ML071930561

V. C. Summer June 2007 Exam Nos. 05000395/2007301 Final SRO as Given Written Exam

ML071930561
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: ML071930561 (104)

See also: IR 05000395/2007301

Text

Final Submittal(BluePaper)

V t,.S)()()1/f)l?r

2(07-

/3/2 ,{)o7 AS Givw Senior Operator Written Examination

v.C.SUMMER JUNE 2007 EXAMEXAMNO.05000395/2007301

JUNE4-8,2007(OP

TEST)JUNE 13,2007 (WRITTEN EXAM)

u.s.Nuclear Regulatory

Commission

Site-Specific

SRO Written Examination

Applicant Information

Name: Date: ,-Facility/Unit:

JUne 13 j 2fJOl V* Region: II Reactor Type: W Start Time: Finish Time: InstructionsUsethe answer sheets provided to document your answers.Staple this cover sheet on top of the answer sheets.To pass the examination

you must achieve a final grade of at least 80.00 percent overall, with 70.00 percent or better on the SRO-only items if given in conjunction

with theROexam;SRO-only exams given alone require a final grade of 80.00 percent to pass.You have 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to complete the combined examination, and 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> if you are only taking the SRO portion.Applicant Certification

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

Signature Results RO/SRO-OnlylTotal

Examination

Values--/--/--Points Applicant's

Scores--/--/--Points-Applicant's

Grade--/--/--Percent

Name:---------------1.Giventhe

following:*Theunitisat85%

poweratMOL.*Acontinuousuncontrolledcontrolrod

withdrawal

occurs.WhichONE(1)ofthe

following parameters

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

Output C.OverpowerDeltaT setpointD.VCTLevel2007NRCExamSRO

1

2007NRCExamSRO

2.Giventhefollowingplant

conditions:*ALOCAhas occurred.*RCSpressureis1750psigandlowering

.*Reactor Building pressureis4psigandrising.*Steam Generator pressuresare1000psigandstable.WhichONE(1)ofthe

following describes the actuationsthatarearesultofthis

condition?

A.SafetyInjectionONLY.

B.SafetyInjectionand

Containment

Ventilation

Isolation ONLY.C.SafetyInjectionand

ContainmentIsolationPhaseAand

Containment

VentilationIsolationONLY.D.SafetyInjectionand

Containment

Isolat ionPhaseAand Containment

VentilationIsolationand

Containment

IsolationPhaseB.2

2007NRCExamSRO3.Giventhe

followingplantcondit

ions:*Thecrewis

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

,andis attempting

an emergency borat ion oftheRCS.*MVT-8104, EMERG BORATE ,valvewillnotopen

.WhichONE(1)ofthe

followingdescribestherequiredactionstobe

performed and why?A.Openthe ChargingPumpSuction

HeaderIsolationvalvesas

directed byAOP-106.1, Emergency Boration, to maximizeBoricAcidflowrate.B.Open LCV-115B/D, RWSTtoCHG PP Suet ,asdirectedby

AOP-106.1, Emergency Boration , to borateviacoldleginjection

.C.Openthe ChargingPumpSuction

HeaderIsolationvalvesas

directedbyEOP-13.0

, Response to Abnormal Nuclear Power Generation

, to maximizeBoricAcidflowrate.D.OpenLCV-115B/D, RWSTto CHG PPSuet,asdirectedbyEOP-13.0,Responseto

Abnormal Nuclear Power Generation

,toborateviacoldleginjection.

3

2007NRCExamSRO

4.WhichONE(1)ofthe

following describes the setpointsforthetwo(2)

annunciators

below?A.B.C.D.RCP AlBIC THERMBAR&BRGFLOLO90gpm90gpm50gpm50gpm CCBP DISCHHDRPRESSLO30psig70psig30psig70psig 4

2007NRCExamSRO

5.Giventhefollowingplant

conditions:*TheplantisinMode5.*ThePZRissolid

.*RCS temperatureis190°F.*RCS pressureis315psig.*Letdown Pressure ControlValvePCV-145isinAUTO.FCV-605A,"A" gyp,andFCV-605B,"B"BYP,arein

MANUAL.WhichONE(1)ofthe

followingdescribesaconditionthatwill

initiallycausePCV-145toCLOSE?A.Loweringthe

outputofthe controllerforthein-serviceRHRheat

exchanger flowcontrolvalve.B.RaisingCCWflow

through the in-serviceRHRHeat Exchanger.C.Loweringthe

setpointofPCV-145.

D.Startingan

additionalRHRPump.5

2007NRCExamSRO

6.Giventhefollowing

plant conditions:*Theplantisin

Mode 6.*"B"TrainRHRisin

service.*"A"TrainRHRisoutofserviceand

expectedtobereturnedto

service in approximately2hours.*Refuelingisin

progress.*Cavitylevelis23.5feetabovethe

reactorvesselflange.

"B"RHRPumptripsand

cannotberestarted

.WhichONE(1)ofthe

following describes the operational

restriction(s)

associated

withthisevent?

A.RefuelingCavitylevel

mustberaisedto

greaterthan24feet

abovethereactorvesselflange

prior to continuingrefuelingactivities.

B.Refueling activities

are permittedforupto1hourwh

ilerepairsareinitiatedto

"B"RHRPump.C.All containment

penetrationswithad irectpathto atmosphere

must immediately

beverifiedclosed

.D.Suspendallactiv

ities thatcouldresultinareductioninboron

concentrationofthe RCS.6

2007 NRC Exam SRO 7.Giventhe following plant conditions:*The plant was operating at 100%power.*7.2KV Transformer

XTF-4waslostduetoafault.*The associated

DIG did NOT start as designed.*Subsequently, a LOCA caused a reactortripand safety injection.*RCS pressure is currently350psigand

trending down slowly.WhichONE(1)ofthe

following describes the operationofRHR Pumps for this condition?A.RHR pump A runningwithits miniflow valve openB.RHR pump A runningwithits miniflow valve closed C.RHR pump B runningwithits miniflow valve openD.RHR pump B runningwithits miniflow valve closed 7

2007 NRC Exam SRO 8.Which ONE (1)of the following directly supplies power to Charging Pump"A"andRHR Pump"A"?A.B.C.D.Charging Pump"A" 1DA 1DA1 1DA 1DA1 RHR Pump"A" 1DA 1DA 1DA1 1DA1 8

2007 NRC Exam SRO 9.Giventhe following plant conditions:*The plant is operating in Mode1at 100%power.*The following indications

are reportedbytheRO.*TI-471, PRT Temperature

is trendingupandis now at 158°F.*PI-472, PRT Pressure is trendingupandis nowat8psig.Which ONE (1)of the following components, if leaking, will cause this condition?

A.XVR-8708A, RHR Pump"A" Suction Relief Valve.B.XVR-8121, RCP Seal Return Relief Valve.C.XVR-7169, RCDT Pumps Suction Relief Valve.D.XVS-8010, PZR Safety Valve.9

2007NRCExamSRO10.WhichONE(1)ofthe

following describes an immediateactionandthebasisforthe

action i n accordance

with EOP-1.0 , Reactor Trip/Safety

Injection Actuation?

A.InsertcontrolrodsinManual;toinsertnegative

reactivitybythemostdirectmanner

possible.B.InsertcontrolrodsinManual;toreduceormaintainRCS

pressuretopreventlifting

the Pressurizer

safety valves.C.PlaceEHCPumpsin

PULL-TO-LK

NON-A;to prevent uncontrolledcooldownofthe

RCS.D.PlaceEHCPumpsin

PULL-TO-LK

NON-A;to minimize secondary makeup requirements.

10

2007NRCExamSRO11.Giventhefollowingplant

conditions:*Areactortripand

safetyinjectionhaveoccurred.*RCS pressureis1050psigandlowering.*Tavgis 550°Fandlowering.

• Pressurizerlevelis65%andrisingrapidly.*ReactorBuildingpressureis2psigandrising.WhichONE(1)ofthefollowingdescribesthecauseofthisevent?

A.Letdownlinebreak.B.SBLOCAonanRCScoldleg.C.Stuckopen

pressurizer

PORV.D.Stuckopen pressurizersprayvalve.

11

2007NRCExamSRO

12.Giventhefollowing:*Theplantisat100%power.*Allsystemsarein

their normal alignments

.*AleakoccursintheLetdownHeat

Exchanger.Assumingnoactionbythecrew,whichONE(1)ofthefollowing

describestheeffect(s)ontheCCWSystem?

A.RM-L2A/B indication

rises.SurgeTankventvalve

PW-7096closeswhentheindicationreachesthe

ALERT level.B.RM-L2A1B indication

rises.SurgeTankventvalve

PW-7096closeswhentheindicationreachestheHIRADlevel.

C.SurgeTanklevellowers

.CCW Booster Pumpswilltriponlowsuctionpressure.D.SurgeTanklevellowers.

CCW Pumps will/ose suctionwhentheSurgeTank

empties.12

2007NRCExamSRO13.Giventhefollowingplantconditions:*ALOCAoccurredandRCS

pressurereached1380psig.*AllactionsofEOP-1.0were

performedasrequired.*Thecrewis

performing

EOP-2.1 , Post-LOCA Coo/down and Depressurization.*RCS pressure is currently1335psig.*RCS temperature

is currently 496°F.*TwoChargingpumpsarerunning

.*Thecrewis

evaluatingstopping1ChargingPump.Giventheaboveconditions,whichONE(1)

ofthefollowing

describes whether theChargingPumpmaybestopped,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

2007NRCExamSRO14.Giventhefollowingplant

conditions:*ThePlantisinMode3

.*APZRPORVbeginsleakingtothePRT.

• Pressurizer

pressureis985psig.*PRTpressureis

steadyat5psig.*PRT temperature

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

followingwouldbethe

approximate

MCB indicationonTI-463 ,RELIEFTEMP

OF?14

2007NRGExamSRO15.Giventhefollowingplantconditions:*The Reactorhastrippedfrom100%power.*"A"and"G" Service Water(SW)pumps were running.*Thecrew implemented

EOP-1.0, Reactor Trip/Safety

Injection Actuation, then transitionedtoEOP-1.1 , ReactorTripRecovery.

• MDEFW pumps startedonLo-LoSGlevelsafterthetr

ip.*Subsequently

,anSI actuatedduetoaLargeBreakLOGA.WhichONE(1)

of the followingdescribestheoperationof

equipmentasaresultofthe

SI?A.MDEFW pumpswilltripandberestartedbythesequencer.

Service Water Pumps"A"and"G"will

continuetorun.B.MDEFW pumps will continuetorun.Service WaterPumps"A"and"G"willtripandberestartedbythe

sequencer.G.MDEFWpumpswilltripandberestartedbythesequencer.

Service Water Pumps"A"and"G"willtripandberestartedbythesequencer.

D.MDEFW pumps will continuetorun.Service

Water Pumps"A" and"G"willcontinuetorun.15

2007NRCExamSRO16.Giventhefollowingplantconditions:*Aloadrejectionhasoccurredfrom100%power.*Allcontrol

systems respondedasdesigned.

• Power level isnowstableat70%.WhichONE(1)ofthefollowing

conditionswillexistduringthis

event?A.ChargingFlowControlValve,FCV-122

,willbethrottlingopen.

B.PressurizerBackupHeaterswillbeenergized.

C.PressurizerPORVswillbeopen.D.Letdown Backpressure

Control ValvePCV-145willbe

throttling

closed.16

2007NRCExamSRO17.Giventhefollowingplant

conditions

• Areactortriphas

occurredfrom100%power.*ReactorTrip

Breaker"B"remainsCLOSED.WhichONE(1)ofthe

followingdescribestheeffectontheSteamDumpSystem?

A.Thesteam dump valveswillopenandmaintainTavgat

55rF.B.Thesteam

dumpswillremainclosedfollowingthereactortripduetolossofthearmingsignal.C.Thesteam

dumpswillremainclosedfollowingthereactortripduetolossofthe'planttrip'

modulation

signal.D.Thesteam dump valveswillopenandmaintainTavgat

559°F.17

2007 NRC Exam SRO18.Which ONE (1)of the following describes the source of control power to Reactor Trip Breaker"B"and Reactor Trip Bypass Breaker"B"?Reactor Trip Breaker B Reactor Trip Bypass Breaker B A.B.C.D.125 VDC Bus 1HB 125 VDCBus1HB 120 VAC APN-5902 120 VAC APN-5902 125 VDCBus1HB 125 VDCBus1HA 120 VAC APN-5902 120 VAC APN-5901 18

2007NRGExamSRO

19.Giventhefollowingplantcond

itions:*Areactortriphas

occurred coincidentwithalossof

off-site power.*While performingactionintheEOPs,thefollowing

events occur:*RGS pressureis1700psigandlowering.*RB pressureis4.7psigandrisingslowly.*Threem inutes after these indicationsareobserved

, APN-5904failsand becomes de-energized.WhichONE(1)ofthe

following describestheeffect ,ifany ,onplant equipment aftertheAPNfailure?

A.TrainAandTrainBEGGS

equipmentisoperatingasrequired

TrainAandTrainBRBSprayPump

discharge valvesareopen.B.TrainAandTra

inBEGGS equipmentisoperatingasrequired;TrainAandTrainBRBSprayPump

dischargevalvesareclosed.G.TrainAEGGS

equipment is operatingasrequired;TrainBEGGS

equipment isNOTrunning;TrainAandTrainBRBSprayPump

dischargevalvesareopen

.D.TrainAEGGS

equipment is operatingasrequired

TrainBEGGS

equipment isNOTrunning;TrainAandTrainBRBSprayPump

dischargevalvesareclosed.

19

2007NRCExamSRO

20.Giventhe following plant conditions:*ALOCAhas occurred.*RCS pressureis200psig.*"A" Reactor Building SprayPumpisOutofService.

• Containment

pressure has exceededtheHigh-3 setpoint.*Train"B" PhaseAhasfailedtoactuate.*All other actuationsandTrain"A"ECCS

equipmentisrunningasrequired.*The most recent Chemistry sampleoftheRCS indicatedthatRCSactivityis

5X10-2 microcuries/ml

Dose Equivalent

Iodine.Assumingno

actionbythecrew,whichONE(1)ofthe

following describestheeffectontheplant?A.Containment

will exceeditsdesignpressure.B.Off-Site

releaseswillexceed

accident analysis assumptions.C.Only1 Containment

Isolation ValveineachPhaseA

penetrat ion w illbeclosed.D.Onlyhalfofthe

Containment

penetrationsrequiredfor

isolationwillreceiveisolation

signa ls.20

2007NRCExamSRO21.Giventhefollowingplantconditions:*Areactorstartupisin

progress.*SR Channel N-31 indicates 7X10 3 CPS.*SRChannelN-32

indicates7X10 3 CPS.*IR Channel N-35 indicates 8.7X10-6%power.*IRChannelN-36indicates

6.0X10-6%power.WhichONE(1)ofthefollowing

describes(1)theexistingplantcondition,(2)thestatusofP-6,and(3)theactionrequiredin

accordance

with AOP-401.8, Intermediate

RangeChannelFailure?

A.(1)N-36is undercompensated

(2)P-6shouldNOTbesatisfied;(3)maintain

powerstableuntilN-36isrepaired.

B.(1)N-36is overcompensated;(2)P-6shouldbe satisfied;(3)maintain

powerstableuntilN-36isrepaired.

C.(1)N-36is undercompensated

(2)P-6shouldbe

satisfied;(3)placetheunitinMode3untilN-36isrepaired

.D.(1)N-36is overcompensated

(2)P-6shouldNOTbesatisfied;(3)placetheunitinMode3untilN-36isrepaired.

21

2007NRCExamSRO

22.Giventhefollowingplant

conditions:*Theplantis

operatingat8%power.*ALossof Component Cooling Waterhasoccurred.*"A"RCP motor bearing temperatureis189°Fandrising slowly.*"A"RCP lower seal water bear ing temperature

is 226°Fandrisingslowly.*Thecrewhasentered

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

following actionsisrequired?

A.RCPmotorbearing

temperatureexceedsoperatinglimits

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

.B.RCPlowerseal

water bearing temperature

exceeds operating limits.Stop'A'RCPandinitiateaplant

shutdown lAW GOP-4B, Power Operation (Mode 1-Descending)

.C.RCP motor bearing temperatureexceedsoperatinglimits

.Tripthereactor

,stop'A'RCP,andgoto

EOP-1.0 , Reactor Trip/Safety

Injection Actuation.

D.RCPlowerseal

water bearing temperature

exceeds operating limits.Tripthe reactor , stop'A'RCP ,andgotoEOP-1

.0 , Reactor Trip/Safety

Injection Actuation.

22

2007NRCExamSRO

23.Giventhe following plant conditions:*TheplantisinMode3.*The following wide-rangepressuresareindicated:*PT-402*PT-403*PT-455A-1335psig-1350psig-1285psig*Subcooling

indication

on TI-499A and TI-499B indicatesthefollowing

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

following describesthecoreexit

temperatureusedto determineRCSsubcoolingforthe

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

2007NRCExamSRO24.Giventhefollowingplant

conditions:*A ReactorTripcondition

existedandtheReactorfailedtotrip.*RCS pressure now indicates2350psig.Assumingnoothereventsarein

progress ,whichONE(1)

ofthefollowingdescribesthe1)appropriateactionandthe2)reasonforthataction?

A.1)VerifyPZRPORVsandBlockValvesopen2)To increaseflowonFI-943

,CHGLOOPBCLO/HOTLEG

FLOW GPM B.1)Ver ifyPZRPORVsandBlockValvesopen2)To increaseflowonFI-110,EMERGBORATE

FLOW GPM C.1)PlacebothESFLSA(B)ResetstoNON-ESFLCKOUTS2)To increaseflowonFI-943

,CHGLOOPBCLO/HOTLEG

FLOW GPMD.1)PlacebothESFLSA(B)ResetstoNON-ESFLCKOUTS2)To increaseflowonFI-110,EMERGBORATE

FLOW GPM 24

2007NRCExamSRO

25.Giventhefollowingplant

conditions:*Theplantwasat100%power.*Areactortripand

safetyinjectionoccurred

.*R8CUs XFN-0064A and XFN-00648startedinSLOW.*While performingtheactionsofEOP-1.0, Reactor Trip/Safety

Injection Actuation, the followingalarmsarereceivedinthe

control room:*XCP-605-3-1, SWFRR8CU 18/28FLOLO*XCP-605-3-2, SWFRR8CU 18/28PRESSLOWhichONE(1)ofthe

followingchoicescontainsbothofthe

conditionsthatcouldeach

independently

cause these annunciatorstoalarm?A.SW8P"8" tripped;MVG-31118, R8CU 648/658TOINDCOOLINGgoing

CLOSED.8.SW8P"8" tripped;MVG-3109C, R8CU 648 OUTLETISOLgoing CLOSED.C.XFN-00648 (18 R8CUSSFAN)tripped;

MVG-3108C, R8CU 648 INLETISOLgoingCLOSED.

D.XFN-00648 (18 R8CUSSFAN)tripped;

MVG-3109D, R8CU 658 OUTLETISOLgoing CLOSED.25

2007NRCExamSRO26.Which ONE (1)of the following describes the power supplies that directly feed Containment

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

A.XSW1DA1 and XSW1DB1 B.XMC1 DA2XandXMC1 DB2Y C.XMC1 DB2XandXMC1 DA2ZD.XMC1 DA2ZandXMC1 DB2X 26

2007NRCExamSRO

27.Giventhefollowingplant

conditions:*ALOCAhasoccurred.*RCS pressureis450psig.*ReactorBuildingpressureis18psigandlowering

.*RWSTlevelislowering.

• ReactorBuildingSumplevelisrising.*"A" Reactor Trip Breakerremainedclosed.WhichONE(1)ofthefollowing

describestheoperationofthe

ReactorBuildingSpraysystemastheevent

continues?RBSprayPumpsuctiontotheRBSumpValves, MVG-3005AandB...A.are manuallyopenedwhenRWSTlevel

reaches its setpoint.RB Spray PumpsuctionvalvesfromRWST,MVG-3001AandB

, are manuallyclosedwhen

MVG-3005AandBarefullyopen.

B.automaticallyopenwhenRWSTlevelreachesitssetpoint.RBSprayPumpsuctionvalvesfromRWST,MVG

-3001AandB, automaticallyclosewhen MVG-3005A andBarefullyopen

.C.are manuallyopenedwhen

ReactorBuildingSumplevelreachesitssetpoint.RBSprayPumpsuction

valvesfromRWST , MVG-3001AandB,are manually closed whenandBarefullyopen.

D.automaticallyopenwhen ReactorBuildingSumplevel

reachesitssetpoint.RBSprayPumpsuctionvalvesfromRWST, MVG-3001AandB, automatically

close when MVG-3005AandBarefullyopen.

27

2007NRCExamSRO28.Withtheunitat100%power,whichONE(1)ofthe

following describesthepotentialconsequenceof

PCV-444C ,PZRSprayValve,failingopen?

A.LossofPZR pressurecanresultinanunwarrantedOPDeltaTrunbackandreactor

trip.B.PZRpressurewillremainstableasPZRheaterswill

compensateforthepressure

reduction.C.LossofPZR pressuremayresultinsteamformationinthereactorvesselheadandSGtubes.I D.LossofPZR pressurecanresultinanunwarrantedOTDeltaTrunbackandreactor

trip.28

2007NRCExamSRO

29.WhichONE(1)ofthe

followingdescribesthepurposeandfunctionoftheReactor

Building Charcoal Cleanup Units?Designedfor...

A.primary meansoflongtermpost

accidentiodineremovalfromtheRBatmosphere.Dischargeis

alignedtotheRBPurgesystemexhaust.B.primarymeansoflongtermpost

accidentiodineremovalfromtheRBatmosphere.DischargeisalignedtotheRB

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

Discharge isalignedtotheRBPurgesystem

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

.DischargeisalignedtotheRB

atmosphere.

29

2007NRCExamSRO

30.Giventhe following plant conditions:*Theunitwas

initially operatingatfull power.*Alossof ALL offsite poweroccurredin

conjunctionwithasteam

generatortuberupture.*All safeguards

equipment functionedasrequi red.*The following plant conditionsnowexist:*Ruptured S/G pressure=1100psig,stable*CoreexitTC=505°F, slowly decreasing*RCS Pressure=1600psig , stable*PZRLevel=4%,stable*TotalSIFlow=600gpm*TheRCShasbeencooleddowntotarget

temperature

.*In accordancewithEOP-4.0, Steam GeneratorTubeRupture,theROopensonePZRPORV.*Soon after openingthevalve,the

operator observes that all channels ofPZRlevelare

rapidly increasing

.*ECCSflowhas

increasedfrom600gpmto650gpm.WhichONE(1)

of the followingisthecauseofthis

indication?

A.PZRlevel instrumentsarenot calibrated

for temperatureslessthan600°F.

B.Safety injectionflowisdrivingtheRCStoawater-solid

condition.C.Voidinginthe

reactor vesselheadisforcingwaterupthesurgeline.

D.Backflowhasbeen establishedfromtherupturedS/GtotheRCS.

30

2007NRCExamSRO31.Giventhefollowing

plant conditions:*ALargeBreakLOCAhasoccurred.

ReactorBuildingH2

concentrationwasat2%andrising.*'A'Hydrogen

Recombiner

is INOPERABLE.WhichONE(1)ofthe

following describestheeffectontheremovalofHydrogenfrom

Containment?

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

ContainmentSprayisplacedinserviceinadditiontothe

Recombiner

.31

2007NRCExamSRO32.WhichONE(1)ofthefollowingdescribesafeatureoftheSpentFuelPool

and/orCoolingsystem

thatwillmaintainradiationdoselevelsat

acceptablelimitsduringplant

operat ions?A.SpentFuel CoolingPumpswilltriponlowsuctionpressurepriortoSpentFuelPool

level dropping below 460'6".B.Boron concentration

is maintainedsothatSpentFuelPool

Keffislessthan0.95andSpentFuelPoolRadiationlevelsare

maintainedlessthan2.5

mr/hratthesurfaceofthepool.

C.Anti-siphoningholesinthecoolingsystemsuctionandreturn

lines ensures thatSpentFuelPoollevelwillnotdropbelow460'6".

D.InterlocksontheSpentFuelPool

ManipulatorCranepreventspentfuelassemblies

from travelling

closerthan23feetfromthe

surfaceofthe SpentFuelPool.32

2007NRCExamSRO

33.WhichONE(1)ofthefollowing

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

SGWLC System ResponseLagcircuitonSGlevelinput

minimizes fluctuations

Programmed

DIPacrosstheFRV

minimizes fluctuations

Programmed

DIPacrossthe FRV minimizes fluctuationsLagcircuitonSGlevelinputm

inimizes fluctuations

33

---

2007NRCExamSRO34.Giventhefollowingplantconditions:*TheplantisinMode6,corereloadisinprogress.*Afuel assemblyisbeinginsertedintothecorewhendownwardmotionstops

.*The RefuelingSROnotesthefollowing:*The SLACKCABLElightisON*The LOWER SLOWZONElightis

OFF*The GRIPPERTUBEDOWNlightisOFFWhichONE(1)

ofthefollowing

describesthereasonthatdownward

movementstoppedandthe

subsequent

operationrelatedtothe

interlock?

A.Totalloadfellmorethan

150-300#belownominalfullload;bypassingtheinterlockisnotpossible.B.Thefuel assembly approached10"fromthebottomofthecore

bypassingtheinterlockisnot

possible.C.Totalloadfellmorethan

150-300#belownominalfullload

bypasstheinterlocktoallowthe assemblytobefullyinserted.

D.Thefuel assembly approached10"fromthebottomofthecore;bypasstheinterlocktoallowthe

assemblytobefullyinserted.

34

2007NRCExamSRO35.Giventhefollowingplant

conditions:

Reactor poweris75%.RCSleakratedataisasfollows:*TotalRCS leakagerateis9.1 gpm.*LeakagetoPRTis7.0gpm

.*Leakagetothe Reactor CoolantDrainTankis1.3gpm

.*Total primary to secondaryleakageis0.33gpm.*SG1-0.09gpm*SG2-0.17gpmSG3-0.07 gpmWhichONE(1)ofthe

following describesRCSleakageinrelationto

TechnicalSpecificationlimits?

A.Identified

leakage exceedstheTSlimitB.Unidentified

leakage exceedstheTSlimitC.Primaryto

Secondary leakageexceedstheTSlimitD.AllRCS leakageiswithinTSlimits

35

2007NRCExamSRO

36.Giventhefollowingplantconditions:*TheunitisinMode3.*Asteamlinebreakhasoccurredon"A"SteamLineinthe

Reactor Building.WhichONE(1)ofthefollowing

describestheplantresponsetothisevent?

A."A"MainSteamLine

pressurewilldrop."B"and"C"MainSteamLinepressureswillremain

constant.AllMSIVswillclosewhenatleast2

Containment

pressure transmitters

indicate3.6psig.B."A"MainSteamLine

pressurewilldrop."B"and"C"MainSteamLinepressureswillremain

constant.AllMSIVswillclosewhen"A"MainSteamLinepressureindicateslessthan675psig.C.All3MainSteamLine

pressureswilldrop.AllMSIVswillclosewhenatleast2

Containment

pressure transmittersindicate3.6psig

.D.All3MainSteamLine

pressureswilldrop.AllMSIVswillclosewhenatleast2MainSteamLines

indicatelessthan675psig

.36

2007NRCExamSRO37.WhichONE(1)

of the following describes the purposeofC-9, Condenser Ava ilability,andC-16 , Condenser Pressure, permissive

signals?A.C-9 prevents2steam dump valves from operating during conditionsthatcould damage the condensers.C-16armsALL

condenser dumpvalveswhen

condenser is below4.5"Hgabsand

adequate eire water pumps are available.B.C-9armsALL

condenser dump valves when condenser is below7.5"Hgabsand

adequate eire waterpumpsareavailable.

C-16 prevents2steam dumpvalvesfrom

operating during conditionsthatcould damage the condensers.C.C-9 anticipates

condenser heat load problems by blocking 2 condenser dumpvalvesat7.5"Hgabs.

C-16 prevents ALL condensersteamdumpvalvesfrom

operatingduringconditionsthatcould damage the condensers.D.C-9 prevents ALL condenser steamdumpvalvesfrom

operatingduringconditionsthatcould damage the condensers.

C-16 anticipates

condenserheatload problems by blocking 2 condenser dumpvalvesat4.5"Hgabs

.37

2007NRCExamSRO38.Giventhefollowingplantconditions:*Theplantisoperatingat100%power.*A FeedwaterLineBreakoccursatthepipingconnectionto"A"SG.WhichONE(1)ofthe

following describestheeffectofthisevent?

A.RCS temperaturerisespriortoreactortrip

.SG"A" continues to depressurize

afterFWIVclosure

.B.RCS temperaturelowerspriortoreactortrip.SG"A" continues to depressurizeafterFWIVclosure.

C.RCS temperatureslowerspriortoreactortrip.SG"A" pressure stablilizes

afterFWIVclosure

.D.RCS temperaturerisespriorto

reactor trip.SG"A"pressure

stablizesafterFWIV closure.38

2007NRCExamSRO39.Giventhefollowingplantconditions:*AStation Blackouthasoccurred.*Thecrewis

restoring off-site powertoBus1DAthroughthenormalfeed.Priortoclosingthenormal

feeder breakertoBus1DA ,whichONE(1)ofthefollow

ingsetsofactionsmustbe

performed , in accordancewithAOP-304.1

, Loss ofBus1DA with Diesel Unavailable?

A.De-energizeTrain"A" ESFLSEnsureBus1DA

TRANSFERINITSwitchisinOFF

B.De-energizeTrain"A" ESFLSEnsureBus1DA

TRANSFERINITSwitchisinON

C.Reset NON-ESF LCKOUTS&AUTO-START

BLOCKSEnsureBus1DA

TRANSFERINITSwitchisinOFFD.Reset NON-ESF LCKOUTS&AUTO-START

BLOCKSEnsureBus1DA

TRANSFERINITSwitchisinON

39

2007NRCExamSRO40.Giventhefollowingplant

conditions:*Alossof off-site powerhasoccurred.*BothEDGshave

respondedasdesigned.

• Subsequently, safetyinjectionoccurs

.*Thefollowing

conditionsexiston"A"EDG:

• Frequency59.9Hz.*Voltage7150Volts*KW Output2600KWRBPressurereachesan

actuation setpointrequiringthestartof"A"RBSpraypumpLoadsstabilize

.....WhichONE(1)ofthe

followingdescribesthestatusof"A"EDG?

A.Alllisted parametersarewithinlimits.B.Frequencyis

belowthelimit.C.Voltageis

belowthelimit.D.Outputexceedsthe

continuousKWrating.40

---

2007NRCExamSRO41.Giventhefollowingplantconditions:

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

, powerhasbeenstabilizedbetween12and15%

.*PreparationsarebeingmadetorolltheMain

Turbineto1800rpm.

• Reactor powerindicatesthefollowing

• IRN-35-1X101%.

• IRN-36-1X101%.

• PRN-41-15%.

• PRN-42-14%

.*PRN-43-14%

.*PRN-44-14%.

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

describestheeffectontheunit?

A.APowerRangeRodStop(C-2)signal,withnochangeinreactor

power.B.Areactortripduetothe

deenergization

of IntermediateRangeChannelN-35.C.Areactortripduetothe

deenergization

of IntermediateRangeChannelN-36.

D.An IntermediateRangeRodStop(C-1)signal

,withno changeinreactorpower.

41

2007NRCExamSRO42.Giventhefollowingplant

conditions:*Theplantis

operatingat100%power.*Thefollowing

annunciatorsarereceivedinthecontrolroom:*XCP-636,4-6,DCSYS

OVRVOL T/UNDRVOL T*XCP-637,1-5,INV

3/4 TROUBLE Inverter output voltageindicates120vac

.Assuming NO otheralarmsarereceived,whichONE(1)ofthefollowing

describes thecommoncauseofboth

of the alarms?A.Lossof AlternateSource1FB.B.LossofNormal

Source1DB2Y.C.LossofvoltageonBus1HB.

D.Inverter has transferred

to AlternateSource1FB.42

2007NRCExamSRO43.Giventhefollowingplant

conditions:Theplantis

operatingat100%power.Thefollowingalarmisreceived:

• XCP-624-1-5

,SGALVLDEV*TheRO determinesthatSG"A"levelisrisingslowlyon

L1-474,475,and476.*SG"B"and"C"levelsarestable.WhichONE(1)ofthe

following describesthecauseofthealarmandtheaction

required?Alarmwasreceivedona

...A.5%deviationfrom

programduetoa Feedwater Control Valvefailure;Place"A" Feedwater Controlvalveinmanualandrestoreleveltonormal.

B.5%deviationfrom

programduetoaSteamFlowinputto"A"SGlevelcontrolfailinglow;Selectthe

alternatefeedflowandsteamflowinputs.C.10%deviation from programduetoa Feedwater Control Valvefailure;Place"A" Feedwater Controlvalveinmanualandrestoreleveltonormal.

D.10%deviationfromprog ramduetoaSteamFlowinputto"A"SGlevelcontrolfailinglow;

Select the alternatefeedflowandsteamflowinputs.

43

2007NRCExamSRO44.WhichONE(1)ofthe

following conditionswillresultinthemost

Emergency Feedwater Systemflowrequiredto

maintainSGlevels constant following a reactor trip?A.B.C.O.Core Burnup 1,000 MWO/MTU 1 ,000 MWO/MTU 10,000MWOMTU 10,000 MWO/MTU Initial Power Level 10%100%10%100%44

2007NRCExamSRO45.Giventhefollowingplant

conditions

• Theplantisat100%

powerduringanA1

maintenance

week.*APN-5901hasbeen

transferredtoAPN-1FAwhileworkisinprogresson

XIT-5901.*Thenormal

feeder breakerforbus1DAtripsopen

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

following describes the subsequent

operationofthe"A"Train

ESFLS?A.Output1willshedloadsandtheESFLSwillgothroughitsnormalsequence.B.Output1willshedloads,butthentheESFLSwillbe

preventedfromoperating.C.Output1willNOTshedloads,buttheESFLSwillgothroughitsnormalsequence.D.Output1willNOTshedloadsandtheESFLSwillbe

preventedfromoperating.

45

2007NRCExamSRO46.WhichONE(1)ofthe

followingdescribesthe

availability

of Channell(TrainA)120VACvital safeguards

powerduringalossofthe

115KVlinefromtheParrGenerating

Complex?A.Isinitially

availablefromBattery1Athrough

inverter XIT-5901, then automaticallyreturnstothenormal

sourceafterDiesel

Generator"A"starts.B.Thestaticswitch

initially transfersthesupplyto1FA,then

automaticallyreturnstothenormal source after Diesel Generator"A"starts.

C.Isinitially

available from Battery1Athrough inverter XIT-5901,thenis manuallyreturnedtothenormal

sourceafterDiesel

Generator"A"starts.D.Thestaticswitch

initially transfersthesupplyto1FA,thenis

manuallyreturnedtothenormal source after Diesel Generator"A"starts.

46

2007NRCExamSRO

47.Theplantisat100%power

.Alossof125VDCcontrol

powertothewillrequireentrytoEOP-1.0

, Reactor Trip/Safety

Injection Actuation.

A.FWBP breakersB.MSIVsC.RCPbreakers

D.PZRSprayValves

47

2007NRCExamSRO48.Giventhefollowingplantconditions:*Alossofoff-site

powerhasoccurred.*BothEDGsstartasrequired.WhichONE(1)ofthe

followingdescribestheoperationoftheEDGRoomVentilation

system?Automaticallystartwhen...

A.DieselRoom

temperatureexceeds88°F,tomaintainroom

temperaturebelowthe Technical Specificationlimitof120°F.B.theassociatedDiesel

Generatorstarts,to maintain room temperaturebelowthe Technical Specificationlimitof88°F.C.DieselRoom

temperatureexceeds72°F,tomaintainroom

temperaturebelowthe Technical Specificationlimitof88°F

.D.theassociatedDiesel

Generator starts , to maintain room temperaturebelowthe Technical Specificationlimitof120°F.

48

2007NRCExamSRO49.Giventhe

following plant conditions:

• Emergency Diesel Generator"A"is paralleledtoits associated

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

following describes the operationofthe diesel generator voltage control switch?A.Loweringthe

voltage control setpointwillcausethe

generatortopickupalargershareoftherealload.B.Raisingthe

voltage control setpointwillcausethe

generatortopickupalargershareoftherealload.C.Loweringthe

voltage control setpointwillcausethe

generatortopickupalargershareofthe

reactive load.D.Raisingthe

voltage control setpointwillcausethe

generatortopickupalargershareofthe

reactive load.49

2007NRCExamSRO50.Giventhe

following plant conditions:*AlossofRB

Instrument

Air has occurred.*RB Instrument

Air header pressure is currently94psigand lowering.Assuming no operator action , whichONE(1)ofthe

following describes the response oftheAir System and why?RB Instrument

Air header pressure decreasesuntil...A.PVA-2659, INSTAIRTORB AIR SERV , automatically

opensat90psigtoensureanair supply for AOVs inside the Reactor Building.B.PVA-2659, INSTAIRTORBAIR

SERV , automatically

opensat93psigtoensureanair supply for AOVs inside the Reactor Building.C.PVT-2660, AIR SPL YTORB , closesat90psigto

isolatetheRB headertoavoidalossof Instrument

Air outside the Reactor Building.D.PVT-2660, AIR SPLYTORB,closesat93psigto

isolatetheRB headertoavoidalossof Instrument

Air outside the Reactor Building.50

2007NRCExamSRO51.Giventhefollowingplant

conditions

• TheplantisinMode6.ReactorBuildingPurgeisinoperation

.*Refueling

activitiesareinprogress.*Aspentfuel

assemblyisdroppedinthecavity.

• Containment

radiation monitor indicationsareallrising.WhichONE(1)ofthe

following describestheradiation

monitorsthatwillinitiateisolationofallorpartofthe

Containment

Purge?RM-A4,RBPurge

Exhaust Particulate(Iodine)(Gas)Atmos

monitor...A.ONLY.B.ANDRM-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

2007NRCExamSRO52.Giventhe

following plant conditions:*An immediate dischargetothe penstocksfromboth Waste Monitortanksis required.*Current conditionsareasfollows.*RM-L5andRM-L9areoutof

service*Fairfield

Hydroisinthe"pumping" mode.WhichONE(1)ofthe

following statements

will provide the MINIMUM conditions

necessary for monitor tank release?A.EitherRM-L5or RM-L9 mustberestoredto

operabil ity prior to release.B.BothRM-L5and

RM-L9 mustberestoredto

operability

prior to release.C.TheFairfield

Hydro must converttothe generatingmodeand redundant samples performed prior to release.Two independent

qualified individuals

must verify release calculations

and valve lineups.D.The Fairfield Hydro must converttothe generatingmodepriorto

releaseandeitherRM-L5orRM-L9

must be restored to operability

.Two independent

qualified individuals

must ver ify release calculationsandvalve lineups.52

2007NRCExamSRO

53.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 radiation alarm on RM-A 1, Control Bldg Supply Air?A.Both XFN-32A&Bandboth XFN-30A&Bstart,all

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

mixedwithasmall

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

XFN-30A&Bstart,all

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

XFN-30A&Bstart, returnairis mixedwithasmall

amount of makeup air.53

2007NRCExamSRO54.Giventhe

following plant conditions:*The plantisin Mode 5.*RHRTrainAisin

service.*RCS temperatureis158°F.*RCS pressureis175psig.*Subsequently,aLoss of Service Water occurs.*Thecrewisperformingactions

contained in AOP-117.1,TotalLoss of Service Water.*NEITHER Service Waterloopcanbe restored.WhichONE(1)ofthe

following describes the effectontheRHR System,andthe procedure that will mitigate the event?A.Stabilize RHR/RCS system temperature

using steam dumps lAW GOP-5, PlantShutdownMode

3toMode5.Goto AOP-115.3, Loss ofRHRwiththeRCSIntact, for long-term mitigation.

B.Stabilize RHR/RCS system temperature

using steam dumps lAW GOP-5, PlantShutdownMode

3toMode 5.Continue using AOP-117.1 ,TotalLoss of Service Water, for long-term mitigation.

C.RHR/RCS system temperaturewillriseasa

resultofaloss of cooling to Component Cooling Water.Goto AOP-115.3 , Loss ofRHRwiththeRCSIntact.

D.RHR/RCS system temperaturewillriseasa

resultofaloss of cooling to Component Cooling Water.Continue using AOP-117.1,TotalLoss of Service Water.54

2007NRCExamSRO55.WhichONE(1)

of the following providestheelectrical

power supplytothe Supplemental

Air Compressor?

A.XSW1DA1 8.XSW1D81C.XSW1A1 D.XSW181 55

2007NRCExamSRO56.Giventhefollowingplant

conditions:*TheF ire ProtectionSystemactuatedduetoaMain

Transformer

Fire.*System pressure droppedto80psigbefore

recoveringduetotheactuationof

necessary equipment.*Thefireisout.*Thedelugevalveisisolatedandreset.WhichONE(1)ofthe

followingdescribesthe

equipmentthatisrunning

,andthemethodofshuttingthe

equipment down?A.ONLY theMotorDrivenFirePumpisrunning;mustbe

stopped locally.B.ONLYthe MotorDrivenFirePumpisrunning

maybe stoppedlocallyorinthecontrolroom

.C.TheMotorDrivenand

EngineDrivenFirePumpsarerunning

.Bothmustbestoppedlocally.D.TheMotorDrivenand

EngineDrivenFirePumpsarerunning.TheMotorDrivenPumpmaybe stopped locallyorinthecontrolroom,the

EngineDrivenPumpmustbestoppedlocally

.56

2007NRCExamSRO57.Giventhefollowingplant

conditions

• ALOCAhasoccurred.*Safety Injectionisactuated

.ReactorBuildingpressure

indicates14psigandrisingslowly.*While performingactionsofEOP-1.0, Reactor Trip/Safety

Injection Actuation ,thefollowingvalvesindicateOPEN:*RCPSL WfRISOL8100*LTDNISOL8152*RBAIR SERVISOL2660WhichONE(1)ofthefollowing

describesthefailurethathas

occurredandtheMINIMUMaction

necessary to mitigate the condition?

A.PhaseAhas partiallyfailed.Place

eitherPhaseA actuation switchesinthe ACTUATE position.B.PhaseAhas partiallyfailed.PlacebothPhaseA

actuation switchesinthe ACTUATE position.C.PhaseBhas

partially failed.Place eitherPhaseB actuation switchesinthe ACTUATE position.D.PhaseBhas

partially failed.PlacebothPhaseB

actuation switchesinthe ACTUATE position.57

2007NRCExamSRO

58.Giventhefollowingplant

conditions

• Thereactorhas

tripped.SafetyInjectionisactuated.*AnRCS cooldownisinprogressin

accordancewithEOP-2.1, Post LOGA Goo/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°FAtwhichtimewastheTech

SpecRCSCooldownratelimit

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

2007NRCExamSRO59.Giventhe

following plant conditions:*A LOCA outside containment

has occurred.*Thecrewis

performing

the actions in EOP-2.5,LOCAOutsideContainment.WhichONE(1)

of the following actionswillbe attempted to isolatethebreakandwhichindicationisusedto

determineiftheleakhasbeenisolatedin

accordance

with EOP-2.5?A.Isolatelow

pressure Safety Injection piping.RCS pressure is monitored, because SI flow will repressurizetheRCSwhenthebreakis isolated.B.Isolatelow

pressure Safety Injection piping.PZRlevelismonitored,becausewhenthe break is isolated, RCS inventory willrapidlyrise.C.Isolatehigh

pressure Safety Injection piping.RCS pressure is monitored, because SI flow will repressurizetheRCSwhenthebreakis isolated.D.Isolatehigh

pressure Safety Injection piping.PZRlevelismonitored,becausewhenthe breakisisolated,RCS

inventory willrapidlyrise.

59

2007NRCExamSRO60.WhichONE(1)ofthe

following describesthereasonthataREDconditionontheIntegrityCSF

StatusTreemay developwhileperformingactionsofEOP-14.1

, Response to DegradedCoreCooling?

A.CoreExit Thermocouple

temperature

will decreaserapidlywhenLowHeadSIPumpsarestartedandSIflowisinitiated

.B.CoreExit

Thermocouple

temperature

will decreaserapidlywhenSG

depressurizationandSI Accumulatorinjectionoccur.C.RCSColdLeg

temperaturewilldecreaserapidlywhenLowHeadSIPumpsarestartedandSIflowisinitiated.D.RCSColdLeg

temperaturewilldecreaserapidlywhenSG

depressurizationandSI Accumulator

injection occur.60

2007 NRC Exam SRO61.Giventhe

following plant conditions:*A LOCA has occurred.*The crew is performing

actions containedinEOP-2.0, Loss of Reactor or Secondary Coolant.*The following conditions

currently exist:*Integrity-RED*Containment-RED*Subcriticality

-ORANGE*Core Cooling-ORANGE*Inventory-YELLOW*Heat Sink-YELLOWWhichONE(1)

of the following describes the correct procedure flowpath for these conditions?

A.EOP-17.0 , ResponsetoHigh Reactor Building Pressure , followed by EOP-16.0, Response to Imminent Pressurizer

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

Thermal Shock Condition , followed by EOP-17.0, ResponsetoHigh Reactor Building Pressure.C.EOP-14.1, Response to Degraded Core Cooling , followed by EOP-16.0, Response to Imminent Pressurizer

Thermal Shock Condition.

D.EOP-16.0, Response to Imminent Pressurizer

Thermal Shock Condition , followed by EOP-14.1 , Response to Degraded Core Cooling.61

2007NRCExamSRO

62.Giventhefollowing

plant conditions:*Areactortriphasoccurredduetoalossofoffsitepower.*Thecrewis

performingactionsofEOP-1.4, Natural CirculationCooldownwithSteamVoidinVessel.*Duringtheevent,RCPsealcoolingwaslost,but

subsequently

restored.*The operatingcrewispreparingtoinitiatetheRCScooldown.Thefollowing

conditionsareindicated:*RVLlSNRlevelis89%.*RCS subcoolingis60°F.*PZRLevelis72%andstable

.WhichONE(1)

of the followingactionsisrequiredin

accordancewithEOP-1.4?

A.UsePZR Heaters as necessary to saturate PZR water and continueinEOP-1.4.

B.Initiate Safety InjectionandgotoEOP-1.0, ReactorTripOr Safety Injection.C.StartaRCPandgotothe

applicableportionofthe

appropriate

GOP.D.ReturntoEOP-1.3, Natural Circulation

Cooldown.62

2007NRCExamSRO63.Giventhefollowingplantconditions:*ALOCAhasoccurred.*DuetolowRHRSumpLevel,thecrewhas

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

.*All automatic actions occurredasdesigned.*TwoChargingpumpsandtwoRHRpumpsarerunning.*BothRB SprayPumpsarerunning.*RHR,Charging,andRB

Spraypumpampsandflowarestable.*RWSTlevelis

approximately5%andcontinuestolower.WhichONE(1)ofthe

following describeshowtheCharging,RHR,andRBSpraypumpsshouldbe

operated in accordancewithEOP-2.4?ChargingPumpsRBSprayPumpsRHRPumps A.StopBOTHLeaveBOTHrunningLeaveBOTHrunning

B.StopONEStopBOTHStopONE C.StopBOTHStopBOTHStopBOTH D.LeaveBOTHrunningLeaveBOTHRunningStopONE

63

2007NRCExamSRO

64.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

coo/downratesabove100°Fper

hour may potentiallyresultin pressurized

thermal shocktothepressurizer.C.LossofSG

inventory may ultimatelyresultintheRCS

Pressure SafetyLimitbeing

exceeded.D.LossofSG

inventory may ultimatelyresultinthe

Reactor Core Safety Lim it being exceeded.64

2007NRCExamSRO65.WhichONE(1)

of the followingdescribesthestatusofRB

ventilationandRBCU'suponcompletion

of the actionscontainedinEOP-17.2, ResponsetoHigh Reactor Building Radiation Level?A.RBPurge isolatedAllRBCUfansin

SLOW B.RBPurge isolatedRBCUfans selectedonswitchRBCUTRAIN

AlB EMERG ,runningin SLOW C.RBMiniPurgein

serviceAllRBCUfansin

SLOW D.RBMiniPurgeinserviceRBCUfans selectedonswitchRBCUTRAINAlBEMERG

,runningin SLOW 65

2007NRCExamSRO

66.Inaccordancewith

OAP-100A, Communication,whichONE(1)ofthefollowing

communicationsshouldusethe

phonetic alphabet?A.Communications

involvingsafetysystemtrains

.(Train Alpha)B.Communications

involving manipulationofplant components.(AlphaCharging

Pump)C.Communications

describing

ContainmentIsolation(PhaseBravo)D.All communicationsthatarenot

'information

only'.66

2007NRCExamSRO67.Giventhe

following plant conditions

• The plantisat46%power and increasing

lAW GOP-4A , Power Operation (Ascending)at3%perhour

.*Alossof Feedwater occurs.*All threeS/GNR levelsareat5%and

lowering.*Itisnow60

seconds later.WhichONE(1)ofthe

followingisthe expected responseofthe ATWS Mitigation

System Actuation Circuitry (AMSAC)?A.AMSAC will NOT actuate becauseitisnotarmed

.B.AMSAC will TRIP the reactor and START the EFW pumps.C.AMSAC will NOT actuate becausethetime delay on reactor powerhasnottimed

out.D.AMSACwill TRIPthemain turbine and START the EFW pumps.67

2007NRCExamSRO68.Giventhefollowingplant

conditions:*AnRCSleakisinprogress.*Thecrewis

performing

the appropriateAOPforthe plant condition.*Letdownisisolated

.*Chargingflowis

maximized.*RCS pressureis1990psigandlowering.

• Reactor Building pressureis1.8psigandrising.

Pressurizerlevelis18%andlowering

.*VCTlevelis15%andlowering.WhichONE(1)ofthe

following describesthestatusofthe

plantandtheaction

required?A.AnRPS setpointhasbeen exceeded.TriptheReactorandinitiateSafetyInjection

when immediateactionsofEOP-1

.0havebeen completed.

B.AnRPS setpointhasbeen exceeded.Tripthereactorand

concurrently

performactionsofthein-useAOPwhen

immediateactionsof EOP-1.0havebeen completed.C.AnRPS setpointhasNOTbeen

exceeded,TriptheReactor,performthe

immediate actionsofEOP-1.0,theninitiateSafetyInjection.

D.AnRPS setpointhasNOTbeen

exceeded,TriptheReactor,performthe

immediate actionsofEOP-1.0,continueto

implementtheAOPconcurrently,then

initiate SafetyInjectionwhen

Pressurizerlevelis<12%

.68

2007NRCExamSRO69.Theunitisat100%power.Allsystemsareinnormal

alignments.WhichONE(1)ofthe

following activitiesrequiresentryintoa

technical specificationLCOaction statement?

A.CCWPumpB mechanicalsealrepair.B.ChargingPumpAremovalfromserviceforoilchange.C.BoricAcid

TransferPumprecircvalveleakrepair.D.RHRHeat Exchanger Dischargeflowcontrolvalverepair.

69

2007NRCExamSRO70.WhichONE(1)ofthe

following describes the MINIMUM Source Range Nuclear Instrumentation

requ irement that mustbemetpriorto

off-loadingfuelfromthe

reactor vessel?Visual in control room Audibleincontrolroom

Audible inRB A.B.C.D.1 2 2 2 1 1 2 2 1 1 1 2 70

2007NRCExamSRO

71.Giventhefollowing

information:*A27yearoldnewV.C

Summer employeehasafully completedNRCForm4anda2007radiationexposurehistoryasfollows

2650 millirem from previous employment

with ProgressEnergyin2007.*110milliremsincebecomingaV.C.Summer employee.WhichONE(1)ofthe

followingdescribestheMAXIMUM

ADDITIONALexposuretheemployeemay

receivepriortoreachinghisMAXIMUMAdmin

istrativeDoseControlLimit,includingany

applicable

extensions

, lAW HPP-0153, Administrative

Exposure Limits?A.1240milliremB.1350millirem

C.2240milliremD.2350millirem

71

2007NRCExamSRO

72.Giventhefollowingplant

conditions

• AGeneral Emergency exists.*TheTSCis manned.*AvalveintheAuxBuildingmustbeclosedtoprevent

damagetovaluablesafetyrelated

equipment.Radiationlevelsare

extremely high.WhichONE(1)ofthe

following describesthemaximumdosethatisallowedtoperformthisoperationand

whose permissionisrequired?Anindividualmayreceive

...A.Upto10Remwith

permissionfromtheDutySSB.25Rem,ormore,with

permissionfromtheDutySSC.Upto10Remwith

permissionfromtheEDD.25Rem,ormore,with

permissionfromtheED 72

2007NRCExamSRO73.Giventhefollowingplantconditions:*Areactortripandsafetyinjectionhaveoccurred.*Off-Site power islost subsequenttosafetyinjectionactuation.

• Equipment failures during performance

of EOP-2.0 , Loss of Reactor or Secondary Coolant,resultedinthefollowingconditions

• Bus1DAis de-energizedduetoafault.*CSF StatusTreesind icateasfollows:*Subcriticality*CoreCooling*HeatSink*Integrity*Containment

• Inventory GREEN ORANGE RED GREEN YELLOW YELLOWWhichONE(1)ofthe

following describes the requirementforCritical

Safety FunctionStatusTree

Monitoring

in accordance

with OAP-103.04, EOPIAOPUser'sGuide?

A.Continuous

monitoringisrequired.B.Monitorevery5-10

minutesunlessachangeinstatusoccurs.C.Monitor every10-20 minutesunlessachangeinstatusoccurs

.D.Monitoredfor

information

only.73

2007NRCExamSRO74.Giventhe

followingplantconditions:

T=OAfireisoccurringintheAuxBuilding436'.T+2FireBrigade

Leaderreportstothescene.

T+15 NotificationofUnusualEventdeclared.

In accordancewithEPP-013, Plant Fire,who,bytitle

, is coordinatingthefirefightingeffortswiththeFireBrigadeLeader?

A.Shift Supervisor

B.Emergency DirectorC.OSC SupervisorD.HealthPhysicsShift

Leader 74

2007NRCExamSRO75.Giventhefollowingplant

conditions

• TheUnitisinMode5.*RCSDra inDowntoMidLoopisinprogressin

preparationforweldingonaHotLegopening

.RHRPumpAisinservice

.*Duringthedraindown

,RHRampsand

discharge pressurebeginfluctuating

erratically.*ThecrewentersAOP-115.1

,RHRPump Vortexing.*The drain-downisstopped.WhichONE(1)ofthe

following describestheFIRSTactionthatwillberequiredinaccordancewith

AOP-115.1?

A.ReduceRHRflow.

B.AligntheRHRPumptotheRWST.C.RaiseRCSlevel.D.Ventthe operatingRHRloop.75

2007NRCExamSRO

76.Giventhe following plant conditions

• The plantisat50%power.*ALL controlsarein automatic.*ALL MCB switchesarein their normal positionforthis power level.*An event occurs resultinginthe following indications:*RCS Tavg rising approximately

5°F above Tref.*Reactor Powerisrising.*First Stage Pressure Transmitter

PT-446 indicates330psigandstable.

• First Stage Pressure Transmitter

PT-447 indicates800psig.*Control BankDis withdrawingat16 steps per minute.WhichONE(1)of

the following describes the procedure entry required to mitigate theeventandthe

reason for the procedural

actions taken?A.AOP-403.3 , Continuous

ControlRodMotion;

to minimize the impact on power distribution

limits.B.AOP-403.3, Continuous

Control Rod Motion;to preventanoutof spec negative DELTA-I.C.AOP-401.7 , Turbine First Stage Pressure Transmitter

Failure;to minimize the impact on power distribution

limits.D.AOP-401.7 , Turbine First Stage Pressure Transmitter

Failure;to preventanoutof spec negative DELTA-I.76

2007NRCExamSRO

77.Giventhe followingplantconditions:*Followinga

turbinerunback,thecrewisstabilizingtheplantin

accordance

with the appropriate

AOP.*ControlBank

"0" Group Countersareat 180 steps.*OnORPI,oneControlBank

"0" rod indicates196steps;allothersindicate182

steps.*The affectedrodhasablown

movable gripperfuseandhasbeen

determined

to be trippable.WhichONE(1)

ofthefollowing

actions is appropriateforthisevent?Realignthe

mispositionedrodtomeetTSlimitswithin

...A.1hourto ensure ShutdownMarginis maintained.B.6hoursto

ensure ShutdownMarginis maintained.

C.1hourto ensure acceptable

power distributionlimitsare maintained.

O.6hoursto ensure acceptable

power distributionlimitsare maintained

.77

2007NRCExamSRO78.Giventhe

following plant conditions

• Reactor poweris100%.*Reactor Trip Breakertestingisbeingperformed.

• ReactorTripBypass

Breaker'A'andReactorTrip

Breaker'B'areboth

RACKEDINand CLOSED.*ReactorTripBypass

Breaker'B'andReactorTrip

Breaker'A'areboth

RACKEDOUTandOPEN.

After completion

ofthetesting

, the ElectriciansRACKINand Operationsattemptsto

CLOSE ReactorTripBypass

Breaker B.*Immediately

upon attemptingclosure,ReactorTrip

Bypass Breaker'B'opens.*NO other breakers reposition

.WhichONE(1)ofthe

following describestheresponsetothis

condition?Thereacto r has...A.NOTtripped, immediately

enter EOP-13.0, Response To Abnormal Nuclear Power Generation

,anddirectthe

NROATC to commence rod insertion.B.NOTtripped, immediately

enter EOP-1.0, Reactor Trip/Safety

Injection Actuation,directthe NROATC to manually tr ipthereactor.

C.tripped ,havean operator"backup"thereactortrip

, then verify the turbine/generatorhastripped

.D.t ripped, direct an operatortoverify turbine/generatorhastripped,whentime

permits , directtheIBAOto locallyopenbothReactorTrip

Breaker'B'andReactorTripBypass

Breaker'A'.78

2007NRCExamSRO

79.Giventhefollowingplant

conditions

• Theplantisat100%power.*Thefollowingalarmsarereceivedinthe

sequence listed, approximately

10 seconds apart:*XCP-616 , 1-5 ,PZRLCSDEV HI/La*XCP-616 ,1-2,PZRLVLHI

• XCP-616, 1-1 ,PZRLVLHI*TheRO determinesthatPZRlevelindicatesthefollowing

• L1-459 indicates95%andrising

• L1-460 indicates56%andlowering

• L1-461 indicates55%andlowering*Trip StatuslightCHAN1PZRLVLHI

isilluminatedWhichONE(1)ofthe

followingdescribestheact

ionsthatwillbed

irectedbytheCRSandtheTS implications?

Se lect unaffec tedPZRlevelchannels

,operatePZRheaters,and...

A.reducechargingflowtomaintainPZRlevel.Doesnot satisfyTSLCO3.3.1, ReactorTripSystem

Instrumentation

ONLY.B.reducechargingflowtomaintainPZRlevel.Doesnot satisfyTSLCO3.3.1,ReactorTripSystem

Instrumentation,ANDdoesnotsatisfyTSLCO3.3.3.6, Accident Monitoring

Instrumentation

.C.raise chargingflowtomainta

inPZRlevel.Doesnot satisfyTSLCO3.3.1 , Reactor Tr ip System Instrumentation

ONLY.D.raisechargingflowto

maintainPZRlevel.Doesnot satisfyTSLCO3.3.1

, Reacto r T rip System Instrumentation

,ANDdoesnotsatisfyTSLCO3.3.3.6

, Accident Moni toring Instrumentation.

79

2007NRCExamSRO80.Giventhefollowingplant

conditions:*Amanualreactortripwas

performedduetohigh turbine vibration.*Thecrewismakingthe

appropriatetransitionfromEOP-1.0, Reactor Trip/Safety

Injection Actuation.*RCS pressureis2175psigand

slowly lowering.*PT-444,CNTRLCHAN

PRESS PSIG ,hasfailedhigh.*TheROreportsthatPZR

SprayValvePCV-444C

indicates open.WhichONE(1)ofthefollowing

describestheprocedurethatwillbeusedandtheactionrequiredtomitigatethis

event?A.RefertoAOP-401

.5, Pressurizer

Pressure Control Channel Failure, whileperformingtheEOPs.

EnsurePZRSprayvalvesareclosedand

energize PZRHeatersto stabilize RCS pressure.B.RefertoAOP-401

.5, Pressurizer

Pressure Control Channel Failure, whileperformingtheEOPs

.TripallRCPsandenergizePZRHeaterstostabilizeRCS

pressure.C.GotoEOP-1.1

, ReactorTripRecovery.TripONLYRCP"A"and

energize PZRHeatersto stabilize RCS pressure.D.GotoEOP-1.1, Reactor Trip Recovery.TripALLRCPsand

energizePZRHeaters

to stabilizeRCSpressure.

80

2007NRCExamSRO

81.Giventhefollowingplant

conditions

• Theplantis

currentlyatfullpower.*Thefollowing

sequenceofeventsoccurred:0200Thenormal

feeder breakerto7.2kVbus1DAtrippedopen

.TheAEDGstartedandthe

sequencercorrectlystartedallloads

.0215TheAEDG

tripped0220DCbus1HAwaslost

No operator actionshavebeentaken.*TheAEDGhasbeenrepairedandtheoperatingcrewispreparingtorestarttheEDGand reenergize

7.2kVbus1DA.WhichONE(1)ofthe

following describes(1)whatactionisrequiredpriortore-energizingthebus

,and(2)thetimeallowed

,byTechSpecs

,tobeinMode37

A.(1)(2)B.(1)(2)C.(1)(2)D.(1)(2)Openallload

breakers on 7.2kVbus1DAfromtheMCB

.2HoursOpenallload

breakerson7.2kVbus1DAfromthe

switchgear

room.2HoursOpenallload

breakers on 7.2kVbus1DAfromtheMCB.1HourOpenallload

breakers on 7.2kVbus1DAfromthe

switchgear

room.1Hour 81

2007 NRC Exam SRO82.Giventhe

following plant conditions:

• The plantisat 100%powerwithall systems in normal alignments.

• The RO determines

that actual Pressurizerlevelis trending DOWNandVCTlevelis trending UP.CHGLINEFLO HI/LO annunciator

has actuated.*FI-122A, CHG FLOW GPM, reads0gpm.*Charging pump currentis5amps.*RCS temperature

and pressure are stable.Which ONE (1)of the following describes the procedure that should be implementedandthe initial actions required?A.AOP-102.2, Loss of Charging;stop the operating Charging Pump and isolate Letdown.B.AOP-102.2, Loss of Charging;reduce letdownto45 gpm and verify the charging system valve lineup.C.AOP-101.1, Loss of ReactorCoo/antNot

Requiring Sf;stopthe operating ChargingPumpand isolate Letdown.D.AOP-101.1, Loss of Reactor Coo/ant Not Requiring Sf;open FCV-122 as necessary and reduce Letdownto45 gpm.82

2007NRCExamSRO83.Giventhe

following plant conditions:

Event 5/21 5/28 5/28 1230 1230 1645BOTHTrainARBCUs

declared inoperabledueto commoncausefailure.

RBCUs not returned to service.Plantshutdownto

Mode3initiated

.PlantinMode3.WhichONE(1)ofthe

following describes the LATESTtimeon5/28

thataninitialreporttotheNRCmustbe

made?A., 1330 B.1630 C.1745 D.2045 83

2007NRCExamSRO84.Giventhefollowingplant

conditions:

• ReactorBuildingPurgeisdesired.

RB EquipmentHatchisOPEN.WhichONE(1)ofthe

followingdescribesan

acceptable

alignment for Reactor Building Purge?A.2supplyfansand1

exhaustfanrunning;RM-A2

operabilitydesiredbutNOTrequiredduringpurge

.B.1supplyfanand2

exhaustfansrunning;RM-A2

operabilitydesiredbutNOTrequiredduringpurge.C.2supplyfansand1

exhaustfanrunning;RM-A2

operabilityrequiredduringpurge

.D.1supplyfanand2

exhaustfansrunning;RM-A2

operabilityrequiredduringpurge

.84

2007NRCExamSRO85.Giventhefollowingplant

conditions:*Theplantisat47%power.*Thefollowingalarmisreceivedinthecontrolroom:

• XCP-646-2-1, RM-G19 HI RAD*TheRO confirms that RM-G19Bisoff-scalehigh.*ChargingPumpflowisrisingslowly.

• ChemistryandHealthPhysicshaveconfirmedthatthealarmisvalid

.WhichONE(1)ofthe

following describesadditionalactionsthatwillberequiredin

accordancewiththealarm

response?A.Remove Condensate

Polishersfromservice;GotoAOP-101

.1, RCS Leak not Requiring SI.B.Remove Condensate

Polishersfromservice;Goto

AOP-112.2, SGTubeLeaknot

Requiring SI.C.Place Condensate

Polishersinservice;GotoAOP-101.1, RCS Leak not Requiring SI.D.Place Condensate

Polishersinservice;Goto

AOP-112.2, SG Tube Leak not Requiring SI.85

2007NRCExamSRO86.Giventhefollowingplant

conditions:*A transient has occurredresultinginthefollowingalarm:*PRFLUXHIRODSTP

• Reactor power indicatesthefollowing:*N41-101.9%andstable*N42-102.8%and

stable*N43-101.9%andstable*N44-103.1%andstable*Tavgis578°Fand

stableWhichONE(1)ofthe

followinghasoccurred,andwhich

action(s)/procedure(s)

is/arerequiredtobe

implemented?A.ARodStopwasinitiatedby1PRchannelONLY

initiateRCSborationtoreducepowerin accordancewiththe applicable

alarm response.B.ARodStopwasinitiatedby2PR

channels;reduce turbineloadtoreducepowerin

accordance

with applicable

alarm response procedures.

C.ARodStopwasinitiatedby2PR

channels;initiateRCS

borationtoreducepower

in accordancewiththe applicablealarmresponse.

D.ARodStopwasinitiatedby1PRchannelONLY;reduce

turbineloadtoreducepowerin accordance

with applicablealarmresponse

procedures.

86

2007NRCExamSRO

87.Giventhefollowingplant

conditions:*Theplantwasoperatingat98%powerwhenalossofoff-site

power occurred.*Eight minuteslater,thefollowingplant

conditions

exist:*1DAand1DBBus

voltageiszero(0).*RCS pressureis2235psigandslowlyincreasing.*RCSLoopT HOTis602°Finall3loopsandstable

.*RCSLoopT COLDis565°Finall3loopsandstable.*CoreexitTCs

indicate approximately610°Fandrisingslowly.*Steam Generator pressures are approximately1100psigandstable

.*PZRlevelis20%andstableWhichONE(1)ofthe

followingdescribesthe

current plant conditionsandactionthatwillbe directed?A.Heatremovalisbeing

maintainedbysteamlinePORVs.

VerifythatNaturalCirculationexistsin

accordancewithEOP-6.2, Loss of AllESFAC Power RecoveryWithSIRequired.

B.Heatremovalisbeing

maintained

by condensersteamdumps.

VerifythatNaturalCirculationexistsin

accordancewithEOP-6.1, Loss of AllESFAC Power RecoveryWithoutSIRequired.C.Natural Circulationdoesnotexist.Heatremovalmaybe

establishedinaccordancewithEOP-6.2, Loss of All ESF AC Power RecoveryWithSIRequired.D.Natural Circulationdoesnotexist.HeatremovalmaybeestablishedinaccordancewithEOP-6.1, Loss of All ESF AC Power Recovery WithoutSIRequired.

87

2007NRCExamSRO88.Giventhefollowingplantconditions:*Areactortriphas

occurredduetolossofoff-sitepower.

ESF equipment responds as designed.*Off-Site powerhasNOTbeenrestored.*CSTlevel indicates14feet.Assumingpowerwillbe

unavailableforanextendedperiodoftime

,(>4hours)whichONE(1)ofthefollowing

describes the event mitigation

strategyuponexitfrom

EOP-1.0, Reactor Trip/Safety

Injection Actuation?

A.GotoEOP-1.1, Reactor Trip Recovery;cooldowntheRCSusing

EOP-1.3 , Natural Circulation

Cooldown.B.GotoEOP-1.1, Reactor Trip Recovery;stabilizetheprimaryand

secondary plants ,andremaininEOP-1.1until

powerisrestored.C.GoToGOP-5

, Reactor Shutdown From StartuptoHot Standby (Mode 2toMode 3);referto AOP-304.3, Loss of All Balance of Plant Buses ,torestoreservicebus

power.D.GoToGOP-5, Reactor Shutdown From StartuptoHot Standby (Mode 2toMode3);referto

SOP-211, Emergency Feedwater System ,toswap EFWtoService Water.88

2007NRCExamSRO

89.Giventhefollowing

plant conditions:*Theplantisina

normal service water system alignmentwith'A'and'B'

SWpumpsrunning.

• XCP-604-1-2"SWP A/C TRIP" alarms.*Annunciator

XCP-604-1-4"SWP AlC DISCH PRESSLO"alarms.

• Annunciator

XCP-605-1-4"SWP B/C DISCH PRESSLO"alarms.*PI-4402, Service Water Pump'A'Discharge Pressure, indicates5psig.*PI-4422, Service Water Pump'B'Discharge Pressure, indicates48psig.*'A'SWpumpwillnotrestart.

• AOP-117.1, Total Loss of Service Water,hasbeen entered.WhichONE(1)ofthe

following describes the actions that shouldbetakento mitigate this event?A.Referto SOP-117, Service Water System, and ensurethe'C'SW pump automatically

startedonlow header pressure.B.Continue in AOP-117.1,TotalLoss ofServiceWater,tripthereactor,andtr

ip all RCPs.C.Referto SOP-117'.Service Water System, and startthe'C'SWpumponthe'A'

train.D.Continue in AOP-117.1,TotalLoss ofServiceWater, and isolateall CCW loads.89

2007NRCExamSRO90.Giventhe

following plant conditions

• The plantisin Mode 5.*Welding activitiesinthe Cable SpreadingRoomarein progress.*The Simplex Panel indicates actuation of Fire Protectionintheroom.*Maintenance

reports that Fire Suppression

is actuated, but thereisnoactual

fire.WhichONE(1)

of the following describesthefire suppression

actuationandtheactiontobe taken?A.C02;Evacuate personnelfromtheareaandstopthe

discharge in accordance

with the associated

Fire Emergency ProcedureandFire Pre-Plan.B.C02;Evacuate personnelfromtheareaandstopthe

discharge in accordance

with SOP-509, Fire Suppression

System.C.Pre-Action

Sprinkler;

Terminate the actuation in accordancewiththe associated

Fire Emergency ProcedureandFire Pre-Plan.D.Pre-Action

Sprinkler;

Terminate the actuation in accordance

with SOP-509, Fire Suppression

System.90

2007NRCExamSRO91.Giventhefollowingplant

conditions:*ASteam GeneratorTubeRupturehasoccurred.*Dueto equipment failures ,thecrewisperformingactionscontainedinEOP-4.3

,SGTRwithLoss

of Reactor Coolant-Saturated Recovery.*TheShift Engineer informsyouthatallCSFStatusTreesareGREENwiththeexceptionofthe

following:*CoreCooling-

YELLOWduetoRVLlSlevel

• Inventory-YELLOWduetoRVLlSlevelWhichONE(1)ofthe

following describesthecorrect

implementationofproceduresforthisevent?

A.Select another post-SGTR cooldown method lAW EOP-4.0.Implementation

ofYellowPath

proceduresisnotallowedwhileinEOP-4

.3.B.RemaininEOP

-4.3 while addressingBOTHYellowPath

procedures

.Youmaychooseto implement the actions of eitherYellowPath

procedure.C.Select another post-SGTR cooldown method lAW EOP-4.0andaddressONLYtheCoreCoolingYellowPath

,duetoitshigherpriority.D.Remainin

EOP-4.3 and addressONLYthe InventoryYellowPathduetoconflictbetweentheCoreCooling

YellowPathandEOP-4

.3 actions.91

2007NRCExamSRO

92.Giventhe following plant conditions.*0547A Reactor Trip occurred*0548Tavg=552°FandRCS pressureis2080psig*0748Tavg=379°FandRCS pressureis1550psig*0948Tavg=248°FandRCS pressureis1850psigWhichONE(1)

of the following describesthelimit thathasbeen exceededandthereasonwhy?(REFERENCE

PROVIDED)Limit A.Plant Operational

Limits Curve T1B.Plant Operational

Limits Curve T1C.TS CooldownLimit(Figure

3.4-3)D.TS CooldownLimit(Figure

3.4-3)Reason RCS pressureistoohigh RCS temperatureistoolow RCS pressureistoohigh RCS temperatureistoolow 92

2007NRCExamSRO93.Giventhefollowingplant

conditions:*ALOCAhasoccurred.*Thecrewhas

completed EOP-1.0, Reactor Trip/Safety

Injection Actuation,tothepointof transition

to another procedure.*AllESF equipment is operatingasdesigned.*Thefollowing

conditionsexistinthe

Reactor Building:*RB Pressure 10.5psigandrisingslowly

.*RHRSumpLevel424feetandrisingslowly.WhichONE(1)

of the following describestheconditionthatexists,theproceduretransitionthatwillbemade

,andthe strategyforrecovery?

A.ORANGEconditiononHigh

ReactorBuildingPressure

.Enter EOP-17.0, Response to Reactor BuildingHighPressure, and attempttolocateandisolatethesourceoftheleak;notifyplant

stafftoobtain recommendedactionfor disposalofwaste.B.ORANGEconditiononRHRSumpLevel.EnterEOP-17.1, Response to Reactor Building Flooding , and attempttolocateandisolatethe

sourceoftheleak;notify

plant stafftoobtain recommendedactionfor disposal of waste.C.ORANGE conditiononHigh ReactorBuildingPressure

.Enter EOP-17.0, Response to Reactor BuildingHighPressure,andensureRBIsolationandHeatRemovalfunctionsare

satisfied.D.ORANGE conditiononRHRSumpLevel.EnterEOP-17

.1, Response to Reactor Building Flooding , and ensureRBIsolationandHeatRemoval

functions are satisfied.

93

2007NRCExamSRO94.Giventhefollowingplant

conditions:*TheplantisinMode1.*Makeupto'A'SI Accumulator

was just completed.*'A'SI Accumulator

parametersareasfollows:*Boron Concentration*Pressure*Level2197ppm650psig 67%WhichONE(1)ofthe

followingdescribestheactionrequiredin

accordance

with Technical Specificationsandwhy?A.Restoreboron

concentrationtowithinlimitswithin1hour.Tominimizethe

potentialforreaching

unacceptable

peak cladding temperaturesduringaLOCAwith

postulatedfailureof1otherSI

Accumulator.B.Restoreboron

concentrationtowithinlimitswithin1hour.Tomaintainthe

calculatedDNBRinthecoreatorabovethedesignlimitduring

short-term

transientsuntilcoreisreflooded

.C.Restore pressuretowithinlimitswithin1hour.

To minimize the potentialforreaching

unacceptable

peak cladding temperaturesduringaLOCAwith

postulatedfailureof1otherSI

Accumulator

.D.Restore pressuretowithinlimitswithin1hour.Tomaintainthe

calculatedDNBRinthecoreatorabovethedesignlimitduring

short-term

transientsuntilcoreisreflooded.

94

2007NRCExamSRO95.G iventhefollowingplant

conditions:*Youarethe

ControlRoomSupervisor.*An explosion occursresultingin

significant

damageintheunit.*TheShift Supervisorwasseriouslyinjuredinthe

explosionandisincapacitated.*Thereareno

proceduresordirectivesthatprovide

adequate directiononcontroloftheplantandrescueofinjuredpeopleforth

is situation.*Immediateactionisrequired.WhichONE(1)ofthe

following describes the requirement

for performingthisaction?

A.Youmayapprovethisactionin

accordance

with 10CFR50.54(x)and(y).B.Youmustobtain

concurrencefromoneotherSROpriortoperformingtheaction.C.TheNRCmustbenotifiedpriortotheactionandshould

concurwiththeactiontobetaken.D.ThePlant Managermustbenotifiedandshould

concurpriortotakingtheaction.

95

2007NRCExamSRO96.Giventhefollowingplant

conditions:*100%power.*AllmajorcontrolsareinAUTO.*ChargingPump"A"isrunning.*ChargingPump"B"hasbeen

out-of-service

for AuxiliaryOilPumpreplacement.*ChargingPump"C"isalignedtoTrain

"B".*ChargingPump"B"isreadyfor

post-maintenance

testing.WhichONE(1)ofthe

choicescorrectlycompletesthefollowing

statement regardingtheoperabilityofTrain"B"duringthe

post-maintenance

testing?Train"B"mustbe

declared inoperable

when_A.ChargingPump"B" breakerisrackedup

.B.ChargingPump"B" control powerisrestored

.C.ChargingPump"C" breakerisrackeddown.D.ChargingPump"C"controlpoweris

de-energized

.96

2007NRCExamSRO

97.TheplantisinMode1.

RCS TemperaturehasgonebelowtheTechnical

Specification

MinimumTemperatureforCriticality.Ifthe conditions

CANNOTbecorrected,whichONE(1)ofthe

followingdescribestheMAXIMUMtimeallowedpriortoplacingtheplantinMode3andthebasisfortheactioninaccordancewith

Technical Specifications?

A.30minutes;RPS Instrumentationisno longeroperatinginitsanalyzedrange.B.30minutes;

Analysis assumptions

for calculationofMode1 ShutdownMarginare no longer valid.C.1hour;RPS Instrumentationisnolongeroperatinginits

analyzed range.D.1hour;Analysis assumptions

for calculationofMode1 ShutdownMarginarenolongervalid

.97

2007NRCExamSRO98.Giventhefollowingplant

conditions:*Theplantiscomingoutofarefuelingoutage.OperationsDept.is

performingsystemvalvelineups.*Avalve alignmentinthe ReactorBuildingshouldtake

approximately30minutesinaradiationfield

of 6 Rem/l-it.WhichONE(1)ofthe

following descrtibestheMINIMUMreview

requirements

thatmustbemetpriorto

performing

the alignment?

A.APre-Job Briefandreviewof

RWP/SRWP forvalvelineupsONLYB.Areviewofthe

RWP/SRWPforvalve lineups and ALARA CommiteereviewONLYC.APre-Job

Brief and ALARA CommiteeReviewONLYD.APre-JobBrief, ReviewofRWP/SRWP

, and ALARA Commitee Review 98

2007NRCExamSRO

99.Giventhefollowingplantconditions:*Mode5withRHRTrain

"A"runninginthe

shutdowncoolingmode.*RCS subcoolingis45 of.*SG"B"and"C"are availableforheatremoval.*Atotalloss

of CCWflowhasoccurred

.*Seal Injectionflowisnormal.*The operatingcrewisinAOP-118.1

, TOTALLOSSOF COMPONENT COOLING WATER,andhasreferredto

AOP-115.3,LOSSOFRHRWITHTHERCSINTACT.WhichONE(1)ofthe

following describesthecorrectactionandthereasonforthat

action?A.StopanyrunningRCPandRHRPump"A

" with in 10 minutes to preventpumpseal damage.B.AlignRCSFeedandBleedwithin10minutestoprovidecoolingandthenstopanyrunningRCP.C.StopRHRPump"A

" immediatelyandalignforRCSBleedandFeedtoprovide

cooling.D.Within90 minutesstop"A"RHRpumpto

preventsystemdamage.

99

2007NRCExamSRO

100.Giventhefollowing

plant conditions

• Theplantis

operatingat100%power.*EDG"B"isout

of serviceandis expectedtoreturnto

serviceintwo(2)hours.

• Subsequently, the following events occur:*Alossof offsite power.*The reactor is trippedandthecrewenters

EOP-1.0 , Reactor Trip or Safety Injection.*SIisNOT actuated.*Thecrewmadea

transitiontoEOP-15.0, Loss of Secondary Heat Sink ,basedona CSFSTREDPath.*EDG"A" output breaker subsequentlytripsona differentia/lockoutonBus 1DA.WhichONE(1)ofthe

following describestheactionsthatwillbe

takenanditsbases?

A.Immediately

transitiontoEOP-6.0 , Loss Of AllESFAC Power.All other proceduresintheERG network assumeboth7.2KVESFbussesare

available.B.Immediately

transitiontoEOP-6.0, Loss Of All ESFACPower.All other proceduresintheERG network assume a minimumofONE(1)7.2KVESFbusisavailable.

C.Remainin EOP-15.0untilfeedisrestoredandtheRED

conditioniscleared , and then transitiontoEOP-6.0 , Loss of All ESF AC Power.REDpath Function Recovery procedures

must be performeduntilthe conditioniscleared.

D.Remainin EOP-15.0 until directedtoreturnto

procedure i n effect ,andthentransitiontoEOP-6

.0 , Loss of AllESFACPower.REDpath Function Recovery procedures

must be finished to completion.

100

INTEGRIT Y EO P-12.0 REVI SION 12 ATTACHM ENT 4 PAGE2of 2 PLAN T OPERATIONAL

LIMITS CUR VE 400 350 300 200250 RCS T c ol d (o F)1 50 0 I I.'._P SIG I (PZR SAFETY VALVE S A S SUMED FULL O P EN)I-10-----R EGION OF ACC EPTABLE OPERATION-----01 LIMIT T2 LIMIT T1 I---I I LIM IT At--.II- I o 100 RCS PR ESSURE (PSIG)300 2500 500 2000 1500 1000 PAGE 9 OF 12

REACTOR COOLANT SYSTEM MATERIAL PROPERTY BASIS LIM ITING MATERIAL: INTERMEDIATE

SHELLPLATEA9154-1

LIMITING ART VALUES@56EFPY: 1/4T , 153°F 3/4T , 138°F Q 5 0 10 0 150 20 0 250 300 35 0 400 45 0 500 550 Moderator Temperature

(0 F)FIGURE 3.4-3 V.C.Summer Unit 1 Reactor Coolant System Cooldown Limitations (Cooldown Ratesupto100 oF/hr)Applicablefor56 EFPY (Without Margins for Instrumentat

ionErrors)Using1998

Appendix G Methodology

SUMMER-UNIT 1 3/44-32 AmendmentNo.53 , 113 , 133,143,174