ML071930548

V. C. Summer June 2007 Exam Nos. 05000395/2007301 Final RO As-Given Written Exam

ML071930548
Person / Time
Site:	Summer
Issue date:	06/13/2007
From:	South Carolina Electric & Gas Co
To:	Office of Nuclear Reactor Regulation
References
2007-301, 50-395/07-301 50-395/07-301
Download: ML071930548 (78)

See also: IR 05000395/2007301

Text

Final Submittal(BluePaper)ZW7-3t)I'3 u,"" e l3, zoo7 As c;i lIcJ Reactor Operator Written ExaminationV.C.SUMMER JUNE2007EXAMEXAMNO.05000395/2007301

JUNE4-8,2007(OP

TEST)JUNE13,2007 (WRITTEN EXAM)

u.s.Nuclear Regulatory

Commission

Site-Specific

RO Written Examination

Applicant Information

Name: Date: Facility/Unit:

'-'" r3 tlW7\/.C.50 (Y1lrncr.)u()e Region: II Reactor Type: W Start Time: Finish Time: Instructions

Use the answer sheets provided to document your answers.Staple this cover sheet on top ofthe answer sheets.To pass the examination, you must achieve a final grade of at least 80.00 percent.Examination

papers will be collected 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after the examination

begins.Applicant Certification

All work done on this examinationismy own.I have neither given nor received aid.Applicant's

Signature Results Examination

Value Points Applicant's

Score Points Applicant's

Grade Percent

Name:---------------

1.Giventhefollowing

• Theunit isat85%poweratMOL.*A continuous

uncontrolledcontrolrod

withdrawal

occurs.WhichONE(1)ofthe

followingparameterswill

DECREASE?A.Steam Generator Pressure B.Main Generator Electrical

OutputC.OverpowerDeltaT

setpoint D.VCTLevel2007NRCExamRO

1

2007NRCExamRO2.Giventhefollowingplantconditions:*ALOCAhasoccurred.*RCS pressureis1750psigandlowering

.*Reactor Building pressureis4psigandrising.*Steam Generator pressuresare1000psigandstable

.WhichONE(1)ofthefollowing

describestheactuationsthatarearesultofthis

condition?

A.SafetyInjectionONLY.B.SafetyInjectionand

Containment

VentilationIsolationONLY.C.SafetyInjectionand

ContainmentIsolationPhaseAand

Containment

VentilationIsolationONLY.D.SafetyInjectionand

ContainmentIsolationPhaseAand

Containment

Ventilation

Isolat ion and ContainmentIsolationPhaseB

.2

2007NRCExamRO3.Giventhe

following plant conditions

• Thecrewis

respondingtoanATWS lAW EOP-13.0, Response to Abnormal Nuclear Power Generation

,andis attempting

an emergencyborationoftheRCS.*MVT-8104,EMERG

BORATE ,valvewillnotopen.WhichONE(1)ofthe

following describestherequiredactionstobe

performed and why?A.Openthe ChargingPumpSuction

HeaderIsolationvalvesas

directed by AOP-106.1, Emergency Boration , to maximizeBoricAcid flowrate.B.Open LCV-115B/D, RWSTtoCHGPPSuet,asdirectedby

AOP-106.1 , Emergency Boration , to borateviacoldleginjection

.C.Openthe ChargingPumpSuction

HeaderIsolationvalvesas

directedbyEOP-13.0,Responseto

Abnormal Nuclear Power Generation

, to maximizeBoricAcidflowrate.D.Open LCV-115B/D

, RWSTtoCHGPPSuet,asdirectedby

EOP-13.0,Responseto

Abnormal Nuclear Power Generation,toborateviacoldleg

inject ion.3

2007 NRC Exam RO 4.WhichONE(1)of the following describes the setpoints forthetwo(2)annunciators

below?A.B.C.D.RCP AlBIC THERM BAR&BRGFLOLO 90 gpm 90 gpm50gpm 50 gpmCCBPDISCHHDRPRESSLO30psig70psig30psig70psig 4

2007NRCExamRO

5.Giventhefollowingplantconditions:*The plantisinMode5.*ThePZRissolid

.*RCS temperatureis190°F.*RCS pressureis315psig.*LetdownPressureControlValvePCV-145isinAUTO.FCV-605A,"A"BYP,and

FCV-605B,"B"BYP ,arein MANUAL.WhichONE(1)ofthefollowing

describesaconditionthatwill

initiallycausePCV-145toCLOSE?A.Loweringtheoutputofthe

controllerforthein-serviceRHRheat

exchanger flowcontrolvalve

.B.Raising CCWflowthroughthe

in-serviceRHRHeatExchanger.C.Loweringthe

setpointofPCV-145.

D.Startingan

additionalRHRPump.5

2007NRCExamRO 6.Giventhe following plant conditions:*The plantisin Mode 6.*"B"Train RHRisin service."A" Train RHRisout of service and expectedtobe returned to service in approximately

2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.*Refuelingisin progress.*Cavitylevelis 23.5 feet above the reactor vessel flange."B"RHRPump trips and cannot be restarted.WhichONE(1)ofthe

following describes the operational

restrict ion(s)associated

with this event?A.Refueling Cavity level mustberaisedto

greater than 24 feet above the reactor vessel flange prior to continuing

refueling activit ies.B.Refueling activities

are permittedforupto1 hour while repairs are initiated to"B"RHRPump.C.All containment

penetrations

w ith a directpathto atmosphere

must immediately

be verified closed.D.Suspend all activities

that could resultina reduction in boron concentrationofthe RCS.6

2007NRCExamRO7.Giventhe

followingplantconditions:*Theplantwasoperatingat100%power.7.2KV TransformerXTF-4waslostduetoafault.

The associated

DIGdidNOTstartasdesigned.

Subsequently,aLOCAcauseda

reactortripand safety injection.RCS pressure is currently350psigandtrendingdown

slowly.WhichONE(1)

ofthefollowing

describestheoperationofRHRPumpsforthis

condition?

A.RHRpumpArunningwithits

miniflowvalveopen B.RHRpumpArunningwithitsmfniflowvalveclosedC.RHRpumpBrunningwithits

miniflowvalveopen D.RHRpumpBrunningwithits

miniflowvalveclosed

7

2007NRCExamRO8.WhichONE(1)ofthe

following directly supplies power to ChargingPump"A"andRHR

Pump"A"?A.B.C.D.ChargingPump"A" 1DA 1DA1 1DA 1DA1*RHRPump"A" 1DA 1DA 1DA1 1DA1 8

2007NRCExamRO

9.Giventhefollowingplant

conditions

• TheplantisoperatinginMode1at100%power

.*Thefollowing

indicationsarereportedbytheRO.*TI-471,PRT

Temperatureistrendingupandisnowat

15SOF.*PI-472,PRT

Pressureistrendingupandisnowat8psig.

Wh ichONE(1)ofthefollowingcomponents,ifleaking,will

causethiscondition?

A.XVR-8708A,RHRPump"A"SuctionReliefValve

.B.XVR-8121 ,RCPSealReturn

Relief Valve.C.XVR-7169,RCDTPumpsSuctionReliefValve.D.XVS-8010

, PZR Safety Valve.9

2007NRCExamRO10.WhichONE(1)ofthefollowing

describes an immediateactionandthebasisfortheactionin accordancewithEOP-1.0, Reactor Trip/Safety

Injection Actuation?

A.InsertcontrolrodsinManual;toinsertnegativereactivitybythemostdirectmanner

possible.B.InsertcontrolrodsinManual;toreduceormaintainRCS

pressuretopreventlifting

the Pressurizersafetyvalves.

C.PlaceEHCPumpsin

PULL-TO-LKNON-A;toprevent

uncontrolledcooldownofthe

RCS.D.PlaceEHCPumpsin

PULL-TO-LKNON-A;tominimize

secondary makeup requirements.

10

2007NRCExamRO11.Giventhefollowingplant

conditions

• Areactortripandsafetyinjectionhaveoccurred.

RCS pressureis1050psigandlowering.*Tavgis550°Fandlowering

.*Pressurizerlevelis65%andrisingrapidly.*ReactorBuildingpressureis2psigandrising.WhichONE(1)ofthe

followingdescribesthecauseofthis

event?A.Letdownlinebreak.

B.SBLOCAonanRCScoldleg.

C.Stuckopen pressurizer

PORV.D.Stuckopen pressurizersprayvalve.

11

2007NRCExamRO12.Giventhe

following:*Theplantisat100%power.*All systemsarein theirnormalalignments.*Aleak occursintheLetdownHeatExchanger.Assumingnoactionbythecrew

,whichONE(1)ofthefollowing

describestheeffect(s)ontheCCW System?A.RM-L2A1B indication

rises.SurgeTankventvalve

PW-7096closeswhentheindicationreachesthe

ALERT level.B.RM-L2A1B indica tion rises.SurgeTankventvalve

PW-7096closeswhentheindicationreachestheHIRADlevel.C.SurgeTank

leve/lowers.

CCW Booster Pumpswilltriponlowsuctionpressure

.D.SurgeTanklevellowers

.CCWPumpswilllose

suctionwhentheSurgeTank

empties.1 2

2007NRCExamRO13.Giventhe

following plant conditions:ALOCAoccurredandRCS

pressurereached1380psig.*AllactionsofEOP-1

.0 were performedasrequired.Thecrewis performing

EOP-2.1 ,Post-LOCACoo/down

and Depressurization.

RCS pressure is currently1335psig.*RCS temperature

is currently 496°F.TwoCharging

pumpsarerunning

.Thecrewis evaluating

stopping1ChargingPump

.Giventheabove

conditions, whichONE(1)ofthefollowing

describes whether theChargingPumpmaybe

stopped ,andwhy?A.No, because subcoolingisnot greaterthan30°F.B.Yes , because subcooling

is greaterthan30°F.C.Yes , because subcooling

is greaterthan87.5°F.D.No, because subcoolingisnot greaterthan87.5°F.13

2007NRCExamRO14.Giventhefollowing

plant conditions

• ThePlantisinMode3.*APZR PORVbeginsleakingtothePRT.

• Pressurizer

pressureis985psig.

PRT pressure is steadyat5psig.*PRT temperature

is steadyat90°F.Assume:*Ambientheatlossesarenegligible.*Steamq ualityinthe pressurizeris100%.WhichONE(1)ofthe

followingwouldbethe

approximateMCBindicationonTI-463,RELIEFTEMP

OF?C.300°F 14

2007NRGExamRO15.Giventhe

following plant conditions:*The Reactor has trippedfrom100%power.*"A"and"G" Service Water (SW)pumps were running.*The crew implemented

EOP-1.0, Reactor Trip/Safety

Injection Actuation, then transitioned

to EOP-1.1, Reactor Trip Recovery.*MDEFW pumps started on Lo-LoSGlevelsafterthetrip

.*Subsequently,anSI actuatedduetoaLargeBreakLOGA.WhichONE(1)ofthe

following describes the operation of equipmentasaresultofthe

SI?A.MDEFW pumpswilltripandbe

restartedbythe sequencer.

Service Water Pumps"A"and"G"will

continuetorun.B.MDEFW pumps will continuetorun.Service Water Pumps"A"and"G"willtripand

be restartedbythe sequencer.

G.MDEFW pumpswilltripandberestartedbythe

sequencer.

Service Water Pumps"A" and"G"willtripandbe

restartedbythe sequencer.D.MDEFW pumps will continuetorun.Service Water Pumps"A"and"G"willcontinuetorun.15

2007NRCExamRO16.Giventhefollowingplant

conditions:*Aloadrejectionhas

occurredfrom100%power.*Allcontrol

systems respondedasdesigned.Powerlevelisnow

stableat70%.WhichONE(1)ofthe

following condit ionswillexistduringthisevent?

A.Charg ingFlowControl

Valve , FCV-122 ,willbethrottlingopen.B.Pressurizer

Backup Heaterswillbeenergized.

C.PressurizerPORVswillbeopen

.D.Letdown Backpressure

ControlValvePCV-145willbe

throttling

closed.16

2007NRCExamRO17.Giventhe

following plant conditions

• A reactortriphas occurredfrom100%power.*Reactor Trip Breaker"B"remains

CLOSED.WhichONE(1)ofthe

following describes the effectontheSteamDumpSystem?A.Thesteam

dump valveswillopenand

maintainTavgat 55JOF.B.Thesteam

dumpswillremainclosed

following the reactortripduetolossofthearmingsignal.C.Thesteam

dumpswillremainclosedfollowingthe

reactortripduetolossofthe'planttrip'

modulation

signal.D.Thesteam dump valveswillopenand

maintainTavgat559°F.

17

2007NRCExamRO 18.Which ONE (1)of the following describes the source of control power to Reactor Trip Breaker"B"and Reactor Trip Bypass Breaker"B"?A.B.C.D.Reactor Trip Breaker B 125 VDCBus1HB 125 VDCBus1HB 120 VAC APN-5902 120 VAC APN-5902 Reactor Trip Bypass Breaker B 125 VDCBus1HB 125 VDC Bus 1HA 120 VAC APN-5902 120 VAC APN-5901 18

2007NRGExamRO19.Giventhefollowingplant

conditions

• Areactortriphas

occurredcoincidentwithalossof

off-site power.*While performingactionintheEOPs,thefollowing

events occur:*RGS pressureis1700psigandlowering.*RB pressureis4.7psigandrisingslowly.*Three minutes aftertheseindicationsareobserved, APN-5904failsand becomes de-energized

.WhichONE(1)ofthe

followingdescribestheeffect,ifany,onplant

equipment aftertheAPNfailure?

A.TrainAandTrainBEGGS

equipmentisoperatingasrequired;TrainAandTrainBRBSprayPump

dischargevalvesareopen.B.TrainAandTrainBEGGS

equipmentisoperatingasrequired;TrainAandTrainBRBSprayPump

dischargevalvesareclosed.G.TrainAEGGS

equipmentisoperatingasrequired;TrainBEGGS

equipment isNOTrunning;TrainAandTrainBRBSprayPump

dischargevalvesareopen.D.TrainAEGGS

equipmentisoperatingasrequi

red;TrainBEGGS

equipment isNOTrunning;Tra

inAandTrainBRBSprayPump

dischargevalvesareclosed.

19

2007NRCExamRO20.Giventhe

following plant conditions

• ALOCAhas occurred.*RCS pressureis200psig."A" Reactor Building SprayPumpisOutofService

.Containment

pressure has exceededtheHigh-3setpoint.Train"B"PhaseAhasfailedto

actuate.All other actuationsandTrain"A"ECCS

equipmentisrunningasrequired.

The most recent Chemistry sample oftheRCSind icatedthatRCS activity is 5X10-2 microcuries/ml

Dose Equivalent

Iodine.Assumingnoact

ionbythecrew ,whichONE(1)ofthefollowing

describestheeffectontheplant?A.Containmentwillexceeditsdesignpressure.

B.Off-Sitereleaseswillexceed

accident analysis assumptions

.C.Only1 Containment

Isolation ValveineachPhaseA

penetrationwillbeclosed.

D.Only halfofthe Containment

penetrationsrequiredforisolationwillreceiveisolation

signals.20

2007 NRC Exam RO 21.Given the follow ing plant conditions:*A reactor startupisin progress.*SR Channel N-31 indicates7X10 3 CPS.*SR Channel N-32 indicates 7X10 3 CPS.*IR Channel N-35 indicates 8.7X10-6%power.*IR Channel N-36 indicates 6.0X10-6%power.Which ONE (1)of the following describes(1)the existing plant cond ition ,(2)the statusofP-6 ,and(3)the action required in accordance

with AOP-401.8, Intermediate

Range Channel Failure?A.(1)N-36 i s undercompensated;(2)P-6 should NOT be satisfied;

(3)maintain power stable until N-36 is repaired.B.(1)N-36 is overcompensated

(2)P-6 should be satisfied;

(3)maintain power stable until N-36 is repaired.C.(1)N-36 is undercompensated;(2)P-6 should be satisfied;

(3)place the unit in Mode3until N-36 is repaired.D.(1)N-36is overcompensated;(2)P-6 should NOT be satisfied;(3)placetheun it in Mode 3 until N-36 is repaired.21

2007NRCExamRO22.Giventhe

following plant conditions

The plant is operatingat8%power.ALossof Component Cooling Waterhasoccurred

.*"A"RCP motor bearing temperatureis189°Fandrisingslowly.*"A"RCP lower seal water bear ing temperatureis226°Fandrisingslowly.Thecrewhas

entered AOP-118.1 , Loss of Component Cooling Water.WhichONE(1)

of the following actionsisrequ ired?A.RCP motor bearing temperature

exceeds operating limits.Stop'A'RCPandinitiateaplant shutdown lAW GOP-4B, Power Operation (Mode 1-Descending).

B.RCPlowerseal

water bearing temperature

exceeds operatinglimits.Stop'A'RCP

and initiate a plant shutdown lAW GOP-4B, Powe r Operation (Mode 1-Descending)

.C.RCP motor bearing temperature

exceeds operatinglimits.Tripthereactor,stop'A'RCP,andgotoEOP-1.0, Reactor Trip/Safety

Injection Actuation.D.RCP lower seal water bearing temperature

exceeds operating limits.Tr ip the reactor , stop'A'RCP ,andgotoEOP-1.0, Reactor Trip/Safety

Injection Actuation.

22

2007NRCExamRO

23.Giventhefollowingplant

conditions:*TheplantisinMode3

.*Thefollowing

wide-rangepressuresareindicated:*PT-402*PT-403*PT-455A-1335psig-1350psig-1285psig*Subcoolingindicationon

TI-499AandTI-499Bindicatesthefollowing:

TI-499A TI-499BWhichONE(1)ofthe

following describesthecoreexit

temperatureusedtodetermine

RCS subcoolingforthe indications

above?A.TrainA-550°F;TrainB-

560°F.B.TrainA-55rF;TrainB-550

°F.C.TrainA-55rF;TrainB-560°F.D.TrainA-560°F;TrainB-

55rF.23

2007NRCExamRO24.Giventhe

following plant conditions

• A Reactor Trip condition existedandthe Reactorfailedtotrip.*RCS pressure now indicates 2350 psig.Assuming no other eventsarein progress, which ONE (1)of the following describesthe1)appropriate

actionandthe2)reason

for that action?A.1)Verify PZR PORVs and Block Valves open2)To increase flow on FI-943 ,CHGLOOPB CLO/HOT LEG FLOW GPM B.1)Verify PZR PORVs and Block Valves open 2)To increase flow on FI-110, EMERG BORATE FLOW GPM C.1)Placeboth ESFLS A(B)Resets to NON-ESF LCKOUTS 2)To increase flow on FI-943,CHGLOOPB CLO/HOT LEG FLOW GPMD.1)Placeboth

ESFLS A(B)Resets to NON-ESF LCKOUTS 2)To increase flow on FI-110, EMERG BORATE FLOW GPM 24

2007NRCExamRO25.Giventhefollowingplant

conditions:*Theplantwasat100%power.*Areactortripandsafetyinjectionoccurred

.*R8CUs XFN-0064A and XFN-00648startedinSLOW.*While performingtheactionsofEOP-1.0, ReactorTrip/SafetyInjection

Actuation ,thefollowingalarmsarereceivedinthecontrolroom:

• XCP-605-3-1, SW FR R8CU 18/28FLOLO*XCP-605-3-2, SWFRR8CU 18/28PRESSLOWhichONE(1)ofthefollowingchoicescontainsbothofthe

conditionsthatcouldeach

independentlycausethese

annunciatorstoalarm?A.SW8P"8" tripped;MVG-31118, R8CU 648/658TOIND COOLINGgoingCLOSED.

8.SW8P"8" tripped;MVG-3109C, R8CU 648 OUTLETISOLgoingCLOSED.

C.XFN-00648 (18 R8CUSSFAN)tripped;

MVG-3108C, R8CU 648 INLETISOLgoingCLOSED.

D.XFN-00648 (18 R8CUSSFAN)tripped;

MVG-3109D, R8CU 658 OUTLETISOLgoingCLOSED.

25

2007NRCExamRO 26.WhichONE(1)ofthe

following describes the power supplies that directly feed Containment

Spray Header Isolation Valves XVG-3003A and XVG-3003B, respectively?A.XSW1DA1andXSW1DB1

B.XMC1DA2XandXMC1 DB2Y C.XMC1 DB2XandXMC1 DA2Z D.XMC1 DA2ZandXMC1 DB2X 26

2007NRCExamRO27.Giventhe

following plant conditions:*ALOCAhasoccurred.*RCS pressureis450psig.

Reactor Building pressureis18psigandlowering.

• RWSTlevelislowering

.Reactor Building Sumplevelisrising

.*"A" Reactor Trip Breakerremainedclosed

.WhichONE(1)ofthe

following describes the operationofthe ReactorBuildingSpraysystemasthe

event continues?RBSprayPumpsuctiontotheRBSump

Valves , MVG-3005AandB...A.are manually openedwhenRWSTlevel

reaches its setpoint.RB Spray Pump suction valvesfromRWST,MVG-3001AandB,are

manuallyclosedwhen

MVG-3005AandBarefullyopen.

B.automaticallyopenwhen RWST level reachesitssetpo int.RB SprayPumpsuctionvalvesfrom

RWST , MVG-3001AandB, automaticallyclosewhen MVG-3005A andBarefullyopen.C.are manually opened when ReactorBuildingSumplevelreachesitssetpo

int.RBSprayPump suction valvesfromRWST , MVG-3001AandB,are manually closed when MVG-3005AandBarefullyopen.

D.automaticallyopenwhen ReactorBuildingSumplevelreachesits

setpoint.RBSprayPump suction valvesfromRWST , MVG-3001AandB , automatically

close when MVG-3005AandBarefullyopen.

27

2007NRCExamRO28.Withtheunitat100%

power ,whichONE(1)ofthefollowing

describesthepotential

consequence

of PCV-444C, PZR Spray Valve ,failingopen?A.LossofPZR

pressurecanresultinan

unwarrantedOPDeltaTrunbackandreactor

trip.B.PZR pressurewillremainstableasPZRheaterswill

compensateforthepressure

reduction.C.LossofPZR

pressuremayresultinsteam

formationinthe reactorvesselheadandSGtubes.D.LossofPZR pressurecanresult inan unwarrantedOTDeltaT runbackandreactor

trip.28

2007NRCExamRO

29.WhichONE(1)ofthe

followingdescribesthe

purpose and functionofthe ReactorBuildingCharcoal

Cleanup Units?Designedfor...

A.primarymeansoflongtermpost

accidentiodineremovalfromtheRB

atmosphere

.Dischargeis

alignedtotheRBPurgesystemexhaust.

B.primarymeansoflongtermpost

accidentiodineremovalfromtheRB

atmosphere.Dischargeis

alignedtotheRBatmosphere.C.RB pre-entry reduction of airborne contaminants

.DischargeisalignedtotheRBPurgesystem

exhaust.D.RB pre-entry reduction of airborne contaminants.

DischargeisalignedtotheRB

atmosphere.

29

2007 PostRetakeNRCExam

Question Review FQue'stion*17rainin'g;,-R efer.en ce:f Res olutibn.',-MissedI'"*(Mes/N(>>)*onsideration I;':1¥es/No),.,".."-e., ,""c x.RO/SROI , B'tes*..Yes*3'.O, Simulator scenarios lirai liling material feed ba GI Cs tit:>m itted tochoices IA&0 to clar ifY"maximize Boric Acid flowrate".Also submitted feedback to include tliis I'-in an IRO/SRO scenario.lReviewed thls question."".._..wit heachcand idate.4 No No IB-2, Simulator Reviewed this questionwitheach candidate.

10 No No EOP-1.0 Reviewed th is questionwitheach candidate.

14 No No EOP-2.1, Simulator scenarios Rev iewed this questionwitheach candidate.

15NoNoIB-1,IB-3, GS-2, Simulator Reviewed this questionwitheach candidate.

scenarios 16NoNo IC-3, Simulator Reviewed this questionwitheachcand

idate.1[8 No Y es*18-9 Feedbac k submitted to include discussion

'ofRTB I" ,f control.power in I C-;: 9.iiII 2 1"NoN o IC-8 Some examinees were confused with terminology

"satisfied/NOTsatisfied"incho ices.Feedback II'.I submittedtoclarify.

Reviewed this question with-..each candidate.";,r;,&1 ,...24 Ye s*No A 0 F2-106.1...."-Il Reducing B.*S pre ssurewouldnot resultina'..I C:Jirect increasein flow on FI-11 O.Feedbacka subm ittedtoclarify.Reviewedthis

questionwit

h I-..B Q..,-each candida te."*g 2 7 N o I'N""....n..AlthougH technically

c orrect, entire answer w as I" 0 not available.Feedback submitted to provide"..0 entire co rrect answer." 28'Q Ye s*No*10-6Some confusio n over"unwarranted".Feedback I'provide d du r.iAgexamto view"unwarranted" as I'"undesired.

" T raining fee dback submittedt o I'I;revisec hoices A&lD similar lY.a......29NoNo AB-17 Reviewed this questionwitheach candidate.

30 No No EOP-4.0 Reviewed this questionwitheach candidate.

1of4

2007NRCExamRO30.Giventhefollowing

plant conditions:*Theunitwasinitially

operatingatfullpower.*Alossof ALL offsite poweroccurredin

conjunctionwitha steam generatortuberupture.*All safeguards

equipment functionedasrequired.*The following plant conditionsnowexist:*RupturedS/G

pressure=1100psig,stable*CoreexitTC

=505°F , slowly decreasing*RCS Pressure=1600psig,stable*PZRLevel=4%,stable*TotalSIFlow

=600gpmTheRCShasbeencooleddownto

target temperature.*In accordancewithEOP-4.0, Steam GeneratorTubeRupture,theROopensonePZRPORV.

Soon after openingthevalve,the

operatorobservesthatall

channels ofPZRlevelare

rapidly increasing.*ECCSflowhas

increasedfrom600gpmto650gpm.WhichONE(1)ofthe

followingisthecauseofthis

indication?

A.PZRlevel instrumentsarenot calibrated

for temperatureslessthan600°F

.B.Safety injectionflowis drivingtheRCStoawater

-solid condition.

C.Voidinginthe

reactor vesselheadisforcing

waterupthesurgeline.

D.Backflowhasbeen establishedfromtherupturedS/GtotheRCS.

30

2007NRCExamRO

31.Giventhe following plant conditions:*ALarge BreakLOCAhasoccurred

.*ReactorBuildingH2

concentrationwasat2%andrising

.*'A'Hydrogen Recombiner

is INOPERABLE.

Wh ichONE(1)ofthe

following describestheeffectontheremovalofHydrogenfromContainment?

A.Hydrogen concentrationwillremainbelow4%withonlyone

Recombiner

in operation.

B.Hydrogen concentrationwillriseabove4%butremain

below6%withonlyone

Recombiner

in operation.C.Hydrogen

concentrationwillremainbelow4%onlyifthe

Containment

PurgeSystemisplacedin

serviceinadditiontothe

Recombiner

.D.Hydrogen concentrationwillremainbelow4%onlyif

Containment

Sprayisplacedinservicein

additiontothe Recombiner

.31

2007NRCExamRO32.WhichONE(1)ofthe

following describes a featureofthe SpentFuelPooland/orCoolingsystem

that will maintainradiationdoselevelsat

acceptablelimitsduringplant

operations?

A.SpentFuel CoolingPumpswilltriponlowsuction

pressure prior to SpentFuelPoolleveldropping

below 460'6".B.Boron concentration

is maintainedsothat SpentFuelPool Keffislessthan0

.95andSpentFuelPool

Radiationlevelsare maintained

less than2.5mr/hratthesurfaceofthepool.

C.Anti-siphoningholesinthecoolingsystemsuctionand

returnlines

ensures thatSpentFuelPoollevelwillnotdropbelow460

'6".D.Interlocksonthe

SpentFuelPool Manipulator

Crane prevent spentfuelassembliesfromtravelling

closerthan23feetfromthe

surfaceofthe SpentFuelPool.32

2007NRCExamRO

33.WhichONE(1)ofthe

followingdescribesthe

initialSGLevel Response and SGWLC System Responseduringarapidincreaseinpower?SGLevel Response A.DecreasesB.DecreasesC.IncreasesD.Increases

SGWLC System ResponseLagcircuitonSGlevelinput

minimizes fluctuations

Programmed

DIPacrosstheFRV

minimizes fluctuations

Programmed

DIPacrosstheFRV

minimizes fluctuationsLagcircuitonSGlevelinput

minimizes fluctuations

33

2007NRCExamRO34.Giventhefollow

ing plant conditions

• TheplantisinMode6

,corereloadisinprogress.*Afuel assemblyisbeinginsertedintothecorewhen

downwardmotionstops

.*TheRefuelingSROnotesthefollowing:*The SLACKCABLElightisON*The LOWER SLOWZONElightisOFF*The GRIPPERTUBEDOWNlightisOFFWhichONE(1)ofthe

followingdescribesthereasonthat

downward movementstoppedandthe

subsequentoperationrelatedtotheinterlock?

A.Totalloadfellmorethan

150-300#belownominalfullload;

bypassingtheinterlockisnotpossible.B.Thefuel assembly approached

10"fromthebottomofthecore

bypassingtheinterlockisnot

possible.C.Totalloadfellmorethan

150-300#belownominalfullload

bypasstheinterlocktoallowthe assemblytobefullyinserted.

D.Thefuel assembly approached10"fromthebottomofthecore

bypasstheinterlocktoallowthe

assemblytobefullyinserted.

34

2007NRCExamRO

35.Giventhefollowing

plant conditions:

• Reactor poweris75%.RCSleakratedataisasfollows:*TotalRCS leakagerateis 9.1 gpm.*LeakagetoPRTis7.0gpm.

Leakagetothe ReactorCoolantDrain

Tankis1.3gpm.*Total primary to secondaryleakageis0

.33 gpm.*SG1-0.09gpm*SG2-0.17gpm*SG3-0.07 gpmWhichONE(1)ofthe

following describes RCS leakageinrelationto

Technical Specif ication limits?A.Identified

leakage exceedstheTSlimitB.Unidentified

leakage exceedstheTSlimitC.Primaryto

Secondary leakageexceedstheTSlimit

D.AllRCS leakageiswithinTSlimits

35

2007NRCExamRO

36.Giventhe following plant conditions

Theunitisin

Mode 3.*Asteamline

breakhasoccurredon"A"SteamLineinthe

Reactor Building.WhichONE(1)ofthe

following describestheplantresponsetothisevent?

A."A"MainSteamLine

pressurewilldrop."B

"and"CMainSteamLinepressureswillremain

constant.AllMSIVswillclosewhenatleast2

Containment

pressure transmitters

indicate3.6psig.B."A"MainSteamLine

pressurewilldrop."B"and"C"Main

SteamLinepressureswillremain

constant.AllMSIVswillclosewhen"A"MainSteamLinepress

ureindicateslessthan675psig.C.All3Main

Steam Line pressureswilldrop.AllMSIVswillclosewhenatleast2

Containment

pressure transmitters

indicate3.6psig.D.All3Main

Steam Line pressureswilldrop.AllMSIVswillclosewhenatleast2

Main Steam Lines indicatelessthan675psig.

36

2007NRCExamRO37.WhichONE(1)ofthe

following describes the purposeofC-9 , Condenser Availability

,andC-16 , Condenser Pressure , permissive

signals?A.C-9prevents2

steam dumpvalvesfrom

operating during conditionsthatcoulddamagethe condensers.C-16armsALL

condenserdumpvalveswhen

condenser is below 4.5"Hgabsand adequate circ water pumps are available.B.C-9armsALL

condenserdumpvalveswhen

condense r is below 7.5"Hgabsand adequate circ water pumpsareavailable.C-16prevents2

steam dumpvalvesfrom

operating during conditionsthatcoulddamagethe condensers

.C.C-9 anticipates

condenserheatload problemsbyblocking2

condenser dumpvalvesat7.5"Hgabs.C-16 prevents ALL condensersteamdump valves from operatingduringconditionsthatcould damage the condensers.

D.C-9 prevents ALL condensersteamdumpvalvesfrom

operatingduringconditionsthatcould damage the condensers.

C-16 anticipates

condenserheatload problemsbyblocking2

condenser dumpvalvesat4.5"Hgabs.

37

2007NRCExamRO38.Giventhe

following plant conditions:Theplantis

operatingat100%power.*A FeedwaterLineBreakoccursatthepiping

connectionto"A"SG.WhichONE(1)

of the following describestheeffectofthis

event?A.RCS temperaturerisespriorto

reactortrip.SG"A" continues to depressurize

afterFWIVclosure.B.RCS temperaturelowerspriortoreactortrip.SG"A" continues to depressurizeafterFWIV closure.C.RCS temperatures

lowerspriortoreactortrip.SG"A" pressure stablil izes after FWIV closure.D.RCS temperature

rises prior to reactortrip.SG"A" pressure stablizesafterFWIV closure.38

2007NRCExamRO

39.Giventhefollowingplant

conditions:*AStation Blackouthasoccurred

.*Thecrewisrestoring

off-site powertoBus1DAthroughthenormalfeed.Priortoclosingthenormal

feeder breakertoBus1DA,whichONE(1)ofthefollowingsetsofactions

must be performed, in accordancewithAOP-304.1

, Loss ofBus1DA with Diesel Unavailable?

A.De-energizeTrain"A"ESFLSEnsureBus1DA

TRANSFERINITSwitchisinOFFB.De-energizeTrain"A"ESFLSEnsureBus1DA

TRANSFERINITSwitchisinONC.Reset NON-ESF LCKOUTS&AUTO-START

BLOCKSEnsureBus1DA

TRANSFERINITSwitchisinOFFD.ResetNON-ESF LCKOUTS&AUTO-START

BLOCKSEnsureBus1DA

TRANSFERINITSwitchisinON

39

2007NRCExamRO40.Giventhefollowingplant

conditions

• Alossof off-site powerhasoccurred.BothEDGshaverespondedasdesigned.

• Subsequently, safetyinjectionoccurs

.*Thefollowing

conditionsexiston"A"EDG:

• Frequency59.9Hz.*Voltage7150Volts KW Output2600KWRBPressure

reaches an actuation setpointrequiringthestartof"A"RBSpraypumpLoadsstabilize

.....WhichONE(1)ofthe

followingdescribesthestatusof"A

" EDG?A.Alllisted parametersarewithinlimits.B.Frequencyis

belowthelimit.C.Voltageis

belowthelimit.D.Output exceeds the continuousKWrating.40

2007NRCExamRO41.Giventhefollowing

plant conditions:

• lAW GOP-4A, Power Operation(Mode1-Ascending), powerhasbeenstabilizedbetween12and15%.

• PreparationsarebeingmadetorolltheMain

Turbineto1800rpm.

Reactor power indicates the following:

• IRN-35-1X101%.*IRN-36-1X10

1%.*PRN-41-15%.

• PRN-42-14%

.*PRN-43-14%

.*PRN-44-14%.

• Inverter XIT-5902 output breakertripsopen.WhichONE(1)ofthe

following describestheeffectontheunit?

A.APowerRangeRodStop(C-2)signal,withno

change in reactor power.B.Areactortripduetothe

deenergization

of Intermediate

Range Channel N-35.C.Areactortripduetothe

deenergizationofIntermed

iate Range Channel N-36.D.An IntermediateRangeRodStop(C-1)signal

,withno change in reactor power.41

2007 NRC Exam RO 42.Giventhe following plant conditions

• The plant is operating at 100%power.*The following annunciators

are receivedinthe control room:*XCP-636 , 4-6 ,DCSYS OVRVOL T/UNDRVOL T*XCP-637 , 1-5, INV 3/4 TROUBLE*Inverter output voltage indicates120vac.Assuming NO other alarms are received, which ONE(1)ofthe following describes the common cause of both of the alarms?A.Loss of Alternate Source1FB.B.Loss of Normal Source 1 DB2Y.C.Loss of voltageonBus1HB.D.Inverter has transferred

to Alternate Source1FB.42

2007NRCExamRO43.Giventhe

following plant conditions:*The plant is operatingat100%power.*The followingalarmisreceived:

• XCP-624-1-5,SGALVLDEV*TheRO determines

thatSG"A"levelisrising

slowly on L1-474,475,and476

.*SG"B"and"C" levels are stable.WhichONE(1)ofthe

following describesthecauseofthealarmandtheaction

required?Alarmwas receivedona...A.5%deviation from programduetoa Feedwater Control Valvefailure;Place"A" Feedwater Control valve in manual and restorelevelto normal.B.5%deviat ion from programduetoaSteamFlowinputto"A"SGlevelcontrolfailing

low;Select the alternatefeedflowand

steamflowinputs

.C.10%deviation from programduetoa Feedwater Control Valvefailure;Place"A" Feedwater Control valve in manual and restoreleveltonormal.D.10%deviation from programduetoaSteamFlowinputto"A"SGlevelcontrolfailinglow;

Select the alternatefeedflowandsteam

flow inputs.43

2007NRCExamRO 44.WhichONE(1)

of the following conditionswillresultinthe

most Emergency FeedwaterSystemflow

required to maintain SG levels constant following a reactor trip?A.B.C.D.Core Burnup 1 ,000 MWD/MTU 1,000 MWD/MTU 10 ,000MWDMTU 10,000 MWD/MTU Initial Power Level 10%100%10%100%44

2007NRCExamRO

45.Giventhefollowingplantconditions:

.*Theplantisat100%

powerduringanA1

maintenance

week.*APN-5901hasbeen transferredtoAPN-1FAwhileworkisinprogresson

XIT-5901.*Thenormal

feeder breakerforbus1DAtripsopen.*"A" DIGfailstostart.WhichONE(1)ofthe

following describes the subsequentoperationofthe"A"Train

ESFLS?A.Output 1willshedloadsandtheESFLSwillgothroughitsnormal

sequence.B.Output1willshedloads,butthentheESFLSwillbe

preventedfromoperating.C.Output 1willNOTshedloads

,buttheESFLSwillgothroughitsnormalsequence.D.Output 1 will NOTshedloadsandtheESFLSwillbepreventedfromoperating.

45

2007 NRC Exam RO46.WhichONE(1)

of the following describes the availability

of Channel I (TrainA)120VACvital safeguards

power duringalossofthe

115KVlinefromthe

Parr Generating

Complex?A.Is initially available from Battery 1A through inverter XIT-5901 , then automaticallyreturnstothe

normal source after Diesel Generator"A" starts.B.The static switch initially transfers the supplyto1FA,then

automaticallyreturnsto the normal source after Diesel Generator"A" starts.C.Is initially available from Battery 1A through inverter XIT-5901 ,thenis manually returned to the normal source after Diesel Generator"A" starts.D.The static switch initially transfers the supplyto1FA,thenis

manually returned to the normal source after Diesel Generator"A"starts.

46

2007NRCExamRO47.Theplantisat100%power.Alossof125VDCcontrol

powertothewillrequireentrytoEOP-1.0, Reactor Trip/Safety

Injection Actuation.

A.FWBPbreakersB.MSIVsC.RCPbreakersD.PZRSprayValves

47

2007NRCExamRO48.Giventhe

followingplantconditions:*Alossof off-site power has occurred.*BothEDGsstartasrequired.WhichONE(1)ofthe

following describestheoperationoftheEDGRoom

Ventilation

system?Automat ically start when...A.DieselRoom

temperature

exceeds 88°F,tomaintainroom

temperaturebelowthe Technical Specificationlimitof120°F.

B.the associated

Diesel Generatorstarts,tomaintainroom

temperaturebelowthe Technical Specificationlimitof88°F.c.DieselRoom

temperature

exceeds 72°F ,tomaintainroom

temperaturebelowthe Technical Specificationlimitof88°F.D.the associated

Diesel Generator starts , to maintain room temperaturebelowthe Technical Specif icationlimitof 120°F.48

2007NRCExamRO49.Giventhe

following plant conditions

Emergency Diesel Generator"A"ispa ralleledtoits associated

Bus.*Alagging power factorhasbeen established.WhichONE(1)ofthe

following describes the operationofthediesel

generator voltagecontrolswitch?

A.Loweringthe

voltage control setpointwillcausethe

generatortopickupalargershareoftherealload.B.Raisingthe

voltage control setpointwillcausethe

generatortopickupalargershareoftherealload.C.Lower ing the voltage control setpointwillcausethe

generatortopickupalargershareofthe

reactive load.D.Raisingthe

voltage control setpointwillcausethe

generatortopickupalargershareofthe

reactive load.49

2007NRCExamRO

50.Giventhefollowingplant

conditions:*AlossofRB

InstrumentAirhasoccurred.*RB Instrument

Air header pressureiscurrently94psigandlowering

.Assumingno

operatoraction,whichONE(1)ofthefollowing

describestheresponseoftheAirSystemandwhy?

RB Instrument

Air header pressure decreasesuntil...A.PVA-2659 ,INSTAIRTORBAIR

SERV , automaticallyopensat90psigtoensureanairsupplyforAOVsinsidethe

Reactor Building.B.PVA-2659,INSTAIRTORBAIRSERV, automatically

opensat93psigtoensureanairsupplyforAOVsinsidethe

Reactor Building.C.PVT-2660

,AIRSPL YTORB,closesat90psigtoisolatetheRB

headertoavoidalossof Instrument

Air outside the Reactor Building.D.PVT-2660 ,AIRSPL YTORB ,closesat93psigtoisolatetheRB

headertoavoidalossof Instrument

Air outside the Reactor Building.50

2007NRCExamRO51.Giventhe

followingplantconditions:*The plantisinMode6.

ReactorBuildingPurgeisinoperation

.Refueling activitiesareinprogress.*Aspentfuel

assemblyisdroppedinthecavity.

Containment

radiation monitor indicationsareallrising

.WhichONE(1)ofthefollowingdescribestheradiationmon

itorsthatw ill initiateisolationofallorpartofthe

Containment

Purge?RM-A4 ,RBPurge Exhaust Particulate(Iodine)(Gas)Atmos

monitor...A.ONLY.B.AND RM-G17A/B , RB ManipulatorCraneAreaGammaONLY

.C.ANDRM-A2 , RB Sample Line Particulate(Iodine)(Gas)Atmos

monitor ONLY.D.AND RM-G17A/B, RB ManipulatorCraneAreaGamma

,ANDRM-A2,RBSample

Line Particulate (Iodine)(Gas)Atmosmonitor.

51

2007NRCExamRO 52.Giventhe following plant conditions

• An immediate dischargetothe penstocksfromboth Waste Monitortanksis required.*Current conditionsareasfollows.RM-L5andRM-L9areoutof

service*FairfieldHydroisinthe"pumping" mode.WhichONE(1)ofthe

following statementswillprovidethe

MINIMUM conditions

necessary for monitor tank release?A.EitherRM-L5orRM-L9mustberestoredto

operability

priortorelease.B.BothRM-L5andRM-L9mustberestoredto

operability

priortorelease.

C.TheFairfieldHydro

must converttothe generatingmodeand redundant samples performed priortorelease.Two

independent

qualified individualsmustverify

release calculationsandvalve lineups.D.TheFa irfield Hydro must converttothe generatingmodepriortoreleaseandeitherRM-L5orRM-L9mustbe

restored to operability.

Two independent

qualified individuals

must verify release calculationsandvalve lineups.52

2007NRCExamRO53.WhichONE(1)

of the following describes operation of XFN-30A(B)

, CONTR RM EMERG FILTERING SYS FAN A(B), and XFN-32A(B), CONTROL ROOM COOLING UNITA(B)FAN upon receipt ofahigh radiationalarmon RM-A 1, Control Bldg Supply Air?A.BothXFN-32A&BandbothXFN

-30A&Bstart,all

outside air sourcesareisolated

.B.Both XFN-32A&Bandboth XFN-30A&Bstart ,returnairis

mixedwithasmall

amount of makeup air.C.Both XFN-32A&BtripandbothXFN

-30A&Bstart,all

outside air sources are isolated.D.Both XFN-32A&Btripandboth

XFN-30A&B start ,returnairis

mixedwithasmall

amount of makeup air.53','

2007NRCExamRO

54.Giventhe following plant conditions

• The plantisinMode5.RHRTrainAisinservice.

RCS temperatureis168°F.RCS pressureis175psig.

• Subsequently

,aLossof Service Water occurs.*Thecrewis

performing

actions containedinAOP-117.1

, Total Loss of Service Water.*NEITHER Service Waterloopcanberestored

.WhichONE(1)ofthe

following describestheeffectontheRHRSystem,andtheprocedurethatwill

mitigate the event?A.Stabilize RHR/RCS system temperatureusingsteam

dumps lAW GOP-6, PlantShutdownMode

3toMode5.Goto AOP-115.3, Loss ofRHRwiththeRCSIntact

, for long-term mitigation.

B.Stabilize RHR/RCS system temperatureusingsteam

dumps lAW GOP-6 , PlantShutdownMode

3toMode 5.Continue us ing AOP-117.1 , Total Loss of Service Water, for long-term mitigation.

C.RHR/RCS system temperaturewillriseasaresultofalossofcoolingto

ComponentCoolingWater.Goto

AOP-115.3 , Loss ofRHRwiththeRCSIntact

.D.RHR/RCS system temperaturewillriseasaresultofalossofcoolingto

ComponentCoolingWater.

Continue using AOP-117.1 , Total Loss of Service Water.54

2007NRCExamRO55.WhichONE(1)ofthe

following providestheelectrical

powersupplytothe

Supplemental

Air Compressor?

A.XSW1DA1 B.XSW1DB1C.XSW1A1D.XSW1B1 55

2007NRCExamRO56.Giventhefollowingplant

conditions

TheFire ProtectionSystemactuatedduetoaMain

Transformer

Fire.System pressuredroppedto80psigbefore

recoveringduetotheactuationof

necessary equipment.*Thefireisout.*The delugevalveisisolatedandreset.WhichONE(1)ofthe

following describes the equipmentthatisrunning

,andthemethodofshutt

ing the equipment down?A.ONLYthe MotorDrivenFirePumpisrunning;mustbe

stopped locally.B.ONLYthe MotorDrivenFirePumpisrunning;maybe

stoppedlocallyorinthecontrolroom

.C.TheMotorDrivenandEngineDrivenFirePumpsarerunning.Bothmustbestoppedlocally.D.TheMotorDrivenandEngineDr

ivenFirePumpsarerunning

.TheMotorDrivenPumpmaybe stoppedlocallyorinthecontrolroom,theEngineDrivenPumpmustbestoppedlocally.

56

2007NRCExamRO57.Giventhefollowingplant

conditions:*ALOCAhasoccurred.

SafetyInjectionis

actuated.Reactor Building pressureindicates14psigandrisingslowly.*While performing

actionsofEOP-1.0, Reactor Trip/SafetyInjectionActuation,thefollowingvalves

indicate OPEN:*RCPSLWTRISOL

8100*LTONISOL8152*RBAIR SERVISOL2660WhichONE(1)ofthe

followingdescribesthefailurethathasoccurredandtheMINIMUMaction

necessary to mitigatethecondition?

A.PhaseAhas partiallyfailed.Place

eitherPhaseA actuation switchesinthe ACTUATE position.B.PhaseAhas

partiallyfailed.PlacebothPhaseAactuation

switchesinthe ACTUATE position.C.PhaseBhas

partiallyfailed.Place

eitherPhaseB actuation switchesinthe ACTUATE position.O.PhaseBhas

partiallyfailed.PlacebothPhaseB

actuation switchesinthe ACTUATE position.57

2007NRCExamRO

58.G iventhefollowingplantcondit

ions:*Thereactorhastripped.

SafetyInjectionisactuated

.*AnRCS cooldownisinprogressinaccordancewithEOP-2.1,PostLOCA Coo/down and Depressurization.

• Thefollowingtableisaplotofthecooldown

TIMERCSTCOLDTIMERCSTCOLD 0800 54rF 0945 425°F 0815 530°F'1000 395°F 0830 520°F 1015 382°F 0845 505°F 1030 364°F 0900 498°F 1045 340°F 0915 478°F 1100 310°F 0930 44rF 1115 280°FAtwh ich t imewastheTech

SpecRCSCooldownratelimit

FIRST exceeded?A.0915.B.0930.C.1000.D.1115 58

2007NRCExamRO

59.Giventhe following plant conditions

• ALOCA outside containmenthasoccurred

.Thecrewis performingtheactionsin

EOP-2.5,LOCAOutsideContainment.WhichONE(1)ofthe

followingactionswillbe

attemptedtoisolatethebreakandwhichindicationisusedto

determineiftheleakhasbeenisolatedin

accordance

with EOP-2.5?A.Isolatelow

pressure SafetyInjectionpiping

.RCS pressure is monitored, becauseSIflowwill

repressurizetheRCSwhenthebreakisisolated.

B.Isolatelow

pressure SafetyInjectionpiping.PZRlevelis

monitored , becausewhenthe breakisisolated

, RCS inventory willrapidlyrise

.C.Isolatehigh

pressure SafetyInjectionpiping.

RCS pressure is monitored, becauseSIflowwill

repressurizetheRCSwhenthebreakisisolated.

D.Isolatehigh

pressure SafetyInjectionpiping.PZRlevelis

monitored , becausewhenthe breakisisolated

, RCS inventory willrapidlyrise

.59

2007NRCExamRO

60.WhichONE(1)ofthe

following describesthereasonthataREDconditionontheIntegrityCSFStatusTreemay

developwhileperformingactionsofEOP-14.1,Responseto

DegradedCoreCooling?

A.CoreExit Thermocouple

temperaturewilldecreaserapidlywhenLowHeadSIPumpsarestartedandSIflowisinitiated

.B.CoreExit

Thermocouple

temperaturewilldecreaserapidlywhenSG

depressurizationandSI Accumulatorinjectionoccur.C.RCSColdLeg

temperaturewilldecreaserapidlywhenLowHeadSIPumpsarestartedandSIflowisinitiated.

D.RCSColdLeg

temperaturewilldecreaserapidlywhenSG

depressurizationandSI Accumulatorinjectionoccur.

60

2007NRCExamRO61.Giventhefollowingplantconditions:*ALOCAhas occurred.*Thecrewis

performingactionscontainedinEOP-2.0, Loss of Reactor or Secondary Coolant.*Thefollowing

conditionscurrentlyexist:Integrity-RED

• Containment-RED*Subcriticality

-ORANGECoreCooling-

ORANGE Inventory-YELLOW*HeatSink-YELLOWWhichONE(1)ofthe

followingdescribesthecorrect

procedureflowpathforthese

conditions?

A.EOP-17.0 , ResponsetoHigh Reactor Building Pressure ,followedby

EOP-16.0 , Response to Imminent Pressurizer

Thermal Shock Condition.B.EOP-16.0, Response to Imminent Pressurizer

Thermal Shock Condition , followedbyEOP-17.0, ResponsetoHigh Reactor Building Pressure.C.EOP-14.1

, Response to Degraded Core Cooling ,followedby

EOP-16.0 , Response to Imminent Pressurizer

Thermal Shock Condition.

D.EOP-16.0 , Response to Imminent Pressurizer

Thermal Shock Condition , followedbyEOP-14.1

, Response to Degraded Core Cooling.61

2007NRCExamRO62.Giventhefollowingplant

conditions

• A reactortriphas occurredduetoalossofoffsite

power.*ThecrewisperformingactionsofEOP-1.4, Natural CirculationCooldownwithSteamVoidinVessel.*Duringtheevent,RCPsealcoolingwaslost,but

subsequently

restored.*The operatingcrewis preparingtoinitiatetheRCScooldown.Thefollowing

conditions

are indicated:*RVLlSNRlevelis89%

.RCSsubcool

ingis60°F.*PZRLevelis72%andstable.WhichONE(1)ofthefollowing

actionsisrequiredin

accordancewithEOP-1.4?

A.UsePZRHeatersas

necessary to saturatePZRwaterand

continueinEOP-1.4.

B.Initiate SafetyInjectionandgotoEOP-1.0

, ReactorTripOr Safety Injection.C.StartaRCPandgotothe

applicableportionofthe

appropriate

GOP.D.ReturntoEOP-1.3

, Natural Circulation

Cooldown.62

2007NRCExamRO63.Giventhefollowingplantconditions:*ALOCAhasoccurred.DuetolowRHRSumpLevel

,thecrewhas

transitionedfromEOP-2.2, TransfertoColdLeg Recirculation,toEOP-2.4 , Loss Of Emergency Coolant Recirculation

.*All automatic actionsoccurredasdesigned

.*TwoCharging

pumpsandtwoRHRpumpsarerunning.BothRBSprayPumpsarerunning

.RHR , Charging ,andRBSpraypumpampsandflowarestable

.RWSTlevelis

approximately5%andcontinuestolower.WhichONE(1)ofthe

followingdescribeshowtheCharging

,RHR,andRBSpraypumpsshouldbe

operated in accordance

with EOP-2.4?ChargingPumpsRBSprayPumpsRHRPumps A.StopBOTHLeaveBOTHrunningLeaveBOTHrunning

B.StopONEStopBOTHStopONE C.StopBOTHStopBOTHStopBOTH D.LeaveBOTHrunningLeaveBOTHRunn

ingStopONE 63

2007NRCExamRO64.Thecrewis

performing

actionsofEOP-3.1, Uncontrolled

Depressurization

of All Steam Generators

.WhichONE(1)ofthe

following describes the Technical Specification

implications

oftheevent?A.RCS cooldown rates above100°Fper hour may potentiallyresultin non-ductilefailureofthe

reactor vessel.B.Pressurizer

cooldownratesabove100°Fperhourmay

potentiallyresultin pressurized

thermal shocktothepressurizer.C.LossofSG

inventory may ultimatelyresultintheRCS

Pressure SafetyLimitbeing

exceeded.D.LossofSG

inventorymay

ultimatelyresultinthe

Reactor Core SafetyLimitbeing

exceeded.64

2007NRCExamRO65.WhichONE(1)ofthefollowing

describesthestatusofRB

ventilationandRBCU'suponcompletionoftheactions

containedinEOP-17.2

, Response to High Reactor Building Radiation Level?A.RBPurgeisolatedAllRBCUfansin

SLOWB.RBPurgeisolatedRBCUfansselectedonswitchRBCUTRAIN

AlBEMERG,runn

ing in SLOW C.RBMiniPurgeinserviceAllRBCUfansin

SLOWD.RBMiniPurgeinserviceRBCUfansselectedonswitchRBCUTRAIN

AlBEMERG,runningin

SLOW 65

2007NRCExamRO66.Inaccordancewith

OAP-100A, Communication

,whichONE(1)ofthefollowing

communicationsshouldusethephoneticalphabet?

A.Communicationsinvolvingsafetysystemtrains

.(Train Alpha)B.Communications

involving manipulationofplant components

.(AlphaCharging

Pump)C.Communications

describing

Conta inmentIsolation(PhaseBravo)D.All communicationsthatarenot'informationonly'

.66

2007NRCExamRO67.Giventhefollowingplantconditions:*Theplantisat46%

power and increasing

lAW GOP-4A , Power Operation (Ascending)at3%perhour.*Alossof Feedwater occurs.*AllthreeS/GNRlevelsareat5%andlowering

.*Itisnow60

seconds later.WhichONE(1)ofthefollowingistheexpectedresponseoftheATWSMitigation

System Actuation Circuitry (AMSAC)?'A.AMSACwillNOT

actuate becauseitisnotarmed.

B.AMSACwillTRIPthereactorand

STARTtheEFWpumps.C.AMSACwillNOT

actuate becausethetimedelayonreactor

powerhasnottimed

out.D.AMSACwillTRIPthemain

turbine and STARTtheEFWpumps

.67

2007NRCExamRO68.Giventhe

following plant conditions:*AnRCSleakisin

progress.*Thecrewis

performing

the appropriate

AOPforthe plant condition.

• Letdown is isolated.*Charging flow is maximized.*RCS pressure is 1990psigandlowering

.*Reactor Building pressureis1.8psigandrising.

• Pressurizerlevelis18%andlowering.

• VCTlevelis15%and

lowering.WhichONE(1)ofthe

following describes the statusofthe plantandtheaction

required?A.AnRPS setpointhasbeen exceeded.Tripthe Reactor and initiate Safety Injection when immediate actions of EOP-1.0havebeen completed.B.AnRPS setpoint has been exceeded.Tripthe reactor and concurrently

perform actionsofthe in-use AOP when immediate actions of EOP-1.0havebeen completed.

C.AnRPS setpoint has NOT been exceeded ,Tripthe Reactor , perform the immediate actions of EOP-1.0,theninitiate

Safety Injection.D.AnRPS setpoint has NOT been exceeded ,Tripthe Reactor, perform the immediate actions of EOP-1.0 , continue to implement the AOP concurrently, then initiate Safety Injection when Pressurizerlevelis<12%.

68

2007NRCExamRO69.Theunitisat100%

power.Allsystemsareinnormal

alignments

.WhichONE(1)ofthefollowingactivitiesrequiresentryintoa

technical specificationLCOaction statement?

A.CCWPumpB mechanicalsealrepair.

B.ChargingPumpAremovalfromserviceforoilchange.

C.BoricAcid TransferPumprecircvalveleakrepair

.D.RHRHeat ExchangerDischargeflowcontrolvalverepair

.69

2007NRCExamRO 70.WhichONE(1)ofthe

following describes the MINIMUM Source Range Nuclear Instrumentation

requirement

that mustbemet prior to off-loadingfuelfromthereactor

vessel?VisualincontrolroomAud

ibleincontrolroom

AudibleinRB A.C.D.1 2 2 2 1 , 1 2 2 1 1 1 2 70

2007NRCExamRO71.Giventhefollowing

information:*A27yearoldnewV.C

Summer employeehasafully completedNRCForm4anda2007 radiation exposurehistoryasfollows:*2650milliremfrom

previous employmentwithProgressEnergyin2007.*110 millirem sincebecomingaV.C

.Summer employee.WhichONE(1)ofthe

followingdescribestheMAXIMUM

ADDITIONALexposuretheemployeemayreceivepriortoreachinghis

MAXIMUM AdministrativeDoseControl

Limit,includingany

applicable

extensions

, lAW HPP-0153 , Administrative

Exposure Limits?A.1240milliremB.1350milliremC.2240millirem

D.2350m illirem 71

2007NRCExamRO72.Giventhefollowingplantconditions:*AGeneral Emergency exists.TheTSCis manned.*AvalveintheAuxBuildingmustbeclosedtoprevent

damage to valuablesafetyrelated

equipment.*Radiationlevelsare

extremely high.WhichONE(1)ofthefollowingdescribesthemaximumdosethatisallowedtoperfo

rmthisoperationandwhose

permission

isrequired?Anindividualmayreceive

...A.Upto10Remwith

permissionfromtheDutySSB.25Rem,ormore

, w ith permissionfromtheDutySSC.Upto10Remwith

permissionfromtheED D.25Rem ,ormore,with

permissionfromtheED 72

2007NRCExamRO73.Giventhefollowing

plant conditions:*Areactortripand

safetyinjectionhaveoccurred.

Off-Site powerislost subsequent

to safety injection actuation.

• Equipment failures during performanceofEOP-2.0, Loss of Reactor or Secondary Coolant,resultedinthefollowingconditions:*Bus1DAis de-energizedduetoafault.*CSF Status Trees indicateasfollows:

• Subcriticality*CoreCooling*HeatSink*Integrity*Containment

Inventory GREEN ORANGE RED GREEN YELLOW YELLOWWhichONE(1)ofthe

followingdescribesthe

requirementforCritical

Safety FunctionStatusTree

Monitoring

in accordance

with OAP-103.04, EOPIAOPUser'sGuide?

A.Continuous

monitoringisrequired.

B.Monitorevery5-10

minutesunlessachangeinstatusoccurs.C.Monitorevery10-20

minutes unless achangeinstatus

occurs.D.Monitoredfor

information

only.73

2007NRCExamRO74.Giventhefollowing

plant conditions:

T=OAfireis occurringintheAuxBuilding436'.T+2FireBrigade

Leaderreportstothescene.T+15 NotificationofUnusualEventdeclared.

In accordance

with EPP-013 , Plant Fire ,who,bytitle,is

coordinatingthefirefightingeffortswiththeFire

Brigade Leader?A.Shift Supervisor

B.Emergency Direc torC.OSC SupervisorD.HealthPhysicsShift

Leader 74

2007NRCExamRO75.Giventhefollowingplantconditions:*TheUnitisinMode5

.RCSDrainDowntoMidLoopisinprogressin

preparationforweldingonaHotLegopening.*RHRPumpAisinservice

.*Duringthedraindown,RHRampsand

discharge pressurebeginfluctuating

erratically.*Thecrew enters AOP-115.1,RHRPumpVorlexing.*The drain-downisstopped.WhichONE(1)ofthefollowing

describestheFIRSTactionthatwillberequiredinaccordancewith

AOP-115.1?A.ReduceRHRflow.B.AligntheRHRPumptotheRWST.C.RaiseRCSlevel.D.Ventthe operatingRHRloop.75