ML082680192
| ML082680192 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 09/24/2008 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| Download: ML082680192 (104) | |
See also: IR 05000261/2008301
Text
Final Submittal(BluePaper)
FINAL RO/Si(.O WRITTEN EXAMINATION
AND
kEy
HLC-08NRCWrittenExam
1000008AK1.011
D2000011EA1.121
D3000015AK2.101
A 4 000022AA1.011 C5000025AA2.061
C6000026AA1.021
B 7000029G2.1.281
D 8000038G2.1.201
B 9000040AA1.021
A 10000054AA1.021
B 11000056AA2.671
A 12000057G2.2.221
A 13000058G2.2.361
C14000062AK3.021
C 15000065AA2.051
D 16 WE04EK3.11
B 17 WEllEK1.21 B 18000077AK2.061
D 19000001AK2.081
D 20000005AK3.011
D 21000028G2.4.41
C 22000032AK1.011
D 23000037AA1.061
B 24000068AA2.051
C 25000069AK1.011
D 26WE13EK2.21
B 27WE15G2.2.381
C 28003K6.041 C 29004A1.051 A 30005K1.061 B 31006K2.011 B 32 007 K4.011 B 33008A4.051 B 34 010 K5.011 B 35 012 K6.011 C 36013G2.2.381
C 37 022 A3.011 A 38 026A1.011 B 39039G2.4.201
D 40059A2.051 B 41 061 A3.011 B 42 062 K2.011 D 43063K3.021 B 44064G2.1.71
C 45 073 A4.011 A46076 A2.011 B47078K1.031
B 1
HLC-08NRCWrittenExam48103K3.011
A49004K3.081
D50007 Al.02 1 B51039 Kl.0ll B52062A3.051
C53039K3.061
C54026A2.041
C55064K6.071
B56002K6.071
B57014 Kl.0ll C58015 K4.011 B 59 017K3.011 C60027 Kl.0l 1 B61034A4.021
A 62035A2.061 B 63041A4.061 C64045 Kl.18 1 A65075K2.031
A 66 G2.1.261 D 67G2.1.281 B 68G2.2.61 A69G2.2.401
C 70G2.3.41 C 71 G2.3.131 B 72G2.3.71 B73G2.4.161
C 74 G2.4.221 A 75 G2.4.231 A 76000008G2.4.111
B77000022AA2.031
B 78000025AA2.071
B 79000026G2.2.381
D 80000055EA2.011
D 81000058G2.1.321
A 82000024AA2.021
A 83000033AA2.101
A 84000059G2.2.141
A 85000074G2.4.211
A86003A2.031
B 87013G2.1.71
A 88061G2.1.271
B 89010A2.031 A 90103G2.4.301
B 91002G2.2.401
B 92011G2.4.501
D 93071G2.2.251
D 94 G2.1.411 B 2
HLC-08NRCWrittenExam
95 96 97 98 99 100 G2.2.181 G2.2.151 G2.2.361
G2.4.61 G2.4.81 G2.4.181 B D C D B B 3
HLC*i08 1 NRC Written Exam 1.Given the following:
-The plant is operatingat1 000/0 RTP.-The PRTisat 74°hand110 of.-Aload rejection resultsina Reactor Trip.-Followingthetrip,a Pressurizer
Safety valve opens,andwill NOT reseat.-The PRT rupture disks function as designed.-Containment
pressure peaksat18 PSIG.Which ONE(1)of the following is the MAXIMUM temperature
indicated by the Safety Valve tailpiece RTD during the entire event?A.222 of.B.254 of.C.328 of.D.338 of.1
HLC-08 NRC Written Exam2.Giventhefollowing:-Theplantwas
operatingat100%RTPwhenaLargeBreakLOCA
occurred.-All systems functionedasdesigned.-Thecrewhas
transitionedtoEPP-10, TRANSFERTOLONGTERM
RECIRCULATION.Howwasthe Charging HeaderSEALEDandwhy?
A.IVSWinitiation
automaticallysealedthe Charging Header.Toprevent leakagebyseatingtheRCPSealInjectionline
check valves.B.Amanualvalve
alignmentofIVSWwas performedtosealthe Charging Header.Toprevent leakagebyseatingtheRCPSealInjectionline
check valves.C.IVSWinitiation
automaticallysealedthe Charging Header.Toprevent leakage from Containment.
D.Amanualvalve
alignmentofIVSWwas performedtosealthe Charging Header.Toprevent leakage from Containment.
2
HLC-08 NRC Written Exam 3.Theplantis
operating at 8%RTPandreadyto
synchronizetothegridwhenthefollowingconditionsarenoted:
-APP-001-B2,RCPLABYRTHSEALLODPisilluminated.
-APP-001-D2,RCP#1SEAL LEAKOFFHIFLOWis illuminated.-Seal LeakoffFlowforRCP"AllispeggedHIGH.-Seal LeakoffFlowforRCPs"B"and
IIC" have decreased slightly.-FCV-626, THERM BARRIER OUTLET,indicatesCLOSED.WhichONE(1)ofthefollowing
describesthefailurethathas
occurredandwhatactionsare
required?A.#1sealhasfailed;Tripthereactor,tripRCP"All;enterPATH-1.
B.The Thermal Barrierhasfailed;Tripthereactor,tripRCP"A";enterPATH-1.
C.#1sealhasfailed;PlaceplantinMODE3lAWGP-006, NORMAL PLANT SHUTDOWN FROM POWER OPERATIONTOHOT SHUTDOWN,andtripRCP"A".
D.The Thermal Barrierhasfailed;PlaceplantinMODE3lAWGP-006, NORMAL PLANT SHUTDOWN FROM POWER OPERATIONTOHOT SHUTDOWN,andtripRCP"A".
3
HLC-08NRC Written Exam4.Giventhe
following:-Theplantis
operatingat1 00%RTP.-RCSboron concentrationis600ppm.-Earlierintheshift,VCTlevel
transmitter,LT-115,failedLOW.-Allactionsof
AOP-003, MALFUNCTION
OF REACTOR MAKEUP CONTROL,havebeen completed.-VCTlevel transmitter,LT-112,is currently30inchesandstable.
Subsequently:-I&Creportstheyhave
inadvertently
deenergizedLT-112.WhichONE(1)ofthe
following describeshowthe ACTUALVCTlevelandT
AVGwillrespond?(Assumeno operator action)A.VCTlevel increases;
T AVG increases.
B.VCTlevel decreases;
T AVG increases.
C.VCTlevel increases;
T AVG decreases.
D.VCTlevel decreases;
TAVG decreases.
4
HLC-08 NRC Written Exam 5.ALargeBreakLOCAhasoccurredandColdLegRecirculationisbeing
established
lAW EPP-9, TRANSFERTOCOLDLEG RECIRCULATION.-RHRPump"A"hasjustbeenstarted.-RHRPump dischargepressureis
fluctuatingby40PSIGandflowis
approximately
3350GPMand oscillating.
-APP-001-A7,RHRHXLOFLOW,hasalarmedandcleared
numerous times.-APP-003-D3,PRTHI/LOLVL,hasjust
illuminatedandisverifiedHIGH.
WhichONE(1)ofthefollowing
malfunctionswouldcausetheaboveevent?
A.ECCSSump screens are clogging.B.SI-871,CSPUMP
SUCTIONRELIEFVALVEiscycling.
C.RHR-706,RHRRELIEFVALVEiscycling.
D.SI-887,RHR
RECIRCULATIONTORWSTVALVEdischas
separatedfromitsvalvestem.
5
HLC-08 NRC Written Exam 6.Giventhe following:-TheCrewis
respondingtoaLBLOCAlAWPATH-1.-ALL attempts to startCCWPumpshavefailed.-AOP-014,CCW
SYSTEM MALFUNCTION,Section"C",CCWPUMP
DISCHARGEPRESSURELOWisbeingperformed.-AnAOwas dispatchedtoperform Attachment
1, EMERGENCY COOLING TO CHARGING PUMPS.-ChargingPump
IIBIIisrunningwithspeed
controller
in MANUALsetat 75°;6.-AllRCP Thermal BarrierDPindicationsareat
approximately3.5inches.-Step9of AOP-014,Section"C"directs
increasing
ChargingPumpspeedtoobtainRCP
Thermal BarrierDPof>5inches.WhichONE(1)ofthe
followingisthebasisfor
INCREASINGtheRCP Thermal Barrier DP?A.Theincreased
chargingensuresRCPSeal
leakagewillbe minimized.
B.Toprovide adequatesealinjectionforRCPSealcooling.
C.The increased chargingensurestheChargingPump
temperaturesremainlowuntil
Attachment1is completed.
D.Increasingthe
ThermalBarrierDPisin
preparation
for restartingtheRCP(s)afterCCWis
restored.6
HLC-08 NRC Written Exam7.WhichONE(1)ofthefollowing
conditionsmustbemetto
ACTUATEAMSACANDwhatistheresultofthe
actuation?
A.2/3S/GLevels<11
%for25 seconds;DirectReactorTrip.
B.1/3S/GLevels<11
%for25seconds;
Direct Turbine Trip.C.1/3S/GLevels<11
%for25 seconds;DirectReactorTrip.
D.2/3S/GLevels<11
%for25 seconds;Direct Turbine Trip.7
H LC-08 NRC Written Exam8.Giventhe
following:-Thecrewis
respondingtoaSGTRinS/G"A"withalossof
offsite power.-SupplementGisinprogress.-ALLS/G pressuresare1025PSIG.-Thestepin
SupplementGwhichrequiresSteamFlowtobeisolatedfromtherupturedS/Ghas justbeenreached.WhichONE(1)ofthe
following describestheactionthatisrequiredregardingtherupturedS/GPORVlAW Supplement
G?A.Raisethe RUPTUREDS/GPORV controller's
setpointtoMAXIMUM.
B.Verifythe RUPTUREDS/GPORV controller's
setpointat1035PSIG.
C.Isolate InstrumentAirtotheRUPTUREDS/GPORV.
D.Verifythe RUPTUREDS/GPORVcontrollers'
setpointis15PSIGlessthantheINTACTS/GPORV controllers.
HLC-08NRC Written Exam 9.Giventhefollowing:-Theplantwas
operatingat1RTPwhenS/G"A" Steamlineseversinside
Containment.WhichONE(1)ofthefollowing
describestheFeed WatervalvesthatwillCLOSEasaresultoftheabove conditions?
A.FRVsforALL
THREES/Gs(FCV-478,488,498)FRVBYPsforALL
THREES/Gs(FCV-479,489,499)FWHDR SECTIONValvesforALLTHREES/Gs (V2-6A/B/C)
B.FRVsforALL
THREES/Gs(FCV-478,488,498)FRVBYPsforALL
THREES/Gs(FCV-479, 489,499)FWHDR SECTIONValveforS/G"A"ONLY(V2-6A)
C.FRVforS/G"A" ONLY (FCV-478)FRVBYPforS/G"A"ONLY(FCV-479)FWHDR SECTIONValveforS/G"A"ONLY(V2-6A)
D.FRVforS/G"A" ONLY (FCV-478)FRVBYPforS/G"A"ONLY(FCV-479)FWHDR SECTIONValvesforALLTHREES/Gs (V2-6A/B/C)
9
HLC-08 NRC Written Exam10.Giventhefollowing:-TheReactorisat
4°k>RTPinpreparationforTurbinestartup.-Main FeedwaterPump"A"isunderclearanceformaintenance.-Main FeedwaterPump"8 11isoperating.-NarrowrangeSteam
Generatorlevelsareat44%.WhichONE (1)ofthefollowing
statementsdescribestheAFWPumpstatus
immediately
after Main FeedwaterPump"8"trips?
A.TheMDAFWandSDAFWPumpsmustbemanuallystarted.
B.TheMDAFWPumpshaveautostartedbuttheSDAFWPumpmustbe
manuallystartedif required.C.TheSDAFWPumphasautostartedbuttheMDAFWPumpsmustbe
manuallystartedif required.D.TheMDAFWand
SDAFWPumpshaveautostarted.
10
HLC-08 NRC Written Exam 11.DuringaLossofAllACPowerevent,EPP-1,LOSSOFALLACPOWER,directstheisolationofsealcoolingforeventsof15minutesormorewithoutRCPsealcooling.WhichONE(1)ofthefollowingisthebasisforisolatingsealcooling?
A.RCPsealsandshaftsmaybedamagedbythermalshockwhenpowerisrestoredtotheOSBus.B.RCPthermalbarriersare
susceptibletorupturefromthermal
shockwhenpowerisrestoredtotheOSBus.
C.SteambindingoftheChargingPumpsfromRCPseal
leakoffflashingwhenaChargingPumpisrestarted.
D.RCPThermalBarriersare
susceptibletorupturefromwater
hammerwhenpowerisrestoredtotheOSBus.
11
HLC-08NRCWrittenExam12.Giventhefollowing:-TheplantisinMODE6withrefuelinginprogress.
-Instrument
Bus 2 trips.WhichONE(1)ofthefollowingLimiting
Conditions
for Operation (LCO)REQUIRED ACTIONS is applicable?
A.VerifyonePAMSourceRange
monitorprovidesindicationintheCRwithin15minutesANDLogindicatedSRcountrateevery30minutes.
B.VerifyonePAMSourceRange
monitorprovidesindicationintheCRwithin15minutes,suspendcore
alterationsANDsuspendpositivereactivity
additions.
C.IMMEDIATELYinitiateactiontorestoreoneSR
monitor to OPERABLEANDsuspendcore
alterations
AND suspendpositivereactivityadditions.
D.IMMEDIATELYinitiateactiontorestoreoneSR
monitor to OPERABLEANDlogindicatedSRcountrateevery30minutes.
12
HLC-08NRC Written Exam 13.Giventhefollowing:-Theplantisoperatingat100
%RTP.-Two electriciansareperformingMST-902,"A"and"B" STATION BATTERY TEST, obtaining batterypilotcelltemperatures,electrolytelevelsandbatterygroundchecks.-Duringthe
batterychecks,BatteryCharger"B"was
inadvertently
tripped.WhichONE(1)ofthefollowingdescribesthe
effectonBatteryBus"B"andanyLCOsthatare
applicable?BatteryBus"B"is...
A.de-energized.AnLCOisineffecttorestorepowertothebus.
B.de-energized.LCO3.0.3isineffect.
C.at-120VDC.AnLCOisineffecttorestoreabattery
chargertoservice.
D.at-120VDC.NOLCOisineffectduetoBatteryBus"B"energizedwithinnormal
parameters.
13
HLC-08 NRC Written Exam 14.Giventhe following:-TheUnitwas
operatingat100%RTP,whena PressurizerPORVfailurecausedaReactorTrip.
-APP-008-F7,SOUTHSWHDRLOPRESS,isreceived.-SouthSW headerpressureis29PSIGandslowly
decreasing.-NorthSW headerpressureis42PSIGandstable.
Valve Nomenclature:V6-16A,SWNORTH
HEADER SUPPLY TO TURBINE BUILDING.V6-16B,SW SOUTH HEADER SUPPLY TO TURBINE BUILDING.V6-16C,SW ISOLATION TO TURBINE BUILDING.Basedontheaboveconditions,whichONE(1)ofthefollowing
describes the correct pressureandtheresponseoftheService
Water system?AfterONE(1)minutewithSouthSWheaderpressurelessthan...
A.40PSIG,ONLYvalvesV6-16B,andV6-16Cwillclose.
B.40PSIG,ValvesV6-16A, V6-16BandV6-16Cwillclose.
c.31 PSIG,ONLYvalvesV6-16Band
V6-16Cwillclose.
D.31PSIG,ValvesV6-16A, V6-16BandV6-16Cwillclose.
14
HLC-08 NRC Written Exam 15.Giventhe following:-Theplantis
operating at 12°k>RTP.-Aline breakinthe InstrumentAirheaderhasoccurred.-IA header pressureis82PSIGand
decreasing
slowly.-Thecrewhas
implementedAOP-017,LOSSOF
INSTRUMENT
AIR.In accordancewithAOP-017,whichONE(1)ofthefollowing
REQUIRESthecrewtomanuallytripthe reactorandenterPATH-1?
A.Letdownisolates.
B.FCV-1740,IADRYERBYPASSValvehasOPENED.
C.RCPsealinjectionflowsincreaseto20
GPM/Pump.D.IA header pressure decreasesto58PSIG.15
HLC-08 NRC Written Exam 16.Giventhe following:-TheReactorhastrippedduetoaLOCA.-ThecrewhasenteredPATH-1.WhichONE(1)ofthefollowingwould
justifyentryintoEPP-20,LOCA
OUTSIDE CONTAINMENT?
A.AuxiliaryBuildingSumplevelrapidlyincreasing.
B.Abnormalradiationinthe
Auxiliary Building.C.RWSTlevelat
27°k.D.Decreasing
CV Pressurewitha decreasing
RCS pressure.16
HLC-08NRC Written Exam 17.Giventhe following:-Theplanthas
experienced
a ReactorTripandLOCA.-RHRisNOT available.-Thecrewhas
implementedEPP-15,LOSSOF
EMERGENCY RECIRCULATION,andisreadyto performStep18, IIInitiateRCS
CooldowntoCold Shutdown",EPP-15,Step18
directsthecrewtocooldowntheRCSat
_(a)_, using_(b)_S/Gs.A.(a)maximum rate(b)only intact B.(a)lessthan100
of/hour(b)anyintact
preferred,butfaultedif
necessary C.(a)maximum rate(b)any intact preferred, but faulted if necessary D.(a)lessthan100
of/hour(b)only intact 17
HLC-08NRC Written Exam 18.Which ONE(1)ofthefollowingisthereasonforplacingthe
GovernorvalvesontheLimiterwhileat 100 0h RTP?A.Reducethe effectsofturbineoverspeedintheeventofaloadrejectionor
Generator outputbreakertrip.
B.Prevent GeneratoroverloadresultingfromTurbineImpulsechannelfailuresand
malfunctions.
c.Prevent Generator load fluctuationsinducedfromImpulsestagepressurefluctuations.
D.Minimize Generator load fluctuationstopreventReactorpowerfromexceedinglicense
limit.18
HLC-08 NRC Written Exam19.Giventhe
following:-Theplantisat
45%power,withpower
escalation
to 100%RTPin progress.-ControlBank
"0"rodsareat185stepsonthestep
counters.-RodControlisin
AUTOMATIC.-TheRO observes ONLY Control Bank"0"rods'IRPI indicators
are increasing.-T AVGis1.5 of lowerthanT REF.The described conditionsindicate...
A.an electrical
problem on Instrument
Bus 7 A.B.aControlBank
"0" Signal ConditioningModulefault.
C.aNormalRod
Withdrawal.
D.an Uncontrolled
Rod Withdrawal.
19
HLC-08 NRC Written Exam 20.Giventhefollowing:-Theplanthasexperienceda
Reactor/TurbineTripfrom 100 0k RTP.-Thecrewis
performingEPP-4,REACTORTRIPRESPONSE.-RodBottomLightforControlRodM6isNOTlit.-IRPIshowsControlRodM6at225steps.WhichONE(1)ofthefollowingaction(s),ifany,mustbeperformedlAWEPP-4andwhy?
A.Borateto1950ppm.Torestore adequateshutdownmargin.
B.Borateforworthofmostreactiverod.Tomaintain
adequateshutdownmargin.
C.InitiateborationtoColdShutdownrequirements.Torestore adequateshutdownmargin.
D.Noactionrequired.
Adequateshutdownmarginexists.
20
HLC-08 NRC Written Exam 21.Giventhefollowing:-Theplantis
operating at 50%RTPfollowinga50%loadrejectionfrom
100°;6 RTP.-APP-003-C8,PZRPROTHILEVELis
illuminated.-All PressurizerLevelchannels,LI-459A,460,and461, indicate 92%.-RTBA&B CLOSED(RED)indicationis
illuminated.WhichONE(1)ofthe
followingistheNEXT procedurethecrewshould
implement?
A.AOP-015, SECONDARY LOAD REJECTION.
INSTRUMENT
FAILURE.C.PATH-1.D.FRP-S.1, RESPONSETONUCLEAR POWER GENERATION
/ATWS.21
HLC-08NRC Written Exam 22.I&Chas just completed a surveillanceonthehighvoltagepower
supplytothe Source Range nuclear instruments.
The surveillance
determined
the as-found voltagewas1400VDC,insteadofthenormal1600VDC.
WhichONE(1)ofthefollowing
describes the effectandreasonthe
lower voltagehasonSRN-31andN-32
instrument
response?N-31andN-32
indicationwill....A.decrease becausealowerinput
voltagetothe Pre-Amplifierresultsinoverallreduced
detector efficiency.
B.increaseduetoareductionofpulse
height discriminationsthatallowsmoreionizationeventstopass
through the discriminator
circuit.C.increaseduetoareductionin
gamma compensation,allowingmore, lower energy eventstopass throughthepulse height discriminator
circuit.D.decrease because reduced voltageresultsin fewerionpairs reaching the detector electrodesduetolower
potentialappliedtothe
detector.22
HLC-08 NRC Written Exam 23.Giventhe following:-Theplantisat
30%RTP,withapowerescalationin
progress.-APP-036-C7, R-24 MONITORHIhasjustalarmed.WhichONE(1)ofthefollowing
describestheR-24,MAIN
STEAMLINEN-16 DETECTORalarmandwhatactionsarerequiredforcurrentplant
conditions?
A.TheR-24alarmisvalid,crewmustenterAOP-005, RADIATION MONITORING
SYSTEM.B.R-24 informationisusefulonlyfortrending.IfR-15, CONDENSER AIR EJECTOR ORR-19,STEAM
GENERATOR BLOWDOWN confirms evidenceofleakage,referto
AOP-035, S/G TUBE LEAKAGE.C.TheR-24alarmisvalid,crewmustenter
AOP-035,S/GTUBE LEAKAGE.D.R-24 informationisusefulonlyfortrending.AdjustR-24
leakage model firmware to support leakage confirmationandleaklocation
determinationlAWEMP-034, OPERATIONOFR-24A, Band C.23
H LC-08 NRC Written Exam 24.WhichONE(1)ofthefollowing
describesthetypeofindication
availableandlocation
OUTSIDEoftheControlRoomto
monitor the availabilityofHeatSink?
A.SteamFlowand
FeedwaterFlowforall3S/Gsatthe
SecondaryControlPanel.
B.All3S/GLevelsandPressuresattheChargingPumpRoomPanel.
C.All3S/GLevelsandPressuresatthe
SecondaryControlPanel.
D.SteamFlowand
FeedwaterFlowforall3S/Gsatthe
ChargingPumpRoomPanel.
24
HLC-08NRC Written Exam25.Giventhefollowing:-ALargeBreakLOCAhasoccurred.-Leakagehasbeenidentifiedfrom
ContainmenttotheAuxiliaryBuilding.
-Containment
pressurepeakedat36PSIGandhasloweredto18PSIG.Currentleakageis
approximatelyofthepeakleakrate.
25
HLC-08NRC Written Exam 26.Giventhe following:-AReactortriphasoccurred.Thecrewispreparingto
transitionfromPATH-1aftercheckingSINOT
actuatedORrequired.-ALLS/Glevelsare1
0-14°hNarrowRange.-AFWflow indicates400GPM.-S/G IIA II and IIB II pressuresindicate1080PSIG.-S/G IICII pressureindicates1150PSIG.WhichONE(1)ofthefollowing
describesthestatusofCSF-3, HEATSINKandtheinitialcrewactionsto addresstheevent?A.RED;Checktotal
feedwaterflowlessthan300GPMdueto
operatoraction,lAWFRP-H.1, RESPONSETOLOSSOF SECONDARYHEATSINK.B.YELLOW;Isolate feedwater to affectedS/GlAWFRP-H.2, RESPONSETOS/G OVERPRESSURE.
C.YELLOW;CheckanyS/Glevel
greater than 75%lAWFRP-H.3, RESPONSETOS/GHIGHLEVEL.
D.YELLOW;Checklevelin affectedS/Glessthan
160/0lAWFRP-H.5, RESPONSE TO STEAM GENERATORLOWLEVEL.26
HLC-08 NRC Written Exam 27.Giventhe following:-ALargeBreakLOCAhasoccurred.-ALL systems automatically
resp-ondasexpected.-CVSumplevel
indicates378inchesandisincreasingslowly.WhichONE(1)ofthefollowingidentifiestheMAJORconcernorlicenselimitation
associatedwiththisconditionlAWFRP-J.2, RESPONSE TO CONTAINMENT
FLOODING?A.Containment
integrity is compromisedduetoreduced
volume and potentiallyincreasedCV
pressure.B.Dilutionofsump
waterwithCCWorFire
Watermaycauseareturntocriticality.
C.Water introducedintotheECCSsumpbeyond
capacity can potentially
affecttheoperationofvital equipment.
D.Lossof inventory from interfacing
cooling systems can potentiallyresultinalossofabilitytoremoveheatfromthereactorcore.
27
HLC-08NRC Written Exam 28.During Containmentisolationvalvetesting, CCW-716A,CCWtoRCP ISOLATION VALVE, was inadvertently
CLOSEDwithRCP"B"running.WhichONE(1)ofthefollowingRCP
components
sufferedalossofcoolingwaterflow?
A.MotorBearingOilCoolersONLY.
B.Thermal Barrier Heat Exchangers
ONLY.C.Thermal Barrier Heat ExchangersandMotorBearingOilCoolers.
D.MotorAirCoolers, ThermalBarrierHeat
Exchangers,andMotorBearingOilCoolers.
28
HLC-08NRCWrittenExam
29.Giventhefollowing:-AS/GTubeRupturehas
occurred.-AnRCSCooldownhasbeen
performedlAWPATH-2.-RapidRCS depressurizationisinprogress.WhichONE(1)ofthe
following describeshowChargingFlowwillbe
controlled
during subsequentactionslAWPATH-2?
A.Reduce ChargingFlowtoMINIMUMwhenPZRlevelexceeds
100/0.B.Reduce ChargingFlowtoMINIMUMONLYwhenPZRlevel
exceeds 24%.C.MaintainMAXIMU,M
ChargingFlowuntilPZRlevelexceeds24%ANDSIPumpsare
stopped.D.Maintain MAXIMUM ChargingFlowuntilRCSpressureislessthanrupturedS/Gpressure.
29
HLC-08NRC Written Exam 30.Giventhe following:-ASmallBreakLOCAoccurred3hoursago.-RCS pressureis210PSIG.-The alignmentoftheECCSforColdLeg
Recirculation
is completelAWEPP-9, TRANSFERTOCOLDLEG RECIRCULATION.WhichONE(1)ofthefollowing
describes the current RHR/ECCS alignment?ONE(1)RHRPumpandONE(1)SIPump
operatinginseries (Piggy-backmode),withthe...
A.RHRANDSIPumpsuctionsfromtheCVsump, dischargingtoRCScoldlegsviaRHRHX(RHRPump),andtheBIT.
B.RHRPumpsuctionfromtheCVsump, dischargingthroughRHRHXtoSIPumpsuction,SIPump dischargingtoRCScoldlegsviatheBIT.
C.RHRPumpsuctionfromtheCVsump, dischargingthroughRHRHXtoRCScoldlegsANDtoSIPumpsuction,SIPump
dischargingtoRCScoldlegsviatheBIT.
D.RHRPumpsuctionfromtheCVsump, dischargingthroughRHRHXtoSIPumpsuction,SIPump dischargingtoRCShotlegs.
30
HLC-08 NRC Written Exam 31.The plant is operating at 100%RTPwitha normal electrical
lineup.-Breaker 52/10, 4kV Bus 1-2TieBkr,trips
OPEN.-An inadvertent
8afety Injection signal occurs.Which ONE(1)ofthe following describes the source of powertothe 81 Pumps?A.81 Pumps"A"and"C"are
powered from off-site power.B.81 Pump"A"is powered fromEDG"A", 81 Pump"C"is powered from off-site power.C.81 Pump"A"is powered from off-site power, 81Pump"C"is powered fromEDG"B".D.81 Pumps"A"and"C"are
poweredfromEDG"A"and"B", respectively.
31
HLC-08NRC Written Exam 32.Giventhefollowing:-TheplantisinMODE3followingaloadrejectionandReactorTripfrom100%RTP.-Duringtheload
rejection/tripevent,a PressurizerPORVopenedforseveral
seconds and reseated.-Pressurizer
Relief Tank Pressure, TemperatureandLevelhave
increased:
-Pressure=4.8PSIG.-Temperature
=153 of (APP-003-B3,PRTHITEMPis
illuminated.)-Level=80%-TheCRSSdirects
implementationofOP-103, PRESSURIZER
RELIEF TANK CONTROL SYSTEMtoreducePRT
temperature.
WhichONE(1)ofthe
following methodswillbeusedtoreducePRT
temperature?
A.ContinuouslyfillthePRTwithPrimary
WateranddrainthePRTviatheRCDTPumpas
necessarytomaintainlevelbetween
70%-80%.B.DrainthePRTviatheRCDTPumpto
70 0k, then alternatelyrefillwith
Primary Water anddrainviatheRCDTPump.
C.FillthePRTwithPrimary
Waterto90%,then
alternatelydrainthePRTviatheRCDTPumpandrefillwithPrimaryWater.
D.Monitor Automatic Primary Waterspray,drainPRTviatheRCDTPumpas
necessary tomaintainlevelbetween
70%-80%.32
HLC-08 NRC Written Exam 33.Giventhe following:-TheplantisinEPP-10, TRANSFERTOLONGTERM
RECIRCULATION.
-APP-002-E5,SIPMP COOL WTRLOFLOWalarmisreceived.WhichONE(1)ofthefollowing
describesthecauseand
effectofthealarm?
A.LossofCCWtotheSIPumpBearingHeat
Exchangers;canresultin
overheatingthepump bearings.B.LossofCCWtotheSIPumpSealCoolers;canresultinlossofSIPumpseals.
c.LossofSWtotheSIPumpBearingHeat
Exchangers;canresultin
overheatingthepump bearings.D.LossofSWtotheSIPumpSealCoolers;canresultinlossofSIPumpseals.
33
HLC-08NRC Written Exam 34.Giventhefollowing:-TheplantisinMODE3.-Thecrewis
performingaplantheatup.
-Pressurizerlevelis 50°k>.-BOTH PressurizerLiquidSpaceandSteamSpace
temperatureindicatorsread622
of.WhichONE(1)ofthefollowingindicatesactualPressurizerPressure?
A.PI-444=1783PSIG.B.PI-445=1798PSIG.C.PI-455=1813PSIG.D.PI-456=1828PSIG.34
HLC-08 NRC Written Exam 35.Giventhe following:-Theplantis
operating at 6%RTPpreparingfor
Turbine roll.-PZRlevelchannelLT-459failed4hoursago.The
bistableshavebeentrippedandallactionsare
complete per AOP-025, RTGB INSTRUMENT
FAILURE.-PZRlevelis
currently 25°konChannelsLT-460and461.WhichONE(1)ofthefollowing
describes the effectsontheplantifPZRlevelchannelLT-461failsHIGH?
A.AReactorTripduetohighPZRlevel.
B.AReactorTripduetolowPZRpressure.
C.The ReactorwillNOTtrip,signalisblockedbyP-7.
D.The ReactorwillNOTtrip,signalisblockedbyP-10.
35
HLC-08NRC Written Exam 36.Giventhe following:-Theplantis
operatingat100%RTPwhenPT-455,PZR
PRESSUREfailsLOW.-Priorto OWP-029, PPT-1 implementation,alossof power to INSTRUMENTBUS2 occurs.WhateffectdoesthishaveonthePZRPressureESFAS
bistables?(Assume NO operator action)A.PZRPressure
ESFAS bistablesonTrain IIA II ONLY are tripped.EnterLCO3.3.2, ConditionD,Placechannelintripwithin6hours.
B.PZRPressure
ESFAS bistablesonTrain IIB II ONLY are tripped.EnterLCO3.3.2, ConditionD,Placechannelintripwithin6hours.
c.PZRPressure
ESFAS bistablesonTrainIIA
IIANDTrain IIB II are tripped.EnterLCO3.0.3,PlaceplantinMODE4within13hours.
D.PZRPressure
ESFAS bistablesonTrainIIA
IIANDTrainIIB
II are tripped.ALL InstrumentationLCOsare currently met.36
HLC-08 NRC Written Exam 37.Giventhe following:-Theplantis
operatingat100%RTP.-HVH-3hasbeen
experiencing
intermittentproblemsandthefanhasbeenstopped.
-APP-002-E6, HVH-1/2/3/4
EMERGENCY CONTROL is illuminated.-CVRECIRCFANHVH-3indicationontheRTGBis
extinguished.-An inadvertent
SafetyInjectionisreceived.WhichONE(1)ofthefollowing
describes the currentstatusofHVH-3?TheFan...A.isstoppedandwillNOTAUTOstart.
B.isstoppedandcanbestartedfromtheRTGB.
C.hasAutostartedduetotheSIsignal.
D.hasAuto startedduetoaLowAirFlowsignal.
37
HLC-08NRC Written Exam 38.Giventhe following:-AReactorTripandSafetyInjectionhaveoccurredduetoaFaultedS/G.-480VBusE-1faultoccurred
coincidentwiththeReactorTripandremains
deenergized.-Thecrewis
performingactionsofPATH-1anddirectionhas
justbeengiventoOPENthe
breakerforHVS-1onMCC-5.
-Containment
pressureis17PSIGandincreasing.WhichONE(1)ofthe
followingistheimpactontheplantandtheactionrequired?
Accident analysis has determined
that Containment
pressure...A.MAYexceeddesign.
ImmediatelytransitiontoFRP-J.1, RESPONSETOHIGH CONTAINMENTPRESSURE,duetoan
ORANGE condition.
B.willNOTexceed
design.ContinueinPATH-1untilSPDSisresetand
transitionasdirected.
C.MAYexceeddesign.ContinueinPATH-1untilSPDSisresetand
transitionasdirected.
D.willNOTexceed
design.TransitiontoFRP-J.1if480VBus
E-1 CANNOTberestored.
38
HLC-08 NRC Written Exam 39.Giventhefollowing:-A SGTRhasoccurredandthecrewis
performingactionslAWPATH-2.-Priorto ReScooldownto
target temperature,aNOTEwarns
against exceeding SteamLineflowratesinexcessoftheHighSteamLineflowsetpoint.
WhatconditionistheNOTEwrittentoprevent?
A.MSIVsisolationonHighSteamLineDeltaP.
B.AnSIinitiationonHighSteamLineDeltaP.
C.AnSIinitiationonHighSteamflow
coincidentwithLowT AVG" D.MSIVsisolationonHighSteamflow
coincidentwithLowT AVG.39
HLC-08 NRC Written Exam 40.Giventhe following:-Theplantis
operating at 50°k>RTPfor maintenanceonMFP IIB II.-The following Main Feedwater Pump IIA II parametersarereported:-Feedpump suctionpressureis225PSIG.-DP indicationonFS-1444AequatestoMain
FeedwaterPumpFlowof2850GPM.
Whatisthe expected responseofthe FeedwaterSystemandwhatactionsarerequiredlAW
AOP-010, MAIN FEEDWATERICONDENSATE
MALFUNCTION.?MFP"A"will...
A.triponlowsuction
pressureONLY,tripthe
ReactorandenterPATH-1.
B.triponlowsuction
pressure coincidentwithlowflow,triptheReactorandenterPATH-1.
C.remainrunning;
verifyFCV-1444,MFP
nAilRECIRCVALVEisOPEN.
D.remainrunning;
verify HCV-1459, FEEDWATER HEATERBYPASSisOPEN.
40
HLC-08 NRC Written Exam 41.Giventhe following:-The plant is operatingat30%RTP.-Alossofthe
Startup Transformer
occurs concurrentwitha Reactor Trip and Safety Injection.-AllS/Glevels
indicate approximately
20%.Which ONE (1)ofthe following describes the AFW system status?A.MDAFW Pumps ONLY are runningat325GPMeach.
B.MDAFW Pumps are runningat325GPMeachAND
SDAFW Pump is runningat500GPM.C.MDAFW Pumps ONLY are runningat300GPMeach.
D.MDAFW Pumps are runningat300GPMeachAND
SDAFW Pump is runningat630GPM.41
HLC-08 NRC Written Exam 42.WhichONE(1)ofthe
following describesthepower suppliesforthe Circulating
Water Pumps?A.CWPump"A"-
4KVBus1CWPump"B"-
4KVBus2CWPump"C"-
4KVBus3 B.CWPump"A"-
4KVBus5CWPump"B"-4KVBus4CWPump"C"-
4KVBus1 C.CWPump"A"-
4KVBus2CWPump"B"-
4KVBus3CWPump"C"-4KVBus4
D.CWPump"A"-
4KVBus1CWPump"B"-4KVBus4
CWPump"C"-
4KVBus5 42
HLC-08 NRC Written Exam 43.ONE(1)minutefollowingaReactorTrip,BOTH52/8,SOUTHOCBand52/9,NORTHOCBbreakersremainCLOSED.WhichONE(1)ofthefollowingdescribesthefailurethatcausedBOTHofthesebreakerstoremainCLOSED?
A.LossofDCBusIIA
II.B.LossofDCBus
118 11.C.Lossofthe AuxiliaryPanelDC.D.Lossofthe AuxiliaryPanelGC.43
HLC-08 NRC Written Exam 44.Giventhefollowing:-Theplantisoperatingat1
000/0 RTP.-480VBus E-1MainBreakertripsonovercurrent.-EDG"A"startsand
re-energizes480VBusE-1.-TheEDG"A" Jacket WaterCoolantPumpshaftshearsduringEDGstart.-APP-01 O-F2,EDGACOOL WTR HI/LaTEMPilluminates.-APP-01 O-A2,EDGA TROUBLE illuminates.WhichONE(1)ofthefollowingistheimpactofthepumpshaftfailureonEDG
Automatic operation?EDG"A"will....
A.shutdownwhencoolantwaterpressuredecreasesto9PSIG.
B.shutdownwhencoolantwater
temperaturereaches205
of.C.continuetooperateduetoALLEDGenginetripsbeingdefeated.
D.continuetooperateduetorunpriorityfromthe
Undervoltage
start.44
HLC-08 NRC Written Exam 45.Giventhe following:-Theplantis
operatingat1RTP.-Areleaseof
Waste CondensateTank(WCT)"A"isinprogress.
-APP-036-E7, RAD MONITOR TROUBLE,isreceived.-TheBOP OperatorreportstheFAILlightforR-18,LIQUID
WASTE DISPOSAL EFFLUENTmonitor,isON.WhichONE(1)ofthefollowing
describesthestatusofRCV-018,LIQUID
WASTE RELEASE ISOLATION VALVE?RCV-018will...
A.NOT automaticallyclose.Thereleasemustbe
manually terminatedfromthe WasteDisposalPanel.
B.automaticallyclose,andR-18RadMonitormustberesettoreopen.
C.NOT automaticallyclose,andmustbe
CLOSED manuallyfromtheRTGB.
D.automaticallyclose,andmustberesetbycyclingthevalves
controller.
45
HLC-08 NRC Written Exam 46.Giventhe following:-Theplantis
operatingat1 00%RTP.-APP-008-E8,NSWHDR STRAINERPITHILVLhas
illuminated.
-APP-008-F8,NORTHSWHDRLOPRESShasilluminated.WhichONE(1)ofthefollowingare
ImmediateActionslAW
AOP-022,LOSSOFSERVICE
WATER?A.CloseV6-12D,NORTHSW
HEADER ISOLATIONVALVE,thenGotoSectionF,SERVICE
WATER PITS FLOODINGININTAKEAREA.
B.CloseV6-12BANDV6-12C,SWX-CONNValves,thenGotoSectionF,SERVICE
WATER PITS FLOODINGININTAKEAREA
C.CloseV6-12BANDV6-12C,SWX-CONNValves,thenGotoEPP-28,LOSSOF
ULTIMATEHEATSINK.D.CloseV6-12D,NORTHSW
HEADER ISOLATIONVALVE,thenGotoEPP-28,LOSSOF
ULTIMATEHEATSINK.46
HLC-08NRC Written Exam 47.Giventhefollowing:-Alinebreakonthe
InstrumentAirheaderinside
Containmenthasresultedinafull
depressurization
of Containment
Instrument
Air.-ThecrewhasclosedPCV-1716, INSTRUMENTAIRTO CONTAINMENT.Basedontheaboveconditions,whichONE(1)ofthefollowingcanbeoperatedfromthe
RTGB?A.PressurizerSprayvalves.
B.Pressurizer
PORVs.C.LetdownLineIsolationvalves.
D.ChargingLineIsolationvalves
47
HLC-08 NRC Written Exam 48.Giventhefollowing:-TheplantisinMODE4,coolingdownlAWGP-007,PLANT
COOLDOWNFROMHOT SHUTDOWNTOCOLD SHUTDOWN.-A spuriousR-11alarmcausesaCVVentilationIsolationsignal.-V12-8andV12-9,CVPURGE
OUTLETVALVES,bothhavedual
OPEN/CLOSED
indications.WhichONE(1)ofthefollowing,ifany,isrequiredto
satisfyLCO3.6.3, CONTAINMENT
ISOLATION VALVES?A.Closeand deactivateEITHERV12-8ORV12-9within1hour.
B.Closeand deactivateBOTHV12-8ANDV12-9within1hour.
C.OverrideEITHERV12-8ORV12-9CLOSEDwithin1hour,usingCVPurgeValveblocking
mechanism.
D.PlantisinMODE4;Noactionrequired.
48
HLC-08 NRC Written Exam 49.Giventhe following:
-ChargingPumpIIA IIisbeing recirculated
following maintenance.-Duringthe
restoration, CVC-291, CHARGINGPUMPIIA II TO SEAL INJECTION Valvewasopenedpriortoclosing
CVC-277C, CHARGINGPUMPIIA II RECIRCROOTvalve.
WhichONE(1)ofthe
followingisthe impactontheCVC System?A.This operationwillhaveNO
effectontheCVCSystem.
B.ONLY Chargingflowon FI-122A decreases to minimum.C.ONLY Seal InjectiononFI-124,FI-127andFI-130
decreases to minimum.D.SealInjectiononFI-124,FI-127andFI-130AND
Chargingflowon FI-122A decreases to minimum.49
HLC-08 NRC Written Exam 50.Giventhe following:-Theplantis
operatingat100 ok>RTP.-PCV-455C,PZRPORVwasleakingbyandhascausedthe
following conditionsinthe PRT:-APP-003-C3,PRTHIPRESS
illuminatesandPRT pressureis6PSIG.-PRTlevelis
69°k>andstable.-PRT Temperatureis115 ofandstable.WhichONE(1)ofthefollowingactionswouldbeusedtoreducePRT
pressurelAWOP-103, PRESSURIZERRELIEFTANK
CONTROL SYSTEM?A.OpenRC-523,PRTDRAIN,toreduce
pressureto1-2PSIG.
B.OpenRC-549,PRTVENT,toreduce
pressureto3-5PSIG.
C.OpenRC-523,PRTDRAIN,toreduce
pressureto3-5PSIG.
D.OpenRC-549,PRTVENT,toreduce
pressureto1-2PSIG.
50
HLC-08 NRC Written Exam 51.Which ONE (1)of the following describes the design feature(s)
which act to limit S/G blowdown rate for a Steam Break accident?A.Swirl Vane Separators
in the upper S/G internals.
B.A set of 7 venturis within each S/G outlet nozzle.C.A Steam Flow venturi in each Main Steam line, located at the operating floor.D.MSIVs are required to close within 5 seconds.51
HLC-08 NRC Written Exam 52.Given the following:-A Loss of Instrument
Bus 1 has occurred.-The crew is performing
actions contained in AOP-024, LOSS OF INSTRUMENT
BUS.-The Pressurizer
Pressure Controller (PC-444J)AUTO light illuminates
for approximately
15 seconds, then extinguishes, and then the MANUAL light is illuminated.
Which ONE (1)of the following correctly describes the status of Instrument
Bus 1 and method of control?A.Instrument
Bus 1 power is NOT restored.Operate Pressurizer
Heaters and Spray valves manually.B.Instrument
Bus 1 power is restored.PC-444J AUTO control has failed, continue to operate in MANUAL.C.Instrument
Bus 1 power is restored.Restore PC-444J to AUTO control.D.Instrument
Bus 1 power is NOT restored.Continue to operate PC-444J in MANUAL.52
HLC-08 NRC Written Exam 53.Given the following:
-The plant is operating at 100%RTP.-The Reactor Operator reports the following:
-RCS Temperature
is lowering rapidly.-RCS Subcooling
is increasing.
-Pressurizer
level is lowering rapidly.-A Reactor Trip and Safety Injection occurs.-Containment
pressure is now reported as 11 PSIG and increasing.
Which ONE (1)of the following describes the event in progress and the current status of the Condenser Steam Dumps?A.Steam Line Break;Condenser Steam Dumps are available.
B.Large Break LOCA;Condenser Steam Dumps are available.
C.Steam Line Break;Condenser Steam Dumps are NOT available.
D.Large Break LOCA;Condenser Steam Dumps are NOT available.
53
HLC-08 NRC Written Exam 54.Given the following:-A LOCA has occurred coincident
with a loss of the Startup Transformer.
-EDG"A" has failed to start.-The crew is performing
actions lAW PATH-1.-Containment
pressure is at 12 PSIG and increasing.
-CV Spray Pump"B" was inadvertently
stopped.Which ONE (1)of the following describes the status of CV Spray Pump"B"?A.The pump will restart because CV pressure is above 10 PSIG.B.The pump is stopped, but can be manually restarted by taking the switch to START.C.The pump is locked out and can be restarted by placing the Containment
Spray Key Switch in the OVRD/RESET
Position.D.The pump is locked out and can ONLY be restarted if the CV Spray Pump Breaker control power fuses are removed and reinstalled.
54
HLC-08 NRC Written Exam 55.Given the following:-A leak in the EDG"A" Air Start Receiver is reducing starting air pressure.Which ONE (1)of the following is the FIRST pressure at which the EDG Air Receiver LeO is entered?A.<100 PSIG.B.<210 PSIG.c.<216 PSIG.D.<220 PSIG.55
HLC-08 NRC Written Exam 56.Given the following:
-The plant has been restarted following a forced outage.-Loop flow measurements
have determined
that RCP"B" impeller has degraded such that its RCS loop flow has DECREASED by 5°k from its original value.-The other RCS loop flows remain UNCHANGED.
Which ONE (1)of the following would be a result of the decreased flow rate in Loop"B"?A.Demand on the PZR Control Group heaters at 2235 PSIG will be lower.B.The reactor core will operate closer to DNB when at full power.C.Core Delta-T at full power will be lower.D.The reactor core will operate further from DNB when at full power.56
HLC-08 NRC Written Exam 57.During withdrawal
of the Control Banks, APP-005-F2, ROD BOTTOM/ROD DROP will CLEAR when Control Bank"A" reaches...A.20 steps as sensed by the Pulse ToAnalogConverter.
B.35 steps as sensed by the Pulse To Analog Converter.
C.20 steps as sensed by the IRPls.D.35 steps as sensed by the IRPls.57
HLC-08 NRC Written Exam 58.During MODE 6, I&C requests permission
to remove two (2)Power Range NI Channels from service at the same time to expedite calibrations.
What impact, if any, will this have on NI System operations?
Simultaneously
removing two (2)Power Range Channels from service will...A.have no impact.All trip and interlock signals from the Power Ranges are blocked during the shutdown and prior to entry into MODE 6.B.insert a P-10 signal which will de-energize
both Source Ranges.C.initiate a Reactor Trip signal, which will result in a Feedwater Isolation Signal being generated.
D.have no impact.Power Range Channels are not required to be OPERABLE in MODE 6, and Source Ranges and Gammametrics
provide full range core monitoring.
58
HLC-08 NRC Written Exam 59.Given the following:
-Both InadequateCoreCooling
Monitors (lCCM)have been deenergized.-A Loss of Offsite Power and Reactor Trip occur.-Natural Circulation
conditions
are being verified in Supplement
E, NATURAL CIRCULATION
VERIFICATION.
Which ONE (1)of the following indications
verifies that Natural Circulation
has been established?
A.T HOT is decreasing.
T COLD is stable.S/G pressure is stable.B.T HOT is stable.T COLD is decreasing.
S/G pressure is stable.c.T HOT is decreasing.
T COLD is decreasing.
S/G pressure is decreasing.
D.T HOT is stable.T COLD is stable.S/G pressure is decreasing.
59
HLC-08 NRC Written Exam 60.Given the following:
-An RCS LOCA has occurred which resulted in a Containment
Spray Actuation.
-ALL ESF equipment has functioned
as designed.-NO ESF signals have been reset.-Containment
pressure is 8 PSIG.The CRSS has directed that SI-845A, SAT DISCH VLV be CLOSED.Which ONE (1)of the following action(s)must the crew perform to allow SI-845A to be CLOSED?Reset...A.SI Signal, and then reset the Containment
Spray Actuation Signal.B.Containment
Spray Actuation Signal ONLY.C.Containment
Isolation Phase B Signal ONLY.D.SI Signal, and then reset the Containment
Isolation Phase B Signal.60
HLC-08 NRC Written Exam 61.Given the following:
-The plant is in MODE 6.-Refueling activities
are in progress.-APP-005-C1, SR HI FLUX AT SHUTDOWN is illuminated.
Which ONE (1)of the following describes the High Flux at Shutdown alarm setpoint and the system response?SR counts are greater than...A.3 times AII-Rods-In
background
and the CV Evacuation
horn will sound.B.3 times AII-Rods-In
background
and the LOCAL Evacuation
alarm will sound.C.2 times AII-Rods-In
background
and the CV Evacuation
horn will sound.D.2 times AII-Rods-In
background
and the LOCAL Evacuation
alarm will sound.61
HLC-08 NRC Written Exam 62.Given the following:
-The plant was operating at 100%RTP when a Small Break LOCA occurred.-Safety Injection has been actuated.-RCPs were tripped due to loss of subcooling.
-Containment
pressure is at 4.5 PSIG.Which ONE (1)of the following describes the REQUIRED action lAW PATH-1 to ensure that core cooling is maintained
during this event?A.Maintain ALL S/G levels>8%.B.Maintain ONE S/G level>18%.C.Maintain ALL S/G levels>18%.D.Maintain ONE S/G level>8%.62
HLC-08 NRC Written Exam 63.Given the following:-A Steam Generator Tube Rupture has occurred.-The crew is preparing to cooldown to a target temperature
of 480 of lAW PATH-2.-A Loss of Off-Site Power occurs.-All equipment functions as required.Which ONE (1)of the following describes how the cooldown to target temperature
will be accomplished?
A.Intact S/G PORVs controllers
set to 6.2 (553 PSIG).B.Steam Dumps in Pressure Control mode set to 3.95 (553 PSIG).C.Intact S/G PORVs controllers
set to maintain full OPEN valve position.D.Steam Dumps in Pressure Control mode set to maximum rate.63
HLC-08 NRC Written Exam 64.Which ONE (1)of the following describes how the Reactor Protection
System provides Runback signals to the Turbine Generator?
The RPS initiates a Turbine (1)runback when 2/3 OT Delta T (2)2/3 OP Delta T signals reach their runback setpoints.
A.(1)Reference (2)OR B.(1)Valve Limiter (2)OR C.(1)Reference (2)AND D.(1)Valve Limiter (2)AND 64
HLC-08 NRC Written Exam 65.Given the following:
-EPP-1, LOSS OF ALL AC POWER, is being performed.
-The RGS has been isolated.-The Inside AO and maintenance
technicians
are working on starting an EOG.-There is NO SI signal present or required.Subsequently, EOG"A" was started.Which ONE (1)of the following actions is necessary following the energization
of 480V Bus E-1?Verify Service Water Pumps...A."A" and"B" are running.B."A" and"G" are running.C."B" and"0" are running.D."G" and"0" are running.65
HLC-08 NRC Written Exam 66.Given the following:
-Operators are performing
valve lineups to support BOP Flush.-Several valves above Heater Drain Tank IIB II are to be repositioned.
-The valves are approximately
15 feet above the floor level.In accordance
with SAF-NGGC-2172, what fallprotectionor
safety measure(s)
is/are required to perform the valve manipulations
safely?A.Tie or secure an extension ladder to structural
components
at BOTH the top and bottom, use 3-point contact while on the ladder.B.Don a full body harness and attach it to the Extraction
Steam line support or snubber rods.C.Secure a step ladder to a structural
component at the bottom, use 3-point contact while on the ladder.D.Don a full body harness and attach it to an approved anchorage point.66
HLC-08 NRC Written Exam 67.Given the following:
-The plant is operating at 100%RTP.-A failure of PT-444 input to PC-444J, PZR PRESSURE controller
has resulted in an actual Pressurizer
pressure increase to 2273 PSIG.-PC-444J has been placed in MANUAL.Which ONE (1)of the following describes the action required to return pressure to 2235 PSIG?A.Decrease the controller
output.B.Increase the controller
output.C.Decrease the pressure setpoint potentiometer.
D.Increase the pressure setpoint potentiometer.
67
HLC-08 NRC Written Exam 68.Given the following:
-The crew has discovered
an error in an AOP.The AOP identified
the proper title of a pressure indicator, but describes the indicator as PI-2098 instead of the correct number PI-2089.-A temporary procedure change has been initiated to correct the error.Which ONE (1)of the following statements
applies to the temporary procedure change process lAW PRO-NGGC-0204, PROCEDURE REVIEW AND APPROVAL?A.The temporary change expires after 21 days unless made permanent by the procedure owner (Operations
Manager).B.The change must be processed as an INTENT change.C.The procedure owner (Operations
Manager)must approve the temporary change prior to use in the field.D.The expiration
date of the temporary change is set at 4 months from the approval date.68
HLC-08 NRC Written Exam 69.With the plant operating at 100 0 k RTP, which ONE (1)of the following equipment failures requires the EARLIEST ACTION per Technical Specifications?
Failure of...A.EDG"A".B.Battery Charger"A".C.RC-551C, PZR SAFETY VALVE.D.PCV-456, PZR PORV.69
HLC-08 NRC Written Exam 70.Given the following:-A 25 year old female started working at Robinson as a permanent employee on July 2nd of this year and has an NRC Form 4 on file.-She previously
worked at Salem and had received 200 mRem exposure for this year.-She has NOT declared pregnancy.
-She has received NO management
exposure extensions
and NO emergency exists.Which ONE (1)of the following is the additional
exposure she can receive withoutmanagementconcurrence
at Robinson this year?A.300 mRem.B.1800 mRem.C.2000 mRem.D.3800 mRem.70
HLC-08 NRC Written Exam 71.Given the following:
-You are in the Spent Fuel Pit performing
fuel handling operations.-A fuel handling accident occurs, and an evacuation
is ordered via a PA announcement.
Which ONE (1)of the following is the area designated
as the assembly point for this event lAW AOP-013, FUEL HANDLING ACCIDENT?A.Immediately
outside the Spent Fuel Pit Building door.B.Landing halfway down the stairs outside the Spent Fuel Pit Building.C.Immediately
outside the New Fuel Handling Building door.D.At the bottom of the stairs outside the Spent Fuel Pit Building.71
HLC-08 NRC Written Exam 72.Given the following:
-While entering the plant to relieve the shift, you notice smoke coming from the Auxiliary Building.-You have NOT logged onto any RWP or obtained proper dosimetry (EAD).-Your assistance
is required in the Auxiliary Building.Which ONE (1)of the following is allowed/required
lAW FP-001, FIRE EMERGENCY for the stated conditions?
A.An exception to the requirement
for obtaining an EAD AND RWP login is allowed for qualified members of the Fire Brigade.B.An EAD must be obtained AND RWP login must be completed prior to Auxiliary Building entry.C.An exception to the requirement
for obtaining an EAD AND RWP login is allowed ONLY IF an RC Tech is present to monitor personnel entry/exit
to the Auxiliary Building.D.RWP login is NOT required, and emergency dosimetry (EAD)is obtained from the Work Control Center.72
HLC-08 NRC Written Exam 73.Given the following:-A loss of Component Cooling Water has occurred.-The crew has implemented
AOP-014, COMPONENT COOLING WATER SYSTEM MALFUNCTION.-A Reactor Trip has occurred.Which ONE (1)of the following describes the continued use of AOP-014 after the Reactor Trip?A.Use of AOP-014 is NOT allowed during EOP performance.
Continue use of AOP-014 upon exiting the EOP network.B.Use of AOP-014 may ONLY be used concurrently
with actions of PATH-1.Use must be suspended upon transition
to any other EOP.C.Use of AOP-014 may ONLY be used concurrently
with EOPs if NO RED or ORANGE path FRPs are being performed.
D.Use of AOP-014 may be used concurrently
as necessary under ALL conditions
of EOP use, as long as use of the AOP does NOT delay the mitigation
of the event.73
HLC-08 NRC Written Exam 74.Given the following:
-The crew is responding
to a RED PATH lAW FRP-P.1.-The STA has just reported a RED PATH on the Heat Sink CSFST AND an ORANGE PATH on Core Cooling CSFST.(Assume ALL conditions
have been validated)
FRP-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK.FRP-P.1, RESPONSE TO IMMINENT PRESSURIZED
THERMAL SHOCK CONDITION.
FRP-C.2, RESPONSE TO DEGRADED CORE COOLING Which ONE (1)of the following is the crew's response?A.Immediately
transition
to FRP-H.1.B.Immediately
transition
to FRP-C.2.C.Continue with FRP-P.1 until complete, then transition
to the highest priority CSF.D.Continue with FRP-P.1, while concurrently
implementing
the highest priority CSF.74
HLC-08 NRC Written Exam 75.Which ONE (1)of the following is the basis for checking for a Faulted S/G prior to checking Containment
conditions
for other possible major accidents during performance
of PATH-1?A.Indications
could potentially
mask other failures.B.Early isolation of AFW is required to prevent challenging
the RCS Integrity CSFST.C.Because of the potential for personnel injury during Steam Break accidents outside of Containment.
D.Because of the increased potential for Containment
failure if all S/Gs are faulted.75
HLC-08 NRC Written Exam 76.Given the following:
-The plant is performing
a controlled
shutdown from 100°(0 RTP.-A PZR Safety valve has momentarily
lifted and continues to leak by.-APP-003-F6, PZR SAFETY VLV LINE HI TEMP, has illuminated
and the crew has performed the applicable
actions.-The crew has stopped the controlled
shutdown at 95%power and has entered AOP-016, EXCESSIVE PRIMARY PLANT LEAKAGE.Which ONE (1)of the following describes the strategy, in the proper order, the crew will use to address the event before tripping the Reactor and entering PATH-1?(Assume the actions performed do NOT stop the level decrease)A.(1)Maximize charging on ALL three Charging Pumps.(2)Isolate Letdown.B.(1)Maximize charging on two Charging Pumps.(2)Isolate Letdown.(3)Start and maximize Charging on the remaining Charging Pump.C.(1)Isolate Letdown.(2)Maximize charging on ALL three Charging Pumps.D.(1)Isolate Letdown.(2)Maximize charging on two Charging Pumps.(3)Start and maximize Charging on the remaining Charging Pump.76
HLC-08 NRC Written Exam 77.Given the following:
-The plant is operating at 100%RTP.-VCT makeup is in progress.-The following indications
are noted:-BA Transfer Pump IIA II is running.-PW Pump IIA" is running.-FCV-113A, BA FLOW, OPEN.-FCV-113B, BLENDED MU TO CHG SUCT, CLOSED.-FCV-114A, PRIMARY WTR FLOW DILUTE MODE, OPEN.-FCV-114B, BLENDED MU TO VCT, CLOSED.-45 seconds later:-APP-003-D5, BA FLOW DEV alarm has illuminated.
-APP-003-E5, MAKEUP WATER DEV alarm has illuminated.
-BOTH VCT level channels have decreased to 15 inches and continue to decrease.Which ONE (1)of the following has caused the alarms and what actions are required to mitigate the event?A.The Charging Pump suction has swapped to the RWST.Isolate Letdown and minimize Charging flow.B.The air supply line to FCV-113B has failed, causing the valve to fail CLOSED.Attempt to establish Makeup to the VCT via FCV-114B.C.The Charging Pump suction has swapped to the RWST.Reduce Turbine load as necessary to maintain T AVG within+/-1.5 of of T REF.D.The air supply line to FCV-113B has failed, causing the valve to fail CLOSED.Attempt to establish Makeup via CVC-356, BORIC ACID BLENDER BYPASS TO CHARGING PUMP SUCTION.77
HLC-08 NRC Written Exam 78.During Mid-Loop operations, the following indications
and conditions
are noted:-RHR Pump IIA II is operating, FCV-605, RHR HEAT EXCHANGER BYPASS is in AUTO.-FI-605 indicates 3600 GPM and is oscillating
+/-100 GPM.-RHR Pump discharge pressure is oscillating
+/-30 PSIG.-RCS standpipes
indicate-73 inches (RTGB)and-74 inches (LOCAL).Which ONE (1)of the following is the NEXT action required lAW AOP-020, LOSS OF RESIDUAL HEAT REMOVAL?A.Reduce total RHR flow by throttling
FCV-605 to 2850 GPM.B.Stop RHR Pump"A" to prevent pump damage.c.Establish Charging flow to restore RCS level?-68 inches.D.Isolate Letdown flow by adjusting HIC-142, PURIFICATION
FLOW CONTROLLER
to 0%.78
HLC-08 NRC Written Exam 79.Given the following:
-The plant is in MODE 3.-The plant experiences
a loss of 480V Bus E-1 and EDG"A" does NOT start.-CCW Pump"C" breaker has tripped on overload.-CCW Pump IIA II is running.Which ONE (1)of the following describes the required actions?A.Enter LCO 3.7.6, COMPONENT COOLING WATER SYSTEM;Place the plant in MODE 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.B.Enter LCO 3.0.3;Place the plant in MODE 4 within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />.C.Enter LCO 3.7.6, COMPONENT COOLING WATER SYSTEM;Restore 1 CCW Train to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.D.Enter LCO 3.0.3;Place the plant in MODE 5 within 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br />.79
HLC-08 NRC Written Exam 80.Given the following:
-The plant is in MODE 5 with RHR Pump"A" in service.-A loss of the Startup Transformer
has occurred.-The Instrument
Air Header is depressurized.
-RCS Temperature
is increasing.
-RHR Pump"A" is NOT running.-The crew has implemented:
-AOP-017, LOSS OF INSTRUMENT
AIR AND-AOP-020, LOSS OF RESIDUAL HEAT REMOVAL (SHUTDOWN COOLING)In addition to restarting
RHR Pump"A", which ONE (1)of the following describes the actions required to restore core cooling to normal operation?
A.Cross-connect
IA with SA by OPENING SA-220 AND 221, SA TO IA CROSS CONNECT FILTER ISOLATION Valves to restore IA pressure.Reposition
FCV-605 and HCV-758 from their Failed SHUT positions.
B.Start Compressor
A and/or B to restore IA pressure.Reposition
FCV-605 and HCV-758 from their Failed OPEN positions.
C.Cross-connect
IA with SA by OPENING SA-220 AND 221, SA TO IA CROSS CONNECT FILTER ISOLATION Valves to restore IA pressure.Reposition
FCV-605 and HCV-758 from their Failed OPEN positions.
D.Start Compressor
A and/or B to restore IA pressure.Reposition
FCV-605 and HCV-758 from their Failed SHUT positions.
80
HLC-08 NRC Written Exam 81.Prior to Step 13 of EPP-26, LOSS OF DC BUS"A", a CAUTION describes a safety issue that prohibits closing the 4160V load breakers onto an energized bus.Which ONE (1)of the following describes the safety issue?A.A personnel hazard exists because the Load Breaker must be closed locally, using a test tool and breaker contact explosion is likely.B.An equipment hazard exists because electrical
fault conditions
at the energized equipment could cause non-isolable
faults on the ESF busses.C.A personnel hazard exists because local, manual 4160V breaker manipulations
have NOT been fully analyzed.D.An equipment hazard exists because the test tool used for locally closing the breaker prevents remote breaker operation for several seconds while the tool is engaged.81
HLC-08 NRC Written Exam 82.Given the following:
-An ATWS condition has occurred from 1000/0 RTP.-The crew is implementing
FRP-S.1, RESPONSE TO NUCLEAR POWER GENERATION/ATWS.
-While attempting
to borate, MOV-350, BA TO CHARGING PMP SUCT, has failed to reposition
from the RTGB.Which ONE (1)of the following is required lAW FRP-S.1 to begin boration?A.OPEN LCV-115B, EMER MU TO CHG SUCT AND CLOSE LCV-115C, VCT OUTLET.B.OPEN FCV-113A, SA FLOW and FCV-113B, BLENDED MU TO CHG SUCT.C.Dispatch an operator to Manually OPEN MOV-350, BA TO CHARGING PMP SUCT.D.OPEN FCV-113A, SA FLOW and FCV-114B, BLENDED MU TO VCT.82
HLC-08 NRC Written Exam 83.Given the following:
-Plant startup is in progress lAW GP-005, POWER OPERATION.
-Reactor is at B°tlc>RTP.-Reactor Engineering
has notified the SSO that BOTH Intermediate
Range High Flux Trip setpoints were determined
to be set non-conservative.
-The SSO has declared BOTH IR Channels INOPERABLE.
Which ONE (1)of the following describes the action(s)that must be taken in order to comply with Technical Specification
requirements?
A.Immediately
suspend operations
involving positive reactivity
additions AND reduce thermal power to<P-6 within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.B.Increase thermal power to>P-10 within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.C.Immediately
OPEN the Reactor Trip Breakers.D.Restore BOTH channels to OPERABLE status prior to increasing
thermal power to>P-10.83
HLC-08 NRC Written Exam 84.Given the following:
-The plant is operating in MODE 3.\-A release is in progress from Monitor Tank"A".-CW Pump IIA II is running.-U1 has ONE CW Pump running.-The release permit states a release rate of 80 GPM with ONE U2 CW Pump running.Subsequently:
-CW Pump IIA II trips.Based on current plant conditions, what is the impact on the release?A.10CFR20 limits may be exceeded.The release must be stopped.B.10CFR20 limits will NOT be exceeded.NPDES Discharge limits for pH may be exceeded.Terminate the release.C.10CFR20 limits will NOT be exceeded.The release may continue.D.10CFR20 limits may be exceeded.Release may continue provided 2 independent
samples were obtained during permit generation.
84
HLC-08 NRC Written Exam 85.Given the following:-A LOCA has occurred.-RCS Subcooling
is 0 of.-RCPs are secured.-RCS temperature
by CETC is 750 of.-RVLIS Full Range is 40%.The mitigative
strategy required for this event is to depressurize
the S/Gs to (1)AND verify at least 2 of 3 RCS Hot Legs are less than (2)prior to isolating the SI Accumulators.
A.(1)140 PSIG (2)365 of B.(1)140 PSIG (2)350 of C.(1)atmospheric
pressure (2)365 of D.(1)atmospheric
pressure (2)350 of 85
HLC-08 NRC Written Exam 86.Given the following;
-The plant is operating at 100%RTP.-CCW temperature
has increased to 102 of due to CCW Heat Exchanger"A" being out of service for scheduled maintenance.
-RCP"C" thrust bearing temperature
has reached 220 of and stabilized.
-APP-001-B5, RCP HIGH VIB and APP-001-F3, RCP C BEARING HI TEMP are illuminated.
-RCP"C" vibration analysis shows that FRAME vibrations
have increased from 2.0 to 3.0 mils in the last 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.Whatactionsare
required lAW AOP-018, REACTOR COOLANT PUMP ABNORMAL CONDITIONS?
Trip the Reactor and trip RCP"C"becausethe
...A.Thrust bearing has exceeded the bearing temperature
limit, close CVC-303C, SEAL RETURN ISOLATION Valve, within 3-5 minutes.B.Thrust bearing has exceeded the bearing temperature
limit, close PCV-455B, PZR SPRAY Valve.c.Pump bearing has exceeded the bearing temperature
limit, close PCV-455B, PZR SPRAY Valve.D.Pump bearing has exceeded the bearing temperature
limit, close CVC-303C, SEAL RETURN ISOLATION Valve, within3-5minutes.
86
H LC-08 NRC Written Exam 87.Given the following:
-The plant is operating at 100%RTP.-MST-023, Train 118 11 SAFEGUARDS
testing is in progress.-I&C reports a condition that would prevent Train 118 11 ESFAS from actuating.
What ONE (1)of the following describes the effect on the plant?A.Containment
Isolation Phase A and Phase B will actuate if required.Enter LCO 3.3.2 and place the plant in MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.B.Containment
Isolation Phase A and Phase B will actuate if required.Train IIBII Safeguards
LCO may be delayed for testing for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided Train IIA II Safeguards
is OPERABLE.C.Containment
Isolation Phase A will actuate.Phase B will NOT actuate.Enter LCO 3.3.2 and place the plant in MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.D.Containment
Isolation Phase A will actuate.Phase B will NOT actuate.Train IIB II Safeguards
LCO may be delayed for testing for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided Train IIA II Safeguards
is OPERABLE.87
HLC-08 NRC Written Exam 88.What is the basis for the Condensate
Storage Tank minimum volume required by LCO 3.7.5, CONDENSATE
STORAGE TANK?A.Ability to remove decay heat for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> in MODE 3 using Condenser Steam Dump valves.B.Ability to remove decay heat for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in MODE 3 by steaming through the Main Steam Safety Valves.C.Ability to maintain at least 1 S/G at 8%level for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> in MODE 3.D.Ability to remove decay heat for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in MODE 3 using Steam Line PORVs.88
HLC-08 NRC Written Exam 89.Given the following:-AReactorTrip
and Safety Injection has occurred.-The crew has entered FRP-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK.-The crew is attempting
to establish RCS bleed and feed.-PCV-456, PZR PORV, failed to open.Which ONE (1)of the following identifies
whether the bleed path is adequate and the required procedural
action lAW FRP-H.1?A.1 PORV is NOT an adequate bleed path, OPEN ALL RCS and PZR vent valves.B.1 PORV is NOT an adequate bleed path, depressurize
ALL S/Gs to atmospheric
pressure.C.Adequate bleed path exists, depressurize
ONE S/G to atmospheric
pressure.D.Adequate bleed path exists, verify SI flow is established.
89
HLC-08 NRC Written Exam 90.Given the following:
-The plant is operating at 50%RTP.-Power ascension in progress lAW GP-005, POWER OPERATION, following a refueling outage.-During paperwork reviews, Maintenance
Supervision
has discovered
that the blind flange on the Refueling Transfer Tube was installed but has NOT been properly torqued.-The Containment
has been declared INOPERABLE
and the plant must be placed in MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.Based on current plant conditions, notification
to the NRC Operations
Center will be required...A.within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> due to invoking 10 CFR 50.54(x), Deviation or Departure from License Condition.
B.within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> due to the initiation
of a shutdown required by the ITS.C.within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> because a Safety System will NOT function as required.D.within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> due to the failure, degradation, or discovered
vulnerability
in a safeguard system.90
HLC-08 NRC Written Exam 91.Given the following:
-The Plant is in MODE 3 at 547 of following a reactor trip from 1 00 ok>RTP.-RCS chemistry sample indicates DOSE EQUIVALENT
1-131 is 73 Micro-Curies/gram.
Which ONE (1)of the following is the REQUIRED action lAW ITS and the basisforthat requirement?
A.Be in MODE 4 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, to place the plant in a MODE where the 1-131 limit is NOT APPLICABLE.
B.Reduce T AVG to<500 of within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, to ensure ReSsaturationpressure
is below the S/G Safety Valve lift setpoint.C.Be in MODE 4 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, to place the plant in a MODE where the 1-131 limit is NOT APPLICABLE.
D.Reduce T AVG to<500 of within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, to place the plant in a MODE where the MSIVs AND PZR PORV Block valves can be closed.91
HLC-08 NRC Written Exam 92.Given the following:
-The plant is operating at 1000/0 RTP.-APP-003-E8, PZR CONTROL HI/LO LVL is illuminated.
-APP-003-F4, CHG PMP HI SPEED is illuminated.
-RCS Pressure is 2215 PSIG and decreasing.-T AVG is equal to T REF.Which ONE (1)of the following is the correct procedure to implement and the appropriate
actions for the event in progress?A.AOP-019, MALFUNCTION
OF RCS PRESSURE CONTROL.Place PC-444J, PZR PRESS in MANUAL and control Heaters and Spray to restore pressure.B.AOP-019, MALFUNCTION
OF RCS PRESSURE CONTROL.Control Charging and Letdown to stabilize PZR level.C.AOP-016, EXCESSIVE PRIMARY LEAKAGE.Place PC-444J, PZR PRESS in MANUAL and control Heaters and Spray to restore pressure.D.AOP-016, EXCESSIVE PRIMARY LEAKAGE.Control Charging and Letdown to stabilize PZR level.92
HLC-08 NRC Written Exam 93.Which ONE (1)of the following describes the TRM limitation
on the quantity of radioactivity
permitted in the Waste Gas Decay Tank(s)AND the basis for that limit?The quantity contained in ill shall be1.9 X 10 4 Curies (Xe-133 Noble Gas)to ensure an uncontrolled
release will (2)A.(1)ALL Waste Gas Decay Tanks combined (2)NOT result in exceeding the annual total body exposure to offsite personnel B.(1)EACH Waste Gas Decay Tank (2)result in onsite exposures that remain within the Accident Analysis C.(1)ALL Waste Gas Decay Tanks combined (2)result in onsite exposures that remain within the Accident Analysis D.(1)EACH Waste Gas Decay Tank (2)NOT result in exceeding the annual total body exposure to offsite personnel 93
HLC-08 NRC Written Exam 94.Given the following:
-The plant is in MODE 6 for Refueling.
-Core offload is in progress with a*Fuel Assembly on the Manipulator.
-The Transfer Cart is loaded with a Fuel Assembly, enroute to the SFP.-You are the Refueling SRO.You observe that Refueling Cavity level is decreasing.
In the current plant conditions, which ONE (1)of the following is the required action lAW AOP-020, LOSS OF RESIDUAL HEAT REMOVAL (SHUTDOWN COOLING)?Place the Fuel Assembly from the Manipulator
in the...A.RCC change fixture.B.core, in it's original location.C.Upender.D.core, in any location that is bordered by 2 other assemblies.
94
HLC-08 NRC Written Exam 95.Given the following:
-RC personnel need to use Demin Water for decon activities
for a spent fuel cask.-They will need to operate one valve for about an hour AND will finish before shift turnover.-The valve manipulation
is NOT covered by an approved procedure.
Which ONE (1)of the following describes how this manipulation
will be tracked and controlled
lAW OMM-001-11, LOGKEEPING?
A.A temporary procedure must be approved prior to manipulation
of the valve.B.The valve manipulation
must be entered in the Start/Stop
Log of Autolog.C.A Caution Tag must be issued for the valve being manipulated.
D.The portion of the system to be realigned must be taken out of service and controlled
with Danger Tags.95
HLC-08 NRC Written Exam 96.Given the following:
-Earlier in the shift, a Clearance was established
for maintenance
activities
on the CV Spray system.-An operator is now restoring the system to normal alignment.
-During system restoration, a valve which was inside the Clearance boundary was found out of alignment.
-It is believed that the valve was mispositioned
during maintenance
activities.
-There are other valves within the Clearance boundary within close proximity to the mispositioned
valve.What minimum procedural
actions are REQUIRED by OMM-001-8, CONTROL OF EQUIPMENT AND SYSTEM STATUS?A.Theevent shall be considered
as a Deliberate
Misposition
Event until the cause is investigated
and established.
B.ONLY the mispositioned
valve must be verified in the correct position lAW the system Operating Procedure.
C.A full system lineup is required lAW the system Operating Procedure.
D.A valve lineup is required for ALL valves within the Clearance boundary lAW the system Operating Procedure.
96
HLC-08 NRC Written Exam 97.Given the following:
-The plant is operating at 1000/0 RTP.-SI Pump"A" is INOPERABLE
due to failed motor be'arings.
-While aligning SI Pump"B" to replace SI Pump"A", the E-1 supply breaker 52-22B breaker racking mechanism was found broken, preventing
the breaker from being racked in and closed.-An audit of surveillance
procedures
has determined
the last quarterly surveillance
on SI Pump"C" was missed.Which ONE (1)of thefollowingdescribes
the appropriate
action?A.Operability
Determination
is required for SI Pump"C" lAW OPS-NGGC-1305, OPERABILITY
DETERMINATIONS.
B.Perform a Safety Function Determination
for SI Pump"C" lAW OMM-007, EQUIPMENT INOPERABLE
RECORD.C.Demonstrate
the operability
of SI Pump"C" within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> OR be in MODE 4 within 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />.D.Demonstrate
the operability
of SI Pump"C" within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OR be in MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.97
HLC-08 NRC Written Exam 98.Given the following:
-The Reactor has tripped from 1 000/0 RTP.-RCS temperature
is 430 of.-RCS pressure is 635 PSIG.-S/G"A II pressure is 100 PSIG.-S/G"B II pressure is 50 PSIG.-S/G"CII pressure is 50 PSIG.-CV pressure is 38 PSIG.Which ONE (1)of the following describes the correct mitigation
strategy?A.Throttle Feedwater to ALL S/Gs to 80 to 90 GPM lAW Foldout A.B.Isolate Feedwater to S/Gs"B II and"CII, continue to feed S/G IIA II lAW Foldout A.C.Isolate Feedwater to S/Gs"B" and"CII, continue to feed S/G"A" lAW EPP-16, UNCONTROLLED
DEPRESSURIZATION
OF ALL STEAM GENERATORS.
D.Throttle Feedwater to ALL S/Gs to 80 to 90 GPM lAW EPP-16, UNCONTROLLED
DEPRESSURIZATION
OF ALL STEAM GENERATORS.
98
HLC-08 NRC Written Exam 99.Given the following:
-The plant was operating at 100°;{, RTP-A major rupture occurs in the CCW Common Discharge Header.-The crew has implemented
AOP-014, COMPONENT COOLING WATER SYSTEM MALFUNCTION.
-The Reactor Operator reports that CCW Surge Tank Level is 5%and lowering.Which ONE (1)of the following describes, in order, the actions required in response to this event?A.1)Verify the Reactor is tripped 2)Perform the Immediate Actions of PATH-1 3)Trip the RCPs.4)Lockout the CCW Pumps B.1)Verify the Reactor is tripped 2)Trip the RCPs 3)Perform the Immediate Actions of PATH-1 4)Lockout the CCW Pumps C.1)Lockout the CCW Pumps 2)Verify the Reactor is tripped 3)Perform the Immediate Actions of PATH-1 4)Trip the RCPs D.1)Lockout the CCW Pumps 2)Verify the Reactor is tripped 3)Trip the RCPs 4)Perform the Immediate Actions of PATH-1 99
HLC-08 NRC Written Exam 100.Which ONE (1)of the following is the strategy and basis for Reactor Coolant Pump (RCP)operation in FRP-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK?A.Verify ONLY ONE RCP is operating prior to initiating
bleed and feed to ensure maximum bleed flow through the PZR PORVs.B.Stop ALL RCPs to eliminate the heat input from the RCPs extending the time available to restore feed flow before bleed and feed criteria is met.C.Verify ONLY ONE RCP is operating to reduce the heat input from the RCPs extending the time available to restore feed flow before bleed and feed criteria is met.D.Stop ALL RCPs to establish Natural Circulation
cooling in preparation
for bleed and feed.100