ML081140047

From kanterella
Revision as of 13:15, 12 July 2019 by StriderTol (talk | contribs) (Created page by program invented by StriderTol)
Jump to navigation Jump to search
March 05000400/2008301 Final RO Written Examination & Reference
ML081140047
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 03/21/2008
From:
NRC/RGN-II
To:
Progress Energy Carolinas
References
50-400/08-301
Download: ML081140047 (65)


See also: IR 05000400/2008301

Text

Final Submittal (Blue Paper)

LlGen5.e3/'0-3/13 l sizs]ZQ)gFINALRO WRITTEN EXAMINATION

AND REFERENCES

I ES-40 Name: Date: 3/21/08 Site-Specific

RO Written Examination

Cover Sheet u.s.Nuclear Regulatory

Commission

Site-Specific

RO Written Examination

Applicant Information

Facility/Unit:

HARRIS PLANTRegion:I D II IX]III D IV D Start Time: Reactor Type: WOO CE D BWD GE DFinishTime:

InstructionsUsethe answersheetsprovided

to document your answers.Staplethis

cover sheetontop of the answersheets.Topassthe

examination,youmust achieveafinal gradeofatleast80.00

percent.Examinationpaperswill

be collected6hoursafterthe

examination

begins.Applicant Certification

All workdoneonthis

examinationismyown.Ihave

neithergivennorreceivedaid.

Applicant's

Signature Results Examination

Value Applicant's

Score Applicant's

GradeES-401,Page30

of 33 Points Points____Percent

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

1.Initial conditions:

Harris 2008ROExamRev FINALForm:0Version:0*The plantisat80%Reactor power and rampingUPat1/2%per minute.*Tave and Tref are matched.*Rod Controlisin AUTOMATIC.

Current conditions:

  • ONE (1)Control BankDRodhas just droppedandis stuckat170 steps.*All Other Control BankDRodsare currently indicating

206 Steps.Assuming NO operator actionistaken, whichONEofthe following describes the DEMAND for rod motion,andthe effect on Axial Flux Difference (AFD)for the channel NEAREST the control rod problem?ROD MOTION AFD EFFECT A.Outward Less Negative B.Outward More Negative C.Inward Less Negative D.Inward More NegativeThursday,March20,200810:35:06AM

1

Harris2008ROExamRevFINAL

2.Initial Plant Conditions:

  • TheplantisSolid.

Current Plant Conditions:*A controller

failurehascaused1CS-38,Letdown

Pressure Controlvalve,toshut.

  • The crew has just entered AOP-019, MalfunctionofRCS Pressure Control.Which ONE of the following describes the effectofthis malfunctiononRCS pressureandthe actions required lAW AOP-019 to mitigate this event?A.RCS Pressurewillincrease;

EnsuretheRCPSeal

WaterReturnvalvesareopenB.RCS Pressurewillincrease;

Secure the running CSIPC.RCS Pressure will decrease;EnsuretheRCPSeal

Water Return valvesareshutD.RCS Pressure will decrease;Increase chargingflowtoraiseRCS

pressure 3.The plant is operatingat100%powerwhenonecontrolroddrops

fullyintothecore

causing Power RangeN-41toread

lowerthanthe other power range channels.WhichONEofthe followingisthe expected QPTR response overthenexttwotosixhoursandwhy?

A.QPTR will increaseduetothe buildupofXenoninthe

droppedrod'sfuel assembly.B.QPTR will decreaseduetothe buildupXenoninthe

droppedrod'sfuel assembly.C.QPTR will increaseduetothe change in temperatureinthe droppedrod'sfuel assembly.D.QPTR will decreaseduetothe change in temperatureinthe droppedrod'sfuel assembly.Thursday,March20,200810:35:06AM

2

Harris2008ROExamRev

FINAL 4.Giventhe following:*A plant startupisin progress.*Reactor poweris20%.*"B"RCPtrips.

Which ONE of the following describes the effectonthe reactorand"B"loop

Tave?A.Reactor remainsatpower;Loop"B" Tave lowersdueto Thot lowering to the valueofTcold.B.Reactor remainsatpower;Loop"B" Taverisesduetothe

decreased flowinthe"B"loop.

C.Reactor automatically

trips;Loop"B" Tave lowersdueto Thotloweringtothe

valueofTcold.D.Reactor automatically

trips;Loop"B" Taverisesduetothe

decreased flowinthe"B"loop.

5.Which ONE of the following evolutions,byitself,will"RAISE Shutdown Margin?A.Lowering the setpointofthe Letdown Temperature

Control Valve, TCV-144,by10 of.B.Raising the flow settingoftheboricacid

flow controllerby2turns during a blended makeuptothe VCT.C.Raising the setting of the blended makeup flow totalizerby100 gallons total during a blended makeuptotheVCT.D.Lowering the settingoftheboricacidbatch

totalizerby20 gallons total during a blended makeuptotheVCT.Thursday,March20,200810:35:06AM

3

Harris2008ROExamRevFINAL

6.WhichONEofthe followingsetsof parameters

and conditions

will satisfy the interlockstoopenthe ResidualHeatRemovalHotLegSuctionvalves

(1RH-1,2,39,and40)?A.RCS temperatureis345 of, RCS pressureis365psig, RHR dischargetoCSIPvalves,1RH-25and1RH-63,areshut, RHR suction from RWSTvalves,1RH-322and1RH-323,areshut:B.RCS temperatureis335 of, RCS pressure355psig, RHR dischargetoCSIPvalves,1RH-25and1RH-63,areshut, RHR suction from RWSTvalves,1RH-322and1RH-323,areshut.C.RCS temperatureis345 of, RCS pressure355psig, RHR suction from RWSTvalves,1RH-322and1R'H-323,areshut.

RHR suction from Containmentsumpvalves1SI-300,301,310,and311areshut.D.RHR temperatureis335 of, RCS pressureis365psig, RHR dischargetoCSIPvalves,1RH-25and1RH-63,areshut, RHR suction from Containmentsumpvalves181-300,301,310,and311areshut.Thursday,March20,200810:35:06AM

4

Harris 2008ROExamRev FINAL 7.Given the following:

  • The plantisin Mode 4.*RHR Train"A"isin service.*RHR Heat Exchanger Bypass Valve 1 RH-20isin automaticwiththe output at 400/0 to maintain3750GPM.*RHR Heat Exchanger outlet valve 1 RH-30 demand positionissetat30%.
  • The Instrument

Air supplylinetoRHR Heat Exchanger Outlet Valve 1 RH-30 becomes severedandis completely

detached.*No other air operated valves are impactedbythe failure.Which ONE of the following describestheRHR system parameter changes from the initial steady state conditiontofinal steady state condition?

RHR HX Outlet Temp Total RHR flow A.Higher Lower B.Higher Higher c.Lower Higher D.Lower LowerThursday,March20,200810:35:07AM

5

Harris2008ROExamRevFINAL

8.Giventhe following:*A reactortripand safetyinjectionhaveoccurred.*RCS pressureis1000psigandlowering.*"A"CSIPfailstooperate.*All other equipment operatesasdesigned.

WhichONEofthe following describestheexpectedMCBChargingFlow

indication (FI-122.1),andthe SafetyInjectionflowindication(FI-943)?A.MCB Chargingflow0gpm;Safety Injection flow is approximately600gpmMCB Charging flow0gpm;Safety Injection flow is approximately450gpmC.MCB Charging flow approximately150gpm;Safety Injection flow is approximately150gpmD.MCB Charging flow approximately150gpm;Safety Injection flow is approximately450gpmThursday,March20,200810:35:07AM

6

Harris2008ROExamRev

FINAL 9.Giventhe following:*"A" Train equipmentisinservice.*A ReactorTripoccurs.*All equipment is operating as designed.*Thecrewis performing

actionsofPath-1.*Conditionsareasfollows:PZRpress.CNMT press.1865psig2.9psig1865psig3.1psigCHIII 1845psig3.1psigCHIV NA2.9psig WhichONEofthe following describes the statusofthe Charging Safety Injection Pumps?A.Both CSIPsarerunningduetoSIsignalonlowPZRpressure.B.Both CSIPsarerunningduetoSIsignalonhigh

Containment

pressure.C.Only"A"CSIPis running,but"B"CSIPwillbestarted

automaticallyifthe additional

required PZR pressure transmitterreachestheSI

actuation setpoint.D.Only"A"CSIPis running,but"B"CSIPwillbestarted

automaticallyififthe additional

required CNMT pressure transmitter

reachestheSI actuation setpoint.Thursday,March20,200810:35:07AM

7

Harris2008ROExamRevFINAL

10.Initial Conditions:*Withtheplantoperatingat

1000/0powerandall

equipmentinitsnormallineup,theROtakestheReactorTripswitchtotheTRIPposition.

Current plant conditions

are:*ReactorTripBreaker"A"Redindicationexists.

  • Reactor Trip Breaker"B"Greenindicationexists.
  • Reactor Power is 40/0andlowering.*Rodbottomlightsarelitwiththe

exceptionofFOURControlBankDrods.

Their positionsareasfollows:*H-8-16steps*K-2-220steps*M-12-8steps*M-8-20steps

Which ONE ofthefollowingdescribestheconditionofthereactor,andtheactionthatwillberequired?A.The reactoristripped;PerformnormalRCSborationforthestuckrodsasdirectedbyEPP-004

referencingOP-107,Chargingand

VolumeControlSystem.B.The reactoristripped;

Initiate emergencyborationforthestuckrodsasdirectedbyEPP-004

referencing

AOP-002, Emergency Boration.C.The reactorisnottripped;

Manuallyinsertcontrolrodsin

accordancewithFRP-S.1untilallrodsareon

bottom.D.The reactorisnottripped;

Initiate emergencyborationforthestuckrodsin

accordancewithFRP-S.1until

adequate ShutdownMarginisverified.Thursday,March

20,200810:35:07AM

8

Harris2008ROExamRevFINAL

11.Giventhe following:*The plantisat100%power.*A PressurizerPORVhasaslowleakthroughtheseatordisk.*The respectivePORVisolationvalvecannotbeclosed.

  • ALB-009-8-1, PRESSURIZER

RELIEF TANK HIGH-LOWLEVELPRESSORTEMP,is actuated.*PRTLevelis

73%.*PRT Temperatureis128 of.*PRT Pressureis6.3Psig.

WhichONEofthe following parametersiscausingthealarm,andwhichONEofthe

followingistheactionrequiredtobe

performedfromOP-100, Reactor Coolant System,Section8, Infrequent

Operations?A.Pressure;

Vent the PRTas necessarytocontrolpressure.B.Pressure;DrainthePRTas

necessarytocontrolpressurewhile

maintaininglevelwithinthenormalband.

C.Temperature;

RecirculatethePRT contentsthroughtheRCDTHeat

Exchangertolower temperature.

D.Temperature;DrainPRTtothelowendofthenormalbandandthenrefillwith

demineralized

water to lower temperature.

Thursday, March20,200810:35:07AM

9

Harris2008ROExamRev

FINAL 12.Given the following:

  • The plantisat1power.*The temperature

input to Letdown Heat Exchanger CCW flow control valve TCV-144,failslow.Which ONE of the following describes the impactonthe plantandthe action that is requiredbythe appropriate

Annunciator

Panel Procedure (APP)?A.High CCW flow to Letdown Heat Exchanger;

Place TCV-144 in manual and adjust flow to restore normal cooling.B.High CCW flow to Letdown Heat Exchanger;

Isolate letdownandplace Excess Letdowninservice.C.High temperature

letdown diversiontoVCT;Place TCV-144 in manual and adjust flow to restore normal cooling.D.High temperature

letdown diversiontoVCT;Isolate letdownandplace Excess Letdowninservice.

13.Giventhe following:*A reactortriphas occurredfrom100%power.*Pressurizer

pressureis2050psigand

lowering.*Pressurizerlevelisrisingrapidly.

  • Containment

pressureis1psigand

slowly rising.Assuming NO operatoraction,whichONEofthe

followingcouldhave caused the event in progress?A.Master Pressure Controller

PT-444 output failed LOWB.Both Pressurizer

Spray ValvesfailedOPEN

C.Master Pressure Controller

PT-444 outputfailedHIGH

D.Small break LOCAonanRCSHotLegThursday,March20,200810:35:07AM

10

Harris2008ROExamRev

FINAL 14.Given the following:*A reactortriphas occurred.*Safety Injection is actuated.*All actions requiredinPath-1havebeentaken.*All RCPs are running.*RCS pressureis1450psigandstable.*SI flowis150GPM.*Containmentpressure.is4.5psigand

slowly rising.*SG pressuresare1 050psigandstable.

Which ONEofthefollowingdescribes

the plant condition upon transition

from Path-1?A.RCPs should NOT be tripped.SGsare required for subsequentRCSheat removal.B.RCPs should NOT be tripped.SGsare NOT required for subsequentRCSheat removal.C.RCPs should be tripped.SGsare required for subsequent

ReS heat removal.D.RCPs should be tripped.SGsare NOT required for subsequent

RCSheat removal.Thursday,March20,200810:35:07AM

11

Harris2008ROExamRevFINAL

15.InitialPlant

Conditions:*Theplantwasat1

00%power.Current plant conditions

are:*ALossof Off-sitePoweroccurs.*Bus 1A-SAislockedout.*All other equipmenthasoperatedasdesigned.*Dieselloading

sequenceiscomplete.*RCS pressureis2180psig.

Assuming NO operatoractionhasbeentaken,whichONEofthe

following describes the statusofthePZRHeaters?A.ALLPZRBackupHeatersare

DE-ENERGIZED.B.GroupBistheonlyPZR

heater group ENERGIZED.C.GroupCistheonlyPZR

heater group ENERGIZED.

D.Groups BandCaretheonlyPZR

heater groups ENERGIZED.Thursday,March20,200810:35:07AM

12

Harris 2008ROExamRev FINAL 16.Which ONE of the following describes the characteristicsofa design basis Large Break LOCA twenty (20)minutesintothe event?A.RCS temperatureisat saturation

temperature

for intact SG pressure;RCS pressure is stable below normal 81 accumulator

pressure, but above RHR pump shutoff head.B.RCS temperatureisat saturation

temperature

for intact 8G pressure;RCS pressure is stable below RHR Pump shutoff head.C.RCS temperature

is below saturation

temperature

for intact 8G pressure;RCS pressure is stable below normal 81 accumulator

pressure, but above RHR pump shutoff head.D.RCS temperature

is below saturation

temperature

for intact 8G pressure;RCS pressure is stable below RHR Pump shutoff head.17.Given the following:

  • The unitisat 1 00%power.*Unit electrical

alignment is normal.*Aux Bus 1 0'deenerqizesandislockedout.

Which ONE of the following loads will de-energize

and automatically

re-energize?A."A" NSW PumpB."B" NSW PumpC."A" CSIPD."B" CSIPThursday,March

20,*200810:35:07AM

13

Harris2008ROExamRevFINAL

18.Giventhe following:*The plant is operating at 30%reactor power, steady state.*I&C technicians

are preparingtoperforma

calibration

on Power Range Channel N-41.*OneI&C technician

mistakenlypullsthecontrol

powerfusesonN-42.

  • Realizing his mistake,hereinsertsthefusesforN-42andthenpullsthecontrol

power fuses for the correctchannel,N-41.

Which ONE of the following describesthestatusofthe

reactor aftertheN-41 fuses werepulledandwhich

bistable(s)inN-42wouldbe

tripped?A.The reactor is tripped;PR PositiveRateTripandPR

NegativeRateTrip.B.The reactor is tripped;PR PostiveRateTripONLY.C.The reactor is NOT tripped;PRPositiveRateTripandPR

NegativeRateTrip.D.The reactor is NOT tripped;PR PositiveRateTrip ONLY 19.Giventhe following:

  • Pressurizer

Pressure Protection

Channel PT-455hasfailed off-scale HIGH.*NO Operatoractionhasbeentaken.

WhichONEofthe following identifies

the MINIMUM additional

channels required to meettheESFandRPS

actuationlogictoinitiatea

reactortripand safety injection on Pressurizer

Pressure?A.ReactorTrip-1;Safety Injection-1 B.ReactorTrip-1;Safety Injection-2 C.ReactorTrip-2;Safety Injection-1 D.ReactorTrip-2;Safety Injection-2Thursday,March20, 2008*10:35:08

AM 14

Harris 2008 RO Exam Rev FINAL 20.Given the following:*A LOCA has occurred.*RCSpressure

is 200 psig.*"A" Containment

Spray Pump is Out of Service.*Containment

pressureis12psigand

slowly increasing.

  • Train"B" PhaseAhas failed to actuate.*Normal Containment

Purgewasin serviceatthe time of the LOCA.*The Containment

Ventilation

Isolation Signal (CVIS)fails to actuate.*All other ECCS equipment is running as required.Assuming no action by the crew, which ONE of the following describes the effect on the plant?A.Containment

Normal Purge Makeup fanswilltripand

their associated

dampers SHUT.B.Offsite dose consequences

will exceed the guidelines

of 10CFR100.C.Normal Containment

Purge Makeup valves (1 CP-6and9)will remain OPEN.D.Only half of the Containment

penetrations

required for containment

isolationwillbe isolated.21.Given the following:

  • The plantisat 200/0 power.*Rod Controlisin AUTO.*The operating crew is preparing to stopRCP1C duetorising vibration.

Assuming that reactor power is maintained

at 200/0, which ONE of the following describes the expected indications

on Loop1andLoop3 flowrates when RCP1Cis stopped?A.B.C.D.Loop 1 Flowrate increase to 110 0/0 increase to 110 0/0 increase to 120%increase to 120%Loop 3 Flowrate decreasesto0 0/0 and stabilizes

decreases to 00/0 then increasesto10 0/0 decreasesto0 0/0 and stabilizes

decreases to 00/0 then increases to 100/0Thursday,March

20,200810:35:08AM

Harris2008ROExamRev

FINAL 22.Given the following:

  • The plantisat 60%power during a plant startup.*Steam Dumpsareinthe Tave mode of control.*First Stage Pressure Transmitter

PT-446failshigh.

Assuming the reactor remainsatpower, whichONEofthe following describes the effect on the steam dump system?A.Steam Dumps will receive an arming signal.B.Steam Dumps will receive a modulation (open)signal.C.Steam Dumps will NOTarmif required.D.Steam Dumps will NOT modulate if required.23.Given the following:

  • The crew is performing

EPP-004, Reactor Trip Response.*Natural circulation

verificationisin progress.*CoreExit ThermocouplesG2andK5have

failedduetoopen circuits.With these open circuitfailures, the input from these thermocouplestothe Inadequate

Core Cooling Monitor (ICCM)willbeandthe subcoolng margin calculated

by ICCMwillbe_A.failed low;higher B.failed low;unaffected

C.failed high;lower D.failed high;unaffectedThursday,March

20,200810:35:08AM

16

Harris2008ROExamRevFINAL

24.Initial Conditions:

  • ContainmentCoolingisintheNormalCoolingModeofoperationwithTrain"A"inservice.
  • Containment

temperaturehasbeenslowlyrising.

Current Conditions:

  • Thecrewhasplacedthe

ContainmentCoolingsysteminMaximumCoolingModeperOP-169, ContainmentCoolingSystem.

  • Containment

temperatureisnowlowering.

WhichONEofthefollowing

identifies

the MINIMUM temperatureatwhicha Technical Specification

action statementmustbeenteredandtheexpected

alignmentforthe ContainmentCoolingSystem?A.118 OFBOTHfansinAH-3andAH-4inhighspeedANDONE(1)faninAH-1andAH-2inhighspeed.

B.118°FBOTHfansinAH-3andAH-4inhighspeedANDBOTHfansinAH-1andAH-2inhighspeed.C.120 OFBOTHfansinAH-3andAH-4inhighspeedANDONE(1)faninAH-1andAH-2inhighspeed.D.120 ofBOTHfansinAH-3andAH-4inhighspeedANDBOTHfansinAH-1andAH-2inhighspeed.Thursday,March

20,200810:35:08AM

17

Harris2008ROExamRev

FINAL 25.Given the following:

  • The plantisat100%power.*VCT Level ChannelLT-112failshigh.

Assuming NO operatoraction,whichONEofthe

following describes the function(s)

lost duetothis failure?A.ONLY DiverttoRHTwillbe

disabled B.ONLY Auto Swapover from RWSTwillbe disabled.C.Auto Swapover from RWST AND Auto Makeupwillbe disabled.D.DiverttoRHT AND Auto Makeupwillbe disabled.Thursday,March20,200810:35:08AM

18

Harris 2008ROExamRev FIN*AL 26.Initial conditions:*Theplantisat1

000/0 power.*Train"B" ContainmentFanCoolingisinservice.

Current conditions:*A Safety Injectionsignalhasoccurred.*All equipment is operatingasdesigned.

WhichONEofthe following describes the operation of Containment

Cooling?OnefanineachFan

CoolerUnitisoperatingin...

A.LOW speed;Normal Service Water aligned.B.HIGHspeed;

Normal Service Water aligned C.LOW speed;Emergency Service Water alignedD.HIGHspeed;

Emergency Service Water alignedThursday,March

20,200810:35:08AM

19

Harris2008

ROExamRevFINAL 27.Initial conditions:*"A" BoricAcidpumpis

under clearance for motor replacement.

Current conditions:*1 B-SB Emergency SafetyBuslocksoutduetoan

86UV failure.*The crew is performing

an Emergency Boration in accordance

with AOP-002, Emergency Boration,duetoa secondary load rejection.

  • The RO performstherequiredvalve

alignment to provide a boration source.Which ONE of the following describestheaction and/or verification

required to ensure that the required boration flow is achieved?A.Verify a minimumof30GPMonFI-110, Emergency Boration flow.B.Verify a minimum of30GPMonFI-113,BoricAcidflow.

C.Adjust FCV-122 as necessary to achieve a minimumof30GPMon FI-122.1, Charging Header flow.D.Adjust FCV-122 as necessary to achieve a minimum of90GPMon FI-122.1, Charging Header flow.Thursday,March20,200810:35:08AM

20

Harris 2008ROExamRevFINAL

28.Giventhefollowing:*Theplantis

inMode5.*AnRCSleakandlossofRHRoccurs..*ThecrewisperformingactionsofAOP-020,LossofRCSInventoryorResidualHeatRemovalWhileShutdown.*ThecrewisaligningtoprovideRCSMakeupusingCSIPflowin

accordance

withsection3.6,EstablishingSIFollowingaMajorRCSLeak.WhichONE ofthefollowingdescribestherequiredactionstoprovideRCSmakeupin

this condition?A.StartONE(1)CSIP;InitiateflowthoughtheBITB.StartONE(1)CSIP;InitiateflowthoughthenormalcharginglineC.Start TWO(2)CSIPs;InitiateflowthoughtheBITD.StartTWO(2)CSIPs;InitiateflowthoughthenormalcharginglineThursday,March

20,200810:35:08AM

21

Harris2008ROExamRevFINAL

29.Initial Conditions:

  • Surveillance

testingisinprogresson

ContainmentSprayTrain"A".*"A" ContainmentSprayPumpisrunning.*1 CT-24-SAand1CT-25-SB;

Containment

Spray Eductor TestValves,areopen

for testing.*1CT-50-SA, ContainmentSprayPump 1A-SA DischargeValve,isclosed.

Current conditions:*A LOCA occurs.*RCS pressure is 600psig.*Containment

Pressureis10.5psig.

WhichONEofthe following correctlyliststhepositionofthe

Containment

Spray Eductor Test Valvesandthe 1A-SA DischarqeValveforthe

current plant conditions?

1 CT-24-SA and 1 CT-25-SB 1CT-50-SA A.OPEN OPEN B.CLOSED OPEN C.OPEN CLOSED D.CLOSED CLOSEDThursday,March20,200810:35:08AM

22

Harris2008ROExamRevFINAL

30.Given the following:TheplantisinMode1.

12:00 ContainmentSprayPump1

A-SA declared INOPERABLEduetoafailed

surveillance.

12:27 ContainmentSprayPump1B-SBalsodeclared

INOPERABLEduetotheresultsofacommoncausefailureanalysis.

14:21 ContainmentSprayPump1A-SAreturnedto

OPERABLE status.14:40 ContainmentSprayPump1B-SBreturnedto

OPERABLE status.WhichONEofthefollowing

describestheTechnical

Specification

requirements

for operationoftheplant?

Actions to initiateaplantshutdownmust

commencenolaterthan...A.12:27;The.shutdown maybeterminatedno

earlierthan14:21.B.12:27;.The shutdownmaybe terminated

no earlierthan14:40.C.13:27;The shutdown maybe terminated

no earlierthan14:21.

D.13:27;.The shutdown maybe terminated

no earlierthan14:40.Thursday,March20, 200810:35:09

AM 23

Harris2008ROExamRevFINAL

31.Giventhefollowing:*Theplantisoperatingat100%power.*AfailureofthePT-444inputtoPK-444A, Pressurizer

Pressure Master Controller,causedactual

pressurizerpressureto

decreaseto2190psig.

  • PK-444AhasbeenplacedinMANUAL.WhichONEofthefollowing

describestheactionrequiredtoreturnpressureto2235

psig?A.Decrease the controller

output.B.Increase the controller

output.C.Lowerthe

pressuresetpoint

adjustment.D.Raisethe

pressure setpoint adjustment.Thursday,March20,200810:35:09AM

24

Harris2008ROExamRevFINAL

32.Giventhefollowing:*Theunit isinMode6.*Refuelingactivitiesareinprogress.*Afuel assembly hasbeenrupturedduringremovalfromthecore.

  • Radiationlevelsarerising

steadilyandarecurrentlyasfollows:*REM-01 LT-3502A-SA,CnmtRCSLeakDetectionMonitor,isinHIGH

ALARM*REM-01 LT-3502B-SB,CnmtPre-EntryPurgeMonitor,isinHIGH

  • ALARM WhichONEofthefollowing

describesthesystemisolationsignal(s),ifany,thathave

been automaticallyinitiated,andactionrequiredin

accordance

with AOP-013, Fuel Handling Accident?A.ONLY a Containrnent

Pre-EntryPurgeisolationsignalhasbeeninitiated.Performan evacuation

from Containment.B.BOTHNormal

ContainmentPurgeAND Containment

Pre-EntryPurgeisolationsignalshavebeeninitiated.Performan evacuation

from Containment.

C.ONLY a Containment

Pre-EntryPurgeisolationsignalhasbeeninitiated.DispatchRadiationProtectionto

determine if ContainmentEvacuationisrequired.D.BOTHNormal

ContainmentPurgeAND Containment

Pre-EntryPurgeisolationsignalshavebeeninitiated.

Dispatch-RadiationProtectionto

determine if ContainmentEvacuationisrequired..

Thursday, March 20,200810:35:09AM

25

Harris2008ROExamRevFINAL

33.Giventhefollowing:*Theplantisat100%power.*A transient on SGlevelrequiredareactortrip, butthereactordidnottrip.*Thecrewis

performingFRP-S.1,ResponseToNuclearPower

Generation

/ATWS.*Thecrewnotesthatthe

Pressurizerpressureis2350psig.*ControlrodsareinsertinginAUTO.

  • All PressurizerPORVvalvepositionindicatinggreenlightsareonandredlightsareoff.

Which ONE of thefollowingactionsarerequiredinrelationtothePZRPORVs?

A.Verify ONLY ONE PressurizerPORVandBlockvalveOPEN;

reduce pressuretolessthan2135psig.

B.Verify ALL Pressurizer

PORVsandBlockvalvesOPEN;

reduce pressuretolessthan2135psig.

C.Verify ONLY ONE PressurizerPORVandBlockvalve

OPEN;reduce pressuretolessthan2235psig.

D.Verify ALL PressurizerPORVsandBlockvalvesOPEN;

reduce" pressuretolessthan2235psig.Thursday,March

20,200810:35:09AM

26

Harris2008ROExamRevFINAL

34.Giventhe following:*Theplantisat40%power.

  • Intermediate

Range ChannelN-35loses compensating

voltage.*I&Ciscalledtoinvestigate.*Priortoanyactionbyf&C,areactortripoccurs.

WhichONEofthe following describestheexpectedSourceRange

responseinthis conditionandwhy?A.Source Range Instruments

will automatically

energize prematurely;theymustbe

manually de-energized

until approximately

5 minutes post-trip to prevent damage to the detectors.

B.Source Range Instruments

will automatically

energize prematurely;theymustbe

manually de-energized

until approximately15minutes post-trip to prevent damagetothe detectors.C.SourceRange

Instrumentswillnot automatically

energizewhenrequired;theymust

be manually energized approximately

5 minutespost-tripto

preventalossof reactor power indication.D.SourceRange

Instrumentswillnot automatically

energizewhenrequired;

they must be manually energized approximately15minutespost-tripto

preventalossof reactor power indication.Thursday,March

20,200810:35:09AM

27

Harris2008ROExamRevFINAL

35.Initial plant conditions:*TheplantisinMode6withRefuelinginprogress.

Current plant conditions

are:*Fuel movementhasstoppedduetoaproblem

withtheManipulator.*TheMainControlRoomhasbeeninformedthatinitial

troubleshootingisin progress onthe Manipulator.*The troubleshootingteamdesirestooperate the TROLLEY INTERLOCK BYPASSswitchto permitforwardandreversemotionofthe

trolley without the gripper tubeatitstoplimit.

Which ON.Eofthefollowing

describesthepermissionandconcurrence,ifany,requiredforthis action?A.The SRO-FuelHandlingmustapprove.No

concurrenceisrequired.B.The SRO-FuelHandlingmustapprovewiththe

concurrenceoftheSSO.C.The SSOmust approve with concurrenceofthe Manager-Mechanical

Maintenance.D.TheSSO mustapprove.Noconcurrence'isrequired.Thursday,March

20;200810:35:09AM

28

Harris2008ROExamRevFINAL

36.Giventhe following:

  • Refueling is in progress.*A spent fuel assemblyisbeingmovedintheFuelHandlingBuilding(FHB)when

-it's damaged by contactingawallofthepool.

  • SpentFuelPoolarea

radiation monitor RM-1 FR-3566A-SAisinHIGHalarm.

  • SpentFuelPoolarearadiation

monitor RM-1 FR-3567B-SBisin ALERT.WhichONEofthe following describes the effectontheplant?

A.ONLY"A"train ofFuelHandlingBuilding

Ventilation

Emergency Exhaust hasreceivedan

automaticstartsignal.B.BOTH"A"and"B"trainsofFuelHandlingBuilding

Ventilation

Emergency Exhausthavereceived.automaticstartsignals.

c.NEITHERtrainofFuelHandlingBuilding

Ventilation

Emergency Exhaust hasreceivedan

automaticstartsignal,andmanualstartisNOTrequired.

D.NEITHER trainofFuelHandlingBuilding

Ventilation

Emergency Exhaust hasreceivedan

automaticstartsignal,butmanualstartisrequiredby

AOP-013, Fuel Handling Accident.Thursday,March20,200810:35:09AM

29

Harris 2008ROExam*Rev

FINAL 37.Given the following:*A Steam Generator Tube Rupture has occurred.*Off-Site powerhasbeenlost.*Both DG's are operating as required.*Pressurizer

level indicates 10%and lowering slowly.*All plant equipment has responded as expectedforthe plant conditions.

Which ONE of the following describes a plant concern during the performance

of Path-2 for these conditions?

A.Voiding in the inactive regionsofthe RCSduringtherapidRCS

cooldown to target temperature.

B.Loss of ReS subcooling

during depressurizationusingmainor

auxiliary spray.C.Voiding in the inactive regionsoftheRCS during depressurizationusingaPZR PORV.D.Loss of RCS subcooling

due to the timerequiredto

cooldown to target temperature

with condenser steam dumps unavailable.Thursday,March20,200810:35:09AM

30

Harris2008ROExamRev

FINAL 38.Giventhe following:*A reactortriphas occurred from 100%power.*All systems functioned

as designed.Which ONE of the following describes the position of valves associatedwiththeMain

Turbine?A.Throttle Valves-CLOSED Intercept Valves-CLOSED Reheat Stop Valves-OPEN B.Governor Valves-OPEN Intercept Valves-OPEN Reheat Stop Valves-CLOSED C.Throttle Valves-CLOSED Intercept Valves-CLOSED Reheat Stop Valves-CLOSED D.Governor Valves-OPEN Intercept Valves-CLOSED Reheat Stop Valves-CLOSEDThursday,March20,2008

10:35:09 AM 31

Harris2008ROExamRev

FINAL 39.Given the following:*A Steam Line break has occurredon"C"SG.*The crew has performed actions contained in EPP-014,FaultedSG isolation.*SG"C" pressureis50psig.*SG"C" WRlevelis off-scale low.*SG"A"and"B"NR

levelsarebeing controlledat25%.*SG"A"and"B" pressures are approximately900psigandstable.

Which ONE of the following describestheaction required lAW EPP-014,andthe.reason for this action?A.Isolate AFW flow to SG"C";Minimize RCS cooldownandthemassand

energy releasefromthe steam line break B.Isolate AFW flowtoSG"C";Failure of componentsin"CSGmay

occurdueto thermal shock C.Initiate AFW flowtoSG"Catthe MINIMUM verifiable

rate;Feedingthe"C"SGis

required for cooldown,buthigh AFW flow rates may cause an excessiveRCS

cooldownrequiringan

undesired transitionoutof EPP-014 D.Initiate AFW flowtoSG"C"atthe

MINIMUM verifiable

rate;Feeding the"C"SGis required forcooldown,.but high AFW flow rates may cause failure ofSG"C" componentsdueto thermal shockThursday,March

20,200810:35:09AM

32

Harris2008ROExamRevFINAL

40.InitialPlant

Conditions:*The plantisat100%power.

Current Plant Conditions:*Aspuriousturbinetripoccurs.*The C-8interlockfailstooperate.*All other plant equipmentsrespondsasexpected.

Which*ONEofthe following describes the responseoftheSteamDump

Control System (SDCS)andtheoverall

effectontheRCS temperature?A.SDCSwillcontrol

temperatureusingthe TurbineTripController;

RCS temperaturewillbecontrolledatnormalno-load

temperature.B.SDCSwillcontrol

temperatureusingtheLoadRejectionController;

RCS temperaturewillbecontrolledatnormalno-load

temperature.

C.SDCSwillcontrol

temperatureusingthe TurbineTripController;

RCS temperaturewillbecontrolledat

approximately

3 degrees above normal no-load temperature.

D.SDCSwillcontrol

temperatureusingtheLoadRejectionController;

Res temperaturewillbecontrolledat

approximately

3 degreesabovenormal

no-load temperature.Thursday,March

20,200810:35:10AM

33

Harris2008ROExamRevFINAL

41.Giventhe following:*The Reactoriscritical

atthePOAH.*Thecrewis

preparingtoperformaturbinestartup

lAWGP-005,Power

Operation.

Which ONE of the following describestheexpectedrodheightforControlBank

"0" rods lAW GP-005 and thebasisforthisband?A.Between95and

115 steps;Helps ensure IRtripandrodstopbistable

setpointsarenotreached

before theycanbe blocked B.Between130and150steps;

Helps ensureIRtripandrodstopbistable

setpointsarenotreached

before theycanbe blocked C.Greater than95steps;Minimum heightrequiredtoremainaboveRodInsertionLimit

o.Greaterthan130steps;

Mi-nimum heightrequiredtoremainaboveRodInsertionLimitThursday,March20, 200810:35:10

AM 34

Harris2008ROExamRev

FINAL 42.Initial Conditions:

  • The plantisat 1000/0 power.*Testing isin progressonthe AFW system.*The"A" MDAFWpumpis runningwiththe MDAFW FCVsopen.Current Conditions:*Atrip of bothMFWpumps

occurs.*The lowestSGlevelsduringthe

transient were:*SG"A"=18%*SG"B"=*SG"C"=28%Assuming NO operator actions have occured,whichONE of the following describes the current status of the MDAFW Flow Control Valves(FCVs)and TDAFW pump for this event?MDAFW FCVs TDAFW Pump A.Open Running B.Open Secured C.FullOpen Running D.FullOpen SecuredThursday,March

20,200810:35:10AM

35

Harris2008

ROExam Rev FINAL 43.Giventhe following:*The plantisat1 000/0 power.*An ExtremeHI-HI,levelisreceivedin

Feedwater Heater 1A.Which ONE of the following describes the impactontheunitandtheaction,ifany,thatisrequiredin

accordancewithOP-136, Feedwater Heaters?A.ONLY Feedwater Heaters1Aand2Aare

bypassed;Reduce TurbineLoadtolessthan70

0/0.B.ONLY Feedwater Heater1Aand2Aare

bypassed;Ensure reactor powerlessthan 1000/0, NO additional

power restrictionsarerequired

c.FeedwaterHeaters1A,2A,1 B, and 28 are bypassed;Reduce TurbineLoadtolessthan

700/0.D.FeedwaterHeaters1A,2A,1 B, and 28 are bypassed;Ensure reactor powerlessthan100

0/0, NO additional

power restrictionsarerequiredThursday,March20,200810:35:10AM

36

Harris 2008ROExamRev FINAL 44.Given the following:

  • The plant was operatingat98%power whenaloss of off-site power occurred.*Twenty minuteslater,the following plant conditions

exist:*RCS pressure is 2235psigand stable.*RCS Loop THOTis596°Finall3

loops and lowering.*RCS Loop TCOLD is 552°Finall3 loops and lowering.*Core exit TCsindicate

approximately

600°F and lowering slowly.*Steam Generator pressures are approximately1048psigand

stable.Which ONE of the'following describes the current plant conditions?(Steam Tables are provided.)

A.Natural Circulation

doesnotexist.Heat removal must be established

by opening the condenser steam dumps.B.Natural Circulation

exists.Heat removal is being maintained

by condenser steam dumps.C.Natural Circulation

does not exist.Heat removal must be established

by openingtheSG PORVs.D.Natural Circulation

exists.Heat removal is being maintainedbySG PORVs.Thursday,March20,200810:35:10AM

37

Harris2008ROExamRev

FINAL*The plant is in Mode 3.*A loss ofDCBus DP-1B-SBhas

occurred.*The crew is performing

actions of AOP-025,LossofOne EmergencyACBus(6.9kV)or ONE EmergencyDCBus(125V)

Which ONE of the following describesthereasonfor

ensuring that letdown orifice valves are shut in accordance

with AOP-025?A.Preventwater

hammer or flashinginthe letdown line.B.Prevent RCS leakage in excess of Technical Specification

limits.C.Minimize reductioninPZRlevelwithloss

of charging flow.D.Prevent damagetothe Regenerative

Heat Exchanger.

46.Forthe Steam Generator Water Level Control System (SGWLCS),whichONE of the following describes this system's normal operation and program level input?A.SGWLCSisa level dominant system that ultimately

adjustsFeedReg valve positionbylevelerror.

Program level isvariab.lebased

on input from Turbine First Stage pressure.B.SGWLCSisalevel dominant system that ultimately

adjustsFeedReg valve positionbylevelerror.

Programlevelis constant at 57°A, NR.C.SGWLCSis a flow dominant system that ultimately

adjustsFeedReg valve position by mismatch in steam flow VS.feedflow.Programlevelis variablebasedon inputfrom Turbine First Stage pressure.D.SGWLCSisa flow dominant system that ultimately

adjustsFeedReg valve position by mismatch in steam flowvs.feedflow.Programlevelis constantat57%NR.Thursday,March

20,200810:35:10

AM 38

Harris2008ROExamRev

FINAL 47.Given the following:

  • The plantisat100%power.
  • The following alarm has justbeenreceived:
  • ALB-04-2-2,REFUELING

WATER STORAGE LOW LEVEL*All other MCR alarms are clear*The crew enters AOP-008, Accidental

ReleaseofLiquid Waste Which ONE of the following describes the setpoint forthealarmreceived,andthe

action required in accordance

with AOP-008?A.9'4.3%;Immediately

beginrefillingthe

RWSTto abovethealarm setpoint B.94.3%;'Stopall additionstothe RWST C.23.40/0;EnsureRHRand Containment

Spray Pumps are de-energized

D.23.40/0.Ensure CSIP suctions are isolated from the RWST 48.Which ONEol the following instruments

failures will cause actual feedwater flowtothe affectedSGto INITIALLY lower?(Assume selected)A.SGlevel fails low B.Feedwater flow fails low C.Steam pressure fails high D.Steam flow fails low Thursday,March20, 200810:35:10AM

39

Harris2008ROExamRevFINAL

49.Giventhe following:*A Gaseous WastereleaseofGasDecayTankCisinprogress.*An ALERTalarmisreceivedonREM-3546, WPBStack5PIGmonitor.

  • Activity leveLisstable

justabovethe ALERT setpoint.WhichONEof the following describestheactionrequiredin

accordance

with OP-120.07?A.The release MUSTbestopped;releasemay

continue under the same release permitafter

REM-3546 is determinedtobe operableandcurie contentofthereleaseis determinedtobewithinlimits.B.The release MUSTbestopped;anewreleasepermitmustbe

generatedpriorto resuming the decay tank release.C.The release may continue;if activity level approaches

or exceeds theHIGHalarm setpoint,stoptherelease;releasemay

continue underthesamerelease

permit after REM-3546 is determinedtobe operableandcurie contentofthereleaseis

determinedtobewithinlimits.

D.The release may continue;if activity level approaches

or exceedstheHIGHalarm

setpoint,stoptherelease;anewrelease

permitmustbe generated prior to resuming the decay tank release.Thursday,March20,200810:35:10AM

40

Harris2008

ROExamRevFINAL 50.Giventhe following:*The plant is operatingat50%*power.*The Turbine Driven AFWpumpwastakenOOS12hoursagofor

bearing replacement.*Both Motor Driven AFW pump motorshavebeen determinedtobe INOPERABLEduetoa common cause failure analysis.WhichONEofthe following actions is required?A.Immediately

initiateactiontorestoreone

AFWtrainto operable status;power operation is currentlyallowedwithallthree

AFW Pumps Inoperable.

B.Restore at least 2 AFWPumpsto servicewithin1hour,orbeinHot

Standby within the following6hours.C.Restore at least 1 AFWPumpto servicewithin1hour,orbeinHot

Standby within the foHowing6 hours.D.ImmediatelyentertheactionofTS3.0.3andbeinatleastHOT

STANDBYwithin7 hours from the timeitwas determined

that no AFWpumpswere operable.Thursday,March20,200810:35:11AM

41

Harris2008ROExamRevFINAL

51.Giventhefollowing:*The plantisinmode3*RCSheatupisinprogress

As AFWfiowtothesteam

generatorsisincreased,whatwillhappentotheinitialheat

transferratebetweenRCSandthesteamgeneratorsandwhy?Theheat transferratewill...A.increase;

because the-cooler

AFW waterwillincreasethedeltaTbetweentheRCSandthe

steam generators.

B.decrease;because the cooler AFW water will decreasethedeltaTbetween-theRCSandthe

steam generators.C.increase;

because increasingSGlevelcausesSGpressureand

saturation

temperature

to increase.D.decrease;because increasing

SGlevelcausesSGpressureand

saturation

temperature

to decrease.Thursday,March

20,200810:35:11AM

42

Harris2008ROExamRevFINAL

52.Giventhe following:

  • The plantisat 100 oiOpower.*RecoveryfromaLoss of InstrumentBus1DP-1A-S1isin

progress.*The crew has de-energized

the associated

Process Instrumentation

Cabinet (PIC)in preparation

for energizing

Instrument

Bus 1DP-1A-S1.

  • Thecrewis evaluating

bistable statuspriorto energizingthebus.WhichONEofthe following describesthereasonfor

checking bistable status?A.When the Instrumentbusis energizedwiththePIC

deenergized, a reactortripmay occur due to'de-enerqize

to actuate'bistables becoming actuated.Checking other bistablesensures'a ReactorTripwillnotoccur.

B.WhenthePICis energized after the InstrumentBusis energized,'energizeto

actuate'bistables may experience

a momentary inadvertent

trip.Checking other bistables ensuresanESF actuation willnotoccur.C.Bistables are checked to ensurethateach parameter for Process or Protection

goestoits requiredstatewhen the InstrumentBusandPICare

energized.

D.Bistables are checked to ensurethatalllights

areout,verifyingthatthePICnormal

and alternate supply breakersareopenpriorto

reenergizing

the Instrument

Bus.Thursday,March20, 200810:35:11AM

43

Harris2008ROExamRevFINAL

53.InitialPlant

Conditions:

  • Yesterday,alossof ESW Header"A"occurredduetoafailure

shaft shearofthe"A"ESW Pump.*Thecrew completed AOP-022, Attachment

1, Equipment AlignmentDuetoLoss of anESW Header.*Thecrew implemented

OWP-SW, Operations

Work Procedure Service Water,duetothe extendedlossofthe"A" ESWheader.

Current Plant Conditions:*Alossof off-sitepoweroccurs

coincidentwitha safety injection actuation.

WhichONEofthe following describes the alignment of ESWloadsforthe

current plant condition?A."A"EDGwill

NOT automatically

start because implementation

of OWP-SW places the diesel in MAINTENANCE

MODE.B."A"EDGwill

automaticallystart,butmustbe

manually tripped becauseitwillhave

no ESWflow.C."AllEDGwill

NOT automatically

start because implementation

of OWP-SW willhavebarredthediesel.D."A"EDGwill

automaticallystart,but operatorsmustrealign

NSWtothe ESW header.Thursday,March20,200810:35:11AM

44

Harris 2008ROExamRev FINAL 54.Given the following:

  • The plantisin Mode 3.*AFW Pump 1 A-SA is operating to provide secondary inventory.*DCBus DP-1A-SA becomes de-energized.

Which ONE of the following describes the effectonthe operating AFW pump?A.MCRcontrol

switch indication

is extinguished.

Pump remains running.MCRbreaker

controlislost B.MCR control switch indication

is extinguished.

Pump remains running.MCR breaker control is available C.MCR control switch indication

is available.

Pump trips.MCR breaker control is lost D.MCRcontrol

switch indication

is available.

Pump trips.MCRbreaker

control is available 55.Which ONE of the following describes the MAXIMUM continuousratingofthe

Emergency Diesel Generators?

A.6500 KWata power factor of 0.8 leading B.6500 KWata power factor ofO'B lagging C.7150 KWata power factor of 0.8 leading D.7150 KWat a power factor of 0.8 laggingThursday,March

20,200810:35:11AM

45

Harris 2008ROExamRev FINAL 56.Giventhe following:

  • The unitisin Mode 4.*Maintenance

reports that the inner dooronthe Containment

Emergency Airlockwillnotseal

properly after leaving Containment.

  • The crew has declared the inner door INOPERABLEandclosedthe

outer door.Which ONE ofthefoHowing

describes the status of CONTAINMENT

INTEGRITY, per Technical Specification

Definitions,andtherequired

Technical Specification

action?A.Containment

IntegrityISmet;Immediately

verify the outer door closed B.Containment

Integrity IS NOT met;Immediately

verify the outer door closed C.Containment

IntegrityISmet;Verify the outer doorclosedwithin1hour.

D.Containment

Integrity IS NOT met;Verify the outer doorclosedwithin1hour.

57.Which ONEofthe following wouldbeusedto changethealarm setpointsfromthe Main Control Room of a safety related radiation monitor?A.RM-11 B.RM-23 C.RM-23P D.RM-80Thursday,March

20,200810:35:11AM

46

Harris2008ROExamRevFINAL

58.Giventhefollowing:*Thecrew enteredFRP-C.1,Responseto

InadequateCoreCooling,withthe

followinq conditions

present:*Lossof Offsitehasoccurred*CoreExit temperatureis737degreesF*RCS pressureis1650psig*RVLISis 36%WhichONEofthefollowing

describestheconditionoftheRCSandtheactionsrequiredin

responsetothiscondition?A.Saturated,heat

transferisdegraded;Establishan

RCSVentpathtolowerpressureand

temperatureB.Saturated,heat

transfer isin jeopardy;Reinitiate

High PressureSafetyInjectiontorestorecorecooling

C.Superheated, heat transferisdegraded;EstablishanRCS

Ventpathtolowerpressureand

temperature

D.Superheated, heat transferisinjeopardy;

Reinitiate

High PressureSafetyInjectionto

restorecorecoolingThursday,March

20,200810:35:11AM

47

Harris 2008 RO Exam Rev FINAL 59.Given the following:

  • The plant is operatingat55%power.*The following annunciator

is receivedinthe Control Room:*APP-ALB-002-7-2, SERV WTR PUMPS DISCHARGE LOW PRESS*The RO notes that Cooling TowerBasinLevelis

decreasing

rapidly.*Service Water header pressureis45psigand

lowering.*One minute"later, Service Water header pressureis25psigand

continues to lower.*CTMU cannot maintain Cooling TowerBasinlevel.

  • The crew enters AOP-022, Loss of Service Water and completes the immediate actions.*APP-ALB-002-7-2isstillinand

the Cooling TowerBasinLevel

continues to decrease rapidly.*RAB Operator reports that a large volume of water is gushing from overhead piping in the vicinity of 1 SW-276, HeadersA&B Return To Normal SW Header valve.The area is inaccessible.

  • All automatic plant systems have functioned

as designed.Which ONE of the following describes the locationoftheleak,andthe

action required?A.Unisolable

leak locatedintheNormalService

Water System;Trip the reactorandgoto PATH-1.B.Unisolable

leak locatedinthe Emergency Service Water System;Trip the reactor and go toPATH-1.C.Isolable leak locatedinthe Normal Service Water System;Ensure NSW is properly aligned to equipmentlistedin AOP-022, Attachment

1.D.Isolable leak locatedinthe Emergency Service Water System;Ensure ESW is properly aligned to equipmentlistedin AOP-022, Attachment

1.Thursday,March20,200810:35:11AM

48

Harris2008ROExamRevFINAL

60.WhichONE of the followingdescribestheoperationofServiceAir

Header IsolationValve,1 SA-506?A.Closes automatically

when Instrument

Air header pressure decreasesbelow75 psig;Automaticallyreopenswhenpressureincreasesabove79psig.B.Closes automatically

when Instrument

Air header pressure decreases below 75 psig;Must bemanuallyreopenedwhenpressureincreasesabove79psig.C.Closes automatically

when Instrument

Air header pressure decreasesbelow90 psig;Automaticallyreopenswhenpressureincreasesabove94psig.D.Closes automatically

when Instrument

Air header pressure decreasesbelow90 psig;Mustbe manuallyreopenedwhenpressure

increasesabove94psig.Thursday,March20, 200810:35:12AM 49

Harris2008ROExamRevFINAL

61.Giventhe following:*Theplantisat100%power.*An inadvertent

ContainmentSprayactuationhasoccurredonTrain"A".*Train"A" Containment

Sprayhasbeensecured.

  • Containment

pressure indicates(-)2.4inches

H20.WhichONEofthe following describes how Containment

pressurewillberestoredtowithinlimits?

A.Containment

Vacuum Reliefsystemwilloperatetorestore

containment

pressure to-1.5 inchesH20.No other actionsarerequired.

B.Containment

Vacuum Reliefsystemwilloperatetorestore

containment

pressure to-1.5 inches H20.Containmentpurgeoperationisthenrequiredtorestoreto-1.0inchesH20.

C.Containment

Vacuum Reliefsystemwilloperatetorestore

containment

pressure to-1.0inchesH20.No

other actionsarerequired.

D.Containment

Vacuum Reliefsystemwilloperateto

restore containment

pressure to-1.0inchesH20.

Containmentpurgeoperationisthenrequiredtorestoreto-0.5inchesH20.Thursday,March

20,200810:35:12

AM 50

Harris2008ROExamRevFINAL

62..r-IThe plant isat1 00%pm'o'ef:'f'3JZI 10K I e, 1'\.<2-:-?If co'0'?0t\l'..\-\-....

ev+

The operatingcrewhasenteredEPP-013,LOCAOutside

ContainmentduetoMCB indications.

Which ONE ofthefollowing

describestheleaklocationthatwouldbeisolatedfirstin

accordancewithEPP-013,LOCAOutside

Containment,andthemethodfor

confirmation

of leak isolation?A.ExcessLetdownHeatExchanger;PZRlevelrising.B.Excess Letdown Heat Exchanger;

RCS pressure rising.C.RHRHeat Exchanger;PZRlevelrising.D.RHRHeat Exchanger;

RCS pressure risingThursday,March20, 200810:35:12

AM 51

Harris2008ROExamRev

FINAL 63.Giventhe following:*The reactor was tripped on simultaneous

loss oftheMain Feedwater Pumps.*All AFW was subsequently

lost.*RCSBleedandFeedisin

progress in accordance

with FRP-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK.*CoreExit Thermocouples

have stabilizedatan averageof595 of.*Main Feedwater Pump"A"hasbeenstarted.

  • Containment

pressureis1.0psigandstable.

Which ONE of the following describes the methodandrate of establishing

feedwater flow?A.Feedone Steam Generatoratthe MINIMUM controllablerateuntilaSG

WIDErangelevelis

>15%usingthe respective

Feedwater Control Bypass Valve.B.Feedone Steam Generatoratthe MAXIMUMrateuntila

SGNARROWrangelevel

is>250/0usingthe respective

Feedwater Control Bypass Valve.C.Feedall Steam Generatorsatthe MINIMUM controllablerateuntilaSG

WIDErangelevelis

>.150/0usingthe Feedwater Control Valves.D.Feedall Steam Generatorsatthe MAXIMUM rate until aSG NARROWrangelevel

is>250/0 using the Feedwater Control Valves.64.GiventhefoUowing:*A reactor tripandlossof off-site power have occurred.*The crew is performing

a cooldown using EPP-007,NaturaICirculation

With Steam Void in Vessel (Without RVLIS).*Off-Site powerhasbeenrestored.

  • Preparationsarebeing madeto startanRCP.Which ONE of the following describes the minimum PZRlevel required for RCP restart in accordance

with EPP-007,andthereasonforthelevel?

A.25%to ensure minimum inventory for adequate pressure control.B.65%to'ensure minimum inventory for adequate pressure control.C.250/0 to ensure adequate volume for collapsingthevoid D.650/0 to ensure adequate volume for collapsingthevoid Thursday,March20,200810:35:12AM

52

Harris2008

ROExamRevFINAL A.TominimizeRCS

leakage;DepressurizetheRCStoachieveRCSsubcoolingbetween10°Fand20°F[40°Fand50°F];.B.To ensure SI Accumulator

injection;

Depressurize

the RCStoachieveRCSsubcoolingbetween10°Fand20°F[40°Fand50°F];C.To minimizeRCS

leakage;Depressurize

the RCStomaintainRCSsubcooling

justabovelOaF[100°F];D.To ensureSI Accumulator

injection;

Depressurize

theRCStomaintainRCSsubcooling

justabove70°F[100°F];Thursday,March

20,200810:35:12AM

53

Harris2008ROExamRev

FINAL 66.Given the following:*Youare assignedastheROondayshift.*You havebeencalled

for FitnessforDuty screening.*You must leave the ControlRoomfor approximately1.5hours.*TheSSO has given permission

and directed no additional

actions are required beyond those stated in OMM-002, Shift Turnover Package.lAW OMM-002, whichONEofthe followingisthe MINIMUMrequiredforthe

shift relief?Note: (Attachment

14, Documentation

of Short Term AssumptionofDuties)(Attachment

5, Control Operator Shift Turnover Checklist)A.Oral turnover to the remaining Board Operator.Both watchstanders

Initial Attachment14.Nolog entry required.B.Oral turnover to the remaining Board Operator.Both watchstanders

Initial Attachment14and document relief for greaterthan1 hourinthe Control Operator log.C.Perform a turnover using Attachment5.Both watchstanders

Initial Attachment

5.Nolog entry required.D.Perform a turnover using Attachment

5.Enterthe informationinthe Control Operatorslog,andsignthelogover.Thursday,March

20,2008 10:35:12 AM 54

Harris2008ROExamRevFINAL

67.Giventhe following:*A power increaseisinprogressin

accordancewithGP-005, Power Operation.

  • Average PowerRangeNls indicate 400/0 power.*Main Turbine load indicates35%power.*Average Loop DeltaT indicates 420/0 power.WhichONEofthe following describestheactionsrequiredin

accordance

with GP-005?A.Power mustbereducedlessthan30%byall

indicationsanda calorimetric

performed to determineactualpower.

B.Power increase shouldbestoppedanda

calorimetricmustbe performed to determineactualpower.

C.Power increase shouldbestoppedandthe

PRNlsadjustedtomatch

turbine power.D.Power increase may continueusingturbine

powerandno furtheractionisrequired

unless turbine power and averagePRNls

deviate by 50/0orgreater.

68.WhichONEofthe followingactivitiesis

considered

ACCEPTABLE

preconditioning

of equipmentrelated.to

performanceofa surveillance

on that equipment?

A.Lubricationofa valvestempriortoeach

scheduled testing ofthevalve.B.Periodic or occasionalventingofpumpspriortotesting,not

associatedwiththe surveillance

being performed.

C.Adjustingthebolt torqueonavalvecollar

priortostroketimetestingofthevalve.

D.Operationofa pump shortlybeforeatest,if

asituationcouldbeavoidedtooperatethepumpwhile

maintainingplantand personnel safety.Thursday,March20,200810:35:12AM

55

Harris 2008ROExamRevFINAL

69.Giventhe following:*The unitisinMode6.

  • Refueling operationsareinprogress.*The30th fuelassemblyisbeingloadedintothecore.
  • Current Boron Concentrationis2450ppm.

According to GP-009,RefuelingCavityFill,Refueling,andDrain

oftheRefueling

Cavity, Modes5-6-5,whichONEofthefollowingwouldrequirefuelloading

operationstobe stopped immediately?

A.Communicationsislostbetween

Containmentandthe Control Room.B.Waterinthe Spent Fuel PoolinnotclearenoughtoviewtheFueltopNozzles

without supplemental

lighting.C.Boron concentrationdropsby10ppmas

determinedbytwo successive

samples of Reactor Coolant.D.An unanticipatedriseincountratebya

factoroftwooccurson1of2

operableSourceRange

channelsduringanysingleloadingstep.

Thursday, March20,2008 10:35:12 AM 56

Harris 2008ROExamRev FINAL 70.Giventhe following conditionsata work site:*Airborne activity-5>DAC*Radiation level-40 mrem/hr.*Radiationlevelwith shielding-20 mrem/hr.*Time to conduct task WITH respirator-40 minutes.*Time to conduct task WITHOUT respirator-

30 minutes.Assumptions:

  • The airborne dosewitha respiratorwillbezero.*A dose rate of 40 mrem/hrwillbereceived

while placing the shieldinq.

Assume no benefit from shielding during placement.*All tasks will performedbyoneworker.

  • Shieldingcanbeplacedin15

minuteswithor without a respirator.

  • The shieldingwillnot removed.Which ONE of the followingwouldresultin

thelowest whole body dose?A.Conduct task WITHOUT respirator

or shielding.

B.Conduct task WITH respirator

and WITHOUT shielding.

C.Place shielding while wearing respirator

and conduct task'WITH respirator.

D.Place shielding while wearing respirator

and conduct task WITHOUT respirator.Thursday,March

20, 200810:35:12AM

57

Harris 2008ROExamRev FINAL 71.Per DOS-NGGC-0004, AdministrativeDoseLimits, which ONE of the following describes the annual Progress Energy dose limitandthe MINIMUM authorization

required for an individual

to exceed that limit?A.2000 mrem;Superintendent

-Radiation Protection

B.2000mrem;Site Vice President C.4000 mrem;Superintendent

-Radiation Protection

D.4000mrem;Site Vice President Thursday, March 20, 200810:35:12

AM 58

Harris2008ROExamRev

FINAL 72.Initial Conditions:

  • The unit is at100%power.Current Conditions:
  • The following alarm is received:*ALB-001-7-1, ACCUMULATOR

TANK A HI-LO PRESSURE*The RO reports the following indications:*ColdLeg Accumulator"A" pressure is 650psig and slowly increasing*ColdLeg Accumulator"A"levelis75

%andslowly'

increasing

Which one of the followingistheaction

required lAW the appropriate

Annunciator

Plant Procedureandthe OPERABILITY

of the"A"ColdLeg Accumulator (CLA)?A.Drain"A" CLA to lower pressure;CLA"A"is INOPERABLE

B.Verify Nitrogen to the accumulators

is isolated and vent excess accumulator

pressure;CLA"A"is INOPERABLEC.Drain"A" CLA to lower pressure;CLA"A"is OPERABLE D.Verify Nitrogen to the accumulators

isisolated*andvent

excess accumulator

pressure;CLA"A'!is OPERABLEThursday,March

20,2008 10:35:13AM

59

Harris2008ROExamRev

FINAL 73.Giventhe following:*At1302,a steam generatortubeleakis

identified.*At 1318,a plant shutdown is commenceddueto exceeding TS leakage limits.*At1319,an

UnusualEventis declared by the Site Emergency Coordinator.(SEC)*At1321,a reactortripoccurs.*At1327,the

crew identifiesSG"A"astherupturedSG.*At1330,an

ALERT is declaredbytheSEC.Which ONE of the following describesthelatesttimethattheinitial

notification

to State/County

officialsANDtheNRCisdue?

State/County

NRC A.1334 1334 B.1334 1419 C.1345 1419 D.1345 1430Thursday,March

20,200810:35:13AM

60

Harris2008ROExamRevFINAL

74.Giventhe following:

One ShutdownBank-A,Group2Rodhasdroppedintothecore.*Thecrewis

recovering

thedroppedrod.

  • ALB-13-7-1, ROD CONT SYSTEM URGENT FAILUREisreceived.

WhichONEofthe following describesthereasonforthealarmandtheplant

response?A.Withdrawing

the rodwhiletheremainingGroup2LiftCoilsare

deenergized.

Rod withdrawalisblockeduntilthealarmisreset.

B.Initiation

of an"out"signalto SOBank"A"Rods,anditsGroup1rodsdonotmove.

Rod withdrawalisblockeduntilthealarmisreset.

C.WithdrawingtherodwhiletheremainingGroup2LiftCoilsare

deenergized.

Rod withdrawal

is unaffectedandrecoverymaycontinue.

O.Initiationofan"out"signalto SOBank"A"RodsanditsGroup1rodsdonotmove.

Rod withdrawal

is unaffectedandrecoverymaycontinue.Thursday,March20, 200810:35:13

AM 61

Harris2008ROExamRev

FINAL 75.Giventhe following:*TheUnithas

experiencedaSBLOCA.

  • EPP-009, Post LOCA Cooldown and Depressurizationisin progress.*AllRCPsarerunning.*RCS pressureis1690psig.
  • AnRCS cooldownhasbeeninitiatedby.

dumpingsteamtothe

atmosphere.

Which ONE of the following describestherequired

RC.P configuration'lAWwith EPP-QOg,andthe basisforthis configuration?A.AllRCPs shouldbe stopped;minimize ReS inventorylosswhen'the

break uncoversB.One RCPshould be stopped;produces effective heat transfer,providesboronmixingforRHR

operations, and provides RCS pressure controlC.AllRCPs should be left running;ensures symmetricheattransfertotheS/Gs,aidsinRCS

pressurecontrol,and

prevents steam voidinginthe Reactor vessel headD.TwoRCPs should be stopped;minimizes RC.Sheat inputandstill produces effective heat transferandRCS pressure control You have completed the test!Thursday,March20,200810:35:13AM

62

Harris2008*301ROInitialLicenseExamination

References1.SteamTables