.9)/N/SM05301/SIRFAlSDR (2.8/2.9)/N/SM0530 1/S/RFA/SDR Which ONE Which ONE of the following of the following correctly correctly describes describes the the purpose purpose andand 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.A. Hot Leg Recirculation, Hot Leg Recirculation, Refueling Refueling Cavity Cavity Cooling, Cooling, Alternate Alternate Water Water supply supply to to Reactor Reactor Building Building Coolers, Pressurizer Relief Tank Cooling.

Coolers, Pressurizer Relief Tank Cooling. RHR can RHR can bebe 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 core core outlet outlet temperature temperature isis maintained maintained at at least least 50°F 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 Recirculation, Alternate Water Water supply supply to Reactor Building to Reactor Building Coolers.

Coolers. RHR RHR can can be be deenergized for deenergized for up up to hour provided to 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> 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 Tank Cooling.

Cooling. RHRRHR can be be deenergized for up up 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 core outlet temperature core outlet temperature is maintained at is maintained least 50°F at least 50°F below below saturation saturation temperature.

D Cold Leg Recirculation, D)/ 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 Feedback Distractor Analysis:

A. Incorrect: Hot Leg Recirculation, Recirculation, Alternate Water supply to Reactor Building Coolers, Pressurizer Relief Tank Cooling are all incorrect functions. 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 100 F below saturation temperature.

B.

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

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

D. Correct D. Correct answer 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 Heat Heat Removal Removal System; System; Knowledge Knowledge of of system system purpose purpose andand oror function.

function.

Categories Categories Tier:

Tier: 22 Group:

Group: 11 Key Word:

KeyWord: RHR RHR Cog Level:

Cog Level: M (2.8/2.9)

M (2.8/2.9)

Source:

Source: NN Exam:

Exam: SM05301 SM05301 Test:

Test: SS Author/Revie AuthorlReviewer:

wer: RFAlSDR RFA/SDR

79.007A2.03

79. 002/2/1 /PRT PRESSURE/C/A 007A2.03 0021211IPRT PRESSURE/C/A(3 .6/3 .9)/N/SM0530 I /S/FJE/SDR 3.6/3.9)/N/SM0530IlS/FJE/SDR Plant conditions Plant conditions are are asas follows:

follows:

-- The unit The unit isis in Cold Shutdown.

in Cold Shutdown.

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

cooling.

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

AUTO.

-- ALL pressurizer ALL pressurizer PORV PORV control control switches switches areare in in AUTO.

AUTO.

RCS temperature is RCS temperature is 140 140 of.

°F.

- PRT level PRT level isis 78%.

78%.

- PRT pressure PRT pressure is is 66 psig.

psig.

PRT temperature is PRT temperature 95 of is 95 °F Assuming no no operator operator action, action, aa _ _ _ _ _ will result in aa pressure result in pressure increase increase in in the PRT PRT and and the crew can can restore PRT PRT parameters parameters by by _ _ _ _ _ __

A. A HIGH HIGH failure of PT-444, pressurizer of PT-444, pressurizer pressure pressure control channel transmitter.

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

B.

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

Draining the PRT to the Recycle Holdup Tanks per SOP-1 SOP-i 08, Liquid Waste Processing System.

C. A HIGH failure of PT-444, pressurizer pressure control channel transmitter.

C.

Draining the PRT to the Recycle Holdup Tanks per SOP-1 SOP-i 08, Liquid Waste Processing System.

D. Loss of air to HCV-142, LTDN FROM RHR.

D.

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

Feedback Feedback DISTRACTORS:

DISTRACTORS:

A Incorrect failure.

A Incorrect failure. AA failure failure of PT-444 of PT high will

-444 high will not not cause cause aa pressurizer pressurizer PORV PORV to to open open because the because the P-11 P-i 1 signal signal (2/3 (2/3 pressurizer pressurizer protection protection channels channels less less than than 1985 psig) will 1985 psig) will prevent automatic operation of the pressurizer prevent automatic operation of the pressurizer PORVs PORVs inin this plant Mode.

this plant Mode.

Plausible because Plausible because thethe 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. ???At

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

bubble).  ???

Spraying the Spraying the PRT PRT would would notnot reduce reduce PRT PRT pressure pressure (but(but would would increase increase PRT PRT pressure pressure as as PRT level PRT level increased increased from from the the addition addition of of reactor reactor makeup makeup water).

water). Plausible Plausible because because thisthis action would action reduce PRT would reduce 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 willwill fail fail shut shut onon loss loss of of air.

air. A failure of A failure of HCV-142 HCV-142 in in the the closed closed position isolates the position isolates RHR system the RHR system from from thethe letdown letdown system.

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

corrective, action.

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

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

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

REFERENCES:

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

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

3. AB-7, Residual Heat Removal System SOP-i 01, Reactor Coolant System

4. SOP-1 K/A CATALOGU KJA CATALOGUE E QUESTION DESCRIPTION:

DESCRIPTION:

- Ability to (a) predict the impacts of the following malfunctions or operations on the P S 5

(Pressurizer Relief Tank 1 / Quench Tank System); and (b) based on those predictions, use procedures to correct, control, or mitigate the consequence consequences s of those malfunctions or operations: Overpressuri zation of the PZR (3.6/3.9)

Overpressurization Categories Tier: 22 Group: 11 Key Word:

KeyWord: PRT PRESSURE Cog Level: C/A(3.6/3.9)

C/A(3.6!3.9)

Source:

Source: N Exam: 5M05301 SM05301 Test: SS Author/Revi Author/Reviewer:

ewer: FJE!SDR FJE/SDR

80. 007EA2.01

80. 007EA2.0 1 002/1/1IREACTOR 002/1/1/REACTORTRIPICIA(4.1/4.3)/M/SM05301lSIMC/SDR TRJP/C/A(4. 1/4.3)/M/SM0530 1/S/MC/SDR At50%

At 50% power, power, the the plant plant experienced experienced aa loss loss ofofBOTH BOTH running running Main Main Feedwater Feedwater Pumps Pumpswith with aa concurrent failure of the concurrent failure of the Reactor trip Reactor trip breaker breakerAA toto open.

open. TheThe crew crew isis performing performing the the immediate immediate actions of actions of EOP-1.0, EOP-1 .0, "Reactor ReactorTrip/Safety Trip/Safety Injection Injection Actuation."

Actuation.

Current plant Current plant conditions conditions are are asas follows:

follows:

-- The Integrated The Integrated Plant Plant Computer Computer SystemSystem has has failed.

failed.

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

lit.

-- Reactor Power Reactor Power isis 7% 7% and and slowly slowly decreasing.

decreasing.

-- All EFW All EFW Pumps Pumps failedfailed toto start.

start.

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

information?

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

Sink.

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

Sink.

C Remain Cy Remain in in EOP-1.0, EOP-1 .0, until directed to monitor Critical Critical Safety Safety Functions Functions then transition transition toto EOP-13.0, Response To EOP-13.0, "Response To Abnormal Nuclear Nuclear Power Power Generation."

Generation.

DDt Transition from EOP-1.0

..... Transition EOP-1.0 to EOP-13.0, EOP-13.0, "Response Response To Abnormal Nuclear Nuclear PowerPower Generation.

Generation."

Feedback Feedback D ISTRACTORS:

DISTRACTORS:

A INCORRECT A INCORRECT Should transition directly to EOP-13.0. EOP-1 3.0.

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

C C INCORREC INCORRECT T Should transition directly to EOP-13.0.

DD CORRECT CORRECT Should transition transition directly directly to to EOP-13.0.

EOP-13.0. SinceSince there there areare nono given given conditions conditions that would would warrant an SI, an SI, the CRS shouldshould follow the the Alternative Alternative Action for for Step Step 55 of of EOP-1.0 EOP-1.0 and and transition transition to to EOP-1.1.

EOP-1.1. Upon Upon transition transition from from EOP-1 EOP-1.0, .0, the the STA STA begins begins monitoring monitoring of of CSFs, CSFs, and and should should infrom infrom CRS CRS of of Red Red path path toto EOP-13.0 EOP-13.0 based based on on power power >5%.

>5%.

REFERENC

REFERENCES:

ES:

1.

1.

KIA KIA CATALOGU CATALOGUE E QUESTION QUESTION DESCRIPTIDESCRIPTION: ON:

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

trip:

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

indications.

Facility Facility POST POST EXAM EXAM comment comment resulted resulted inin accepting accepting twotwo answers answers for for this this question.

question. With With aa decreasing decreasing power power level level the the applicant applicant may may not not transition transition immediately immediately based based on on the the indications indications present present and and wait wait until until directed directed by by the the status status trees.

trees.

Categories Categories Tier:

Tier: I Group:

Group: 11 Key Word:

KeyWord: REACTOR TRIP REACTOR TRIP Cog Level:

Cog Level: C/A(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

81. 008A2.04

81. 008A2.04002/2111CCW/CIA 002/2/1/CCW/C/A(3.3/3.5)/M/SM0530IlSIRFAlSDR (3.3/3.5)/M/SM05301/S/RFA/SDR The Unit The Unit isis operating operating atat 100%

100% power powerwith all systems with all systems inin normal normal lineups lineups when when thethe following following annunciators annunciators actuate: actuate:

- LLTDN/SL TDN/SL WTR WTR HX FLO LO HX FLO LO TEMP TEMP HI HI

--CC LOOP AA RM-L2A CC LOOP RM-L2A HI HI RAD RAD

- CC

- SRG TK CC SRG TK VENT VENT 70967096 CLSD CLSD HI HI RAD RAD CCW SRG TK LVL

- CCW SRG TK LVL HI/LO/LO-LO HI/LO/LO-L O NO other NO other annunciators annunciators are are litlit and and all all associated associated automatic automatic functions functions have have occurred.

occurred.

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 the Letdown Letdown HX; HX; verify verify closure closure ofof PVT-8152, PVT-8152, LTDNLTDN LINE LINE ISOL, ISOL, perper SOP-i 02, CHEMICAL SOP-102, CHEMICAL AND VOLUME AND VOLUME CONTROL CONTROL SYSTEM, SYSTEM, and and manually manually shut shut PW-7096, PW-7096, CCSURGET CC SURGE TK KVLVVL V B B.

..... A leak exists A leak exists inin the the Letdown Letdown HX; HX; manually manually close close PVT-8152, PVT-8152, LTDNLTDN LINELINE ISOL, ISOL, perper SOP-i 02, CHEMICAL SOP-102, CHEMICAL AND AND VOLUME VOLUME CONTROL CONTROL SYSTEM, SYSTEM, and and verify closure of verify closure of PW-7096, CC SURGE TK VLV PW-7096, C. RCP C. RCP "A" A thermal barrier has been breached. Conduct a normal shutdown per GOP-4B, POWER OPERATION POWER OPERATION (MODE 11 - 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-1 01, REACTOR COOLANT SYSTEM.

D. A D. A Phase Phase "B" B Containment Isolation has actuated due to RM-L2A&B (Component Cooling) alarming.

alarming. Immediately trip the reactor and trip ALL RCPs and enter EOP 1.0.

Feedback Feedback Distractor Distractor Analysis:Analysis:

A.

A. Incorrect.

Incorrect. PVT-81 PVT-8152 52 must be manually shut and PVV-7096 PW-7096 should close automatically and and be be verified verified closed.

B.

B. Correct:

Correct:

C.

C. Incorrect:

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

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

apply.

D.

D. Incorrect:

Incorrect: RM-L2A&B RM-L2A&B 99 will will not not 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 SOP 102.2, 102.2, CHEMICAL CHEMICAL AND AND VOLUME VOLUME CONTROLCONTROL SYSTEM,SYSTEM, page page 70,70, ARP-001-XC ARP-001-XCP-601, page 16 P-601, page 16 KIA CATALOGU K/A CATALOGUE E QUESTION QUESTION DESCRIPTI DESCRIPTION: ON:

- Component

- Component Cooling WaterCooling Water SystemSystem (CCWS);

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

(b) based based on on those those predictions, predictions, use use procedures procedures toto correct, correct, control, control, or or mitigate mitigate the the consequence consequences s of ofthose 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:

Author/Reviewer: RFAJSDR RFAlSDR

82. 009EG2.4.30

82. 009EG2.4.30 002/1/I1REPORTABILITYIM(2.2/3.6)/N/SM0530IlSIRFAlSDR 002/1/1/REPORTABILITY/M(2.2/3 .6)/N/SM0530 1/SIRFAJSDR Which ONE Which ONE of of the the following following identifies identifies an an event event that that isis required required to to be be reported reported to to the the NRC NRC withinwithin hour per 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> per EPP-002, EPP-002, COMMUNICATION COMMUNICATION AND AND NOTIFICATION.

NOTIFICATION.

A. An A. unplanned ECCS An unplanned 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.v An ECCS

..... An ECCS 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 ofof>

> 2X2X Appendix Appendix BB limits.

limits.

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

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 notnot 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 hour notification requirement.

requirement.

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

C. Incorrect: 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 D. Incorrect: 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 D.

Reference:

EPP-002,

Reference:

EPP-002, page 27 K/A CATALOGUE KIA CATALOGUE QUESTION DESCRIPTION: DESCRIPTION:

Small

- Small

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

Categories Categories Tier:

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

Source:

Source: N Exam: SM05301 Test:

Test: SS Author/Revi Author/Reviewer:

ewer: RFAJSDR RFAlSDR

83. 022AG2.4.49 OOl/1/l1RCS

83. 022AG2.4.49 00 1/1/1/RCS MAKEUP/CIA MAKEUP/C/A(4.0/4.0)/N/SM05301lSIRFAlSDR (4.0/4.O)/N/SM05301/S/RFAJSDR The plant The plant was was operating operating at at 80%

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

in:

- REGEN HX REGEN HX LLTDN TDN OUTOUT TEMPTEMP HI HI

- VCT LVL VCT LVL HIILO HI/LO

- CHG LINE CHG LINE FLO FLO HIILO HI/LO

- PZR LCS PZR LCS DEV HIILO DEV HI/LO Charging pump Charging pump amps amps are are fluctuating fluctuating between between 25 25 andand 3030 amps amps Charging flow Charging flow isis fluctuating fluctuating between between 25 25 and and 30 gpm 30 gpm Charging pressure Charging pressure isis oscillating oscillating between between 25002500 andand 2600 2600 psig psig Which ONE Which ONE of of the the following following set of actions set of actions should should thethe supervisor supervisor direct direct his his board board operators operators toto perform (These actions perform (These actions are not are all inclusive)?

not all inclusive)?

A.% Secure A.II Secure the the operating operating charging charging pump, pump, close close allall letdown letdown isolation isolation valves, valves, andand close close FCV-122, charging FCV-122, charging flow flow control control valve.

valve.

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

C. Secure the operating charging pump, realign charging pump suction, and close both LCV-1 15B(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 D.

LCV-115C(E), VCT OUTLET ISOL.

LCV-115C(E),

Feedback Feedback Distractor Analysis:

A.

A. Correct answer per AOP-1 02.2, page 4-6 AOP-102.2, B,C, and D. Charging flow is abnormal - must go to the RNO column. Closing

- ClOSing both LCV-1 1 5B(D), RWST TO CHG PP SUCT, LCV-115B(D), SUCT, is is an an action action ifif charging charging was initially initially aligned aligned toto the the RWST.

Reference:

AOP-1 02.2, page AOP-102.2, page 4-6 4-6 K/A KIA CATALOGU CATALOGUE E QUESTION QUESTION DESCRIP11 DESCRIPTION: ON:

- Loss of

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

controls.

Categories Categories Tier:

Tier: 1 Group:

Group: 1 Key Word:

KeyWord: RCS MAKEUP RCSMAKEUP Cog Cog Level:

Level: CIA (4.0/4.0)

C/A (4.0/4.0)

Source:

Source: NN Exam:

Exam: SM05301 SM05301 Test:

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

84. 032AA2.08

84. 032AA2.08 003/l/2/SRNIIM(2.2/3.1 003/112/SRNI/M(2.2/3. 1)IN/SM053

)/N/SM053001/S/MCIRF AISDR l/SIMCIRF AlSDR Refueling operations Refueling operations are are inin progress, progress, with with SR monitor N33 SR monitor N33 out of service, out of service, when when power power isis suddenly lost to source range neutron suddenly lost to source range neutron flux monitor N31 flux monitor N31 andand subsequently subsequently regained regained 30 30 minutes minutes later.

later.

Which ONE Which ONE of of the the following following describes describes the the action action to be taken to be taken forfor this this situation situation when when powerpower isis lost?

lost?

A."A. Suspend Suspend all all core core alterations alterations andand perform perform an an analog analog channel channel operational operational testtest ofof source source range neutron flux range neutron flux monitor N31monitor within 88 hours0.00102 days <br />0.0244 hours <br />1.455026e-4 weeks <br />3.3484e-5 months <br /> N31 within hours prior prior toto the the initial initial start.of startof core core alterations.

alterations.

B.B. Suspend Suspend all all core core alterations alterations andand perform perform aa neutron neutron fluxflux response response time time test test AND AND operational operational test of test source range of source range neutron neutron flux flux detector detector N31N31 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 to the the initial initial start start of of core core alterations.

alterations.

C. Determine boron C. Determine boron concentration concentration and perform aa channel and perform channel checkcheck of of source source range range neutron neutron flux flux monitor monitor N31 N31 withinwithin 1212 hours0.014 days <br />0.337 hours <br />0.002 weeks <br />4.61166e-4 months <br />.

hours.

D.D. Determine Determine boron concentration and perform a neutron neutron flux response response time test of source source range neutron range neutron flux detector detector N31N31 within 12 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

hours.

Feedback Feedback DISTRACTORS:

DISTRACTORS:

A CORRECT T.S. 3.9.2 requires immediate suspension of CORE ALTERATIONS ALTERATIONS when one of the two SR monitors are lost INCORRECT B INCORRECT (*

B Per T.S. Table 3.3-2 (* and Note 1), neutron detectors (not the channel) are exempt from response time testing.

C INCORREC INCORRECT T Boron concentration measuremen measurements ts are only required when both monitors are down.

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

REFERENC

REFERENCES:

ES:

1. TS 3.9.2,

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

2. TS

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

3. TS

3. TS Table Table 3.3-2, 3.3-2, Reactor "Reactor TripTrip System System Instrumentat Instrumentationion Response Response Times.

Times."

4.

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

24,48, 50.

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

- Loss of Source

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

restored.

Categories Categories Tier:

Tier: 1 Group:

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

Cog Level: M(2.2/3.1)

M(2.2/3.1)

Source:

Source: N N Exam:

Exam: SM05301 SM0530 1 Test:

Test: SS Author/Revie wer:

AuthorlReviewer: MC/RFAlSDR MC/RFAJSD R

85. 035G2.4.20

85. 035G2.4.20 002/2/2/SGIC/A 002/2/2/SG/C/A (3.3/3.4)/N/SM05301lSIRFAlSDR (3.3/3.4)/N/SM0530 1/SIRFAJSDR The crew The crew hashas just just entered entered EOP-15.0, EOP-15.O, "Response Response to to Loss Loss ofof Secondary Secondary Heat Heat Sink" Sink from from EOP-12.O, Monitoring of Critical EOP-12.0, Monitoring of Critical Safety Safety Functions.

Functions.

The following The following conditions conditions exist:exist:

-- WR SG WR SG "A"A level level isis 25%

25%

-- WR SG WR SG "B" B level level isis 12%

12%

- WR SG "c" level is 11%

WR SG C level is 11%

-- Total Feed Total Feed Flow isFlow is 290 290 gpm gpm Which ONE Which ONE of the following of the following sets sets of actions (not of actions (not all all inclusive) inclusiye) should should be be taken taken as as directed directed byby EOP-1 5.0, "Response EOP-15.0, Response to to Loss Loss of of Secondary Secondary Heat Heat Sink"?

Sink?

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

SG.

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

Generators.

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

C. Reset C.

D D~ Trip ALL RCPs, actuate SI, establish an RCS bleed path:

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

other Distractor Analysis:

Distractor A, B, C. Incorrect:

Incorrect: Not allowed due to caution prior to step 4. These steps are bypassed when when the CAUTION the CAUTION prior to Step 4 is implemented implemented..

D D Correct:

Correct:

Reference:

EOP-12, EOP-12, page page 99 EOP-15, EOP-15, page page 33 caution prior to step step 44 K/A KIA CATALOGU CATALOGUE E QUESTION QUESTION DESCRIPTI DESCRIPTION: ON:

- Steam Steam Generator; Generator; Knowledge Knowledge of of operational operational implications implications of of EOP EOP warnings, warnings, cautions, cautions, and and notes.

notes.

Categories Categories Tier:

Tier: 22 Group:

Group: 22 Key Word:

KeyWord: SG SG Cog Cog Level:

Level: CIA (3.3/3.4)

C/A (3.3/3.4)

Source:

Source: NN Exam:

Exam: SM05301 SM05301 Test:

Test: SS Author/Revi Author/Reviewer:

ewer: RFAlSDR RFAJSDR

86. 054AA2.03

86. 054AA2.03 0021111/MFW/C/A 002/1/1/MFW/C/A (4.1I4.2)/N/SM05301lSIRFAlSDR (4. 1/4.2)/N/SM0530 1!SIRFA!SDR 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 isolation valves

- SG blowdown isolation

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

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

ISOL) closed closed Current SG narrow range

- Current SG narrow range levels

- levels inin "A",

A, "B", and "c" B, and C SGs SGs are are 8%,10%,

8%, 10%, and and 10%, respectively, 10%, respectively, and and decreasing decreasing Which ONE Which ONE of of the the following following correctly correctly states states the initiating event the initiating event that that caused caused thethe trip trip and and the the expected automatic expected automatic actions actions based based on on these these conditions?

conditions?

A. The A. The operating operating MFPMFP tripped tripped and ONLY the and ONLY the motor motor driven driven EFW EFW pumps pumps havehave aa current current start start signal.

signal.

BB.v The operating

..... The operating MFPMFP tripped and BOTH the turbine driven and BOTH driven AND AND motor motor driven driven EFW EFW pumps pumps have aa current have current start start signal.

signal.

C. All SG flow control valves drifted closed and AMSAC should should have actuated.

D. All D. All SG flow control valves drifted closed and ONLY the turbine driven EFW pump has aa current start signal.

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

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

A(B)(C)

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

Distractor Analysis:

A. Incorrect:

A. Incorrect: LO LO level both MDEFP AND TDEFP will start B. Correct:

C.

C. Incorrect:

Incorrect: All SG SG flow control control valves drifting drifting closed couldcould cause cause this.

this. ????Howeve

????However, SG r, SG blowdown blowdown isolationisolation valves valves (PVG-503A(

(PVG-503A(B)(C),B)(C), A(B)(C) ISOL) ISOL) closed which dont don't according according to ARP XCP-624.???

XCP-624. ????  ? Additionally Additionally,, AMSAC AMSAC will not not actuate since initial initial power power was <40%< 40%

D. Incorrect:

D. Incorrect: All SG flow control All SG control valves valves drifting drifting closed closed could could cause cause this.

this. ????Howeve

????However, SG r, SG blowdown isolation blowdown isolation valves valves (PVG-503A(

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

A(B)(C) ISOL)

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

XCP-624. ???? ???? Additionally Additionally,, both both MDEFP MDEFP AND AND TDEFP TDEFP will will start.

start.

Reference:

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

- Loss of Main Feedwater (MEW);

- Loss of Main Feedwater (MFW); Ability to Ability to determine determine and and interpret interpret the the following following asas they they apply apply to the Loss of Main Feedwater to the Loss of Main Feedwater (MFW): (MFW): Conditions Conditions and and reasons reasons for for AFW AFW pump pump startup.

startup.

Categories Categories Tier:

Tier: 1 Group:

Group: 11 Key Word:

KeyWord: MFW MFW Cog Level:

Cog Level: CIA C/A (4.114.2)

(4.1/4.2)

Source:

Source: NN Exam:

Exam: SM05301 SM05301 Test:

Test: SS Author/Reviewer:

AuthorlReviewer: RFA/SDR RFAISDR

87. 068G2.1.20 B7. 068G2. 1.20002/2/2/U 002/2/2/LIQU DIDiDRADWASTE/C/A(4.3/4.2 RADWASTE/C/A(4.3/4.2/N/SM05301/SIRFAlSDR

)/N/SM05301/S/RFA/SDR Liquid Radwaste AA Liquid Radwaste Release Release isis been been inin progress:

progress:

-- XCP-646 2-5, XCP-646 2-5, MON MON TK TK DISCH DISCH RM-L5RM-L5 HI HI RAD, RAD, hashasjust just actuated actuated for forthe the second second time.

time.

-- RCV0001 8-WL, Liquid RCV0001B-WL, Liquid Radioactive Radioactive Waste Waste Control Control Valve, Valve, indicates indicates shut.

shut.

-- Within 30 Within 30 seconds seconds of ofthe the alarm, alarm RM-L5's

, RM-L5s reading reading returns returns toto below below thethe setpoint.

setpoint.

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

taken.

A. The A." The tank tank must must be be sampled sampled and and activity activity levels levels verified, verified, then then open open RCV0001B-WL RCV00018-WL and and resume the resume release per the release per SOP-10B.

SOP-108.

B. Verify that B. Verify that the the RM-L5's RM-L5s reading reading isis below below thethe setpoint, setpoint, then then open open RCV0001B-WL RCV00018-WL and and resume the release per resume the release per SOP-1 OB.SOP-i 08.

C. Verify that C. Verify that the the RM-L5's RM-L5s reading reading is is below below thethe setpoint, setpoint, then then open open RCV0001B-WL RCV00018-WL and and resume the resume release per the release per SOP-1 SOP-108. Direct Heath OB. Direct Heath Physics Physics to to continue continue to to monitor monitor thethe release release and reduce and reduce the release rate.

the release rate.

Dv Notify Dy Notify Health Health Physics Physics andand request request aa radiological radiological survey.

survey. TheThe release release cancan not not be be reinitiated reinitiated under the current release under release permit.

permit.

Feedback Feedback DISTRACTORS:

DISTRACTORS:

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

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

INCORRECT C INCORRECT This is the action if this is the first time the release has been automatically terminated, ????coupled with the actions for a malfunctioni malfunctioning RM-L5. ????

ng RM-L5.????

D INCORREC D INCORRECT T This would be plausible if itit is believed that the release can not 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-i, 4-1, page page 22.

22.

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

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

steps.

Facility Facility POST POST EXAMEXAM comment comment resulted accepting two resulted inin accepting two answers answers for for this this question.

question. The The additional information provided additional information provided by by the the facility facility inin HPP-710 HPP-710 supports supports distractor distractor DD as as an an additional additional correct correct answer.

answer. Additionally Additionally,, this this additional additional answer answer was was not not identified identified by by the the facility facility during during the the examination examination review review andand validation validation activities.

activities. HPP-710 HPP-710 indicates indicates that that the the current current release release permit permit must must be be closed.

closed.

Categories Categories Tier:

Tier: 22 Group:

Group: 22 Key Word:

KeyWord: LIQUID RADW LIQUID RADWASTE ASTE Cog Level:

Cog Level: C/A(4.3/4.2)

C/A(4.3/4.2)

Source:

Source: NN Exam:

Exam: SM05301 SM05301 Test:

Test: SS Author/Reviewer:

AuthorlReviewer: RFA/SDR RF AlSDR

88. I03G2.1.30

88. 1 03G2. 1.30 002/2/I/CONTAINMENT 002/211 /CONTAfNMENT AlRLOCKIM AIRLOCKJM (3.9/3.4)/N/SM05301/SIFJEIRFNSDR (3.9/3 .4)/N1SM0530 1 /SIFJE/RFAISDR 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 work

- All major work inside inside containment containment was was completed completed two two hours hours agoago and and there there are are NO NO personnel inside personnel inside thethe Reactor Reactor Building.

Building.

- An

- auxiliary operator An auxiliary operator has has just just called called toto report report that that the the red red indicating indicating light light above above the the Personnel Escape Airlock is LIT and Personnel Escape Airlock is LIT and that he was unablethat he was unable to to operate operate the the Fuel Fuel Handling Handling Building door Building door usingusing the the handwheel.

handwhee!.

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

Integrity?

A The A.v The Reactor Reactor Building Building door door isis OPEN.

OPEN.

The Personnel Escape The Personnel Escape Airlock is Airlock is INOPERABLE.

INOPERABLE.

B. The Reactor B. The Reactor Building Building door door is CLOSED.

is CLOSED.

The Personnel The Personnel Escape Escape Airlock Airlock isis INOPERABLE.

INOPERABLE.

C. Only the Reactor C. Reactor Building Building door position position indicator indicator has has malfunctioned.

malfunctioned.

The Personnel Escape Airlock is is OPERABLE.

OPERABLE.

D. The Personnel Escape Airlock is OPERABLE.

D. OPERABLE.

The Personnel The Personnel Escape Airlock door interlock is INOPERABLE. INOPERABLE.

Feedback Feedback Distractor Analysis Distractor A Correct.

A Correct. The red bulkhead light and the inability to operate door operating handle NO.4 No. 4 (after unlocking (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 personnel in containment for two hours, the air lock is NOT being used for normal transit entry and exit.

BB Incorrect.

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

C.C. The The indicator indicator is is aa positive positive indication indication of of the status of of the the door.

door. The The door door isis open.

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

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

door. The The door door isis open.

open. The The Personnel Escape Airlock Personnel Escape Airlock is INOPERABLE.is INOPERABL E.

Reference:

Technical Technical Specification Specification 3.6.1.3, 3.6.1.3, Containment Containment Air Air Locks Locks KJA KIA CATALOGU CATALOGUE E QUESTION QUESTION DESCRIPTIDESCRIPTION: ON:

- 103 Containment

- 103 Containment System System

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

(3.9/3.4)

Categories Categories Tier:

Tier: 22 Group:

Group: 1 Key Word:

KeyWord: CONTAINMENTAIRLOCK CONTAINMENT AIRLOCK Cog Level:

CogLevel: MM(3.9/3.4)

(3.9/3.4)

Source:

Source: NN Exam:

Exam: SM05301 5M05301 Test:

Test: SS Author/Reviewer:

AuthorlReviewer: FJEIRF AlSDRR FJE/RFAJSD

89. G2.I.l3

89. G2.1.13002/3//ADMINIM 002/3//ADMINIM(2.0/2.9)/N/SM05301lSIRFAlSDR (2 .O/2.9)IN/SM0530 1 !S/RFAISDR Which ONE Which ONE of ofthe the following following (as (as stated stated inin SAP-200, SAP-200, Conduct Conductof ofOperations)

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

question?

A.A. General General Manager, Manager, Nuclear Nuclear Plant Plant Operations Operations BB.v Shift Supervisor

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

Distractor Analysis:

A. Incorrect:

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

D. Incorrect: per per SAPSAP 200, Paragraph Paragraph 6.5.2 H, H, page page 1010

Reference:

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

K/A CATALOGUE DESCRIPTION:

Knowledge of facility requirements for controlling vital/controlled

- Knowledge vital I controlled access.

Categories Categories Tier:

Tier: 33 Group:

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

M Source:

Source: N N Exam:

Exam: SM05301 SM05301 Test:

Test: SS Author/Revi Author/Reviewer: RFAlSDR ewer: RFA/SDR

90. G2.1.34

90. G2.1.34 002/311CONDUCT 002/3//CONDUCT OF OF OPS/CIA(2.3/2.9)/B/SM0530l/SIMC/SDR OPS/C/A(2.3/2.9)/B/SM0530 1/S/MC/SDR The unit The unit isis undergoing undergoing aa normal normal heatup.

heatup. Plant Plant conditions conditions areare asas follows:

follows:

Hydrazine was

- Hydrazine was added added whenwhen RCSRCS temperature temperature was was 185°F.

185°F.

RCS temperature

- RCS temperature isis 200°F.

- 200° F.

- AA reactor

- reactor coolant coolant sample sample shows shows dissolved dissolved oxygen oxygen concentrations concentrations of of 1.1 1.1 ppm.

ppm.

Given the Given the above above conditions conditions and and inin accordance accordance with with GOP-2,"Plant GOP-2,Plant Startup Startup andand 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.A. Secure Secure the the Heatup, Heatup, plantplant chemistry chemistry isis NOT NOT inin compliance compliance with with GOP-2; GOP-2; an an LCO LCO HASHAS been been entered.

entered.

BB. Secure the

...... Secure the Heatup Heatup to to prevent prevent plant plant chemistry chemistry from NOT being from NOT being inin compliance compliance with with GOP-2; GOP-2; an LCO an LCO has has NOT NOT beenbeen entered.

entered.

C. The C. The heatup heatup cancan continue, continue, plant plant chemistry chemistry IS IS in in compliance compliance withwith GOP-2; GOP-2; an an LCO LCO HASHAS been been entered.

entered.

D. The heatup D. heatup can continue, plant plant chemistry IS IS in in compliance with GOP-2;GOP-2; an LCO LCO hashas NOT NOT been entered.

been Feedback 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 specification.. Although the Steady State Limit for Oxygen is 0.lppm 0.1 ppm in Modes 11 - 4, it is not applicable with Tavg ~

- 250°F

< 250°F (per

• note below Table 3.4-2).

CC INCORREC INCORRECT T Plant Plant temperature has has exceeded the GOP-2 GOP-2 limit limit of 200°F 200°F but but not not the TS TS limit limit ofof 250°F.

250°F.

DD INCORREC INCORRECT T Plant Plant temperature has has exceeded exceeded the the GOP-2 GOP-2 limit limit of of 200°F.

200°F.

REFERENC

REFERENCES:

ES:

1. Tech

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

Modes."

2.

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

Limits."

2:

2. GOP-2,Plan GOP-2,"Plantt StartupStartup and and Heatup Heatup (Mode (Mode 55 to to Mode Mode 3), Step 2.la 3)," Step 2.1a page page 2, 2, Step Step 3.1 3.1 page page 5, 5,

&& the Reference the Reference Page. Page.

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

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

limits.

Categories Categories Tier:

Tier: 33 Group:

Group:

Key KeyWord: Word: CONDUCT CONDUCT OF OF OPS OPS Cog Cog Level:

Level: CIA(2.3/2.9)

C/A(2.3/2.9)

Source:

Source: BB Exam:

Exam: SM05301 SM05301 Test:

Test: SS Author/Reviewer: MC/SDR AuthorlReviewer: MC/SDR

91. G2.2.20 OO1l31ITROUBLESHOOTINGIM2.2/3.3IMISM05301lSIFJE/SDR

91. G2.2.20 001 /3//TROTJBLESHOOTING/M2.2/3 .3/M/SM0530 I /S/FJE/SDR 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, or component, the condition of the condition of which which isis specified specified by by aa Technical Technical Specification Specification Action Action Statement.

Statement.

A AA Temporary A:" Temporary Restoration Restoration to Service isis used to Service used even even though though an alternative method an alternative method of of completing the completing the work work that that will will meet meet the the action action statement statement requirement requirement waswas identified.

identified.

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

component.

C. The Temporary C. The Temporary Inoperable Inoperable Status Status Change Change required required toto perform perform the the troubleshooting troubleshooting was was approved by approved by thethe Duty Duty Shift Shift Supervisor.

Supervisor.

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

Feedback Feedback DISTRACTORS:

DISTRACTORS:

A Correct per SAP-205, 6.7.2.B B Incorrect. Acceptable per 6.7.3.A.1. and 6.7.3.A.2. Plausible if applicant believes that immediately restore" the need to "immediately restore would prevent a troubleshooting troubleshooting activity.

C Incorrect. SAP-205, Attachment V, Temporary Inoperable Status Change, requires approval 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 Incorrect. Allowed per SAP-0148 section 2.2. Plausible if applicant believes a Bypass Authorizatio Authorization n Request is not used to authorize installation of electrical jumpers or that administrativ administrative e procedures prohibit the use of electrical jumers during troubleshoot troubleshooting.ing.

REFERENC

REFERENCES:

ES:

1.

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

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

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

Categories Tier:

Tier: 33 Group:

Group:

Key Word:

KeyWord: TROUBLES HOOTfNG TROUBLESHOOTING Cog Cog Level:

Level: M2.2/3.3 M2.2/3.3 Source:

Source: MM Exam:

Exam: SM05301 SM05301 Test:

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

92. G2 .2.7 001l311EQUIPMENT

92. G2.2.7 001/3//EQUIPMENT CONTROLlM(2.0/3.2)/B/SM05301/S/MC/SDR CONTROL/M(2.0/3 .2)/B/SM0530 1/S/MC/SDR 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 Control,"

Lifted Lead Control, requires requires prior prior PSRC PSRC and and NSRC NSRC review review for which ONE for which ONE ofof 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. AA review B. review indicates indicates that that 10 10 CFR CFR 50 50 Appendix Appendix RR fire fire protection protection criteria criteria are are impacted.

impacted.

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

diminished.

Dy review indicates Dy AA review indicates that that aa full safety evaluation full safety evaluation isis required required per 10 CFR per 10 CFR 50.59.

50.59.

Feedback Feedback DISTRACTORS:

DISTRACTORS:

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

REFERENCES:

1. SAP-148,

1. SAP-i 48, "Temporary Temporary Bypass, Jumper, and Lifted Lead Control." Control. Attachment 1, page 14 of 20.

KIA CATALOGUE QUESTION DESCRIPTION:

K/A CATALOGUE DESCRIPTION:

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

analysis report.

Categories Tier:

Tier: 33 Group:

Key Word:

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

Source:

Source: BB Exam: SM05301 Test:

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

93. G2.3.2

93. G2.3 .2 002/3///M(2.5/2.9 002/3///M(2.5/2.9)/N/SM 0530 1/SIRFA!SDR

/N/SM0530l/S/RFAlSDR Which ONE Which ONE of of the the following following isis correct correct per per HPP-HPP- 709, 709, Sampling Sampling and and Release Release ofof Radioactive Radioactive Gaseous Effluents:

Gaseous Effluents:

A. Discharges Aol Discharges from from the Waste Gas the Waste Gas Decay Decay Tank Tank or or other other high high activity activity gaseous gaseous releases releases should should be avoided when the wind is from the East-Southea be avoided when the wind is from the East-Southeast. st. This will prevent This will prevent the the released released activity activity from being from being drawn drawn into into the Auxiliary Building the Auxiliary Building ventilation.

ventilation.

B.B. Discharges Discharges from from the the Waste 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 thethe wind wind isis from from the the West-Southwest.

West-Southwest. This This 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. Discharges C. Discharges from the the Waste Gas Gas Decay Decay Tank Tank or or other other high high activity activity gaseous gaseous releases releases should should be avoided be avoided when when thethe 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 being drawn drawn intointo the the Control Control Building Building ventilation.

ventilation.

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

West-Southwest. This This will prevent prevent the released the released activity from being drawn into activity into the Control Control Building Building ventilation.

Feedback Distractor Analysis:

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

drawn into drawn into the Auxiliary Building ventilation. Per HPP-709 NOTE 5.1.H B, C, B, C, D Incorrect D Incorrect

Reference:

HPP-HPP- 709, Sampling Sampling and Release of Radioactive Gaseous Effluents, page 10 10 KIA CATALOGU K/A CATALOGUE E QUESTION DESCRIPTIDESCRIPTION: ON:

- Knowledge of of facility ALARA ALARA program.

program.

Categories Tier:

Tier: 33 Group:

Group:

Key Word:

KeyWord: Cog Cog Level:

Level: M(2.5/2.9)

M(2.5/2.9)

Source:

Source: N N Exam:

Exam: SM05301 SM05301 Test:

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

94. G2.4.33

94. G2 .4.33 002/311INOPERABLE 002/3//iNOPERABLEALARMIM2.4/2.8/B/SM05301lSIFJE/SDR ALARM/M2.4/2 8/B/SM0530 I /S/FJE/SDR Which ONE Which ONE of of the the following following individual's individuals approval approval isis required required to to extend extend the the time time that that an an invalid invalid nuisance annunciator isis removed nuisance annunciator removed from from service service past past 96 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br />?

hours?

A. Duty A. Duty Shift Shift Engineeer Engineeer B. Duty Shift

8. Duty Shift Supervisor Supervisor Manager, Operations C Manager, Cy Operations D. General Manager, D. General Manager, Nuclear Nuclear Plant Plant Operations Operations Feedback Feedback DISTRACTORS:

DISTRACTORS:

A A

B B

C Correct per C Correct per OAP-100.5, CAP-i 00.5, Section Section 14.0 14.0 D

D

REFERENCES:

1.

1.

K/A CATALOGUE KIA CATALOGUE QUESTION DESCRIPTION: DESCRIPTION:

Knowledge of the process used to track inoperable alarms.

- Knowledge Categories Categories Tier:

Tier: 33 Group:

Key Word:

KeyWord: INOPERAB INOPERABLE LE ALARM Cog Level: M2.4/2.8 Source:

Source: B Exam: SM05301 Test:

Test: SS Author/Revi AuthorlReviewer:

ewer: FJE/SDR

95. G2.4.38

95. G2.4.38 002/311EMERGENCY 002/3//EMERGENCY PROCEDURESIM(2.2/4.0)IMISM05301lSIMC/SDR PROCEDURESJM(2 .2/4.0)/M/SM0530 1/S/MC/SDR Plant conditions Plant conditions are are as as follows:

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 the from the south.

south.

Which ONE Which ONE of of the following must the following must assume assume thethe duties duties 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. Shift Supervisor; Supervisor; Evacuate Evacuate to to their their personal personal residence.

residence.

BB.% Shift Supervisor;

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

Area.

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

residence.

D. Manager, Operations:

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

Area.

Feedback Feedback DISTRACTORS:

DISTRACTORS:

A INCORRECT A INCORRECT Correct individual; however, if there is a potential for personnel or vheicle contamination, the evacuation would NOT be to peronal residence.

contamination, B CORRECT B CORRECT C INCORRECT C INCORRECT If there is a potential for personnel or vheicle contaminatio contamination, n, the evacuation would NOT be to peronal residence.

D D INCORREC INCORRECT T REFERENC

REFERENCES:

ES:

1.

1. SAP-109, Managemen "Managementt Duty Supervisor.

Supervisor."

2. EPP-012, Onsite Personnel

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

9.

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

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

coordinator.

Categories 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(2.2/4.0)

Source:

Source: MM Exam:

Exam: SM05301 5M05301 Test:

Test: SS Author/Revi AuthorlReviewer:

ewer: MC/SDR MC/SDR

96. W/E02EG2.4.6

96. W/EO2EG2 .4.6 OOl/l/2/SI 001/1/2/SITERMINATION/CIA(3.1/4.0)INISM05301/S/FJE/SDR TERMINATION/C/A(3.1 /4.0)/N/SM0530 I /S/FJE/SDR Plant conditions Plant conditions areare as as follows:

follows:

- AA reactor

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

break.

- ALL

- ALL Main Main Steam Steam Isolation 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 inin progress progress at at Step Step 17, 17, Establish Normal Establish Normal Charging.

Charging.

- PZR

- PZR level level isis 58%.

58%.

- EFW flowrate

- EFW flowrate isis 50 50 gpm gpm to each Steam to each Steam Generator Generator due due to to required required operator operator action.

action.

All Steam Generator Narrow

- All Steam Generator

- Narrow Range Range levels levels areare 4%.

4%.

Reactor Building

- Reactor

- Building pressure pressure has has remained remained belowbelow 11 psig.

psig.

- RCS

- RCS pressure pressure isis 1750 1750 psig and going psig and going UP.

UP.

- Core

- Exit TCs Core Exit TCs areare 435 435 OF °F and going DOWN.

and going DOWN.

The "c" The Main Steam C Main Steam Isolation Isolation Valve Valve closed closed 30 30 seconds seconds ago and "c" ago and C Steam Steam Generator Generator pressure pressure has changed has changed from 80 80 to 130130 psig.

psig.

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

take?

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

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

B. IMMEDIATELY Cv C ..... Complete EOP-3.1 thrQugh through Step 20, verify SI Flow is NOT required, and then transition to 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 D.

Termination, Step 1.

Feedback Feedback DISTRACTORS:

DISTRACTORS:

AA Incorrect.

Incorrect. The The CC SGSG pressure pressure has has increased.

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

20.

Plausible ifif applicant Plausible applicant does does notnot 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 crew should the crew should go go to to EOP-3.0 EOP-3.0 ifif any any SG SG pressure pressure increases increases at any time at any time EXCEPT EXCEPT while while performing performing SI SI Termination Termination inin steps steps 1515 through through 20.20. Plausilbe Plausilbe ifif applicant applicant does does not recognize step not recognize step number number or or step step description description as an as an SI SI Termination Termination stepstep oror does does notnot remember remember an an exception exception to to Secondary Secondary Integrigy Integrigy Transition Critierion.

Transition Critierion.

CC Correct Correct per EOP-3.1, Reference per EOP-3.1, 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 crew crew should transition to to EOP-3.0 EOP-3.0 after completing SI Termination in Steps after completing SI Termination in Steps 15 through 15 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 a transition to EOP-1.2.EOP-1 .2.

REFERENCES:

1. EOP-3.1, Uncontrolled Depressurization

1. Depressurization of All Steam Generators

2. EOP-3.1 EOP3. 1 LP, Uncontrolled Depressurization Depressurization of All Steam Generators Lesson Plan K/A CATALOGUE KIA CATALOGUE QUESTION DESCRIPTION: DESCRIPTION:

- W/E02 SI Termination Knowledge symptom based EOP mitigation strategies (3.1/4.0).

- Knowledge Categories Tier: 1 Group: 22 Key KeyWord:Word: SI TERMINAT TERMINATION ION Cog Level: CIA(3 .114.0)

C/A(3.l/4O)

Source:

Source: N Exam: SM05301 Test:

Test: SS Author/Revi AuthorlReviewer:

ewer: FJE/SDR

97. W/EOSEA2.1

97. W/EO5EA2. 00 001/1/1/HEA 1111 1IHEATT SINK/CIA SNKJC/A (3.4/4.4)/B/SMOS30IlS/GWLIRFAlSDR (3 .4/4.4)/B/SM0530 1/S/GWL/RFAJSDR The Crew The Crew has entered EOP-16.0 has entered EOP-16.0 "Response Response to Pressurized Thermal to Pressurized Thermal Shock" Shock duedue to to an an Orange Orange pathpath on the integrity on the integrity CSF CSF status status tree.

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

Increasing.

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

CSF status tree.

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

crew?

A. Remain A. Remain in in EOP-16.0 EOP-16.O untiluntil itit isis completed, completed, then then transition transition toto EOP-1S.0, EOP-15.0, Response Response to to Loss Loss of of Secondary Heat Secondary Heat Sink.

Sink.

B. Remain in B. Remain EOP-16.0 until in EOP-16.0 until the OrangeOrange path path is is cleared, cleared, then then tranistion tranistion to to EOP-1S.0.

EOP-15.O.

CY' IMMEDIATELY transition C IMMEDIATELY transition to EOP-15.0.

to EOP-1S.0.

D. The transition to EOP-1S.0 D. EOP-15.0 is is NOT NOT required required since EOP EOP 16.0 provides actions for adjusting 16.0 provides E FW.

EFW.

Feedback DISTRACTORS:

DISTRACTORS:

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

immediately.

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

tranistion immediately.

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

immediately.

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

immediately. EOP-1S.0 EOP-15.0 has a caution that states:

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

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

REFERENC

REFERENCES:

ES:

1.

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

12.0. Summer Summer Exam Exam bank bank question question EOPS EOPS 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 I1oror monitor monitor the the folowing folowing as as they they apply apply toto the the (Loss (Loss ofof Secondary Secondary Heat Heat Sink)

Sink) Facility Facility conditions conditions and and 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: SM0530 SM05301 1 Test:

Test: SS Author/Reviewer:

AuthorlReviewer: GWLlRF GWL/RFAJSAlSDRDR

98. W/E09EA2.2

98. W/EO9EA2.2 OOll112!NATURAL 001 / 1 /2/NATURALCIRCIC/A(3.4/3.8)IMISM05301lS/GWLlSDR CIRC/C/A(3 .4/3. 8)/M/SM0530 1/S/GWL/SDR AA Reactor Reactor TripTrip with with aa loss loss of Off-site power of Off-site power hashas occurred.

occurred. Power Power willwill not not be be restored restored for for atat least eight hours, and least eight hours, and aa cooldown cooldown isis desired.

desired.

RCS temperature

- RCS

- temperature isis currently currently 557 557 of°F Only one

- Only

- CRDM fan one CRDM fan isis operable.

operable.

Which ONE Which ONE of the following of the following correctly correctly describes describes the actions to the actions to be be taken taken inin accordance accordance with with 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 RCS RCS subcooing subcooing greater greater than than 80 80 of,

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

°F/hr.

B. Maintain B.",; Maintain RCS RCS pressure pressure aboveabove 1925 1925 psig, psig, maintain maintain RCSRCS subcooling subcooling greater greater than than 130 130°F of and cooldown cooldown shall not not exceed 50 of/hr.F/hr.

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

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

Feedback DISTRACTORS:

DISTRACTORS:

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

BB Correct, RCS pressure should be maintained above 1925, 1925, subcooling must be greater than 130°F, 0

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

F/hr.

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

of/hr.

DD Incorrect, Incorrect, the cooldown is is limited limited to 50 0 to 50 F /hr.

of/hr.

REFERENC

REFERENCES:

ES:

1.

1. EOP-1 EOP-1.3 .3 Natrual Natrual Circulation Circulation Cooldown.

Cooldown.

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

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

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

(3.4/3.8)

Categories Categories Tier:

Tier: 1 Group:

Group: 22 Key Word:

KeyWord: NATURAL NATURAL CIRC CIRC Cog Cog Level:

Level: C/A(3.4/3.8)

C/A(3.4/3.8)

Source:

Source: M M Exam:

Exam: SM05301 SM05301 Test:

Test: SS Author/Revie AuthorlReviewer:

wer: GWLlSDR GWL/SDR

99. W/E12EG2.4.4

99. W/E 1 2EG2.4.4 0021111/STEAM 002/1/1/STEAM LINE LINE RUPTURE/C/A(4.014.3 RUPTURE/C/A(4.0/4.3)/N /SM0530 1/S/FJE/SDR

/N/SM05301lSIFJE/SDR Plant conditions Plant conditions are are as follows:

as follows:

The Unit

- The

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

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

Generator (SG).

The crew

- The

- crew isis currently currently performing 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 asas listed listed below:

below:

Loop AA Loop Loop 8B Loop Loop Loop C 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 557 °F 556 556 of°F 557 557 of°F RCS Pressure: 1350 psig NOTE: ALL plant parameters were stable, with the exception of 8B SG NR Level, which was going UP.

CURRENT plant parameters are as follows:

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

SGPORV SG PORV SHUT SHUT SHUT RCS Temperature 520 °Fof 550 °Fof 550 °Fof RCS Pressure: 1000 1000 psig ALL above parameters are are all all decreasing (going (going DOWN),

DOWN), withwith Loop Loop A parameters decreasing faster than Loops Loops B8 and and C.

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

Procedures?

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

Coolant.

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

Isolation.

C. RETURN C. RETURN to to EOP-4.0, EOP-4.0, Steam Steam Generator Generator Tube Tube Rupture, Rupture, Step Step 1.1.

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

Isolation.

Feedback Feedback DISTRACTORS:

DISTRACTORS:

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 indicated by decreasing decreasing RCS RCS pressure pressure and and Loop Loop BB SG SG pressure ONLY, NOT a large pressure ONLY, NOT a large decrease inin Loop decrease Loop AA SG SG pressure, pressure, level, level, and and RCSRCS temperature.

temperature.

BB Correct Correct per EOP-4.0, Reference per EOP-4.0, Reference Page, Page, Secondary Secondary Integrity Integrity Transition Transition Criteria Criteria C Incorrect. Plausible C Incorrect. Plausible because because this this isis item item 44 (Multiple (Multiple Tube Tube Rupture Rupture Criteria)

Criteria) on on the the EOP-4.O reference EOP-4.0 reference page.

page.

DD Incorrect.

Incorrect. EOPEOP rules rules of usage require of usage require immediate immediate transition transition after after performing performing applicable applicable immediate actions. EOP-4.0 immediate actions. 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 thethe ruptured ruptured SGSG is is aa higher higher priority priority than than isolating the isolating faulted SG.

the faulted SG.

REFERENCES:

1. EOP-4.0,

1. EOP-4.0, Steam Generator Generator Tube Tube Rupture, Rupture, Reference Page, Page, item item 2, Secondary Integrity Integrity Transition Criteria.

Emergency Operating Procedures.

2. EO-2, Usage of Emergency Procedures.

KIA CATALOGUE QUESTION DESCRIPTION:

K/A CATALOGUE 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).

entry-level Categories Categories Tier: 1 Group: 11 Key Word:

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

C/A(4.O/4.3)

Source:

Source: N Exam: SM0530 1 SM05301 Test:

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

1 00.W/E13EG2.2.25 100. W/E1 3EG2.2.2500ll1l2/S/G 00 1/1/2/S/GOVERPRESSUREIM2.5/3.7/N/SM05301lSIFJE/SDR OVERPRESSURE/M2.5/3.7/N/SM0530 1/SIFJE/SDR Which ONE Which ONEofofthe thefollowing following describes describesthe thebasis basisforforreducing reducingthe thePower PowerRange Range Neutron Neutron FluxFlux High Trip Setpoint, in accordance High Trip Setpoint, in accordance with with Summer SummerTechnical Technical Specification SpecificationTableTable3.7-1, 3.7-1, ififone oneor or more main more main steam steam lineline code codesafety safetyvalves valves are are inoperable inoperablefor formore morethanthan 44 hours5.092593e-4 days <br />0.0122 hours <br />7.275132e-5 weeks <br />1.6742e-5 months <br />?

hours?

A.v To A.II To ensure ensure that thatsufficient sufficient relieving relieving capacity capacityisis available availabletoto limit limit secondary secondarysystem system pressure pressure to within 110% of design to within 110% of design pressure. pressure.

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

valve(s).

C.C. To To limit limit the pressure rise the pressure rise within within the the reactor reactor building building to to within within thethe values values assumed assumed inin thethe accident analysis in the event of a steam line accident analysis in the event of a steam line rupture within rupture within the the reactor reactor building.

building.

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

limits.

Feedback Feedback DISTRACTORS:

DISTRACTORS:

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

BB Incorrect.

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

FWIVs.

C Incorrect.

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

and FWIVs.

D Incorrect.

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

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

NOP/NOT.

REFERENC

REFERENCES:

ES:

1. SummerTech

1. Summer Technical nical Specification Bases Bases 3/4.7.1.1, 3/4.7.1.1, 3/4.7.1.5, 3/4.7.1.5, 3/4.7.1.6, 3/4.7.1.6, 3/4.7.2 3/4.7.2 KJA CATALOGU K/A CATALOGUE E QUESTION QUESTION DESCRIPTI DESCRIPTION: ON:

- W/E 13

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

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

and safety limits (2.5/3.7).

Categories Categories Tier:

Tier: 1 Group:

Group: 22 Key Word:

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

Level: M2.5/3.7 M2.5/3.7 Source:

Source: NN Exam:

Exam: SM05301 SM05301 Test:

Test: SS Author/Revi AuthorlReviewer:

ewer: FJE/SDR FJE/SDR

Final Submittal (Btue Paper)

(Slue FINAL SRO WRITTEN EXAMINATION 2/9/06

VC Summer Nuclear Plant 2005-301 SRO Inital Exam

76. 002A2.04 001 A large LOCA has occurred. Which ONE of the following actions are corrrect given the following conditions:

• RWST level is 17% and continues to decrease.

• RHR sump level is 410 feet and increasing.

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

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

• EOP-2.2, TRANSFER TO COLD LEG RECIRCULATION

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

A. EOP-2.4 from EOP-2.0. When RHR sump level reaches the required level, transition 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.

D9 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.

Summer Nuclear VC Summer Nuclear Plant Plant 2005-301 SRO SRO Inital Inital Exam Exam

77. 003A2.03

77. 003A2.03 002002 The following conditions The conditions exist:

exist:

- Reactor Power is 9%.

- A Total Loss of All Service Water has occurred.

Total Loss of Service Water,"

- AOP-117.1, "Total

- Water, has been entered.

- RCP temperatures are beginning to rise.

- Service Water can not be restored.

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

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

A.>I -

DESCEND ING). Stop up to TWO RCPs. Isolate unnecessary CCW DESCENDING). COW loads, and ensure FS D/Gs. When an RCP motor bearing temperatures or lower seal water is aligned to the DIGs.

bearing temperature exceeds the specified limit, stop the affected RCP.

B. Initiate a reactor plant shutdown per GOP-4B, POWER OPERATION (MODE 1 1 -

DESCENDING). Isolate unnecessary CCW COW loads, and ensure FS is aligned to the DIGs.

Secure an RCP only if motor bearing temperatures or lower seal water bearing temperature exceeds the specified limit.

C. Initiate a reactor plant shutdown per GOP-4B, POWER OPERATION (MODE 1 1 -

DESCENDING). Stop at least TWO RCPs. Isolate unnecessary CCW COW loads, and ensure D/Gs. When the running RCP FS is aligned to the DIGs. ROP motor bearing temperatures or lower seal water bearing temperature exceeds the specified limit, increase monitoring and continue pump operation until the unit is shutdown then stop the affected pump.

D. Stop ONE RCP. Initiate a a reactor plant shutdown per GOP-4B, POWER OPERATION (MODE 1 1 - DESCENDING). When an RCP motor bearing temperatures or lower seal water bearing temperature exceeds the specified limit, trip the reactor and stop the affected!

affected RCP.

VC Summer VC Summer Nuclear Nuclear Plant Plant 2005-301 SRO Inital 2005-301 SRO Inital Exam Exam

78. 005G2.1.27 005G2.1.27 001 001 Which ONE Which ONE of of the the following correctly correctly describes describes the the purpose purpose and and or or function (not (not all all inclusive) inclusive) of the RHR system and one of its Mode 4 Technical Specification requirements?

A. Hot Leg Recirculation, Refueling Cavity Cooling, Alternate Water supply to Reactor Building' Building Coolers, Pressurizer Relief Tank Cooling. RHR can 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 /> provided that core outlet temperature is maintained at least 50°F below saturation temperature.

B. Cold Leg Recirculation, Hot Leg Recirculation, Simultaneous Cold Leg - Hot Leg Recirculation, Alternate Water supply to Reactor Building Coolers. RHR can be deenergized for up to 11 hour provided that core outlet temperature is maintained at least 10°F below saturation temperature.

100F C. Refueling Cavity Draining, Cold Overpressure Protection, Simultaneous Cold Leg - Hot Leg -

Recirculation, Pressurizer Relief Tank Cooling. RHR can 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 /> 50°F below saturation provided that core outlet temperature is maintained at least 500F temperature.

D D~ Cold Leg Recirculation, Refueling Cavity Draining, Cold Overpressure Protection, Cold Leg Injection. RHR can be deenergized for up to 1 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> provided that core outlet temperature 10°F below saturation temperature.

is maintained at least 100F

Summer Nuclear VC Summer Nuclear Plant Plant 2005-301 SRO Inital 2005-301 SRO Inital Exam Exam

79. 007A2.03

79. 007A2.03 002 002 Plant conditions are Plant are as as follows:

- The unit is in Cold Shutdown.

- The RCS is water solid with one train of RHR providing shutdown cooling:

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

- ALL pressurizer PORV control switches are in AUTO.

- RCS temperature is 140 of.

- °F.

- PRT level is 78%.

- PRT pressure is 6 psig.

- PRT temperature is 95 of

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

A. A HIGH failure of PT-444, pressurizer pressure control channel transmitter.

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

B.

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

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

c.

C. A HIGH failure of PT-444, pressurizer pressure control channel transmitter.

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

HCV-i42, LTDN FROM RHR.

D. Loss of air to HCV-142, Spraying down the PRT using reactor makeup water per SOP-1 SOP-i 01, Reactor Coolant System.

VC Summer Summer Nuclear PlantPlant Inital Exam 2005-301 SRO Inital Exam

80. 007EA2.01 002

80. 007EA2.01 At 50% power, the plant experienced a loss of BOTH runningrunning Main Main Feedwater Pumps Pumps with aa concurrent failure of the Reactor trip breaker A to open. The crew is performing the immediate FOP-i .0, "Reactor actions of EOP-1.0, Reactor Trip/Safety Injection Actuation."

Actuation.

Current plant conditions are as follows:

- The Integrated Plant Computer System has failed.

- SG LO-LO Level annunciators are lit.

- Reactor Power is 7% and slowly decreasing.

FFW Pumps failed to start.

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

A. FOP-i .0, until directed to monitor Critical Safety Functions then transition to Remain in EOP-1.0, EOP-15.0, Response To Loss of Secondary Heat Sink."

FOP-i 5.0, "Response Sink.

FOP-i5.0, "Response B. Directly enter EOP-15.0, Response To Loss of Secondary Heat Sink."

Sink.

FOP-i .0, until directed to monitor Critical Safety Functions then transition to C. Remain in EOP-1.0, EOP-13.0, Response To Abnormal Nuclear Power Generation."

FOP-i 3.0, "Response Generation.

D Transition from EOP-1.0 Dy FOP-i 3.0, "Response FOP-i .0 to EOP-13.0, Response To Abnormal Nuclear Power Generation."

Generation.

VC Summer VC Summer Nuclear Nuclear Plant Plant 2005-301 SRO 2005-301 SRO Inital Inital Exam Exam

81. 008A2.04 81.

c--------'--c--c--

008A2.04 002 002 The Unit Unit is is operating operating at at 100%

100% power power with all all systems in in normal normal lineups lineups when the following annunciators actuate:

- LLTDN/SL

- TDN/SL WTR HX FLO LO [0 TEMP HI

- CC LOOP A RM-L2A HI RAD

- CC SRG TK VENT 7096 CLSD HI RAD

- CCW SRG TK LVL HI/LO/LO-LO NO other annunciators are lit and all associated automatic functions have occurred.

Which ONE of the following is the correct cause and action?

A. A leak exists in the Letdown HX; verify closure of PVT-8152, LLTDN TON LINE ISOL, per SOP-i 02, CHEMICAL AND VOLUME CONTROL SYSTEM, and manually shut PVV-7096, SOP-102, CCSURGETKVLV CC SURGE TK VLV BB.

..... A leak exists in the Letdown HX; manually close PVT-8152, PVT-8i52, LLTDN TON LINE ISOL, per SOP-i 02, CHEMICAL AND VOLUME CONTROL SYSTEM, and verify closure of SOP-102, PVV-7096, CC SURGE TK VLV C. RCP "A" A thermal barrier has been breached. Conduct a normal shutdown per GOP-4B, POWER OPERATION (MODE 1 1 - 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-lOi, SOP-1 01, REACTOR COOLANT SYSTEM.

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

VC Summer VC Summer Nuclear Nuclear Plant Plant 2005-301 SRO 2005-301 SRO Inital InitaJ Exam Exam

82. 009EG2.4.30

82. 009EG2.4.30 002002 Which ONE ONE of the following identifies identifies an event that is is required required to be be reported reported toto the NRC NRC within 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> per EPP-002, COMMUNICATION AND NOTIFICATION.

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

B.%

B ..... An ECCS discharge to the RCS in response to a small break LOCA.

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

D. A liquid release of of>> 2X Appendix B limits.

VC Summer Nuclear Plant 2005-301 SRO Inital Exam

83. 022AG2.4.49 001 The plant was operating at 80% power when the following annunciators (not all inclusive) came in:

- REGEN HX L LTDN TDN OUT TEMP HI

- VCT LVL HI/LO

- CHG LINE FLO HIILO Hl!LO

- LOS DEV HI/LO PZR LCS Hl!LO Charging pump amps are fluctuating between 25 and 30 amps Charging flow is fluctuating between 25 and 30 gpm pressure is oscillating between 2500 and 2600 psig Charging pre,ssure Which ONE of the following set of actions should the supervisor direct his board operators to perform (These actions are not all inclusive)?

A.

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

B. Verify at least one charging pump is operating, verify FCV-122 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-115B(D),

LCV-1 1 5B(D), RWST TO CHG PP SUCT.

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),

VC Summer VC Summer Nuclear Nuclear Plant Plant 2005-301 2005-301 SRO SRO Inital Inital Exam Exam

84. 032AA2.08

84. 032AA2.08 003003 Refueling operations Refueling are in operations are in progress, progress, with SR SR monitor monitor N33 N33 out out of of service, service, when power power is is suddenly lost to source range neutron flux monitor N31 and subsequently regained 30 minutes j later.

Which ONE of the following describes the action to be taken for this situation when power is lost?

A. Suspend all core alterations and perform an analog channel operational test of source A>o/

range neutron flux monitor N31 within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to the initial start of core alterations.

B. Suspend all core alterations and perform a neutron flux response time test AND operational test of source range neutron flux detector N31 within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to the initial start of core alterations.

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

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

VC Summer Nuclear Plant 2005-301 SRO Inital Exam

85. 035G2.4.20 002 The crew has just entered EOP-15.0, "Response Response to Loss of Secondary Heat Sink" Sink from EOP-12.0, Monitoring of Critical Safety Functions.

The following conditions exist:

- WR SG "A"

- A level is 25%

- WR SG "8"

- B level is 12%

- WR SG "c"

- C level is 11%

- Total Feed Flow is 290 gpm Which ONE of the following sets of actions (not all inclusive) should be taken as directed by EOP-1 5.0, "Response EOP-15.0, Response to Loss of Secondary Heat Sink"?

Sink?

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

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

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

D..... Trip ALL RCPs, actuate SI, establish an RCS bleed path:

D

VC Summer Summer Nuclear Nuclear Plant Plant 2005-301 2005-301 SRO SRO Inital Inital Exam Exam

86. 054AA2.03 002 following conditions The following conditions exist:

- A plant startup was in progress.

- Power level was at 38%

- The reactor tripped

- SG blowdown isolation valves (PVG-503A(B)(C), A(B)(C) ISOL)

- SQL) closed A, "B",

- Current SG narrow range levels in "A",

- B, and "C" C SGs are 8%, 10%, and 10%, respectively, and decreasing Which ONE of the following correctly states the initiating event that caused the trip and the expected automatic actions based on these conditions?

A. The operating MFP tripped and ONLY the motor driven EFW pumps have a current start signal.

B.v B ..... The operating MFP tripped and BOTH the turbine driven AND motor driven EFW pumps have a current start signal.

C. All SG flow control valves drifted closed and AMSAC should have actuated.

D. All SG flow control valves drifted closed and ONLY the turbine driven EFW pump has a a current start signal.

VC Summer Nuclear Plant 2005-301 SRO Inital Inital Exam

87. 068G2.1.20 002002 A Liquid Radwaste Release is been in progress:

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

RCV00018-WL, Liquid Radioactive Waste Control Valve, indicates shut.

- Within 30 seconds of the alarm, alarm RM-L5's

, RM-L5s reading returns to below the setpoint.

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

A.

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

RM-L5s reading is below the setpoint, then open RCV00018-WL B. Verify that the RM-L5's RCV000i8-WL and SOP-i 08.

resume the release per SOP-1

c. RM-L5s reading is below the setpoint, then open RCV00018-WL and C. Verify that the RM-L5's SOP-i08.

resume the release per SOP-1 08. Direct Heath Physics to continue to monitor the release and reduce the release rate.

D. Notify Health Physics and request a radiological survey. The release can not be reinitiated under the current release permit.

VC Summer Nuclear Plant 2005-301 SRO Inital Exam

88. 103G2.1.30 002 Plant conditions are as follows:

- The unit is currently in MODE 4, with temperature and pressure increasing.

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

- An auxiliary operator has just called to report that the red indicating light above the Personnel Escape Airlock is LIT and that he was unable to operate the Fuel Handling Building door using the handwheel.

Which ONE of the following is correct regarding the status of the Personnel Escape Airlock AND Containment Integrity?

A.oI be avoided when the wind is from the East-Southeast. This will prevent the released activity from being drawn into the Auxiliary Building ventilation.

B. Discharges from the Waste Gas Decay Tank or other high activity gaseous releases should: should be avoided when the wind is from the West-Southwest. This will prevent the released activity from being drawn into the Auxiliary Building ventilation.

C. Discharges from the Waste Gas Decay Tank or other high activity gaseous releases should be avoided when the wind is from the East-Southeast. This will prevent the released activity from being drawn into the Control Building ventilation.

D. Discharges from the Waste Gas Decay Tank or other high activity gaseous releases should be avoided when the wind is from the West-Southwest. This will prevent the released activity from being drawn into the Control Building ventilation.

VC Summer Summer Nuclear Nuclear Plant Plant 2005-301 SROSRO Inital Inital Exam Exam

94. G2.4.33

94. G2.4 33 002 002 ONE of Which ONE of the following individual's individuals approval is is required required to extend the the time that an an invalid invalid nuisance annunciator is removed from service past 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br />?

A. Duty Shift Engineeer B. Duty Shift Supervisor C Manager, Operations Cy D. General Manager, Nuclear Plant Operations

VC Summer Nuclear Plant 2005-301 SRO Inital Exam

95. G2.4.38 002 Plant conditions are as follows:

• An event has occurred resulting in substantial core degradation with potential loss of containment integrity.

• A General Emergency has been declared.

• The prevailing wind is blowing from the south.

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

A. Shift Supervisor; Evacuate to their personal residence.

B.%

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

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

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

VC Summer Nuclear Nuclear Plant Plant 2005-301 SRO Inital Exam

96. W/E02EG2.4.6 W/EO2EG2.4.6 001 001 Plant conditions are as follows:

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

- ALL Main Steam Isolation Valves initially failed to close.

- EOP-3. 1, Uncontrolled Depressurization of All Steam Generators, is in progress at Step 17,

- EOP-3.1, 1 7, Establish Normal Charging.

- PZR level is 58%.

- EFW flowrate is 50 gpm to each Steam Generator due to required operator action.

- All Steam Generator Narrow Range levels are 4%.

- Reactor Building pressure has remained below 11 psig.

- RCS pressure is 1750 psig and going UP.

- Core Exit TCs are 435 of

- °F and going DOWN.

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

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

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

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

C..... Complete EOP-3.1 through Step 20, verify SI Flow is NOT required, and then transition to C

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.

VC Summer Summer Nuclear Nuclear Plant Plant 2005-301 SRO 2005-301 SRO Inital Inital Exam Exam

97. W/EOSEA2.1 W/EO5EA2.1 001 001 The Crew The Crew has has entered EOP-16.0 "Response entered EOP-16.0 Response to Pressurized Pressurized Thermal Thermal Shock" Shock duedue to to an an Orange path on the integrity CSF status tree. The Crew is at the step for Checking RCS Tcold I Stable or Increasing.

While checking EFW flow it is determined that a Red path condition exists on the Heat Sink CSF status tree.

Which ONE of the following correctly describes the action that should be taken by the crew?

A. Remain in EOP-16.0 until it is completed, then transition to EOP-15.0, Response to Loss of I Secondary Heat Sink.

B. Remain in EOP-16.0 until the Orange path is cleared, then tranistion to EOP-15.0.

EOP-1 5.0.

C9 IMMEDIATELY transition to EOP-15.0.

C.""

D. The transition to EOP-15.0 EOP-1 5.0 is NOT required since EOP 16.0 provides actions for adjusting EFW.

VC Summer Nuclear Plant 2005-301 SRO Inital lnital Exam

98. W/E09EA2.2 W/EO9EA2.2 001 A Reactor Trip with a loss of Off-site power has occurred. Power will not be restored for at least eight hours, and a cooldown is desired.

- RCS temperature is currently 557 of

- °F

- Only one CRDM fan is operable.

Which ONE of the following correctly describes the actions to be taken in accordance with FOP-i .3 "Natural EOP-1.3 Natural Circulation Cooldown"?

Cooldown?

A. Reduce RCS pressure to below 1925 psig, maintain RCS subcooing greater than 80 of, 80°F, F/hr.

0 cooldown shall not exceed 50 of/hr.

By B ..... Maintain RCS pressure above 1925 psig, maintain RCS subcooling greater than 130 130°Fof F/hr.

0 and cooldown shall not exceed 50 of/hr.

C. Reduce RCS pressure to below 1925 psig, maintain RCS subcooing greater than 130 °F, of, F!hr.

0 cooldown shall not exceed 25 of/hr.

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

°F/hr.

VC Summer Summer Nuclear Nuclear Plant Plant 2005-301 SROSRO Inital Inital Exam Exam

99. W/E12EG2.4.4 W/E12EG2.4.4 002 002 Plant conditions Plant conditions are as as follows:

- The Unit experienced a Steam Generator Tube Rupture (SGTR) on the "8" B Steam Generator (SG).

- The crew is currently performing EOP-4.0, Steam Generator Tube Rupture, Step 3, Isolate flow from each RUPTURED SG.

When the crew transitioned from EOP-1.0 EOP-1 .0 to EOP-4.0, FOUR (4) minutes ago, plant parameters were as listed below:

Loop A Loop 8B Loop C SG Pressure 800 psig 1200 psig 800 psig SG NR Level 40% 80% 45%

SGPORV SG PORV SHUT OPEN SHUT RCS Temperature 557 of

°F 556 of

°F 557 of

°F RCS Pressure: 1350 psig NOTE: ALL plant parameters were stable, with the exception of 8 B SG NR Level, which was going UP.

CURRENT plant parameters are as follows:

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

SGPORV SG PORV SHUT SHUT SHUT RCS Temperature 520 of

°F 550 of

°F 550 of

°F RCS Pressure: 10001000 psig ALL above parameters are all decreasing (going DOWN), with Loop A parameters decreasing faster than Loops B8 and C.

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

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

B.v B. . . IMMEDIATELY go go to EOP-3.O, EOP-3.0, Faulted Steam Steam Generator Isolation.

Isolation.

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

1.

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

Isolation.

VC SummerSummer NuclearNuclear Plant Plant 2005-301 SRO SRO Inital Inital Exam Exam 100. W/E13EG2.2.2S 100.

W/E13EG2.2.25 001 001 Which ONE ONE of of the following following describes describes the basis basis for reducing reducing the Power Power Range Range Neutron Neutron Flux Flux High Trip Setpoint, in accordance with Summer Technical Specification Table 3.7-1, if one or more main steam line code safety valves are inoperable for more than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />?

A. To ensure that sufficient relieving capacity is available to limit secondary system pressure A.>oI to within 110% of design pressure.

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

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

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

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