ML081140047
ML081140047 | |
Person / Time | |
---|---|
Site: | Harris |
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
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
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
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:
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
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
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