ML071930561
ML071930561 | |
Person / Time | |
---|---|
Site: | Summer ![]() |
Issue date: | 06/13/2007 |
From: | South Carolina Electric & Gas Co |
To: | Office of Nuclear Reactor Regulation |
References | |
2007-301, 50-395/07-301 50-395/07-301 | |
Download: ML071930561 (104) | |
See also: IR 05000395/2007301
Text
Final Submittal(BluePaper)
V t,.S)()()1/f)l?r
2(07-
/3/2 ,{)o7 AS Givw Senior Operator Written Examination
v.C.SUMMER JUNE 2007 EXAMEXAMNO.05000395/2007301
JUNE4-8,2007(OP
TEST)JUNE 13,2007 (WRITTEN EXAM)
u.s.Nuclear Regulatory
Commission
Site-Specific
SRO Written Examination
Applicant Information
Name: Date: ,-Facility/Unit:
JUne 13 j 2fJOl V* Region: II Reactor Type: W Start Time: Finish Time: InstructionsUsethe answer sheets provided to document your answers.Staple this cover sheet on top of the answer sheets.To pass the examination
you must achieve a final grade of at least 80.00 percent overall, with 70.00 percent or better on the SRO-only items if given in conjunction
with theROexam;SRO-only exams given alone require a final grade of 80.00 percent to pass.You have 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to complete the combined examination, and 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> if you are only taking the SRO portion.Applicant Certification
All work done on this examinationismy own.I have neither given nor received aid.Applicant's
Signature Results RO/SRO-OnlylTotal
Examination
Values--/--/--Points Applicant's
Scores--/--/--Points-Applicant's
Grade--/--/--Percent
Name:---------------1.Giventhe
following:*Theunitisat85%
poweratMOL.*Acontinuousuncontrolledcontrolrod
withdrawal
occurs.WhichONE(1)ofthe
following parameters
will DECREASE?A.Steam Generator Pressure B.Main Generator Electrical
Output C.OverpowerDeltaT setpointD.VCTLevel2007NRCExamSRO
1
2007NRCExamSRO
2.Giventhefollowingplant
conditions:*ALOCAhas occurred.*RCSpressureis1750psigandlowering
.*Reactor Building pressureis4psigandrising.*Steam Generator pressuresare1000psigandstable.WhichONE(1)ofthe
following describes the actuationsthatarearesultofthis
condition?
A.SafetyInjectionONLY.
B.SafetyInjectionand
Containment
Ventilation
Isolation ONLY.C.SafetyInjectionand
ContainmentIsolationPhaseAand
Containment
VentilationIsolationONLY.D.SafetyInjectionand
Containment
Isolat ionPhaseAand Containment
VentilationIsolationand
Containment
IsolationPhaseB.2
2007NRCExamSRO3.Giventhe
followingplantcondit
ions:*Thecrewis
respondingtoanATWS lAW EOP-13.0, Response to Abnormal Nuclear Power Generation
,andis attempting
an emergency borat ion oftheRCS.*MVT-8104, EMERG BORATE ,valvewillnotopen
.WhichONE(1)ofthe
followingdescribestherequiredactionstobe
performed and why?A.Openthe ChargingPumpSuction
HeaderIsolationvalvesas
directed byAOP-106.1, Emergency Boration, to maximizeBoricAcidflowrate.B.Open LCV-115B/D, RWSTtoCHG PP Suet ,asdirectedby
AOP-106.1, Emergency Boration , to borateviacoldleginjection
.C.Openthe ChargingPumpSuction
HeaderIsolationvalvesas
directedbyEOP-13.0
, Response to Abnormal Nuclear Power Generation
, to maximizeBoricAcidflowrate.D.OpenLCV-115B/D, RWSTto CHG PPSuet,asdirectedbyEOP-13.0,Responseto
Abnormal Nuclear Power Generation
,toborateviacoldleginjection.
3
2007NRCExamSRO
4.WhichONE(1)ofthe
following describes the setpointsforthetwo(2)
below?A.B.C.D.RCP AlBIC THERMBAR&BRGFLOLO90gpm90gpm50gpm50gpm CCBP DISCHHDRPRESSLO30psig70psig30psig70psig 4
2007NRCExamSRO
5.Giventhefollowingplant
conditions:*TheplantisinMode5.*ThePZRissolid
.*RCS temperatureis190°F.*RCS pressureis315psig.*Letdown Pressure ControlValvePCV-145isinAUTO.FCV-605A,"A" gyp,andFCV-605B,"B"BYP,arein
MANUAL.WhichONE(1)ofthe
followingdescribesaconditionthatwill
initiallycausePCV-145toCLOSE?A.Loweringthe
outputofthe controllerforthein-serviceRHRheat
exchanger flowcontrolvalve.B.RaisingCCWflow
through the in-serviceRHRHeat Exchanger.C.Loweringthe
setpointofPCV-145.
D.Startingan
additionalRHRPump.5
2007NRCExamSRO
6.Giventhefollowing
plant conditions:*Theplantisin
Mode 6.*"B"TrainRHRisin
service.*"A"TrainRHRisoutofserviceand
expectedtobereturnedto
service in approximately2hours.*Refuelingisin
progress.*Cavitylevelis23.5feetabovethe
reactorvesselflange.
"B"RHRPumptripsand
cannotberestarted
.WhichONE(1)ofthe
following describes the operational
restriction(s)
associated
withthisevent?
A.RefuelingCavitylevel
mustberaisedto
greaterthan24feet
abovethereactorvesselflange
prior to continuingrefuelingactivities.
B.Refueling activities
are permittedforupto1hourwh
ilerepairsareinitiatedto
"B"RHRPump.C.All containment
penetrationswithad irectpathto atmosphere
must immediately
beverifiedclosed
.D.Suspendallactiv
ities thatcouldresultinareductioninboron
concentrationofthe RCS.6
2007 NRC Exam SRO 7.Giventhe following plant conditions:*The plant was operating at 100%power.*7.2KV Transformer
XTF-4waslostduetoafault.*The associated
DIG did NOT start as designed.*Subsequently, a LOCA caused a reactortripand safety injection.*RCS pressure is currently350psigand
trending down slowly.WhichONE(1)ofthe
following describes the operationofRHR Pumps for this condition?A.RHR pump A runningwithits miniflow valve openB.RHR pump A runningwithits miniflow valve closed C.RHR pump B runningwithits miniflow valve openD.RHR pump B runningwithits miniflow valve closed 7
2007 NRC Exam SRO 8.Which ONE (1)of the following directly supplies power to Charging Pump"A"andRHR Pump"A"?A.B.C.D.Charging Pump"A" 1DA 1DA1 1DA 1DA1 RHR Pump"A" 1DA 1DA 1DA1 1DA1 8
2007 NRC Exam SRO 9.Giventhe following plant conditions:*The plant is operating in Mode1at 100%power.*The following indications
are reportedbytheRO.*TI-471, PRT Temperature
is trendingupandis now at 158°F.*PI-472, PRT Pressure is trendingupandis nowat8psig.Which ONE (1)of the following components, if leaking, will cause this condition?
A.XVR-8708A, RHR Pump"A" Suction Relief Valve.B.XVR-8121, RCP Seal Return Relief Valve.C.XVR-7169, RCDT Pumps Suction Relief Valve.D.XVS-8010, PZR Safety Valve.9
2007NRCExamSRO10.WhichONE(1)ofthe
following describes an immediateactionandthebasisforthe
action i n accordance
with EOP-1.0 , Reactor Trip/Safety
Injection Actuation?
A.InsertcontrolrodsinManual;toinsertnegative
reactivitybythemostdirectmanner
possible.B.InsertcontrolrodsinManual;toreduceormaintainRCS
pressuretopreventlifting
the Pressurizer
safety valves.C.PlaceEHCPumpsin
PULL-TO-LK
NON-A;to prevent uncontrolledcooldownofthe
RCS.D.PlaceEHCPumpsin
PULL-TO-LK
NON-A;to minimize secondary makeup requirements.
10
2007NRCExamSRO11.Giventhefollowingplant
conditions:*Areactortripand
safetyinjectionhaveoccurred.*RCS pressureis1050psigandlowering.*Tavgis 550°Fandlowering.
- Pressurizerlevelis65%andrisingrapidly.*ReactorBuildingpressureis2psigandrising.WhichONE(1)ofthefollowingdescribesthecauseofthisevent?
A.Letdownlinebreak.B.SBLOCAonanRCScoldleg.C.Stuckopen
pressurizer
PORV.D.Stuckopen pressurizersprayvalve.
11
2007NRCExamSRO
12.Giventhefollowing:*Theplantisat100%power.*Allsystemsarein
their normal alignments
.*AleakoccursintheLetdownHeat
Exchanger.Assumingnoactionbythecrew,whichONE(1)ofthefollowing
describestheeffect(s)ontheCCWSystem?
A.RM-L2A/B indication
rises.SurgeTankventvalve
PW-7096closeswhentheindicationreachesthe
ALERT level.B.RM-L2A1B indication
rises.SurgeTankventvalve
PW-7096closeswhentheindicationreachestheHIRADlevel.
C.SurgeTanklevellowers
.CCW Booster Pumpswilltriponlowsuctionpressure.D.SurgeTanklevellowers.
CCW Pumps will/ose suctionwhentheSurgeTank
empties.12
2007NRCExamSRO13.Giventhefollowingplantconditions:*ALOCAoccurredandRCS
pressurereached1380psig.*AllactionsofEOP-1.0were
performedasrequired.*Thecrewis
performing
EOP-2.1 , Post-LOCA Coo/down and Depressurization.*RCS pressure is currently1335psig.*RCS temperature
is currently 496°F.*TwoChargingpumpsarerunning
.*Thecrewis
evaluatingstopping1ChargingPump.Giventheaboveconditions,whichONE(1)
ofthefollowing
describes whether theChargingPumpmaybestopped,andwhy?
A.No,because
subcoolingisnot greaterthan30°F.B.Yes, because subcooling
is greaterthan30°F.C.Yes,because
subcooling
is greaterthan87.5°F.D.No, because subcoolingisnot greaterthan87.5°F.
13
2007NRCExamSRO14.Giventhefollowingplant
conditions:*ThePlantisinMode3
.*APZRPORVbeginsleakingtothePRT.
- Pressurizer
pressureis985psig.*PRTpressureis
steadyat5psig.*PRT temperature
is steadyat90°F.Assume:*Ambientheatlossesarenegligible.*Steam qualityinthe pressurizeris100%.WhichONE(1)ofthe
followingwouldbethe
approximate
MCB indicationonTI-463 ,RELIEFTEMP
OF?14
2007NRGExamSRO15.Giventhefollowingplantconditions:*The Reactorhastrippedfrom100%power.*"A"and"G" Service Water(SW)pumps were running.*Thecrew implemented
EOP-1.0, Reactor Trip/Safety
Injection Actuation, then transitionedtoEOP-1.1 , ReactorTripRecovery.
- MDEFW pumps startedonLo-LoSGlevelsafterthetr
ip.*Subsequently
,anSI actuatedduetoaLargeBreakLOGA.WhichONE(1)
of the followingdescribestheoperationof
equipmentasaresultofthe
SI?A.MDEFW pumpswilltripandberestartedbythesequencer.
Service Water Pumps"A"and"G"will
continuetorun.B.MDEFW pumps will continuetorun.Service WaterPumps"A"and"G"willtripandberestartedbythe
sequencer.G.MDEFWpumpswilltripandberestartedbythesequencer.
Service Water Pumps"A"and"G"willtripandberestartedbythesequencer.
D.MDEFW pumps will continuetorun.Service
Water Pumps"A" and"G"willcontinuetorun.15
2007NRCExamSRO16.Giventhefollowingplantconditions:*Aloadrejectionhasoccurredfrom100%power.*Allcontrol
systems respondedasdesigned.
- Power level isnowstableat70%.WhichONE(1)ofthefollowing
conditionswillexistduringthis
event?A.ChargingFlowControlValve,FCV-122
,willbethrottlingopen.
B.PressurizerBackupHeaterswillbeenergized.
C.PressurizerPORVswillbeopen.D.Letdown Backpressure
Control ValvePCV-145willbe
throttling
closed.16
2007NRCExamSRO17.Giventhefollowingplant
conditions
- Areactortriphas
occurredfrom100%power.*ReactorTrip
Breaker"B"remainsCLOSED.WhichONE(1)ofthe
followingdescribestheeffectontheSteamDumpSystem?
A.Thesteam dump valveswillopenandmaintainTavgat
55rF.B.Thesteam
dumpswillremainclosedfollowingthereactortripduetolossofthearmingsignal.C.Thesteam
dumpswillremainclosedfollowingthereactortripduetolossofthe'planttrip'
modulation
signal.D.Thesteam dump valveswillopenandmaintainTavgat
559°F.17
2007 NRC Exam SRO18.Which ONE (1)of the following describes the source of control power to Reactor Trip Breaker"B"and Reactor Trip Bypass Breaker"B"?Reactor Trip Breaker B Reactor Trip Bypass Breaker B A.B.C.D.125 VDC Bus 1HB 125 VDCBus1HB 120 VAC APN-5902 120 VAC APN-5902 125 VDCBus1HB 125 VDCBus1HA 120 VAC APN-5902 120 VAC APN-5901 18
2007NRGExamSRO
19.Giventhefollowingplantcond
itions:*Areactortriphas
occurred coincidentwithalossof
off-site power.*While performingactionintheEOPs,thefollowing
events occur:*RGS pressureis1700psigandlowering.*RB pressureis4.7psigandrisingslowly.*Threem inutes after these indicationsareobserved
, APN-5904failsand becomes de-energized.WhichONE(1)ofthe
following describestheeffect ,ifany ,onplant equipment aftertheAPNfailure?
A.TrainAandTrainBEGGS
equipmentisoperatingasrequired
- TrainAandTrainBRBSprayPump
discharge valvesareopen.B.TrainAandTra
inBEGGS equipmentisoperatingasrequired;TrainAandTrainBRBSprayPump
dischargevalvesareclosed.G.TrainAEGGS
equipment is operatingasrequired;TrainBEGGS
equipment isNOTrunning;TrainAandTrainBRBSprayPump
dischargevalvesareopen
.D.TrainAEGGS
equipment is operatingasrequired
- TrainBEGGS
equipment isNOTrunning;TrainAandTrainBRBSprayPump
dischargevalvesareclosed.
19
2007NRCExamSRO
20.Giventhe following plant conditions:*ALOCAhas occurred.*RCS pressureis200psig.*"A" Reactor Building SprayPumpisOutofService.
- Containment
pressure has exceededtheHigh-3 setpoint.*Train"B" PhaseAhasfailedtoactuate.*All other actuationsandTrain"A"ECCS
equipmentisrunningasrequired.*The most recent Chemistry sampleoftheRCS indicatedthatRCSactivityis
5X10-2 microcuries/ml
Dose Equivalent
Iodine.Assumingno
actionbythecrew,whichONE(1)ofthe
following describestheeffectontheplant?A.Containment
will exceeditsdesignpressure.B.Off-Site
releaseswillexceed
accident analysis assumptions.C.Only1 Containment
Isolation ValveineachPhaseA
penetrat ion w illbeclosed.D.Onlyhalfofthe
Containment
penetrationsrequiredfor
isolationwillreceiveisolation
signa ls.20
2007NRCExamSRO21.Giventhefollowingplantconditions:*Areactorstartupisin
progress.*SR Channel N-31 indicates 7X10 3 CPS.*SRChannelN-32
indicates7X10 3 CPS.*IR Channel N-35 indicates 8.7X10-6%power.*IRChannelN-36indicates
6.0X10-6%power.WhichONE(1)ofthefollowing
describes(1)theexistingplantcondition,(2)thestatusofP-6,and(3)theactionrequiredin
accordance
with AOP-401.8, Intermediate
RangeChannelFailure?
A.(1)N-36is undercompensated
- (2)P-6shouldNOTbesatisfied;(3)maintain
powerstableuntilN-36isrepaired.
B.(1)N-36is overcompensated;(2)P-6shouldbe satisfied;(3)maintain
powerstableuntilN-36isrepaired.
C.(1)N-36is undercompensated
- (2)P-6shouldbe
satisfied;(3)placetheunitinMode3untilN-36isrepaired
.D.(1)N-36is overcompensated
- (2)P-6shouldNOTbesatisfied;(3)placetheunitinMode3untilN-36isrepaired.
21
2007NRCExamSRO
22.Giventhefollowingplant
conditions:*Theplantis
operatingat8%power.*ALossof Component Cooling Waterhasoccurred.*"A"RCP motor bearing temperatureis189°Fandrising slowly.*"A"RCP lower seal water bear ing temperature
is 226°Fandrisingslowly.*Thecrewhasentered
AOP-118.1, Loss of Component Cooling Water.WhichONE(1)ofthe
following actionsisrequired?
A.RCPmotorbearing
temperatureexceedsoperatinglimits
.Stop'A'RCPandinitiateaplant shutdown lAW GOP-4B , Power Operation (Mode 1-Descending)
.B.RCPlowerseal
water bearing temperature
exceeds operating limits.Stop'A'RCPandinitiateaplant
shutdown lAW GOP-4B, Power Operation (Mode 1-Descending)
.C.RCP motor bearing temperatureexceedsoperatinglimits
.Tripthereactor
,stop'A'RCP,andgoto
EOP-1.0 , Reactor Trip/Safety
Injection Actuation.
D.RCPlowerseal
water bearing temperature
exceeds operating limits.Tripthe reactor , stop'A'RCP ,andgotoEOP-1
.0 , Reactor Trip/Safety
Injection Actuation.
22
2007NRCExamSRO
23.Giventhe following plant conditions:*TheplantisinMode3.*The following wide-rangepressuresareindicated:*PT-402*PT-403*PT-455A-1335psig-1350psig-1285psig*Subcooling
indication
on TI-499A and TI-499B indicatesthefollowing
- TI-499A TI-499BWhichONE(1)ofthe
following describesthecoreexit
temperatureusedto determineRCSsubcoolingforthe
indications
above?A.TrainA-550°F;TrainB-560°F.
B.TrainA-55rF;TrainB-550°F.C.TrainA-55rF;TrainB-560°F.
D.TrainA-560°F;TrainB-
55rF.23
2007NRCExamSRO24.Giventhefollowingplant
conditions:*A ReactorTripcondition
existedandtheReactorfailedtotrip.*RCS pressure now indicates2350psig.Assumingnoothereventsarein
progress ,whichONE(1)
ofthefollowingdescribesthe1)appropriateactionandthe2)reasonforthataction?
A.1)VerifyPZRPORVsandBlockValvesopen2)To increaseflowonFI-943
,CHGLOOPBCLO/HOTLEG
FLOW GPM B.1)Ver ifyPZRPORVsandBlockValvesopen2)To increaseflowonFI-110,EMERGBORATE
FLOW GPM C.1)PlacebothESFLSA(B)ResetstoNON-ESFLCKOUTS2)To increaseflowonFI-943
,CHGLOOPBCLO/HOTLEG
FLOW GPMD.1)PlacebothESFLSA(B)ResetstoNON-ESFLCKOUTS2)To increaseflowonFI-110,EMERGBORATE
FLOW GPM 24
2007NRCExamSRO
25.Giventhefollowingplant
conditions:*Theplantwasat100%power.*Areactortripand
safetyinjectionoccurred
.*R8CUs XFN-0064A and XFN-00648startedinSLOW.*While performingtheactionsofEOP-1.0, Reactor Trip/Safety
Injection Actuation, the followingalarmsarereceivedinthe
control room:*XCP-605-3-1, SWFRR8CU 18/28FLOLO*XCP-605-3-2, SWFRR8CU 18/28PRESSLOWhichONE(1)ofthe
followingchoicescontainsbothofthe
conditionsthatcouldeach
independently
cause these annunciatorstoalarm?A.SW8P"8" tripped;MVG-31118, R8CU 648/658TOINDCOOLINGgoing
CLOSED.8.SW8P"8" tripped;MVG-3109C, R8CU 648 OUTLETISOLgoing CLOSED.C.XFN-00648 (18 R8CUSSFAN)tripped;
MVG-3108C, R8CU 648 INLETISOLgoingCLOSED.
D.XFN-00648 (18 R8CUSSFAN)tripped;
MVG-3109D, R8CU 658 OUTLETISOLgoing CLOSED.25
2007NRCExamSRO26.Which ONE (1)of the following describes the power supplies that directly feed Containment
Spray Header Isolation Valves XVG-3003A and XVG-3003B , respectively?
A.XSW1DA1 and XSW1DB1 B.XMC1 DA2XandXMC1 DB2Y C.XMC1 DB2XandXMC1 DA2ZD.XMC1 DA2ZandXMC1 DB2X 26
2007NRCExamSRO
27.Giventhefollowingplant
conditions:*ALOCAhasoccurred.*RCS pressureis450psig.*ReactorBuildingpressureis18psigandlowering
.*RWSTlevelislowering.
- ReactorBuildingSumplevelisrising.*"A" Reactor Trip Breakerremainedclosed.WhichONE(1)ofthefollowing
describestheoperationofthe
ReactorBuildingSpraysystemastheevent
continues?RBSprayPumpsuctiontotheRBSumpValves, MVG-3005AandB...A.are manuallyopenedwhenRWSTlevel
reaches its setpoint.RB Spray PumpsuctionvalvesfromRWST,MVG-3001AandB
, are manuallyclosedwhen
MVG-3005AandBarefullyopen.
B.automaticallyopenwhenRWSTlevelreachesitssetpoint.RBSprayPumpsuctionvalvesfromRWST,MVG
-3001AandB, automaticallyclosewhen MVG-3005A andBarefullyopen
.C.are manuallyopenedwhen
ReactorBuildingSumplevelreachesitssetpoint.RBSprayPumpsuction
valvesfromRWST , MVG-3001AandB,are manually closed whenandBarefullyopen.
D.automaticallyopenwhen ReactorBuildingSumplevel
reachesitssetpoint.RBSprayPumpsuctionvalvesfromRWST, MVG-3001AandB, automatically
close when MVG-3005AandBarefullyopen.
27
2007NRCExamSRO28.Withtheunitat100%power,whichONE(1)ofthe
following describesthepotentialconsequenceof
PCV-444C ,PZRSprayValve,failingopen?
A.LossofPZR pressurecanresultinanunwarrantedOPDeltaTrunbackandreactor
trip.B.PZRpressurewillremainstableasPZRheaterswill
compensateforthepressure
reduction.C.LossofPZR pressuremayresultinsteamformationinthereactorvesselheadandSGtubes.I D.LossofPZR pressurecanresultinanunwarrantedOTDeltaTrunbackandreactor
trip.28
2007NRCExamSRO
29.WhichONE(1)ofthe
followingdescribesthepurposeandfunctionoftheReactor
Building Charcoal Cleanup Units?Designedfor...
A.primary meansoflongtermpost
accidentiodineremovalfromtheRBatmosphere.Dischargeis
alignedtotheRBPurgesystemexhaust.B.primarymeansoflongtermpost
accidentiodineremovalfromtheRBatmosphere.DischargeisalignedtotheRB
atmosphere.C.RB pre-entry reduction of airborne contaminants.
Discharge isalignedtotheRBPurgesystem
exhaust.D.RB pre-entry reduction of airborne contaminants
.DischargeisalignedtotheRB
atmosphere.
29
2007NRCExamSRO
30.Giventhe following plant conditions:*Theunitwas
initially operatingatfull power.*Alossof ALL offsite poweroccurredin
conjunctionwithasteam
generatortuberupture.*All safeguards
equipment functionedasrequi red.*The following plant conditionsnowexist:*Ruptured S/G pressure=1100psig,stable*CoreexitTC=505°F, slowly decreasing*RCS Pressure=1600psig , stable*PZRLevel=4%,stable*TotalSIFlow=600gpm*TheRCShasbeencooleddowntotarget
temperature
.*In accordancewithEOP-4.0, Steam GeneratorTubeRupture,theROopensonePZRPORV.*Soon after openingthevalve,the
operator observes that all channels ofPZRlevelare
rapidly increasing
.*ECCSflowhas
increasedfrom600gpmto650gpm.WhichONE(1)
of the followingisthecauseofthis
indication?
A.PZRlevel instrumentsarenot calibrated
for temperatureslessthan600°F.
B.Safety injectionflowisdrivingtheRCStoawater-solid
condition.C.Voidinginthe
reactor vesselheadisforcingwaterupthesurgeline.
D.Backflowhasbeen establishedfromtherupturedS/GtotheRCS.
30
2007NRCExamSRO31.Giventhefollowing
plant conditions:*ALargeBreakLOCAhasoccurred.
ReactorBuildingH2
concentrationwasat2%andrising.*'A'Hydrogen
Recombiner
is INOPERABLE.WhichONE(1)ofthe
following describestheeffectontheremovalofHydrogenfrom
Containment?
A.Hydrogen concentrationwillremainbelow4%withonlyone
Recombiner
in operation.
B.Hydrogen concentrationwillriseabove4%butremain
below6%withonlyone
Recombiner
in operation.C.Hydrogen concentrationwillremainbelow4%onlyifthe
Containment
PurgeSystemisplacedin
serviceinadditiontothe
Recombiner.D.Hydrogen
concentrationwillremainbelow4%onlyif
ContainmentSprayisplacedinserviceinadditiontothe
Recombiner
.31
2007NRCExamSRO32.WhichONE(1)ofthefollowingdescribesafeatureoftheSpentFuelPool
and/orCoolingsystem
thatwillmaintainradiationdoselevelsat
acceptablelimitsduringplant
operat ions?A.SpentFuel CoolingPumpswilltriponlowsuctionpressurepriortoSpentFuelPool
level dropping below 460'6".B.Boron concentration
is maintainedsothatSpentFuelPool
Keffislessthan0.95andSpentFuelPoolRadiationlevelsare
maintainedlessthan2.5
mr/hratthesurfaceofthepool.
C.Anti-siphoningholesinthecoolingsystemsuctionandreturn
lines ensures thatSpentFuelPoollevelwillnotdropbelow460'6".
D.InterlocksontheSpentFuelPool
ManipulatorCranepreventspentfuelassemblies
from travelling
closerthan23feetfromthe
surfaceofthe SpentFuelPool.32
2007NRCExamSRO
33.WhichONE(1)ofthefollowing
describes the initialSGLevel Response and SGWLC.System Responseduringarapidincreaseinpower?SGLevel Response A.DecreasesB.DecreasesC.IncreasesD.Increases
SGWLC System ResponseLagcircuitonSGlevelinput
minimizes fluctuations
Programmed
DIPacrosstheFRV
minimizes fluctuations
Programmed
DIPacrossthe FRV minimizes fluctuationsLagcircuitonSGlevelinputm
inimizes fluctuations
33
2007NRCExamSRO34.Giventhefollowingplantconditions:*TheplantisinMode6,corereloadisinprogress.*Afuel assemblyisbeinginsertedintothecorewhendownwardmotionstops
.*The RefuelingSROnotesthefollowing:*The SLACKCABLElightisON*The LOWER SLOWZONElightis
OFF*The GRIPPERTUBEDOWNlightisOFFWhichONE(1)
ofthefollowing
describesthereasonthatdownward
movementstoppedandthe
subsequent
operationrelatedtothe
interlock?
A.Totalloadfellmorethan
150-300#belownominalfullload;bypassingtheinterlockisnotpossible.B.Thefuel assembly approached10"fromthebottomofthecore
- bypassingtheinterlockisnot
possible.C.Totalloadfellmorethan
150-300#belownominalfullload
- bypasstheinterlocktoallowthe assemblytobefullyinserted.
D.Thefuel assembly approached10"fromthebottomofthecore;bypasstheinterlocktoallowthe
assemblytobefullyinserted.
34
2007NRCExamSRO35.Giventhefollowingplant
conditions:
Reactor poweris75%.RCSleakratedataisasfollows:*TotalRCS leakagerateis9.1 gpm.*LeakagetoPRTis7.0gpm
.*Leakagetothe Reactor CoolantDrainTankis1.3gpm
.*Total primary to secondaryleakageis0.33gpm.*SG1-0.09gpm*SG2-0.17gpmSG3-0.07 gpmWhichONE(1)ofthe
following describesRCSleakageinrelationto
TechnicalSpecificationlimits?
A.Identified
leakage exceedstheTSlimitB.Unidentified
leakage exceedstheTSlimitC.Primaryto
Secondary leakageexceedstheTSlimitD.AllRCS leakageiswithinTSlimits
35
2007NRCExamSRO
36.Giventhefollowingplantconditions:*TheunitisinMode3.*Asteamlinebreakhasoccurredon"A"SteamLineinthe
Reactor Building.WhichONE(1)ofthefollowing
describestheplantresponsetothisevent?
A."A"MainSteamLine
pressurewilldrop."B"and"C"MainSteamLinepressureswillremain
constant.AllMSIVswillclosewhenatleast2
Containment
pressure transmitters
indicate3.6psig.B."A"MainSteamLine
pressurewilldrop."B"and"C"MainSteamLinepressureswillremain
constant.AllMSIVswillclosewhen"A"MainSteamLinepressureindicateslessthan675psig.C.All3MainSteamLine
pressureswilldrop.AllMSIVswillclosewhenatleast2
Containment
pressure transmittersindicate3.6psig
.D.All3MainSteamLine
pressureswilldrop.AllMSIVswillclosewhenatleast2MainSteamLines
indicatelessthan675psig
.36
2007NRCExamSRO37.WhichONE(1)
of the following describes the purposeofC-9, Condenser Ava ilability,andC-16 , Condenser Pressure, permissive
signals?A.C-9 prevents2steam dump valves from operating during conditionsthatcould damage the condensers.C-16armsALL
condenser dumpvalveswhen
condenser is below4.5"Hgabsand
adequate eire water pumps are available.B.C-9armsALL
condenser dump valves when condenser is below7.5"Hgabsand
adequate eire waterpumpsareavailable.
C-16 prevents2steam dumpvalvesfrom
operating during conditionsthatcould damage the condensers.C.C-9 anticipates
condenser heat load problems by blocking 2 condenser dumpvalvesat7.5"Hgabs.
C-16 prevents ALL condensersteamdumpvalvesfrom
operatingduringconditionsthatcould damage the condensers.D.C-9 prevents ALL condenser steamdumpvalvesfrom
operatingduringconditionsthatcould damage the condensers.
C-16 anticipates
condenserheatload problems by blocking 2 condenser dumpvalvesat4.5"Hgabs
.37
2007NRCExamSRO38.Giventhefollowingplantconditions:*Theplantisoperatingat100%power.*A FeedwaterLineBreakoccursatthepipingconnectionto"A"SG.WhichONE(1)ofthe
following describestheeffectofthisevent?
A.RCS temperaturerisespriortoreactortrip
.SG"A" continues to depressurize
afterFWIVclosure
.B.RCS temperaturelowerspriortoreactortrip.SG"A" continues to depressurizeafterFWIVclosure.
C.RCS temperatureslowerspriortoreactortrip.SG"A" pressure stablilizes
afterFWIVclosure
.D.RCS temperaturerisespriorto
reactor trip.SG"A"pressure
stablizesafterFWIV closure.38
2007NRCExamSRO39.Giventhefollowingplantconditions:*AStation Blackouthasoccurred.*Thecrewis
restoring off-site powertoBus1DAthroughthenormalfeed.Priortoclosingthenormal
feeder breakertoBus1DA ,whichONE(1)ofthefollow
ingsetsofactionsmustbe
performed , in accordancewithAOP-304.1
, Loss ofBus1DA with Diesel Unavailable?
A.De-energizeTrain"A" ESFLSEnsureBus1DA
TRANSFERINITSwitchisinOFF
B.De-energizeTrain"A" ESFLSEnsureBus1DA
TRANSFERINITSwitchisinON
C.Reset NON-ESF LCKOUTS&AUTO-START
BLOCKSEnsureBus1DA
TRANSFERINITSwitchisinOFFD.Reset NON-ESF LCKOUTS&AUTO-START
BLOCKSEnsureBus1DA
TRANSFERINITSwitchisinON
39
2007NRCExamSRO40.Giventhefollowingplant
conditions:*Alossof off-site powerhasoccurred.*BothEDGshave
respondedasdesigned.
- Subsequently, safetyinjectionoccurs
.*Thefollowing
conditionsexiston"A"EDG:
- Frequency59.9Hz.*Voltage7150Volts*KW Output2600KWRBPressurereachesan
actuation setpointrequiringthestartof"A"RBSpraypumpLoadsstabilize
.....WhichONE(1)ofthe
followingdescribesthestatusof"A"EDG?
A.Alllisted parametersarewithinlimits.B.Frequencyis
belowthelimit.C.Voltageis
belowthelimit.D.Outputexceedsthe
continuousKWrating.40
2007NRCExamSRO41.Giventhefollowingplantconditions:
- lAW GOP-4A , Power Operation(Mode1-Ascending)
, powerhasbeenstabilizedbetween12and15%
.*PreparationsarebeingmadetorolltheMain
Turbineto1800rpm.
- Reactor powerindicatesthefollowing
- IRN-35-1X101%.
- IRN-36-1X101%.
- PRN-41-15%.
- PRN-42-14%
.*PRN-43-14%
.*PRN-44-14%.
- Inverter XIT-5902 output breakertripsopen.WhichONE(1)ofthefollowing
describestheeffectontheunit?
A.APowerRangeRodStop(C-2)signal,withnochangeinreactor
power.B.Areactortripduetothe
deenergization
of IntermediateRangeChannelN-35.C.Areactortripduetothe
deenergization
of IntermediateRangeChannelN-36.
D.An IntermediateRangeRodStop(C-1)signal
,withno changeinreactorpower.
41
2007NRCExamSRO42.Giventhefollowingplant
conditions:*Theplantis
operatingat100%power.*Thefollowing
annunciatorsarereceivedinthecontrolroom:*XCP-636,4-6,DCSYS
OVRVOL T/UNDRVOL T*XCP-637,1-5,INV
3/4 TROUBLE Inverter output voltageindicates120vac
.Assuming NO otheralarmsarereceived,whichONE(1)ofthefollowing
describes thecommoncauseofboth
of the alarms?A.Lossof AlternateSource1FB.B.LossofNormal
Source1DB2Y.C.LossofvoltageonBus1HB.
D.Inverter has transferred
to AlternateSource1FB.42
2007NRCExamSRO43.Giventhefollowingplant
conditions:Theplantis
operatingat100%power.Thefollowingalarmisreceived:
- XCP-624-1-5
,SGALVLDEV*TheRO determinesthatSG"A"levelisrisingslowlyon
L1-474,475,and476.*SG"B"and"C"levelsarestable.WhichONE(1)ofthe
following describesthecauseofthealarmandtheaction
required?Alarmwasreceivedona
...A.5%deviationfrom
programduetoa Feedwater Control Valvefailure;Place"A" Feedwater Controlvalveinmanualandrestoreleveltonormal.
B.5%deviationfrom
programduetoaSteamFlowinputto"A"SGlevelcontrolfailinglow;Selectthe
alternatefeedflowandsteamflowinputs.C.10%deviation from programduetoa Feedwater Control Valvefailure;Place"A" Feedwater Controlvalveinmanualandrestoreleveltonormal.
D.10%deviationfromprog ramduetoaSteamFlowinputto"A"SGlevelcontrolfailinglow;
Select the alternatefeedflowandsteamflowinputs.
43
2007NRCExamSRO44.WhichONE(1)ofthe
following conditionswillresultinthemost
Emergency Feedwater Systemflowrequiredto
maintainSGlevels constant following a reactor trip?A.B.C.O.Core Burnup 1,000 MWO/MTU 1 ,000 MWO/MTU 10,000MWOMTU 10,000 MWO/MTU Initial Power Level 10%100%10%100%44
2007NRCExamSRO45.Giventhefollowingplant
conditions
- Theplantisat100%
powerduringanA1
maintenance
week.*APN-5901hasbeen
transferredtoAPN-1FAwhileworkisinprogresson
XIT-5901.*Thenormal
feeder breakerforbus1DAtripsopen
.*"A" DIGfailstostart.WhichONE(1)ofthe
following describes the subsequent
operationofthe"A"Train
ESFLS?A.Output1willshedloadsandtheESFLSwillgothroughitsnormalsequence.B.Output1willshedloads,butthentheESFLSwillbe
preventedfromoperating.C.Output1willNOTshedloads,buttheESFLSwillgothroughitsnormalsequence.D.Output1willNOTshedloadsandtheESFLSwillbe
preventedfromoperating.
45
2007NRCExamSRO46.WhichONE(1)ofthe
followingdescribesthe
availability
of Channell(TrainA)120VACvital safeguards
powerduringalossofthe
115KVlinefromtheParrGenerating
Complex?A.Isinitially
availablefromBattery1Athrough
inverter XIT-5901, then automaticallyreturnstothenormal
sourceafterDiesel
Generator"A"starts.B.Thestaticswitch
initially transfersthesupplyto1FA,then
automaticallyreturnstothenormal source after Diesel Generator"A"starts.
C.Isinitially
available from Battery1Athrough inverter XIT-5901,thenis manuallyreturnedtothenormal
sourceafterDiesel
Generator"A"starts.D.Thestaticswitch
initially transfersthesupplyto1FA,thenis
manuallyreturnedtothenormal source after Diesel Generator"A"starts.
46
2007NRCExamSRO
47.Theplantisat100%power
.Alossof125VDCcontrol
powertothewillrequireentrytoEOP-1.0
, Reactor Trip/Safety
Injection Actuation.
A.FWBP breakersB.MSIVsC.RCPbreakers
D.PZRSprayValves
47
2007NRCExamSRO48.Giventhefollowingplantconditions:*Alossofoff-site
powerhasoccurred.*BothEDGsstartasrequired.WhichONE(1)ofthe
followingdescribestheoperationoftheEDGRoomVentilation
system?Automaticallystartwhen...
A.DieselRoom
temperatureexceeds88°F,tomaintainroom
temperaturebelowthe Technical Specificationlimitof120°F.B.theassociatedDiesel
Generatorstarts,to maintain room temperaturebelowthe Technical Specificationlimitof88°F.C.DieselRoom
temperatureexceeds72°F,tomaintainroom
temperaturebelowthe Technical Specificationlimitof88°F
.D.theassociatedDiesel
Generator starts , to maintain room temperaturebelowthe Technical Specificationlimitof120°F.
48
2007NRCExamSRO49.Giventhe
following plant conditions:
- Emergency Diesel Generator"A"is paralleledtoits associated
Bus.*Alagging power factorhasbeen established.WhichONE(1)ofthe
following describes the operationofthe diesel generator voltage control switch?A.Loweringthe
voltage control setpointwillcausethe
generatortopickupalargershareoftherealload.B.Raisingthe
voltage control setpointwillcausethe
generatortopickupalargershareoftherealload.C.Loweringthe
voltage control setpointwillcausethe
generatortopickupalargershareofthe
reactive load.D.Raisingthe
voltage control setpointwillcausethe
generatortopickupalargershareofthe
reactive load.49
2007NRCExamSRO50.Giventhe
following plant conditions:*AlossofRB
Instrument
Air has occurred.*RB Instrument
Air header pressure is currently94psigand lowering.Assuming no operator action , whichONE(1)ofthe
following describes the response oftheAir System and why?RB Instrument
Air header pressure decreasesuntil...A.PVA-2659, INSTAIRTORB AIR SERV , automatically
opensat90psigtoensureanair supply for AOVs inside the Reactor Building.B.PVA-2659, INSTAIRTORBAIR
SERV , automatically
opensat93psigtoensureanair supply for AOVs inside the Reactor Building.C.PVT-2660, AIR SPL YTORB , closesat90psigto
isolatetheRB headertoavoidalossof Instrument
Air outside the Reactor Building.D.PVT-2660, AIR SPLYTORB,closesat93psigto
isolatetheRB headertoavoidalossof Instrument
Air outside the Reactor Building.50
2007NRCExamSRO51.Giventhefollowingplant
conditions
- TheplantisinMode6.ReactorBuildingPurgeisinoperation
.*Refueling
activitiesareinprogress.*Aspentfuel
assemblyisdroppedinthecavity.
- Containment
radiation monitor indicationsareallrising.WhichONE(1)ofthe
following describestheradiation
monitorsthatwillinitiateisolationofallorpartofthe
Containment
Purge?RM-A4,RBPurge
Exhaust Particulate(Iodine)(Gas)Atmos
monitor...A.ONLY.B.ANDRM-G17A/B,RB
ManipulatorCraneAreaGammaONLY.
C.ANDRM-A2,RB
Sample Line Particulate(Iodine)(Gas)Atmos
monitor ONLY.D.AND RM-G17A/B, RB ManipulatorCraneAreaGamma
,ANDRM-A2,RBSample
Line Particulate(Iodine)(Gas)Atmosmonitor.
51
2007NRCExamSRO52.Giventhe
following plant conditions:*An immediate dischargetothe penstocksfromboth Waste Monitortanksis required.*Current conditionsareasfollows.*RM-L5andRM-L9areoutof
service*Fairfield
Hydroisinthe"pumping" mode.WhichONE(1)ofthe
following statements
will provide the MINIMUM conditions
necessary for monitor tank release?A.EitherRM-L5or RM-L9 mustberestoredto
operabil ity prior to release.B.BothRM-L5and
RM-L9 mustberestoredto
operability
prior to release.C.TheFairfield
Hydro must converttothe generatingmodeand redundant samples performed prior to release.Two independent
qualified individuals
must verify release calculations
and valve lineups.D.The Fairfield Hydro must converttothe generatingmodepriorto
releaseandeitherRM-L5orRM-L9
must be restored to operability
.Two independent
qualified individuals
must ver ify release calculationsandvalve lineups.52
2007NRCExamSRO
53.WhichONE(1)of the following describes operation of XFN-30A(B), CONTR RM EMERG FILTERING SYS FAN A(B), and XFN-32A(B), CONTROL ROOM COOLING UNITA(B)FAN upon receipt ofahigh radiation alarm on RM-A 1, Control Bldg Supply Air?A.Both XFN-32A&Bandboth XFN-30A&Bstart,all
outside air sourcesareisolated.B.Both XFN-32A&Bandboth XFN-30A&Bstart,returnairis
mixedwithasmall
amount of makeup air.C.Both XFN-32A&Btripandboth
XFN-30A&Bstart,all
outside air sources are isolated.D.Both XFN-32A&Btripandboth
XFN-30A&Bstart, returnairis mixedwithasmall
amount of makeup air.53
2007NRCExamSRO54.Giventhe
following plant conditions:*The plantisin Mode 5.*RHRTrainAisin
service.*RCS temperatureis158°F.*RCS pressureis175psig.*Subsequently,aLoss of Service Water occurs.*Thecrewisperformingactions
contained in AOP-117.1,TotalLoss of Service Water.*NEITHER Service Waterloopcanbe restored.WhichONE(1)ofthe
following describes the effectontheRHR System,andthe procedure that will mitigate the event?A.Stabilize RHR/RCS system temperature
using steam dumps lAW GOP-5, PlantShutdownMode
3toMode5.Goto AOP-115.3, Loss ofRHRwiththeRCSIntact, for long-term mitigation.
B.Stabilize RHR/RCS system temperature
using steam dumps lAW GOP-5, PlantShutdownMode
3toMode 5.Continue using AOP-117.1 ,TotalLoss of Service Water, for long-term mitigation.
C.RHR/RCS system temperaturewillriseasa
resultofaloss of cooling to Component Cooling Water.Goto AOP-115.3 , Loss ofRHRwiththeRCSIntact.
D.RHR/RCS system temperaturewillriseasa
resultofaloss of cooling to Component Cooling Water.Continue using AOP-117.1,TotalLoss of Service Water.54
2007NRCExamSRO55.WhichONE(1)
of the following providestheelectrical
power supplytothe Supplemental
Air Compressor?
A.XSW1DA1 8.XSW1D81C.XSW1A1 D.XSW181 55
2007NRCExamSRO56.Giventhefollowingplant
conditions:*TheF ire ProtectionSystemactuatedduetoaMain
Transformer
Fire.*System pressure droppedto80psigbefore
recoveringduetotheactuationof
necessary equipment.*Thefireisout.*Thedelugevalveisisolatedandreset.WhichONE(1)ofthe
followingdescribesthe
equipmentthatisrunning
,andthemethodofshuttingthe
equipment down?A.ONLY theMotorDrivenFirePumpisrunning;mustbe
stopped locally.B.ONLYthe MotorDrivenFirePumpisrunning
- maybe stoppedlocallyorinthecontrolroom
.C.TheMotorDrivenand
EngineDrivenFirePumpsarerunning
.Bothmustbestoppedlocally.D.TheMotorDrivenand
EngineDrivenFirePumpsarerunning.TheMotorDrivenPumpmaybe stopped locallyorinthecontrolroom,the
EngineDrivenPumpmustbestoppedlocally
.56
2007NRCExamSRO57.Giventhefollowingplant
conditions
- ALOCAhasoccurred.*Safety Injectionisactuated
.ReactorBuildingpressure
indicates14psigandrisingslowly.*While performingactionsofEOP-1.0, Reactor Trip/Safety
Injection Actuation ,thefollowingvalvesindicateOPEN:*RCPSL WfRISOL8100*LTDNISOL8152*RBAIR SERVISOL2660WhichONE(1)ofthefollowing
describesthefailurethathas
occurredandtheMINIMUMaction
necessary to mitigate the condition?
A.PhaseAhas partiallyfailed.Place
eitherPhaseA actuation switchesinthe ACTUATE position.B.PhaseAhas partiallyfailed.PlacebothPhaseA
actuation switchesinthe ACTUATE position.C.PhaseBhas
partially failed.Place eitherPhaseB actuation switchesinthe ACTUATE position.D.PhaseBhas
partially failed.PlacebothPhaseB
actuation switchesinthe ACTUATE position.57
2007NRCExamSRO
58.Giventhefollowingplant
conditions
- Thereactorhas
tripped.SafetyInjectionisactuated.*AnRCS cooldownisinprogressin
accordancewithEOP-2.1, Post LOGA Goo/down and Depressurization
.*Thefollowingtableisaplotofthecooldown:
TIMERCSTCOLDTIMERCSTCOLD 0800 54rF 0945 425°F 0815 530°F 1000 395°F 0830 520°F 1015 382°F 0845 505°F 1030 364°F 0900 498°F 1045 340°F 0915 478°F 1100 310°F 0930 44rF 1115 280°FAtwhichtimewastheTech
SpecRCSCooldownratelimit
FIRST exceeded?A.0915.B.0930.C.1000.D.1115 58
2007NRCExamSRO59.Giventhe
following plant conditions:*A LOCA outside containment
has occurred.*Thecrewis
performing
the actions in EOP-2.5,LOCAOutsideContainment.WhichONE(1)
of the following actionswillbe attempted to isolatethebreakandwhichindicationisusedto
determineiftheleakhasbeenisolatedin
accordance
with EOP-2.5?A.Isolatelow
pressure Safety Injection piping.RCS pressure is monitored, because SI flow will repressurizetheRCSwhenthebreakis isolated.B.Isolatelow
pressure Safety Injection piping.PZRlevelismonitored,becausewhenthe break is isolated, RCS inventory willrapidlyrise.C.Isolatehigh
pressure Safety Injection piping.RCS pressure is monitored, because SI flow will repressurizetheRCSwhenthebreakis isolated.D.Isolatehigh
pressure Safety Injection piping.PZRlevelismonitored,becausewhenthe breakisisolated,RCS
inventory willrapidlyrise.
59
2007NRCExamSRO60.WhichONE(1)ofthe
following describesthereasonthataREDconditionontheIntegrityCSF
StatusTreemay developwhileperformingactionsofEOP-14.1
, Response to DegradedCoreCooling?
A.CoreExit Thermocouple
temperature
will decreaserapidlywhenLowHeadSIPumpsarestartedandSIflowisinitiated
.B.CoreExit
Thermocouple
temperature
will decreaserapidlywhenSG
depressurizationandSI Accumulatorinjectionoccur.C.RCSColdLeg
temperaturewilldecreaserapidlywhenLowHeadSIPumpsarestartedandSIflowisinitiated.D.RCSColdLeg
temperaturewilldecreaserapidlywhenSG
depressurizationandSI Accumulator
injection occur.60
2007 NRC Exam SRO61.Giventhe
following plant conditions:*A LOCA has occurred.*The crew is performing
actions containedinEOP-2.0, Loss of Reactor or Secondary Coolant.*The following conditions
currently exist:*Integrity-RED*Containment-RED*Subcriticality
-ORANGE*Core Cooling-ORANGE*Inventory-YELLOW*Heat Sink-YELLOWWhichONE(1)
of the following describes the correct procedure flowpath for these conditions?
A.EOP-17.0 , ResponsetoHigh Reactor Building Pressure , followed by EOP-16.0, Response to Imminent Pressurizer
Thermal Shock Cond ition.B.EOP-16.0 , Response to Imminent Pressurizer
Thermal Shock Condition , followed by EOP-17.0, ResponsetoHigh Reactor Building Pressure.C.EOP-14.1, Response to Degraded Core Cooling , followed by EOP-16.0, Response to Imminent Pressurizer
Thermal Shock Condition.
D.EOP-16.0, Response to Imminent Pressurizer
Thermal Shock Condition , followed by EOP-14.1 , Response to Degraded Core Cooling.61
2007NRCExamSRO
62.Giventhefollowing
plant conditions:*Areactortriphasoccurredduetoalossofoffsitepower.*Thecrewis
performingactionsofEOP-1.4, Natural CirculationCooldownwithSteamVoidinVessel.*Duringtheevent,RCPsealcoolingwaslost,but
subsequently
restored.*The operatingcrewispreparingtoinitiatetheRCScooldown.Thefollowing
conditionsareindicated:*RVLlSNRlevelis89%.*RCS subcoolingis60°F.*PZRLevelis72%andstable
.WhichONE(1)
of the followingactionsisrequiredin
accordancewithEOP-1.4?
A.UsePZR Heaters as necessary to saturate PZR water and continueinEOP-1.4.
B.Initiate Safety InjectionandgotoEOP-1.0, ReactorTripOr Safety Injection.C.StartaRCPandgotothe
applicableportionofthe
appropriate
GOP.D.ReturntoEOP-1.3, Natural Circulation
Cooldown.62
2007NRCExamSRO63.Giventhefollowingplantconditions:*ALOCAhasoccurred.*DuetolowRHRSumpLevel,thecrewhas
transitionedfromEOP-2.2, TransfertoColdLegRecirculation,toEOP-2.4, Loss Of Emergency Coolant Recirculation
.*All automatic actions occurredasdesigned.*TwoChargingpumpsandtwoRHRpumpsarerunning.*BothRB SprayPumpsarerunning.*RHR,Charging,andRB
Spraypumpampsandflowarestable.*RWSTlevelis
approximately5%andcontinuestolower.WhichONE(1)ofthe
following describeshowtheCharging,RHR,andRBSpraypumpsshouldbe
operated in accordancewithEOP-2.4?ChargingPumpsRBSprayPumpsRHRPumps A.StopBOTHLeaveBOTHrunningLeaveBOTHrunning
B.StopONEStopBOTHStopONE C.StopBOTHStopBOTHStopBOTH D.LeaveBOTHrunningLeaveBOTHRunningStopONE
63
2007NRCExamSRO
64.Thecrewis performing
actionsofEOP-3.1, Uncontrolled
Depressurization
of All Steam Generators.WhichONE(1)ofthe
following describes the Technical Specification
implications
oftheevent?A.RCS cooldown rates above100°Fper hour may potentiallyresultin non-ductilefailureofthe
reactor vessel.B.Pressurizer
coo/downratesabove100°Fper
hour may potentiallyresultin pressurized
thermal shocktothepressurizer.C.LossofSG
inventory may ultimatelyresultintheRCS
Pressure SafetyLimitbeing
exceeded.D.LossofSG
inventory may ultimatelyresultinthe
Reactor Core Safety Lim it being exceeded.64
2007NRCExamSRO65.WhichONE(1)
of the followingdescribesthestatusofRB
ventilationandRBCU'suponcompletion
of the actionscontainedinEOP-17.2, ResponsetoHigh Reactor Building Radiation Level?A.RBPurge isolatedAllRBCUfansin
SLOW B.RBPurge isolatedRBCUfans selectedonswitchRBCUTRAIN
AlB EMERG ,runningin SLOW C.RBMiniPurgein
serviceAllRBCUfansin
SLOW D.RBMiniPurgeinserviceRBCUfans selectedonswitchRBCUTRAINAlBEMERG
,runningin SLOW 65
2007NRCExamSRO
66.Inaccordancewith
OAP-100A, Communication,whichONE(1)ofthefollowing
communicationsshouldusethe
phonetic alphabet?A.Communications
involvingsafetysystemtrains
.(Train Alpha)B.Communications
involving manipulationofplant components.(AlphaCharging
Pump)C.Communications
describing
ContainmentIsolation(PhaseBravo)D.All communicationsthatarenot
'information
only'.66
2007NRCExamSRO67.Giventhe
following plant conditions
- The plantisat46%power and increasing
lAW GOP-4A , Power Operation (Ascending)at3%perhour
.*Alossof Feedwater occurs.*All threeS/GNR levelsareat5%and
lowering.*Itisnow60
seconds later.WhichONE(1)ofthe
followingisthe expected responseofthe ATWS Mitigation
System Actuation Circuitry (AMSAC)?A.AMSAC will NOT actuate becauseitisnotarmed
.B.AMSAC will TRIP the reactor and START the EFW pumps.C.AMSAC will NOT actuate becausethetime delay on reactor powerhasnottimed
out.D.AMSACwill TRIPthemain turbine and START the EFW pumps.67
2007NRCExamSRO68.Giventhefollowingplant
conditions:*AnRCSleakisinprogress.*Thecrewis
performing
the appropriateAOPforthe plant condition.*Letdownisisolated
.*Chargingflowis
maximized.*RCS pressureis1990psigandlowering.
- Reactor Building pressureis1.8psigandrising.
Pressurizerlevelis18%andlowering
.*VCTlevelis15%andlowering.WhichONE(1)ofthe
following describesthestatusofthe
plantandtheaction
required?A.AnRPS setpointhasbeen exceeded.TriptheReactorandinitiateSafetyInjection
when immediateactionsofEOP-1
.0havebeen completed.
B.AnRPS setpointhasbeen exceeded.Tripthereactorand
concurrently
performactionsofthein-useAOPwhen
immediateactionsof EOP-1.0havebeen completed.C.AnRPS setpointhasNOTbeen
exceeded,TriptheReactor,performthe
immediate actionsofEOP-1.0,theninitiateSafetyInjection.
D.AnRPS setpointhasNOTbeen
exceeded,TriptheReactor,performthe
immediate actionsofEOP-1.0,continueto
implementtheAOPconcurrently,then
initiate SafetyInjectionwhen
Pressurizerlevelis<12%
.68
2007NRCExamSRO69.Theunitisat100%power.Allsystemsareinnormal
alignments.WhichONE(1)ofthe
following activitiesrequiresentryintoa
technical specificationLCOaction statement?
A.CCWPumpB mechanicalsealrepair.B.ChargingPumpAremovalfromserviceforoilchange.C.BoricAcid
TransferPumprecircvalveleakrepair.D.RHRHeat Exchanger Dischargeflowcontrolvalverepair.
69
2007NRCExamSRO70.WhichONE(1)ofthe
following describes the MINIMUM Source Range Nuclear Instrumentation
requ irement that mustbemetpriorto
off-loadingfuelfromthe
reactor vessel?Visual in control room Audibleincontrolroom
Audible inRB A.B.C.D.1 2 2 2 1 1 2 2 1 1 1 2 70
2007NRCExamSRO
71.Giventhefollowing
information:*A27yearoldnewV.C
Summer employeehasafully completedNRCForm4anda2007radiationexposurehistoryasfollows
- 2650 millirem from previous employment
with ProgressEnergyin2007.*110milliremsincebecomingaV.C.Summer employee.WhichONE(1)ofthe
followingdescribestheMAXIMUM
ADDITIONALexposuretheemployeemay
receivepriortoreachinghisMAXIMUMAdmin
istrativeDoseControlLimit,includingany
applicable
extensions
, lAW HPP-0153, Administrative
Exposure Limits?A.1240milliremB.1350millirem
C.2240milliremD.2350millirem
71
2007NRCExamSRO
72.Giventhefollowingplant
conditions
- AGeneral Emergency exists.*TheTSCis manned.*AvalveintheAuxBuildingmustbeclosedtoprevent
damagetovaluablesafetyrelated
equipment.Radiationlevelsare
extremely high.WhichONE(1)ofthe
following describesthemaximumdosethatisallowedtoperformthisoperationand
whose permissionisrequired?Anindividualmayreceive
...A.Upto10Remwith
permissionfromtheDutySSB.25Rem,ormore,with
permissionfromtheDutySSC.Upto10Remwith
permissionfromtheEDD.25Rem,ormore,with
permissionfromtheED 72
2007NRCExamSRO73.Giventhefollowingplantconditions:*Areactortripandsafetyinjectionhaveoccurred.*Off-Site power islost subsequenttosafetyinjectionactuation.
- Equipment failures during performance
of EOP-2.0 , Loss of Reactor or Secondary Coolant,resultedinthefollowingconditions
- Bus1DAis de-energizedduetoafault.*CSF StatusTreesind icateasfollows:*Subcriticality*CoreCooling*HeatSink*Integrity*Containment
- Inventory GREEN ORANGE RED GREEN YELLOW YELLOWWhichONE(1)ofthe
following describes the requirementforCritical
Safety FunctionStatusTree
Monitoring
in accordance
with OAP-103.04, EOPIAOPUser'sGuide?
A.Continuous
monitoringisrequired.B.Monitorevery5-10
minutesunlessachangeinstatusoccurs.C.Monitor every10-20 minutesunlessachangeinstatusoccurs
.D.Monitoredfor
information
only.73
2007NRCExamSRO74.Giventhe
followingplantconditions:
T=OAfireisoccurringintheAuxBuilding436'.T+2FireBrigade
Leaderreportstothescene.
T+15 NotificationofUnusualEventdeclared.
In accordancewithEPP-013, Plant Fire,who,bytitle
, is coordinatingthefirefightingeffortswiththeFireBrigadeLeader?
A.Shift Supervisor
B.Emergency DirectorC.OSC SupervisorD.HealthPhysicsShift
Leader 74
2007NRCExamSRO75.Giventhefollowingplant
conditions
- TheUnitisinMode5.*RCSDra inDowntoMidLoopisinprogressin
preparationforweldingonaHotLegopening
.RHRPumpAisinservice
.*Duringthedraindown
,RHRampsand
discharge pressurebeginfluctuating
erratically.*ThecrewentersAOP-115.1
,RHRPump Vortexing.*The drain-downisstopped.WhichONE(1)ofthe
following describestheFIRSTactionthatwillberequiredinaccordancewith
A.ReduceRHRflow.
B.AligntheRHRPumptotheRWST.C.RaiseRCSlevel.D.Ventthe operatingRHRloop.75
2007NRCExamSRO
76.Giventhe following plant conditions
- The plantisat50%power.*ALL controlsarein automatic.*ALL MCB switchesarein their normal positionforthis power level.*An event occurs resultinginthe following indications:*RCS Tavg rising approximately
5°F above Tref.*Reactor Powerisrising.*First Stage Pressure Transmitter
PT-446 indicates330psigandstable.
- First Stage Pressure Transmitter
PT-447 indicates800psig.*Control BankDis withdrawingat16 steps per minute.WhichONE(1)of
the following describes the procedure entry required to mitigate theeventandthe
reason for the procedural
actions taken?A.AOP-403.3 , Continuous
ControlRodMotion;
to minimize the impact on power distribution
limits.B.AOP-403.3, Continuous
Control Rod Motion;to preventanoutof spec negative DELTA-I.C.AOP-401.7 , Turbine First Stage Pressure Transmitter
Failure;to minimize the impact on power distribution
limits.D.AOP-401.7 , Turbine First Stage Pressure Transmitter
Failure;to preventanoutof spec negative DELTA-I.76
2007NRCExamSRO
77.Giventhe followingplantconditions:*Followinga
turbinerunback,thecrewisstabilizingtheplantin
accordance
with the appropriate
AOP.*ControlBank
"0" Group Countersareat 180 steps.*OnORPI,oneControlBank
"0" rod indicates196steps;allothersindicate182
steps.*The affectedrodhasablown
movable gripperfuseandhasbeen
determined
to be trippable.WhichONE(1)
ofthefollowing
actions is appropriateforthisevent?Realignthe
mispositionedrodtomeetTSlimitswithin
...A.1hourto ensure ShutdownMarginis maintained.B.6hoursto
ensure ShutdownMarginis maintained.
C.1hourto ensure acceptable
power distributionlimitsare maintained.
O.6hoursto ensure acceptable
power distributionlimitsare maintained
.77
2007NRCExamSRO78.Giventhe
following plant conditions
- Reactor poweris100%.*Reactor Trip Breakertestingisbeingperformed.
- ReactorTripBypass
Breaker'A'andReactorTrip
Breaker'B'areboth
RACKEDINand CLOSED.*ReactorTripBypass
Breaker'B'andReactorTrip
Breaker'A'areboth
RACKEDOUTandOPEN.
After completion
ofthetesting
, the ElectriciansRACKINand Operationsattemptsto
CLOSE ReactorTripBypass
Breaker B.*Immediately
upon attemptingclosure,ReactorTrip
Bypass Breaker'B'opens.*NO other breakers reposition
.WhichONE(1)ofthe
following describestheresponsetothis
condition?Thereacto r has...A.NOTtripped, immediately
enter EOP-13.0, Response To Abnormal Nuclear Power Generation
,anddirectthe
NROATC to commence rod insertion.B.NOTtripped, immediately
enter EOP-1.0, Reactor Trip/Safety
Injection Actuation,directthe NROATC to manually tr ipthereactor.
C.tripped ,havean operator"backup"thereactortrip
, then verify the turbine/generatorhastripped
.D.t ripped, direct an operatortoverify turbine/generatorhastripped,whentime
permits , directtheIBAOto locallyopenbothReactorTrip
Breaker'B'andReactorTripBypass
Breaker'A'.78
2007NRCExamSRO
79.Giventhefollowingplant
conditions
- Theplantisat100%power.*Thefollowingalarmsarereceivedinthe
sequence listed, approximately
10 seconds apart:*XCP-616 , 1-5 ,PZRLCSDEV HI/La*XCP-616 ,1-2,PZRLVLHI
- XCP-616, 1-1 ,PZRLVLHI*TheRO determinesthatPZRlevelindicatesthefollowing
- L1-459 indicates95%andrising
- L1-460 indicates56%andlowering
- L1-461 indicates55%andlowering*Trip StatuslightCHAN1PZRLVLHI
isilluminatedWhichONE(1)ofthe
followingdescribestheact
ionsthatwillbed
irectedbytheCRSandtheTS implications?
Se lect unaffec tedPZRlevelchannels
,operatePZRheaters,and...
A.reducechargingflowtomaintainPZRlevel.Doesnot satisfyTSLCO3.3.1, ReactorTripSystem
Instrumentation
ONLY.B.reducechargingflowtomaintainPZRlevel.Doesnot satisfyTSLCO3.3.1,ReactorTripSystem
Instrumentation,ANDdoesnotsatisfyTSLCO3.3.3.6, Accident Monitoring
Instrumentation
.C.raise chargingflowtomainta
inPZRlevel.Doesnot satisfyTSLCO3.3.1 , Reactor Tr ip System Instrumentation
ONLY.D.raisechargingflowto
maintainPZRlevel.Doesnot satisfyTSLCO3.3.1
, Reacto r T rip System Instrumentation
,ANDdoesnotsatisfyTSLCO3.3.3.6
, Accident Moni toring Instrumentation.
79
2007NRCExamSRO80.Giventhefollowingplant
conditions:*Amanualreactortripwas
performedduetohigh turbine vibration.*Thecrewismakingthe
appropriatetransitionfromEOP-1.0, Reactor Trip/Safety
Injection Actuation.*RCS pressureis2175psigand
slowly lowering.*PT-444,CNTRLCHAN
PRESS PSIG ,hasfailedhigh.*TheROreportsthatPZR
SprayValvePCV-444C
indicates open.WhichONE(1)ofthefollowing
describestheprocedurethatwillbeusedandtheactionrequiredtomitigatethis
event?A.RefertoAOP-401
.5, Pressurizer
Pressure Control Channel Failure, whileperformingtheEOPs.
EnsurePZRSprayvalvesareclosedand
energize PZRHeatersto stabilize RCS pressure.B.RefertoAOP-401
.5, Pressurizer
Pressure Control Channel Failure, whileperformingtheEOPs
.TripallRCPsandenergizePZRHeaterstostabilizeRCS
pressure.C.GotoEOP-1.1
, ReactorTripRecovery.TripONLYRCP"A"and
energize PZRHeatersto stabilize RCS pressure.D.GotoEOP-1.1, Reactor Trip Recovery.TripALLRCPsand
energizePZRHeaters
to stabilizeRCSpressure.
80
2007NRCExamSRO
81.Giventhefollowingplant
conditions
- Theplantis
currentlyatfullpower.*Thefollowing
sequenceofeventsoccurred:0200Thenormal
feeder breakerto7.2kVbus1DAtrippedopen
.TheAEDGstartedandthe
sequencercorrectlystartedallloads
.0215TheAEDG
tripped0220DCbus1HAwaslost
No operator actionshavebeentaken.*TheAEDGhasbeenrepairedandtheoperatingcrewispreparingtorestarttheEDGand reenergize
7.2kVbus1DA.WhichONE(1)ofthe
following describes(1)whatactionisrequiredpriortore-energizingthebus
,and(2)thetimeallowed
,byTechSpecs
,tobeinMode37
A.(1)(2)B.(1)(2)C.(1)(2)D.(1)(2)Openallload
breakers on 7.2kVbus1DAfromtheMCB
.2HoursOpenallload
breakerson7.2kVbus1DAfromthe
switchgear
room.2HoursOpenallload
breakers on 7.2kVbus1DAfromtheMCB.1HourOpenallload
breakers on 7.2kVbus1DAfromthe
switchgear
room.1Hour 81
2007 NRC Exam SRO82.Giventhe
following plant conditions:
- The plantisat 100%powerwithall systems in normal alignments.
- The RO determines
that actual Pressurizerlevelis trending DOWNandVCTlevelis trending UP.CHGLINEFLO HI/LO annunciator
has actuated.*FI-122A, CHG FLOW GPM, reads0gpm.*Charging pump currentis5amps.*RCS temperature
and pressure are stable.Which ONE (1)of the following describes the procedure that should be implementedandthe initial actions required?A.AOP-102.2, Loss of Charging;stop the operating Charging Pump and isolate Letdown.B.AOP-102.2, Loss of Charging;reduce letdownto45 gpm and verify the charging system valve lineup.C.AOP-101.1, Loss of ReactorCoo/antNot
Requiring Sf;stopthe operating ChargingPumpand isolate Letdown.D.AOP-101.1, Loss of Reactor Coo/ant Not Requiring Sf;open FCV-122 as necessary and reduce Letdownto45 gpm.82
2007NRCExamSRO83.Giventhe
following plant conditions:
Event 5/21 5/28 5/28 1230 1230 1645BOTHTrainARBCUs
declared inoperabledueto commoncausefailure.
RBCUs not returned to service.Plantshutdownto
Mode3initiated
.PlantinMode3.WhichONE(1)ofthe
following describes the LATESTtimeon5/28
thataninitialreporttotheNRCmustbe
made?A., 1330 B.1630 C.1745 D.2045 83
2007NRCExamSRO84.Giventhefollowingplant
conditions:
- ReactorBuildingPurgeisdesired.
RB EquipmentHatchisOPEN.WhichONE(1)ofthe
followingdescribesan
acceptable
alignment for Reactor Building Purge?A.2supplyfansand1
exhaustfanrunning;RM-A2
operabilitydesiredbutNOTrequiredduringpurge
.B.1supplyfanand2
exhaustfansrunning;RM-A2
operabilitydesiredbutNOTrequiredduringpurge.C.2supplyfansand1
exhaustfanrunning;RM-A2
operabilityrequiredduringpurge
.D.1supplyfanand2
exhaustfansrunning;RM-A2
operabilityrequiredduringpurge
.84
2007NRCExamSRO85.Giventhefollowingplant
conditions:*Theplantisat47%power.*Thefollowingalarmisreceivedinthecontrolroom:
- XCP-646-2-1, RM-G19 HI RAD*TheRO confirms that RM-G19Bisoff-scalehigh.*ChargingPumpflowisrisingslowly.
- ChemistryandHealthPhysicshaveconfirmedthatthealarmisvalid
.WhichONE(1)ofthe
following describesadditionalactionsthatwillberequiredin
accordancewiththealarm
response?A.Remove Condensate
Polishersfromservice;GotoAOP-101
.1, RCS Leak not Requiring SI.B.Remove Condensate
Polishersfromservice;Goto
AOP-112.2, SGTubeLeaknot
Requiring SI.C.Place Condensate
Polishersinservice;GotoAOP-101.1, RCS Leak not Requiring SI.D.Place Condensate
Polishersinservice;Goto
AOP-112.2, SG Tube Leak not Requiring SI.85
2007NRCExamSRO86.Giventhefollowingplant
conditions:*A transient has occurredresultinginthefollowingalarm:*PRFLUXHIRODSTP
- Reactor power indicatesthefollowing:*N41-101.9%andstable*N42-102.8%and
stable*N43-101.9%andstable*N44-103.1%andstable*Tavgis578°Fand
stableWhichONE(1)ofthe
followinghasoccurred,andwhich
action(s)/procedure(s)
is/arerequiredtobe
implemented?A.ARodStopwasinitiatedby1PRchannelONLY
- initiateRCSborationtoreducepowerin accordancewiththe applicable
alarm response.B.ARodStopwasinitiatedby2PR
channels;reduce turbineloadtoreducepowerin
accordance
with applicable
alarm response procedures.
C.ARodStopwasinitiatedby2PR
channels;initiateRCS
borationtoreducepower
in accordancewiththe applicablealarmresponse.
D.ARodStopwasinitiatedby1PRchannelONLY;reduce
turbineloadtoreducepowerin accordance
with applicablealarmresponse
procedures.
86
2007NRCExamSRO
87.Giventhefollowingplant
conditions:*Theplantwasoperatingat98%powerwhenalossofoff-site
power occurred.*Eight minuteslater,thefollowingplant
conditions
exist:*1DAand1DBBus
voltageiszero(0).*RCS pressureis2235psigandslowlyincreasing.*RCSLoopT HOTis602°Finall3loopsandstable
.*RCSLoopT COLDis565°Finall3loopsandstable.*CoreexitTCs
indicate approximately610°Fandrisingslowly.*Steam Generator pressures are approximately1100psigandstable
.*PZRlevelis20%andstableWhichONE(1)ofthe
followingdescribesthe
current plant conditionsandactionthatwillbe directed?A.Heatremovalisbeing
maintainedbysteamlinePORVs.
VerifythatNaturalCirculationexistsin
accordancewithEOP-6.2, Loss of AllESFAC Power RecoveryWithSIRequired.
B.Heatremovalisbeing
maintained
by condensersteamdumps.
VerifythatNaturalCirculationexistsin
accordancewithEOP-6.1, Loss of AllESFAC Power RecoveryWithoutSIRequired.C.Natural Circulationdoesnotexist.Heatremovalmaybe
establishedinaccordancewithEOP-6.2, Loss of All ESF AC Power RecoveryWithSIRequired.D.Natural Circulationdoesnotexist.HeatremovalmaybeestablishedinaccordancewithEOP-6.1, Loss of All ESF AC Power Recovery WithoutSIRequired.
87
2007NRCExamSRO88.Giventhefollowingplantconditions:*Areactortriphas
occurredduetolossofoff-sitepower.
ESF equipment responds as designed.*Off-Site powerhasNOTbeenrestored.*CSTlevel indicates14feet.Assumingpowerwillbe
unavailableforanextendedperiodoftime
,(>4hours)whichONE(1)ofthefollowing
describes the event mitigation
strategyuponexitfrom
EOP-1.0, Reactor Trip/Safety
Injection Actuation?
A.GotoEOP-1.1, Reactor Trip Recovery;cooldowntheRCSusing
EOP-1.3 , Natural Circulation
Cooldown.B.GotoEOP-1.1, Reactor Trip Recovery;stabilizetheprimaryand
secondary plants ,andremaininEOP-1.1until
powerisrestored.C.GoToGOP-5
, Reactor Shutdown From StartuptoHot Standby (Mode 2toMode 3);referto AOP-304.3, Loss of All Balance of Plant Buses ,torestoreservicebus
power.D.GoToGOP-5, Reactor Shutdown From StartuptoHot Standby (Mode 2toMode3);referto
SOP-211, Emergency Feedwater System ,toswap EFWtoService Water.88
2007NRCExamSRO
89.Giventhefollowing
plant conditions:*Theplantisina
normal service water system alignmentwith'A'and'B'
SWpumpsrunning.
- XCP-604-1-2"SWP A/C TRIP" alarms.*Annunciator
XCP-604-1-4"SWP AlC DISCH PRESSLO"alarms.
- Annunciator
XCP-605-1-4"SWP B/C DISCH PRESSLO"alarms.*PI-4402, Service Water Pump'A'Discharge Pressure, indicates5psig.*PI-4422, Service Water Pump'B'Discharge Pressure, indicates48psig.*'A'SWpumpwillnotrestart.
- AOP-117.1, Total Loss of Service Water,hasbeen entered.WhichONE(1)ofthe
following describes the actions that shouldbetakento mitigate this event?A.Referto SOP-117, Service Water System, and ensurethe'C'SW pump automatically
startedonlow header pressure.B.Continue in AOP-117.1,TotalLoss ofServiceWater,tripthereactor,andtr
ip all RCPs.C.Referto SOP-117'.Service Water System, and startthe'C'SWpumponthe'A'
train.D.Continue in AOP-117.1,TotalLoss ofServiceWater, and isolateall CCW loads.89
2007NRCExamSRO90.Giventhe
following plant conditions
- The plantisin Mode 5.*Welding activitiesinthe Cable SpreadingRoomarein progress.*The Simplex Panel indicates actuation of Fire Protectionintheroom.*Maintenance
reports that Fire Suppression
is actuated, but thereisnoactual
fire.WhichONE(1)
of the following describesthefire suppression
actuationandtheactiontobe taken?A.C02;Evacuate personnelfromtheareaandstopthe
discharge in accordance
with the associated
Fire Emergency ProcedureandFire Pre-Plan.B.C02;Evacuate personnelfromtheareaandstopthe
discharge in accordance
with SOP-509, Fire Suppression
System.C.Pre-Action
Sprinkler;
Terminate the actuation in accordancewiththe associated
Fire Emergency ProcedureandFire Pre-Plan.D.Pre-Action
Sprinkler;
Terminate the actuation in accordance
with SOP-509, Fire Suppression
System.90
2007NRCExamSRO91.Giventhefollowingplant
conditions:*ASteam GeneratorTubeRupturehasoccurred.*Dueto equipment failures ,thecrewisperformingactionscontainedinEOP-4.3
,SGTRwithLoss
of Reactor Coolant-Saturated Recovery.*TheShift Engineer informsyouthatallCSFStatusTreesareGREENwiththeexceptionofthe
following:*CoreCooling-
YELLOWduetoRVLlSlevel
- Inventory-YELLOWduetoRVLlSlevelWhichONE(1)ofthe
following describesthecorrect
implementationofproceduresforthisevent?
A.Select another post-SGTR cooldown method lAW EOP-4.0.Implementation
ofYellowPath
proceduresisnotallowedwhileinEOP-4
.3.B.RemaininEOP
-4.3 while addressingBOTHYellowPath
procedures
.Youmaychooseto implement the actions of eitherYellowPath
procedure.C.Select another post-SGTR cooldown method lAW EOP-4.0andaddressONLYtheCoreCoolingYellowPath
,duetoitshigherpriority.D.Remainin
EOP-4.3 and addressONLYthe InventoryYellowPathduetoconflictbetweentheCoreCooling
YellowPathandEOP-4
.3 actions.91
2007NRCExamSRO
92.Giventhe following plant conditions.*0547A Reactor Trip occurred*0548Tavg=552°FandRCS pressureis2080psig*0748Tavg=379°FandRCS pressureis1550psig*0948Tavg=248°FandRCS pressureis1850psigWhichONE(1)
of the following describesthelimit thathasbeen exceededandthereasonwhy?(REFERENCE
PROVIDED)Limit A.Plant Operational
Limits Curve T1B.Plant Operational
Limits Curve T1C.TS CooldownLimit(Figure
3.4-3)D.TS CooldownLimit(Figure
3.4-3)Reason RCS pressureistoohigh RCS temperatureistoolow RCS pressureistoohigh RCS temperatureistoolow 92
2007NRCExamSRO93.Giventhefollowingplant
conditions:*ALOCAhasoccurred.*Thecrewhas
completed EOP-1.0, Reactor Trip/Safety
Injection Actuation,tothepointof transition
to another procedure.*AllESF equipment is operatingasdesigned.*Thefollowing
conditionsexistinthe
Reactor Building:*RB Pressure 10.5psigandrisingslowly
.*RHRSumpLevel424feetandrisingslowly.WhichONE(1)
of the following describestheconditionthatexists,theproceduretransitionthatwillbemade
,andthe strategyforrecovery?
A.ORANGEconditiononHigh
ReactorBuildingPressure
.Enter EOP-17.0, Response to Reactor BuildingHighPressure, and attempttolocateandisolatethesourceoftheleak;notifyplant
stafftoobtain recommendedactionfor disposalofwaste.B.ORANGEconditiononRHRSumpLevel.EnterEOP-17.1, Response to Reactor Building Flooding , and attempttolocateandisolatethe
sourceoftheleak;notify
plant stafftoobtain recommendedactionfor disposal of waste.C.ORANGE conditiononHigh ReactorBuildingPressure
.Enter EOP-17.0, Response to Reactor BuildingHighPressure,andensureRBIsolationandHeatRemovalfunctionsare
satisfied.D.ORANGE conditiononRHRSumpLevel.EnterEOP-17
.1, Response to Reactor Building Flooding , and ensureRBIsolationandHeatRemoval
functions are satisfied.
93
2007NRCExamSRO94.Giventhefollowingplant
conditions:*TheplantisinMode1.*Makeupto'A'SI Accumulator
was just completed.*'A'SI Accumulator
parametersareasfollows:*Boron Concentration*Pressure*Level2197ppm650psig 67%WhichONE(1)ofthe
followingdescribestheactionrequiredin
accordance
with Technical Specificationsandwhy?A.Restoreboron
concentrationtowithinlimitswithin1hour.Tominimizethe
potentialforreaching
unacceptable
peak cladding temperaturesduringaLOCAwith
postulatedfailureof1otherSI
Accumulator.B.Restoreboron
concentrationtowithinlimitswithin1hour.Tomaintainthe
calculatedDNBRinthecoreatorabovethedesignlimitduring
short-term
transientsuntilcoreisreflooded
.C.Restore pressuretowithinlimitswithin1hour.
To minimize the potentialforreaching
unacceptable
peak cladding temperaturesduringaLOCAwith
postulatedfailureof1otherSI
.D.Restore pressuretowithinlimitswithin1hour.Tomaintainthe
calculatedDNBRinthecoreatorabovethedesignlimitduring
short-term
transientsuntilcoreisreflooded.
94
2007NRCExamSRO95.G iventhefollowingplant
conditions:*Youarethe
ControlRoomSupervisor.*An explosion occursresultingin
significant
damageintheunit.*TheShift Supervisorwasseriouslyinjuredinthe
explosionandisincapacitated.*Thereareno
proceduresordirectivesthatprovide
adequate directiononcontroloftheplantandrescueofinjuredpeopleforth
is situation.*Immediateactionisrequired.WhichONE(1)ofthe
following describes the requirement
for performingthisaction?
A.Youmayapprovethisactionin
accordance
with 10CFR50.54(x)and(y).B.Youmustobtain
concurrencefromoneotherSROpriortoperformingtheaction.C.TheNRCmustbenotifiedpriortotheactionandshould
concurwiththeactiontobetaken.D.ThePlant Managermustbenotifiedandshould
concurpriortotakingtheaction.
95
2007NRCExamSRO96.Giventhefollowingplant
conditions:*100%power.*AllmajorcontrolsareinAUTO.*ChargingPump"A"isrunning.*ChargingPump"B"hasbeen
out-of-service
for AuxiliaryOilPumpreplacement.*ChargingPump"C"isalignedtoTrain
"B".*ChargingPump"B"isreadyfor
post-maintenance
testing.WhichONE(1)ofthe
choicescorrectlycompletesthefollowing
statement regardingtheoperabilityofTrain"B"duringthe
post-maintenance
testing?Train"B"mustbe
declared inoperable
when_A.ChargingPump"B" breakerisrackedup
.B.ChargingPump"B" control powerisrestored
.C.ChargingPump"C" breakerisrackeddown.D.ChargingPump"C"controlpoweris
de-energized
.96
2007NRCExamSRO
97.TheplantisinMode1.
RCS TemperaturehasgonebelowtheTechnical
Specification
MinimumTemperatureforCriticality.Ifthe conditions
CANNOTbecorrected,whichONE(1)ofthe
followingdescribestheMAXIMUMtimeallowedpriortoplacingtheplantinMode3andthebasisfortheactioninaccordancewith
Technical Specifications?
A.30minutes;RPS Instrumentationisno longeroperatinginitsanalyzedrange.B.30minutes;
Analysis assumptions
for calculationofMode1 ShutdownMarginare no longer valid.C.1hour;RPS Instrumentationisnolongeroperatinginits
analyzed range.D.1hour;Analysis assumptions
for calculationofMode1 ShutdownMarginarenolongervalid
.97
2007NRCExamSRO98.Giventhefollowingplant
conditions:*Theplantiscomingoutofarefuelingoutage.OperationsDept.is
performingsystemvalvelineups.*Avalve alignmentinthe ReactorBuildingshouldtake
approximately30minutesinaradiationfield
of 6 Rem/l-it.WhichONE(1)ofthe
following descrtibestheMINIMUMreview
requirements
thatmustbemetpriorto
performing
the alignment?
A.APre-Job Briefandreviewof
RWP/SRWP forvalvelineupsONLYB.Areviewofthe
RWP/SRWPforvalve lineups and ALARA CommiteereviewONLYC.APre-Job
Brief and ALARA CommiteeReviewONLYD.APre-JobBrief, ReviewofRWP/SRWP
, and ALARA Commitee Review 98
2007NRCExamSRO
99.Giventhefollowingplantconditions:*Mode5withRHRTrain
"A"runninginthe
shutdowncoolingmode.*RCS subcoolingis45 of.*SG"B"and"C"are availableforheatremoval.*Atotalloss
of CCWflowhasoccurred
.*Seal Injectionflowisnormal.*The operatingcrewisinAOP-118.1
, TOTALLOSSOF COMPONENT COOLING WATER,andhasreferredto
AOP-115.3,LOSSOFRHRWITHTHERCSINTACT.WhichONE(1)ofthe
following describesthecorrectactionandthereasonforthat
action?A.StopanyrunningRCPandRHRPump"A
" with in 10 minutes to preventpumpseal damage.B.AlignRCSFeedandBleedwithin10minutestoprovidecoolingandthenstopanyrunningRCP.C.StopRHRPump"A
" immediatelyandalignforRCSBleedandFeedtoprovide
cooling.D.Within90 minutesstop"A"RHRpumpto
preventsystemdamage.
99
2007NRCExamSRO
100.Giventhefollowing
plant conditions
- Theplantis
operatingat100%power.*EDG"B"isout
of serviceandis expectedtoreturnto
serviceintwo(2)hours.
- Subsequently, the following events occur:*Alossof offsite power.*The reactor is trippedandthecrewenters
EOP-1.0 , Reactor Trip or Safety Injection.*SIisNOT actuated.*Thecrewmadea
transitiontoEOP-15.0, Loss of Secondary Heat Sink ,basedona CSFSTREDPath.*EDG"A" output breaker subsequentlytripsona differentia/lockoutonBus 1DA.WhichONE(1)ofthe
following describestheactionsthatwillbe
takenanditsbases?
A.Immediately
transitiontoEOP-6.0 , Loss Of AllESFAC Power.All other proceduresintheERG network assumeboth7.2KVESFbussesare
available.B.Immediately
transitiontoEOP-6.0, Loss Of All ESFACPower.All other proceduresintheERG network assume a minimumofONE(1)7.2KVESFbusisavailable.
C.Remainin EOP-15.0untilfeedisrestoredandtheRED
conditioniscleared , and then transitiontoEOP-6.0 , Loss of All ESF AC Power.REDpath Function Recovery procedures
must be performeduntilthe conditioniscleared.
D.Remainin EOP-15.0 until directedtoreturnto
procedure i n effect ,andthentransitiontoEOP-6
.0 , Loss of AllESFACPower.REDpath Function Recovery procedures
must be finished to completion.
100
INTEGRIT Y EO P-12.0 REVI SION 12 ATTACHM ENT 4 PAGE2of 2 PLAN T OPERATIONAL
LIMITS CUR VE 400 350 300 200250 RCS T c ol d (o F)1 50 0 I I.'._P SIG I (PZR SAFETY VALVE S A S SUMED FULL O P EN)I-10-----R EGION OF ACC EPTABLE OPERATION-----01 LIMIT T2 LIMIT T1 I---I I LIM IT At--.II- I o 100 RCS PR ESSURE (PSIG)300 2500 500 2000 1500 1000 PAGE 9 OF 12
REACTOR COOLANT SYSTEM MATERIAL PROPERTY BASIS LIM ITING MATERIAL: INTERMEDIATE
SHELLPLATEA9154-1
LIMITING ART VALUES@56EFPY: 1/4T , 153°F 3/4T , 138°F Q 5 0 10 0 150 20 0 250 300 35 0 400 45 0 500 550 Moderator Temperature
(0 F)FIGURE 3.4-3 V.C.Summer Unit 1 Reactor Coolant System Cooldown Limitations (Cooldown Ratesupto100 oF/hr)Applicablefor56 EFPY (Without Margins for Instrumentat
ionErrors)Using1998
Appendix G Methodology
SUMMER-UNIT 1 3/44-32 AmendmentNo.53 , 113 , 133,143,174