ML071930561

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

ML071930561
Person / Time
Site:	Summer
Issue date:	06/13/2007
From:	South Carolina Electric & Gas Co
To:	Office of Nuclear Reactor Regulation
References
2007-301, 50-395/07-301 50-395/07-301
Download: ML071930561 (104)

Text

Final Submittal(BluePaper)

V t,.S)()()1/f)l?r 2(07-

/3/2 ,{)o7 AS Givw Senior Operator Written Examination v.C.SUMMER JUNE 2007 EXAMEXAMNO.05000395/2007301 JUNE4-8,2007(OP TEST)JUNE 13,2007 (WRITTEN EXAM) u.s.Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Information Name: Date: ,-Facility/Unit:

JUne 13 j 2fJOl V* Region: II Reactor Type: W Start Time: Finish Time: InstructionsUsethe answer sheets provided to document your answers.Staple this cover sheet on top of the answer sheets.To pass the examination you must achieve a final grade of at least 80.00 percent overall, with 70.00 percent or better on the SRO-only items if given in conjunction with theROexam;SRO-only exams given alone require a final grade of 80.00 percent to pass.You have 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to complete the combined examination, and 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> if you are only taking the SRO portion.Applicant Certification All work done on this examinationismy own.I have neither given nor received aid.Applicant's Signature Results RO/SRO-OnlylTotal Examination Values--/--/--Points Applicant's Scores--/--/--Points-Applicant's Grade--/--/--Percent Name:---------------1.Giventhe following:*Theunitisat85%

poweratMOL.*Acontinuousuncontrolledcontrolrod withdrawal occurs.WhichONE(1)ofthe following parameters will DECREASE?A.Steam Generator Pressure B.Main Generator Electrical Output C.OverpowerDeltaT setpointD.VCTLevel2007NRCExamSRO 1

2007NRCExamSRO 2.Giventhefollowingplant conditions:*ALOCAhas occurred.*RCSpressureis1750psigandlowering

.*Reactor Building pressureis4psigandrising.*Steam Generator pressuresare1000psigandstable.WhichONE(1)ofthe following describes the actuationsthatarearesultofthis condition?

A.SafetyInjectionONLY.

B.SafetyInjectionand Containment Ventilation Isolation ONLY.C.SafetyInjectionand ContainmentIsolationPhaseAand Containment VentilationIsolationONLY.D.SafetyInjectionand Containment Isolat ionPhaseAand Containment VentilationIsolationand Containment IsolationPhaseB.2 2007NRCExamSRO3.Giventhe followingplantcondit ions:*Thecrewis respondingtoanATWS lAW EOP-13.0, Response to Abnormal Nuclear Power Generation

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

.WhichONE(1)ofthe followingdescribestherequiredactionstobe performed and why?A.Openthe ChargingPumpSuction HeaderIsolationvalvesas directed byAOP-106.1, Emergency Boration, to maximizeBoricAcidflowrate.B.Open LCV-115B/D, RWSTtoCHG PP Suet ,asdirectedby AOP-106.1, Emergency Boration , to borateviacoldleginjection

.C.Openthe ChargingPumpSuction HeaderIsolationvalvesas directedbyEOP-13.0

, Response to Abnormal Nuclear Power Generation

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

,toborateviacoldleginjection.

3 2007NRCExamSRO 4.WhichONE(1)ofthe following describes the setpointsforthetwo(2) annunciators below?A.B.C.D.RCP AlBIC THERMBAR&BRGFLOLO90gpm90gpm50gpm50gpm CCBP DISCHHDRPRESSLO30psig70psig30psig70psig 4 2007NRCExamSRO 5.Giventhefollowingplant conditions:*TheplantisinMode5.*ThePZRissolid

.*RCS temperatureis190°F.*RCS pressureis315psig.*Letdown Pressure ControlValvePCV-145isinAUTO.FCV-605A,"A" gyp,andFCV-605B,"B"BYP,arein MANUAL.WhichONE(1)ofthe followingdescribesaconditionthatwill initiallycausePCV-145toCLOSE?A.Loweringthe outputofthe controllerforthein-serviceRHRheat exchanger flowcontrolvalve.B.RaisingCCWflow through the in-serviceRHRHeat Exchanger.C.Loweringthe setpointofPCV-145.

D.Startingan additionalRHRPump.5 2007NRCExamSRO 6.Giventhefollowing plant conditions:*Theplantisin Mode 6.*"B"TrainRHRisin service.*"A"TrainRHRisoutofserviceand expectedtobereturnedto service in approximately2hours.*Refuelingisin progress.*Cavitylevelis23.5feetabovethe reactorvesselflange.

"B"RHRPumptripsand cannotberestarted

.WhichONE(1)ofthe following describes the operational restriction(s) associated withthisevent?

A.RefuelingCavitylevel mustberaisedto greaterthan24feet abovethereactorvesselflange prior to continuingrefuelingactivities.

B.Refueling activities are permittedforupto1hourwh ilerepairsareinitiatedto "B"RHRPump.C.All containment penetrationswithad irectpathto atmosphere must immediately beverifiedclosed

.D.Suspendallactiv ities thatcouldresultinareductioninboron concentrationofthe RCS.6 2007 NRC Exam SRO 7.Giventhe following plant conditions:*The plant was operating at 100%power.*7.2KV Transformer XTF-4waslostduetoafault.*The associated DIG did NOT start as designed.*Subsequently, a LOCA caused a reactortripand safety injection.*RCS pressure is currently350psigand trending down slowly.WhichONE(1)ofthe following describes the operationofRHR Pumps for this condition?A.RHR pump A runningwithits miniflow valve openB.RHR pump A runningwithits miniflow valve closed C.RHR pump B runningwithits miniflow valve openD.RHR pump B runningwithits miniflow valve closed 7 2007 NRC Exam SRO 8.Which ONE (1)of the following directly supplies power to Charging Pump"A"andRHR Pump"A"?A.B.C.D.Charging Pump"A" 1DA 1DA1 1DA 1DA1 RHR Pump"A" 1DA 1DA 1DA1 1DA1 8 2007 NRC Exam SRO 9.Giventhe following plant conditions:*The plant is operating in Mode1at 100%power.*The following indications are reportedbytheRO.*TI-471, PRT Temperature is trendingupandis now at 158°F.*PI-472, PRT Pressure is trendingupandis nowat8psig.Which ONE (1)of the following components, if leaking, will cause this condition?

A.XVR-8708A, RHR Pump"A" Suction Relief Valve.B.XVR-8121, RCP Seal Return Relief Valve.C.XVR-7169, RCDT Pumps Suction Relief Valve.D.XVS-8010, PZR Safety Valve.9 2007NRCExamSRO10.WhichONE(1)ofthe following describes an immediateactionandthebasisforthe action i n accordance with EOP-1.0 , Reactor Trip/Safety Injection Actuation?

A.InsertcontrolrodsinManual;toinsertnegative reactivitybythemostdirectmanner possible.B.InsertcontrolrodsinManual;toreduceormaintainRCS pressuretopreventlifting the Pressurizer safety valves.C.PlaceEHCPumpsin PULL-TO-LK NON-A;to prevent uncontrolledcooldownofthe RCS.D.PlaceEHCPumpsin PULL-TO-LK NON-A;to minimize secondary makeup requirements.

10 2007NRCExamSRO11.Giventhefollowingplant conditions:*Areactortripand safetyinjectionhaveoccurred.*RCS pressureis1050psigandlowering.*Tavgis 550°Fandlowering.

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

A.Letdownlinebreak.B.SBLOCAonanRCScoldleg.C.Stuckopen pressurizer PORV.D.Stuckopen pressurizersprayvalve.

11 2007NRCExamSRO 12.Giventhefollowing:*Theplantisat100%power.*Allsystemsarein their normal alignments

.*AleakoccursintheLetdownHeat Exchanger.Assumingnoactionbythecrew,whichONE(1)ofthefollowing describestheeffect(s)ontheCCWSystem?

A.RM-L2A/B indication rises.SurgeTankventvalve PW-7096closeswhentheindicationreachesthe ALERT level.B.RM-L2A1B indication rises.SurgeTankventvalve PW-7096closeswhentheindicationreachestheHIRADlevel.

C.SurgeTanklevellowers

.CCW Booster Pumpswilltriponlowsuctionpressure.D.SurgeTanklevellowers.

CCW Pumps will/ose suctionwhentheSurgeTank empties.12 2007NRCExamSRO13.Giventhefollowingplantconditions:*ALOCAoccurredandRCS pressurereached1380psig.*AllactionsofEOP-1.0were performedasrequired.*Thecrewis performing EOP-2.1 , Post-LOCA Coo/down and Depressurization.*RCS pressure is currently1335psig.*RCS temperature is currently 496°F.*TwoChargingpumpsarerunning

.*Thecrewis evaluatingstopping1ChargingPump.Giventheaboveconditions,whichONE(1) ofthefollowing describes whether theChargingPumpmaybestopped,andwhy?

A.No,because subcoolingisnot greaterthan30°F.B.Yes, because subcooling is greaterthan30°F.C.Yes,because subcooling is greaterthan87.5°F.D.No, because subcoolingisnot greaterthan87.5°F.

13 2007NRCExamSRO14.Giventhefollowingplant conditions:*ThePlantisinMode3

.*APZRPORVbeginsleakingtothePRT.

• Pressurizer pressureis985psig.*PRTpressureis steadyat5psig.*PRT temperature is steadyat90°F.Assume:*Ambientheatlossesarenegligible.*Steam qualityinthe pressurizeris100%.WhichONE(1)ofthe followingwouldbethe approximate MCB indicationonTI-463 ,RELIEFTEMP OF?14 2007NRGExamSRO15.Giventhefollowingplantconditions:*The Reactorhastrippedfrom100%power.*"A"and"G" Service Water(SW)pumps were running.*Thecrew implemented EOP-1.0, Reactor Trip/Safety Injection Actuation, then transitionedtoEOP-1.1 , ReactorTripRecovery.

• MDEFW pumps startedonLo-LoSGlevelsafterthetr ip.*Subsequently

,anSI actuatedduetoaLargeBreakLOGA.WhichONE(1) of the followingdescribestheoperationof equipmentasaresultofthe SI?A.MDEFW pumpswilltripandberestartedbythesequencer.

Service Water Pumps"A"and"G"will continuetorun.B.MDEFW pumps will continuetorun.Service WaterPumps"A"and"G"willtripandberestartedbythe sequencer.G.MDEFWpumpswilltripandberestartedbythesequencer.

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

D.MDEFW pumps will continuetorun.Service Water Pumps"A" and"G"willcontinuetorun.15 2007NRCExamSRO16.Giventhefollowingplantconditions:*Aloadrejectionhasoccurredfrom100%power.*Allcontrol systems respondedasdesigned.

• Power level isnowstableat70%.WhichONE(1)ofthefollowing conditionswillexistduringthis event?A.ChargingFlowControlValve,FCV-122

,willbethrottlingopen.

B.PressurizerBackupHeaterswillbeenergized.

C.PressurizerPORVswillbeopen.D.Letdown Backpressure Control ValvePCV-145willbe throttling closed.16 2007NRCExamSRO17.Giventhefollowingplant conditions

• Areactortriphas occurredfrom100%power.*ReactorTrip Breaker"B"remainsCLOSED.WhichONE(1)ofthe followingdescribestheeffectontheSteamDumpSystem?

A.Thesteam dump valveswillopenandmaintainTavgat 55rF.B.Thesteam dumpswillremainclosedfollowingthereactortripduetolossofthearmingsignal.C.Thesteam dumpswillremainclosedfollowingthereactortripduetolossofthe'planttrip' modulation signal.D.Thesteam dump valveswillopenandmaintainTavgat 559°F.17 2007 NRC Exam SRO18.Which ONE (1)of the following describes the source of control power to Reactor Trip Breaker"B"and Reactor Trip Bypass Breaker"B"?Reactor Trip Breaker B Reactor Trip Bypass Breaker B A.B.C.D.125 VDC Bus 1HB 125 VDCBus1HB 120 VAC APN-5902 120 VAC APN-5902 125 VDCBus1HB 125 VDCBus1HA 120 VAC APN-5902 120 VAC APN-5901 18 2007NRGExamSRO 19.Giventhefollowingplantcond itions:*Areactortriphas occurred coincidentwithalossof off-site power.*While performingactionintheEOPs,thefollowing events occur:*RGS pressureis1700psigandlowering.*RB pressureis4.7psigandrisingslowly.*Threem inutes after these indicationsareobserved

, APN-5904failsand becomes de-energized.WhichONE(1)ofthe following describestheeffect ,ifany ,onplant equipment aftertheAPNfailure?

A.TrainAandTrainBEGGS equipmentisoperatingasrequired

TrainAandTrainBRBSprayPump discharge valvesareopen.B.TrainAandTra inBEGGS equipmentisoperatingasrequired;TrainAandTrainBRBSprayPump dischargevalvesareclosed.G.TrainAEGGS equipment is operatingasrequired;TrainBEGGS equipment isNOTrunning;TrainAandTrainBRBSprayPump dischargevalvesareopen

.D.TrainAEGGS equipment is operatingasrequired

TrainBEGGS equipment isNOTrunning;TrainAandTrainBRBSprayPump dischargevalvesareclosed.

19 2007NRCExamSRO 20.Giventhe following plant conditions:*ALOCAhas occurred.*RCS pressureis200psig.*"A" Reactor Building SprayPumpisOutofService.

• Containment pressure has exceededtheHigh-3 setpoint.*Train"B" PhaseAhasfailedtoactuate.*All other actuationsandTrain"A"ECCS equipmentisrunningasrequired.*The most recent Chemistry sampleoftheRCS indicatedthatRCSactivityis 5X10-2 microcuries/ml Dose Equivalent Iodine.Assumingno actionbythecrew,whichONE(1)ofthe following describestheeffectontheplant?A.Containment will exceeditsdesignpressure.B.Off-Site releaseswillexceed accident analysis assumptions.C.Only1 Containment Isolation ValveineachPhaseA penetrat ion w illbeclosed.D.Onlyhalfofthe Containment penetrationsrequiredfor isolationwillreceiveisolation signa ls.20 2007NRCExamSRO21.Giventhefollowingplantconditions:*Areactorstartupisin progress.*SR Channel N-31 indicates 7X10 3 CPS.*SRChannelN-32 indicates7X10 3 CPS.*IR Channel N-35 indicates 8.7X10-6%power.*IRChannelN-36indicates 6.0X10-6%power.WhichONE(1)ofthefollowing describes(1)theexistingplantcondition,(2)thestatusofP-6,and(3)theactionrequiredin accordance with AOP-401.8, Intermediate RangeChannelFailure?

A.(1)N-36is undercompensated

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

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

C.(1)N-36is undercompensated

(2)P-6shouldbe satisfied;(3)placetheunitinMode3untilN-36isrepaired

.D.(1)N-36is overcompensated

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

21 2007NRCExamSRO 22.Giventhefollowingplant conditions:*Theplantis operatingat8%power.*ALossof Component Cooling Waterhasoccurred.*"A"RCP motor bearing temperatureis189°Fandrising slowly.*"A"RCP lower seal water bear ing temperature is 226°Fandrisingslowly.*Thecrewhasentered AOP-118.1, Loss of Component Cooling Water.WhichONE(1)ofthe following actionsisrequired?

A.RCPmotorbearing temperatureexceedsoperatinglimits

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

.B.RCPlowerseal water bearing temperature exceeds operating limits.Stop'A'RCPandinitiateaplant shutdown lAW GOP-4B, Power Operation (Mode 1-Descending)

.C.RCP motor bearing temperatureexceedsoperatinglimits

.Tripthereactor

,stop'A'RCP,andgoto EOP-1.0 , Reactor Trip/Safety Injection Actuation.

D.RCPlowerseal water bearing temperature exceeds operating limits.Tripthe reactor , stop'A'RCP ,andgotoEOP-1

.0 , Reactor Trip/Safety Injection Actuation.

22 2007NRCExamSRO 23.Giventhe following plant conditions:*TheplantisinMode3.*The following wide-rangepressuresareindicated:*PT-402*PT-403*PT-455A-1335psig-1350psig-1285psig*Subcooling indication on TI-499A and TI-499B indicatesthefollowing

TI-499A TI-499BWhichONE(1)ofthe following describesthecoreexit temperatureusedto determineRCSsubcoolingforthe indications above?A.TrainA-550°F;TrainB-560°F.

B.TrainA-55rF;TrainB-550°F.C.TrainA-55rF;TrainB-560°F.

D.TrainA-560°F;TrainB-55rF.23 2007NRCExamSRO24.Giventhefollowingplant conditions:*A ReactorTripcondition existedandtheReactorfailedtotrip.*RCS pressure now indicates2350psig.Assumingnoothereventsarein progress ,whichONE(1) ofthefollowingdescribesthe1)appropriateactionandthe2)reasonforthataction?

A.1)VerifyPZRPORVsandBlockValvesopen2)To increaseflowonFI-943

,CHGLOOPBCLO/HOTLEG FLOW GPM B.1)Ver ifyPZRPORVsandBlockValvesopen2)To increaseflowonFI-110,EMERGBORATE FLOW GPM C.1)PlacebothESFLSA(B)ResetstoNON-ESFLCKOUTS2)To increaseflowonFI-943

,CHGLOOPBCLO/HOTLEG FLOW GPMD.1)PlacebothESFLSA(B)ResetstoNON-ESFLCKOUTS2)To increaseflowonFI-110,EMERGBORATE FLOW GPM 24 2007NRCExamSRO 25.Giventhefollowingplant conditions:*Theplantwasat100%power.*Areactortripand safetyinjectionoccurred

.*R8CUs XFN-0064A and XFN-00648startedinSLOW.*While performingtheactionsofEOP-1.0, Reactor Trip/Safety Injection Actuation, the followingalarmsarereceivedinthe control room:*XCP-605-3-1, SWFRR8CU 18/28FLOLO*XCP-605-3-2, SWFRR8CU 18/28PRESSLOWhichONE(1)ofthe followingchoicescontainsbothofthe conditionsthatcouldeach independently cause these annunciatorstoalarm?A.SW8P"8" tripped;MVG-31118, R8CU 648/658TOINDCOOLINGgoing CLOSED.8.SW8P"8" tripped;MVG-3109C, R8CU 648 OUTLETISOLgoing CLOSED.C.XFN-00648 (18 R8CUSSFAN)tripped; MVG-3108C, R8CU 648 INLETISOLgoingCLOSED.

D.XFN-00648 (18 R8CUSSFAN)tripped; MVG-3109D, R8CU 658 OUTLETISOLgoing CLOSED.25 2007NRCExamSRO26.Which ONE (1)of the following describes the power supplies that directly feed Containment Spray Header Isolation Valves XVG-3003A and XVG-3003B , respectively?

A.XSW1DA1 and XSW1DB1 B.XMC1 DA2XandXMC1 DB2Y C.XMC1 DB2XandXMC1 DA2ZD.XMC1 DA2ZandXMC1 DB2X 26 2007NRCExamSRO 27.Giventhefollowingplant conditions:*ALOCAhasoccurred.*RCS pressureis450psig.*ReactorBuildingpressureis18psigandlowering

.*RWSTlevelislowering.

• ReactorBuildingSumplevelisrising.*"A" Reactor Trip Breakerremainedclosed.WhichONE(1)ofthefollowing describestheoperationofthe ReactorBuildingSpraysystemastheevent continues?RBSprayPumpsuctiontotheRBSumpValves, MVG-3005AandB...A.are manuallyopenedwhenRWSTlevel reaches its setpoint.RB Spray PumpsuctionvalvesfromRWST,MVG-3001AandB

, are manuallyclosedwhen MVG-3005AandBarefullyopen.

B.automaticallyopenwhenRWSTlevelreachesitssetpoint.RBSprayPumpsuctionvalvesfromRWST,MVG

-3001AandB, automaticallyclosewhen MVG-3005A andBarefullyopen

.C.are manuallyopenedwhen ReactorBuildingSumplevelreachesitssetpoint.RBSprayPumpsuction valvesfromRWST , MVG-3001AandB,are manually closed whenandBarefullyopen.

D.automaticallyopenwhen ReactorBuildingSumplevel reachesitssetpoint.RBSprayPumpsuctionvalvesfromRWST, MVG-3001AandB, automatically close when MVG-3005AandBarefullyopen.

27 2007NRCExamSRO28.Withtheunitat100%power,whichONE(1)ofthe following describesthepotentialconsequenceof PCV-444C ,PZRSprayValve,failingopen?

A.LossofPZR pressurecanresultinanunwarrantedOPDeltaTrunbackandreactor trip.B.PZRpressurewillremainstableasPZRheaterswill compensateforthepressure reduction.C.LossofPZR pressuremayresultinsteamformationinthereactorvesselheadandSGtubes.I D.LossofPZR pressurecanresultinanunwarrantedOTDeltaTrunbackandreactor trip.28 2007NRCExamSRO 29.WhichONE(1)ofthe followingdescribesthepurposeandfunctionoftheReactor Building Charcoal Cleanup Units?Designedfor...

A.primary meansoflongtermpost accidentiodineremovalfromtheRBatmosphere.Dischargeis alignedtotheRBPurgesystemexhaust.B.primarymeansoflongtermpost accidentiodineremovalfromtheRBatmosphere.DischargeisalignedtotheRB atmosphere.C.RB pre-entry reduction of airborne contaminants.

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

.DischargeisalignedtotheRB atmosphere.

29 2007NRCExamSRO 30.Giventhe following plant conditions:*Theunitwas initially operatingatfull power.*Alossof ALL offsite poweroccurredin conjunctionwithasteam generatortuberupture.*All safeguards equipment functionedasrequi red.*The following plant conditionsnowexist:*Ruptured S/G pressure=1100psig,stable*CoreexitTC=505°F, slowly decreasing*RCS Pressure=1600psig , stable*PZRLevel=4%,stable*TotalSIFlow=600gpm*TheRCShasbeencooleddowntotarget temperature

.*In accordancewithEOP-4.0, Steam GeneratorTubeRupture,theROopensonePZRPORV.*Soon after openingthevalve,the operator observes that all channels ofPZRlevelare rapidly increasing

.*ECCSflowhas increasedfrom600gpmto650gpm.WhichONE(1) of the followingisthecauseofthis indication?

A.PZRlevel instrumentsarenot calibrated for temperatureslessthan600°F.

B.Safety injectionflowisdrivingtheRCStoawater-solid condition.C.Voidinginthe reactor vesselheadisforcingwaterupthesurgeline.

D.Backflowhasbeen establishedfromtherupturedS/GtotheRCS.

30 2007NRCExamSRO31.Giventhefollowing plant conditions:*ALargeBreakLOCAhasoccurred.

ReactorBuildingH2 concentrationwasat2%andrising.*'A'Hydrogen Recombiner is INOPERABLE.WhichONE(1)ofthe following describestheeffectontheremovalofHydrogenfrom Containment?

A.Hydrogen concentrationwillremainbelow4%withonlyone Recombiner in operation.

B.Hydrogen concentrationwillriseabove4%butremain below6%withonlyone Recombiner in operation.C.Hydrogen concentrationwillremainbelow4%onlyifthe Containment PurgeSystemisplacedin serviceinadditiontothe Recombiner.D.Hydrogen concentrationwillremainbelow4%onlyif ContainmentSprayisplacedinserviceinadditiontothe Recombiner

.31 2007NRCExamSRO32.WhichONE(1)ofthefollowingdescribesafeatureoftheSpentFuelPool and/orCoolingsystem thatwillmaintainradiationdoselevelsat acceptablelimitsduringplant operat ions?A.SpentFuel CoolingPumpswilltriponlowsuctionpressurepriortoSpentFuelPool level dropping below 460'6".B.Boron concentration is maintainedsothatSpentFuelPool Keffislessthan0.95andSpentFuelPoolRadiationlevelsare maintainedlessthan2.5 mr/hratthesurfaceofthepool.

C.Anti-siphoningholesinthecoolingsystemsuctionandreturn lines ensures thatSpentFuelPoollevelwillnotdropbelow460'6".

D.InterlocksontheSpentFuelPool ManipulatorCranepreventspentfuelassemblies from travelling closerthan23feetfromthe surfaceofthe SpentFuelPool.32 2007NRCExamSRO 33.WhichONE(1)ofthefollowing describes the initialSGLevel Response and SGWLC.System Responseduringarapidincreaseinpower?SGLevel Response A.DecreasesB.DecreasesC.IncreasesD.Increases SGWLC System ResponseLagcircuitonSGlevelinput minimizes fluctuations Programmed DIPacrosstheFRV minimizes fluctuations Programmed DIPacrossthe FRV minimizes fluctuationsLagcircuitonSGlevelinputm inimizes fluctuations 33

---

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

.*The RefuelingSROnotesthefollowing:*The SLACKCABLElightisON*The LOWER SLOWZONElightis OFF*The GRIPPERTUBEDOWNlightisOFFWhichONE(1) ofthefollowing describesthereasonthatdownward movementstoppedandthe subsequent operationrelatedtothe interlock?

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

bypassingtheinterlockisnot possible.C.Totalloadfellmorethan 150-300#belownominalfullload

bypasstheinterlocktoallowthe assemblytobefullyinserted.

D.Thefuel assembly approached10"fromthebottomofthecore;bypasstheinterlocktoallowthe assemblytobefullyinserted.

34 2007NRCExamSRO35.Giventhefollowingplant conditions:

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

.*Leakagetothe Reactor CoolantDrainTankis1.3gpm

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

A.Identified leakage exceedstheTSlimitB.Unidentified leakage exceedstheTSlimitC.Primaryto Secondary leakageexceedstheTSlimitD.AllRCS leakageiswithinTSlimits 35 2007NRCExamSRO 36.Giventhefollowingplantconditions:*TheunitisinMode3.*Asteamlinebreakhasoccurredon"A"SteamLineinthe Reactor Building.WhichONE(1)ofthefollowing describestheplantresponsetothisevent?

A."A"MainSteamLine pressurewilldrop."B"and"C"MainSteamLinepressureswillremain constant.AllMSIVswillclosewhenatleast2 Containment pressure transmitters indicate3.6psig.B."A"MainSteamLine pressurewilldrop."B"and"C"MainSteamLinepressureswillremain constant.AllMSIVswillclosewhen"A"MainSteamLinepressureindicateslessthan675psig.C.All3MainSteamLine pressureswilldrop.AllMSIVswillclosewhenatleast2 Containment pressure transmittersindicate3.6psig

.D.All3MainSteamLine pressureswilldrop.AllMSIVswillclosewhenatleast2MainSteamLines indicatelessthan675psig

.36 2007NRCExamSRO37.WhichONE(1) of the following describes the purposeofC-9, Condenser Ava ilability,andC-16 , Condenser Pressure, permissive signals?A.C-9 prevents2steam dump valves from operating during conditionsthatcould damage the condensers.C-16armsALL condenser dumpvalveswhen condenser is below4.5"Hgabsand adequate eire water pumps are available.B.C-9armsALL condenser dump valves when condenser is below7.5"Hgabsand adequate eire waterpumpsareavailable.

C-16 prevents2steam dumpvalvesfrom operating during conditionsthatcould damage the condensers.C.C-9 anticipates condenser heat load problems by blocking 2 condenser dumpvalvesat7.5"Hgabs.

C-16 prevents ALL condensersteamdumpvalvesfrom operatingduringconditionsthatcould damage the condensers.D.C-9 prevents ALL condenser steamdumpvalvesfrom operatingduringconditionsthatcould damage the condensers.

C-16 anticipates condenserheatload problems by blocking 2 condenser dumpvalvesat4.5"Hgabs

.37 2007NRCExamSRO38.Giventhefollowingplantconditions:*Theplantisoperatingat100%power.*A FeedwaterLineBreakoccursatthepipingconnectionto"A"SG.WhichONE(1)ofthe following describestheeffectofthisevent?

A.RCS temperaturerisespriortoreactortrip

.SG"A" continues to depressurize afterFWIVclosure

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

C.RCS temperatureslowerspriortoreactortrip.SG"A" pressure stablilizes afterFWIVclosure

.D.RCS temperaturerisespriorto reactor trip.SG"A"pressure stablizesafterFWIV closure.38 2007NRCExamSRO39.Giventhefollowingplantconditions:*AStation Blackouthasoccurred.*Thecrewis restoring off-site powertoBus1DAthroughthenormalfeed.Priortoclosingthenormal feeder breakertoBus1DA ,whichONE(1)ofthefollow ingsetsofactionsmustbe performed , in accordancewithAOP-304.1

, Loss ofBus1DA with Diesel Unavailable?

A.De-energizeTrain"A" ESFLSEnsureBus1DA TRANSFERINITSwitchisinOFF B.De-energizeTrain"A" ESFLSEnsureBus1DA TRANSFERINITSwitchisinON C.Reset NON-ESF LCKOUTS&AUTO-START BLOCKSEnsureBus1DA TRANSFERINITSwitchisinOFFD.Reset NON-ESF LCKOUTS&AUTO-START BLOCKSEnsureBus1DA TRANSFERINITSwitchisinON 39 2007NRCExamSRO40.Giventhefollowingplant conditions:*Alossof off-site powerhasoccurred.*BothEDGshave respondedasdesigned.

• Subsequently, safetyinjectionoccurs

.*Thefollowing conditionsexiston"A"EDG:

• Frequency59.9Hz.*Voltage7150Volts*KW Output2600KWRBPressurereachesan actuation setpointrequiringthestartof"A"RBSpraypumpLoadsstabilize

.....WhichONE(1)ofthe followingdescribesthestatusof"A"EDG?

A.Alllisted parametersarewithinlimits.B.Frequencyis belowthelimit.C.Voltageis belowthelimit.D.Outputexceedsthe continuousKWrating.40

---

2007NRCExamSRO41.Giventhefollowingplantconditions:

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

, powerhasbeenstabilizedbetween12and15%

.*PreparationsarebeingmadetorolltheMain Turbineto1800rpm.

• Reactor powerindicatesthefollowing

• IRN-35-1X101%.

• IRN-36-1X101%.

• PRN-41-15%.

• PRN-42-14%

.*PRN-43-14%

.*PRN-44-14%.

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

A.APowerRangeRodStop(C-2)signal,withnochangeinreactor power.B.Areactortripduetothe deenergization of IntermediateRangeChannelN-35.C.Areactortripduetothe deenergization of IntermediateRangeChannelN-36.

D.An IntermediateRangeRodStop(C-1)signal

,withno changeinreactorpower.

41 2007NRCExamSRO42.Giventhefollowingplant conditions:*Theplantis operatingat100%power.*Thefollowing annunciatorsarereceivedinthecontrolroom:*XCP-636,4-6,DCSYS OVRVOL T/UNDRVOL T*XCP-637,1-5,INV 3/4 TROUBLE Inverter output voltageindicates120vac

.Assuming NO otheralarmsarereceived,whichONE(1)ofthefollowing describes thecommoncauseofboth of the alarms?A.Lossof AlternateSource1FB.B.LossofNormal Source1DB2Y.C.LossofvoltageonBus1HB.

D.Inverter has transferred to AlternateSource1FB.42 2007NRCExamSRO43.Giventhefollowingplant conditions:Theplantis operatingat100%power.Thefollowingalarmisreceived:

• XCP-624-1-5

,SGALVLDEV*TheRO determinesthatSG"A"levelisrisingslowlyon L1-474,475,and476.*SG"B"and"C"levelsarestable.WhichONE(1)ofthe following describesthecauseofthealarmandtheaction required?Alarmwasreceivedona

...A.5%deviationfrom programduetoa Feedwater Control Valvefailure;Place"A" Feedwater Controlvalveinmanualandrestoreleveltonormal.

B.5%deviationfrom programduetoaSteamFlowinputto"A"SGlevelcontrolfailinglow;Selectthe alternatefeedflowandsteamflowinputs.C.10%deviation from programduetoa Feedwater Control Valvefailure;Place"A" Feedwater Controlvalveinmanualandrestoreleveltonormal.

D.10%deviationfromprog ramduetoaSteamFlowinputto"A"SGlevelcontrolfailinglow; Select the alternatefeedflowandsteamflowinputs.

43 2007NRCExamSRO44.WhichONE(1)ofthe following conditionswillresultinthemost Emergency Feedwater Systemflowrequiredto maintainSGlevels constant following a reactor trip?A.B.C.O.Core Burnup 1,000 MWO/MTU 1 ,000 MWO/MTU 10,000MWOMTU 10,000 MWO/MTU Initial Power Level 10%100%10%100%44 2007NRCExamSRO45.Giventhefollowingplant conditions

• Theplantisat100%

powerduringanA1 maintenance week.*APN-5901hasbeen transferredtoAPN-1FAwhileworkisinprogresson XIT-5901.*Thenormal feeder breakerforbus1DAtripsopen

.*"A" DIGfailstostart.WhichONE(1)ofthe following describes the subsequent operationofthe"A"Train ESFLS?A.Output1willshedloadsandtheESFLSwillgothroughitsnormalsequence.B.Output1willshedloads,butthentheESFLSwillbe preventedfromoperating.C.Output1willNOTshedloads,buttheESFLSwillgothroughitsnormalsequence.D.Output1willNOTshedloadsandtheESFLSwillbe preventedfromoperating.

45 2007NRCExamSRO46.WhichONE(1)ofthe followingdescribesthe availability of Channell(TrainA)120VACvital safeguards powerduringalossofthe 115KVlinefromtheParrGenerating Complex?A.Isinitially availablefromBattery1Athrough inverter XIT-5901, then automaticallyreturnstothenormal sourceafterDiesel Generator"A"starts.B.Thestaticswitch initially transfersthesupplyto1FA,then automaticallyreturnstothenormal source after Diesel Generator"A"starts.

C.Isinitially available from Battery1Athrough inverter XIT-5901,thenis manuallyreturnedtothenormal sourceafterDiesel Generator"A"starts.D.Thestaticswitch initially transfersthesupplyto1FA,thenis manuallyreturnedtothenormal source after Diesel Generator"A"starts.

46 2007NRCExamSRO 47.Theplantisat100%power

.Alossof125VDCcontrol powertothewillrequireentrytoEOP-1.0

, Reactor Trip/Safety Injection Actuation.

A.FWBP breakersB.MSIVsC.RCPbreakers D.PZRSprayValves 47 2007NRCExamSRO48.Giventhefollowingplantconditions:*Alossofoff-site powerhasoccurred.*BothEDGsstartasrequired.WhichONE(1)ofthe followingdescribestheoperationoftheEDGRoomVentilation system?Automaticallystartwhen...

A.DieselRoom temperatureexceeds88°F,tomaintainroom temperaturebelowthe Technical Specificationlimitof120°F.B.theassociatedDiesel Generatorstarts,to maintain room temperaturebelowthe Technical Specificationlimitof88°F.C.DieselRoom temperatureexceeds72°F,tomaintainroom temperaturebelowthe Technical Specificationlimitof88°F

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

48 2007NRCExamSRO49.Giventhe following plant conditions:

• Emergency Diesel Generator"A"is paralleledtoits associated Bus.*Alagging power factorhasbeen established.WhichONE(1)ofthe following describes the operationofthe diesel generator voltage control switch?A.Loweringthe voltage control setpointwillcausethe generatortopickupalargershareoftherealload.B.Raisingthe voltage control setpointwillcausethe generatortopickupalargershareoftherealload.C.Loweringthe voltage control setpointwillcausethe generatortopickupalargershareofthe reactive load.D.Raisingthe voltage control setpointwillcausethe generatortopickupalargershareofthe reactive load.49 2007NRCExamSRO50.Giventhe following plant conditions:*AlossofRB Instrument Air has occurred.*RB Instrument Air header pressure is currently94psigand lowering.Assuming no operator action , whichONE(1)ofthe following describes the response oftheAir System and why?RB Instrument Air header pressure decreasesuntil...A.PVA-2659, INSTAIRTORB AIR SERV , automatically opensat90psigtoensureanair supply for AOVs inside the Reactor Building.B.PVA-2659, INSTAIRTORBAIR SERV , automatically opensat93psigtoensureanair supply for AOVs inside the Reactor Building.C.PVT-2660, AIR SPL YTORB , closesat90psigto isolatetheRB headertoavoidalossof Instrument Air outside the Reactor Building.D.PVT-2660, AIR SPLYTORB,closesat93psigto isolatetheRB headertoavoidalossof Instrument Air outside the Reactor Building.50 2007NRCExamSRO51.Giventhefollowingplant conditions

• TheplantisinMode6.ReactorBuildingPurgeisinoperation

.*Refueling activitiesareinprogress.*Aspentfuel assemblyisdroppedinthecavity.

• Containment radiation monitor indicationsareallrising.WhichONE(1)ofthe following describestheradiation monitorsthatwillinitiateisolationofallorpartofthe Containment Purge?RM-A4,RBPurge Exhaust Particulate(Iodine)(Gas)Atmos monitor...A.ONLY.B.ANDRM-G17A/B,RB ManipulatorCraneAreaGammaONLY.

C.ANDRM-A2,RB Sample Line Particulate(Iodine)(Gas)Atmos monitor ONLY.D.AND RM-G17A/B, RB ManipulatorCraneAreaGamma

,ANDRM-A2,RBSample Line Particulate(Iodine)(Gas)Atmosmonitor.

51 2007NRCExamSRO52.Giventhe following plant conditions:*An immediate dischargetothe penstocksfromboth Waste Monitortanksis required.*Current conditionsareasfollows.*RM-L5andRM-L9areoutof service*Fairfield Hydroisinthe"pumping" mode.WhichONE(1)ofthe following statements will provide the MINIMUM conditions necessary for monitor tank release?A.EitherRM-L5or RM-L9 mustberestoredto operabil ity prior to release.B.BothRM-L5and RM-L9 mustberestoredto operability prior to release.C.TheFairfield Hydro must converttothe generatingmodeand redundant samples performed prior to release.Two independent qualified individuals must verify release calculations and valve lineups.D.The Fairfield Hydro must converttothe generatingmodepriorto releaseandeitherRM-L5orRM-L9 must be restored to operability

.Two independent qualified individuals must ver ify release calculationsandvalve lineups.52 2007NRCExamSRO 53.WhichONE(1)of the following describes operation of XFN-30A(B), CONTR RM EMERG FILTERING SYS FAN A(B), and XFN-32A(B), CONTROL ROOM COOLING UNITA(B)FAN upon receipt ofahigh radiation alarm on RM-A 1, Control Bldg Supply Air?A.Both XFN-32A&Bandboth XFN-30A&Bstart,all outside air sourcesareisolated.B.Both XFN-32A&Bandboth XFN-30A&Bstart,returnairis mixedwithasmall amount of makeup air.C.Both XFN-32A&Btripandboth XFN-30A&Bstart,all outside air sources are isolated.D.Both XFN-32A&Btripandboth XFN-30A&Bstart, returnairis mixedwithasmall amount of makeup air.53 2007NRCExamSRO54.Giventhe following plant conditions:*The plantisin Mode 5.*RHRTrainAisin service.*RCS temperatureis158°F.*RCS pressureis175psig.*Subsequently,aLoss of Service Water occurs.*Thecrewisperformingactions contained in AOP-117.1,TotalLoss of Service Water.*NEITHER Service Waterloopcanbe restored.WhichONE(1)ofthe following describes the effectontheRHR System,andthe procedure that will mitigate the event?A.Stabilize RHR/RCS system temperature using steam dumps lAW GOP-5, PlantShutdownMode 3toMode5.Goto AOP-115.3, Loss ofRHRwiththeRCSIntact, for long-term mitigation.

B.Stabilize RHR/RCS system temperature using steam dumps lAW GOP-5, PlantShutdownMode 3toMode 5.Continue using AOP-117.1 ,TotalLoss of Service Water, for long-term mitigation.

C.RHR/RCS system temperaturewillriseasa resultofaloss of cooling to Component Cooling Water.Goto AOP-115.3 , Loss ofRHRwiththeRCSIntact.

D.RHR/RCS system temperaturewillriseasa resultofaloss of cooling to Component Cooling Water.Continue using AOP-117.1,TotalLoss of Service Water.54 2007NRCExamSRO55.WhichONE(1) of the following providestheelectrical power supplytothe Supplemental Air Compressor?

A.XSW1DA1 8.XSW1D81C.XSW1A1 D.XSW181 55 2007NRCExamSRO56.Giventhefollowingplant conditions:*TheF ire ProtectionSystemactuatedduetoaMain Transformer Fire.*System pressure droppedto80psigbefore recoveringduetotheactuationof necessary equipment.*Thefireisout.*Thedelugevalveisisolatedandreset.WhichONE(1)ofthe followingdescribesthe equipmentthatisrunning

,andthemethodofshuttingthe equipment down?A.ONLY theMotorDrivenFirePumpisrunning;mustbe stopped locally.B.ONLYthe MotorDrivenFirePumpisrunning

maybe stoppedlocallyorinthecontrolroom

.C.TheMotorDrivenand EngineDrivenFirePumpsarerunning

.Bothmustbestoppedlocally.D.TheMotorDrivenand EngineDrivenFirePumpsarerunning.TheMotorDrivenPumpmaybe stopped locallyorinthecontrolroom,the EngineDrivenPumpmustbestoppedlocally

.56 2007NRCExamSRO57.Giventhefollowingplant conditions

• ALOCAhasoccurred.*Safety Injectionisactuated

.ReactorBuildingpressure indicates14psigandrisingslowly.*While performingactionsofEOP-1.0, Reactor Trip/Safety Injection Actuation ,thefollowingvalvesindicateOPEN:*RCPSL WfRISOL8100*LTDNISOL8152*RBAIR SERVISOL2660WhichONE(1)ofthefollowing describesthefailurethathas occurredandtheMINIMUMaction necessary to mitigate the condition?

A.PhaseAhas partiallyfailed.Place eitherPhaseA actuation switchesinthe ACTUATE position.B.PhaseAhas partiallyfailed.PlacebothPhaseA actuation switchesinthe ACTUATE position.C.PhaseBhas partially failed.Place eitherPhaseB actuation switchesinthe ACTUATE position.D.PhaseBhas partially failed.PlacebothPhaseB actuation switchesinthe ACTUATE position.57 2007NRCExamSRO 58.Giventhefollowingplant conditions

• Thereactorhas tripped.SafetyInjectionisactuated.*AnRCS cooldownisinprogressin accordancewithEOP-2.1, Post LOGA Goo/down and Depressurization

.*Thefollowingtableisaplotofthecooldown:

TIMERCSTCOLDTIMERCSTCOLD 0800 54rF 0945 425°F 0815 530°F 1000 395°F 0830 520°F 1015 382°F 0845 505°F 1030 364°F 0900 498°F 1045 340°F 0915 478°F 1100 310°F 0930 44rF 1115 280°FAtwhichtimewastheTech SpecRCSCooldownratelimit FIRST exceeded?A.0915.B.0930.C.1000.D.1115 58 2007NRCExamSRO59.Giventhe following plant conditions:*A LOCA outside containment has occurred.*Thecrewis performing the actions in EOP-2.5,LOCAOutsideContainment.WhichONE(1) of the following actionswillbe attempted to isolatethebreakandwhichindicationisusedto determineiftheleakhasbeenisolatedin accordance with EOP-2.5?A.Isolatelow pressure Safety Injection piping.RCS pressure is monitored, because SI flow will repressurizetheRCSwhenthebreakis isolated.B.Isolatelow pressure Safety Injection piping.PZRlevelismonitored,becausewhenthe break is isolated, RCS inventory willrapidlyrise.C.Isolatehigh pressure Safety Injection piping.RCS pressure is monitored, because SI flow will repressurizetheRCSwhenthebreakis isolated.D.Isolatehigh pressure Safety Injection piping.PZRlevelismonitored,becausewhenthe breakisisolated,RCS inventory willrapidlyrise.

59 2007NRCExamSRO60.WhichONE(1)ofthe following describesthereasonthataREDconditionontheIntegrityCSF StatusTreemay developwhileperformingactionsofEOP-14.1

, Response to DegradedCoreCooling?

A.CoreExit Thermocouple temperature will decreaserapidlywhenLowHeadSIPumpsarestartedandSIflowisinitiated

.B.CoreExit Thermocouple temperature will decreaserapidlywhenSG depressurizationandSI Accumulatorinjectionoccur.C.RCSColdLeg temperaturewilldecreaserapidlywhenLowHeadSIPumpsarestartedandSIflowisinitiated.D.RCSColdLeg temperaturewilldecreaserapidlywhenSG depressurizationandSI Accumulator injection occur.60 2007 NRC Exam SRO61.Giventhe following plant conditions:*A LOCA has occurred.*The crew is performing actions containedinEOP-2.0, Loss of Reactor or Secondary Coolant.*The following conditions currently exist:*Integrity-RED*Containment-RED*Subcriticality

-ORANGE*Core Cooling-ORANGE*Inventory-YELLOW*Heat Sink-YELLOWWhichONE(1) of the following describes the correct procedure flowpath for these conditions?

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

D.EOP-16.0, Response to Imminent Pressurizer Thermal Shock Condition , followed by EOP-14.1 , Response to Degraded Core Cooling.61 2007NRCExamSRO 62.Giventhefollowing plant conditions:*Areactortriphasoccurredduetoalossofoffsitepower.*Thecrewis performingactionsofEOP-1.4, Natural CirculationCooldownwithSteamVoidinVessel.*Duringtheevent,RCPsealcoolingwaslost,but subsequently restored.*The operatingcrewispreparingtoinitiatetheRCScooldown.Thefollowing conditionsareindicated:*RVLlSNRlevelis89%.*RCS subcoolingis60°F.*PZRLevelis72%andstable

.WhichONE(1) of the followingactionsisrequiredin accordancewithEOP-1.4?

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

B.Initiate Safety InjectionandgotoEOP-1.0, ReactorTripOr Safety Injection.C.StartaRCPandgotothe applicableportionofthe appropriate GOP.D.ReturntoEOP-1.3, Natural Circulation Cooldown.62 2007NRCExamSRO63.Giventhefollowingplantconditions:*ALOCAhasoccurred.*DuetolowRHRSumpLevel,thecrewhas transitionedfromEOP-2.2, TransfertoColdLegRecirculation,toEOP-2.4, Loss Of Emergency Coolant Recirculation

.*All automatic actions occurredasdesigned.*TwoChargingpumpsandtwoRHRpumpsarerunning.*BothRB SprayPumpsarerunning.*RHR,Charging,andRB Spraypumpampsandflowarestable.*RWSTlevelis approximately5%andcontinuestolower.WhichONE(1)ofthe following describeshowtheCharging,RHR,andRBSpraypumpsshouldbe operated in accordancewithEOP-2.4?ChargingPumpsRBSprayPumpsRHRPumps A.StopBOTHLeaveBOTHrunningLeaveBOTHrunning B.StopONEStopBOTHStopONE C.StopBOTHStopBOTHStopBOTH D.LeaveBOTHrunningLeaveBOTHRunningStopONE 63 2007NRCExamSRO 64.Thecrewis performing actionsofEOP-3.1, Uncontrolled Depressurization of All Steam Generators.WhichONE(1)ofthe following describes the Technical Specification implications oftheevent?A.RCS cooldown rates above100°Fper hour may potentiallyresultin non-ductilefailureofthe reactor vessel.B.Pressurizer coo/downratesabove100°Fper hour may potentiallyresultin pressurized thermal shocktothepressurizer.C.LossofSG inventory may ultimatelyresultintheRCS Pressure SafetyLimitbeing exceeded.D.LossofSG inventory may ultimatelyresultinthe Reactor Core Safety Lim it being exceeded.64 2007NRCExamSRO65.WhichONE(1) of the followingdescribesthestatusofRB ventilationandRBCU'suponcompletion of the actionscontainedinEOP-17.2, ResponsetoHigh Reactor Building Radiation Level?A.RBPurge isolatedAllRBCUfansin SLOW B.RBPurge isolatedRBCUfans selectedonswitchRBCUTRAIN AlB EMERG ,runningin SLOW C.RBMiniPurgein serviceAllRBCUfansin SLOW D.RBMiniPurgeinserviceRBCUfans selectedonswitchRBCUTRAINAlBEMERG

,runningin SLOW 65 2007NRCExamSRO 66.Inaccordancewith OAP-100A, Communication,whichONE(1)ofthefollowing communicationsshouldusethe phonetic alphabet?A.Communications involvingsafetysystemtrains

.(Train Alpha)B.Communications involving manipulationofplant components.(AlphaCharging Pump)C.Communications describing ContainmentIsolation(PhaseBravo)D.All communicationsthatarenot

'information only'.66 2007NRCExamSRO67.Giventhe following plant conditions

• The plantisat46%power and increasing lAW GOP-4A , Power Operation (Ascending)at3%perhour

.*Alossof Feedwater occurs.*All threeS/GNR levelsareat5%and lowering.*Itisnow60 seconds later.WhichONE(1)ofthe followingisthe expected responseofthe ATWS Mitigation System Actuation Circuitry (AMSAC)?A.AMSAC will NOT actuate becauseitisnotarmed

.B.AMSAC will TRIP the reactor and START the EFW pumps.C.AMSAC will NOT actuate becausethetime delay on reactor powerhasnottimed out.D.AMSACwill TRIPthemain turbine and START the EFW pumps.67 2007NRCExamSRO68.Giventhefollowingplant conditions:*AnRCSleakisinprogress.*Thecrewis performing the appropriateAOPforthe plant condition.*Letdownisisolated

.*Chargingflowis maximized.*RCS pressureis1990psigandlowering.

• Reactor Building pressureis1.8psigandrising.

Pressurizerlevelis18%andlowering

.*VCTlevelis15%andlowering.WhichONE(1)ofthe following describesthestatusofthe plantandtheaction required?A.AnRPS setpointhasbeen exceeded.TriptheReactorandinitiateSafetyInjection when immediateactionsofEOP-1

.0havebeen completed.

B.AnRPS setpointhasbeen exceeded.Tripthereactorand concurrently performactionsofthein-useAOPwhen immediateactionsof EOP-1.0havebeen completed.C.AnRPS setpointhasNOTbeen exceeded,TriptheReactor,performthe immediate actionsofEOP-1.0,theninitiateSafetyInjection.

D.AnRPS setpointhasNOTbeen exceeded,TriptheReactor,performthe immediate actionsofEOP-1.0,continueto implementtheAOPconcurrently,then initiate SafetyInjectionwhen Pressurizerlevelis<12%

.68 2007NRCExamSRO69.Theunitisat100%power.Allsystemsareinnormal alignments.WhichONE(1)ofthe following activitiesrequiresentryintoa technical specificationLCOaction statement?

A.CCWPumpB mechanicalsealrepair.B.ChargingPumpAremovalfromserviceforoilchange.C.BoricAcid TransferPumprecircvalveleakrepair.D.RHRHeat Exchanger Dischargeflowcontrolvalverepair.

69 2007NRCExamSRO70.WhichONE(1)ofthe following describes the MINIMUM Source Range Nuclear Instrumentation requ irement that mustbemetpriorto off-loadingfuelfromthe reactor vessel?Visual in control room Audibleincontrolroom Audible inRB A.B.C.D.1 2 2 2 1 1 2 2 1 1 1 2 70 2007NRCExamSRO 71.Giventhefollowing information:*A27yearoldnewV.C Summer employeehasafully completedNRCForm4anda2007radiationexposurehistoryasfollows

2650 millirem from previous employment with ProgressEnergyin2007.*110milliremsincebecomingaV.C.Summer employee.WhichONE(1)ofthe followingdescribestheMAXIMUM ADDITIONALexposuretheemployeemay receivepriortoreachinghisMAXIMUMAdmin istrativeDoseControlLimit,includingany applicable extensions

, lAW HPP-0153, Administrative Exposure Limits?A.1240milliremB.1350millirem C.2240milliremD.2350millirem 71 2007NRCExamSRO 72.Giventhefollowingplant conditions

• AGeneral Emergency exists.*TheTSCis manned.*AvalveintheAuxBuildingmustbeclosedtoprevent damagetovaluablesafetyrelated equipment.Radiationlevelsare extremely high.WhichONE(1)ofthe following describesthemaximumdosethatisallowedtoperformthisoperationand whose permissionisrequired?Anindividualmayreceive

...A.Upto10Remwith permissionfromtheDutySSB.25Rem,ormore,with permissionfromtheDutySSC.Upto10Remwith permissionfromtheEDD.25Rem,ormore,with permissionfromtheED 72 2007NRCExamSRO73.Giventhefollowingplantconditions:*Areactortripandsafetyinjectionhaveoccurred.*Off-Site power islost subsequenttosafetyinjectionactuation.

• Equipment failures during performance of EOP-2.0 , Loss of Reactor or Secondary Coolant,resultedinthefollowingconditions

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

• Inventory GREEN ORANGE RED GREEN YELLOW YELLOWWhichONE(1)ofthe following describes the requirementforCritical Safety FunctionStatusTree Monitoring in accordance with OAP-103.04, EOPIAOPUser'sGuide?

A.Continuous monitoringisrequired.B.Monitorevery5-10 minutesunlessachangeinstatusoccurs.C.Monitor every10-20 minutesunlessachangeinstatusoccurs

.D.Monitoredfor information only.73 2007NRCExamSRO74.Giventhe followingplantconditions:

T=OAfireisoccurringintheAuxBuilding436'.T+2FireBrigade Leaderreportstothescene.

T+15 NotificationofUnusualEventdeclared.

In accordancewithEPP-013, Plant Fire,who,bytitle

, is coordinatingthefirefightingeffortswiththeFireBrigadeLeader?

A.Shift Supervisor B.Emergency DirectorC.OSC SupervisorD.HealthPhysicsShift Leader 74 2007NRCExamSRO75.Giventhefollowingplant conditions

• TheUnitisinMode5.*RCSDra inDowntoMidLoopisinprogressin preparationforweldingonaHotLegopening

.RHRPumpAisinservice

.*Duringthedraindown

,RHRampsand discharge pressurebeginfluctuating erratically.*ThecrewentersAOP-115.1

,RHRPump Vortexing.*The drain-downisstopped.WhichONE(1)ofthe following describestheFIRSTactionthatwillberequiredinaccordancewith AOP-115.1?

A.ReduceRHRflow.

B.AligntheRHRPumptotheRWST.C.RaiseRCSlevel.D.Ventthe operatingRHRloop.75 2007NRCExamSRO 76.Giventhe following plant conditions

• The plantisat50%power.*ALL controlsarein automatic.*ALL MCB switchesarein their normal positionforthis power level.*An event occurs resultinginthe following indications:*RCS Tavg rising approximately 5°F above Tref.*Reactor Powerisrising.*First Stage Pressure Transmitter PT-446 indicates330psigandstable.

• First Stage Pressure Transmitter PT-447 indicates800psig.*Control BankDis withdrawingat16 steps per minute.WhichONE(1)of the following describes the procedure entry required to mitigate theeventandthe reason for the procedural actions taken?A.AOP-403.3 , Continuous ControlRodMotion; to minimize the impact on power distribution limits.B.AOP-403.3, Continuous Control Rod Motion;to preventanoutof spec negative DELTA-I.C.AOP-401.7 , Turbine First Stage Pressure Transmitter Failure;to minimize the impact on power distribution limits.D.AOP-401.7 , Turbine First Stage Pressure Transmitter Failure;to preventanoutof spec negative DELTA-I.76 2007NRCExamSRO 77.Giventhe followingplantconditions:*Followinga turbinerunback,thecrewisstabilizingtheplantin accordance with the appropriate AOP.*ControlBank "0" Group Countersareat 180 steps.*OnORPI,oneControlBank "0" rod indicates196steps;allothersindicate182 steps.*The affectedrodhasablown movable gripperfuseandhasbeen determined to be trippable.WhichONE(1) ofthefollowing actions is appropriateforthisevent?Realignthe mispositionedrodtomeetTSlimitswithin

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

C.1hourto ensure acceptable power distributionlimitsare maintained.

O.6hoursto ensure acceptable power distributionlimitsare maintained

.77 2007NRCExamSRO78.Giventhe following plant conditions

• Reactor poweris100%.*Reactor Trip Breakertestingisbeingperformed.

• ReactorTripBypass Breaker'A'andReactorTrip Breaker'B'areboth RACKEDINand CLOSED.*ReactorTripBypass Breaker'B'andReactorTrip Breaker'A'areboth RACKEDOUTandOPEN.

After completion ofthetesting

, the ElectriciansRACKINand Operationsattemptsto CLOSE ReactorTripBypass Breaker B.*Immediately upon attemptingclosure,ReactorTrip Bypass Breaker'B'opens.*NO other breakers reposition

.WhichONE(1)ofthe following describestheresponsetothis condition?Thereacto r has...A.NOTtripped, immediately enter EOP-13.0, Response To Abnormal Nuclear Power Generation

,anddirectthe NROATC to commence rod insertion.B.NOTtripped, immediately enter EOP-1.0, Reactor Trip/Safety Injection Actuation,directthe NROATC to manually tr ipthereactor.

C.tripped ,havean operator"backup"thereactortrip

, then verify the turbine/generatorhastripped

.D.t ripped, direct an operatortoverify turbine/generatorhastripped,whentime permits , directtheIBAOto locallyopenbothReactorTrip Breaker'B'andReactorTripBypass Breaker'A'.78 2007NRCExamSRO 79.Giventhefollowingplant conditions

• Theplantisat100%power.*Thefollowingalarmsarereceivedinthe sequence listed, approximately 10 seconds apart:*XCP-616 , 1-5 ,PZRLCSDEV HI/La*XCP-616 ,1-2,PZRLVLHI

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

• L1-459 indicates95%andrising

• L1-460 indicates56%andlowering

• L1-461 indicates55%andlowering*Trip StatuslightCHAN1PZRLVLHI isilluminatedWhichONE(1)ofthe followingdescribestheact ionsthatwillbed irectedbytheCRSandtheTS implications?

Se lect unaffec tedPZRlevelchannels

,operatePZRheaters,and...

A.reducechargingflowtomaintainPZRlevel.Doesnot satisfyTSLCO3.3.1, ReactorTripSystem Instrumentation ONLY.B.reducechargingflowtomaintainPZRlevel.Doesnot satisfyTSLCO3.3.1,ReactorTripSystem Instrumentation,ANDdoesnotsatisfyTSLCO3.3.3.6, Accident Monitoring Instrumentation

.C.raise chargingflowtomainta inPZRlevel.Doesnot satisfyTSLCO3.3.1 , Reactor Tr ip System Instrumentation ONLY.D.raisechargingflowto maintainPZRlevel.Doesnot satisfyTSLCO3.3.1

, Reacto r T rip System Instrumentation

,ANDdoesnotsatisfyTSLCO3.3.3.6

, Accident Moni toring Instrumentation.

79 2007NRCExamSRO80.Giventhefollowingplant conditions:*Amanualreactortripwas performedduetohigh turbine vibration.*Thecrewismakingthe appropriatetransitionfromEOP-1.0, Reactor Trip/Safety Injection Actuation.*RCS pressureis2175psigand slowly lowering.*PT-444,CNTRLCHAN PRESS PSIG ,hasfailedhigh.*TheROreportsthatPZR SprayValvePCV-444C indicates open.WhichONE(1)ofthefollowing describestheprocedurethatwillbeusedandtheactionrequiredtomitigatethis event?A.RefertoAOP-401

.5, Pressurizer Pressure Control Channel Failure, whileperformingtheEOPs.

EnsurePZRSprayvalvesareclosedand energize PZRHeatersto stabilize RCS pressure.B.RefertoAOP-401

.5, Pressurizer Pressure Control Channel Failure, whileperformingtheEOPs

.TripallRCPsandenergizePZRHeaterstostabilizeRCS pressure.C.GotoEOP-1.1

, ReactorTripRecovery.TripONLYRCP"A"and energize PZRHeatersto stabilize RCS pressure.D.GotoEOP-1.1, Reactor Trip Recovery.TripALLRCPsand energizePZRHeaters to stabilizeRCSpressure.

80 2007NRCExamSRO 81.Giventhefollowingplant conditions

• Theplantis currentlyatfullpower.*Thefollowing sequenceofeventsoccurred:0200Thenormal feeder breakerto7.2kVbus1DAtrippedopen

.TheAEDGstartedandthe sequencercorrectlystartedallloads

.0215TheAEDG tripped0220DCbus1HAwaslost No operator actionshavebeentaken.*TheAEDGhasbeenrepairedandtheoperatingcrewispreparingtorestarttheEDGand reenergize 7.2kVbus1DA.WhichONE(1)ofthe following describes(1)whatactionisrequiredpriortore-energizingthebus

,and(2)thetimeallowed

,byTechSpecs

,tobeinMode37 A.(1)(2)B.(1)(2)C.(1)(2)D.(1)(2)Openallload breakers on 7.2kVbus1DAfromtheMCB

.2HoursOpenallload breakerson7.2kVbus1DAfromthe switchgear room.2HoursOpenallload breakers on 7.2kVbus1DAfromtheMCB.1HourOpenallload breakers on 7.2kVbus1DAfromthe switchgear room.1Hour 81 2007 NRC Exam SRO82.Giventhe following plant conditions:

• The plantisat 100%powerwithall systems in normal alignments.

• The RO determines that actual Pressurizerlevelis trending DOWNandVCTlevelis trending UP.CHGLINEFLO HI/LO annunciator has actuated.*FI-122A, CHG FLOW GPM, reads0gpm.*Charging pump currentis5amps.*RCS temperature and pressure are stable.Which ONE (1)of the following describes the procedure that should be implementedandthe initial actions required?A.AOP-102.2, Loss of Charging;stop the operating Charging Pump and isolate Letdown.B.AOP-102.2, Loss of Charging;reduce letdownto45 gpm and verify the charging system valve lineup.C.AOP-101.1, Loss of ReactorCoo/antNot Requiring Sf;stopthe operating ChargingPumpand isolate Letdown.D.AOP-101.1, Loss of Reactor Coo/ant Not Requiring Sf;open FCV-122 as necessary and reduce Letdownto45 gpm.82 2007NRCExamSRO83.Giventhe following plant conditions:

Event 5/21 5/28 5/28 1230 1230 1645BOTHTrainARBCUs declared inoperabledueto commoncausefailure.

RBCUs not returned to service.Plantshutdownto Mode3initiated

.PlantinMode3.WhichONE(1)ofthe following describes the LATESTtimeon5/28 thataninitialreporttotheNRCmustbe made?A., 1330 B.1630 C.1745 D.2045 83 2007NRCExamSRO84.Giventhefollowingplant conditions:

• ReactorBuildingPurgeisdesired.

RB EquipmentHatchisOPEN.WhichONE(1)ofthe followingdescribesan acceptable alignment for Reactor Building Purge?A.2supplyfansand1 exhaustfanrunning;RM-A2 operabilitydesiredbutNOTrequiredduringpurge

.B.1supplyfanand2 exhaustfansrunning;RM-A2 operabilitydesiredbutNOTrequiredduringpurge.C.2supplyfansand1 exhaustfanrunning;RM-A2 operabilityrequiredduringpurge

.D.1supplyfanand2 exhaustfansrunning;RM-A2 operabilityrequiredduringpurge

.84 2007NRCExamSRO85.Giventhefollowingplant conditions:*Theplantisat47%power.*Thefollowingalarmisreceivedinthecontrolroom:

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

• ChemistryandHealthPhysicshaveconfirmedthatthealarmisvalid

.WhichONE(1)ofthe following describesadditionalactionsthatwillberequiredin accordancewiththealarm response?A.Remove Condensate Polishersfromservice;GotoAOP-101

.1, RCS Leak not Requiring SI.B.Remove Condensate Polishersfromservice;Goto AOP-112.2, SGTubeLeaknot Requiring SI.C.Place Condensate Polishersinservice;GotoAOP-101.1, RCS Leak not Requiring SI.D.Place Condensate Polishersinservice;Goto AOP-112.2, SG Tube Leak not Requiring SI.85 2007NRCExamSRO86.Giventhefollowingplant conditions:*A transient has occurredresultinginthefollowingalarm:*PRFLUXHIRODSTP

• Reactor power indicatesthefollowing:*N41-101.9%andstable*N42-102.8%and stable*N43-101.9%andstable*N44-103.1%andstable*Tavgis578°Fand stableWhichONE(1)ofthe followinghasoccurred,andwhich action(s)/procedure(s) is/arerequiredtobe implemented?A.ARodStopwasinitiatedby1PRchannelONLY

initiateRCSborationtoreducepowerin accordancewiththe applicable alarm response.B.ARodStopwasinitiatedby2PR channels;reduce turbineloadtoreducepowerin accordance with applicable alarm response procedures.

C.ARodStopwasinitiatedby2PR channels;initiateRCS borationtoreducepower in accordancewiththe applicablealarmresponse.

D.ARodStopwasinitiatedby1PRchannelONLY;reduce turbineloadtoreducepowerin accordance with applicablealarmresponse procedures.

86 2007NRCExamSRO 87.Giventhefollowingplant conditions:*Theplantwasoperatingat98%powerwhenalossofoff-site power occurred.*Eight minuteslater,thefollowingplant conditions exist:*1DAand1DBBus voltageiszero(0).*RCS pressureis2235psigandslowlyincreasing.*RCSLoopT HOTis602°Finall3loopsandstable

.*RCSLoopT COLDis565°Finall3loopsandstable.*CoreexitTCs indicate approximately610°Fandrisingslowly.*Steam Generator pressures are approximately1100psigandstable

.*PZRlevelis20%andstableWhichONE(1)ofthe followingdescribesthe current plant conditionsandactionthatwillbe directed?A.Heatremovalisbeing maintainedbysteamlinePORVs.

VerifythatNaturalCirculationexistsin accordancewithEOP-6.2, Loss of AllESFAC Power RecoveryWithSIRequired.

B.Heatremovalisbeing maintained by condensersteamdumps.

VerifythatNaturalCirculationexistsin accordancewithEOP-6.1, Loss of AllESFAC Power RecoveryWithoutSIRequired.C.Natural Circulationdoesnotexist.Heatremovalmaybe establishedinaccordancewithEOP-6.2, Loss of All ESF AC Power RecoveryWithSIRequired.D.Natural Circulationdoesnotexist.HeatremovalmaybeestablishedinaccordancewithEOP-6.1, Loss of All ESF AC Power Recovery WithoutSIRequired.

87 2007NRCExamSRO88.Giventhefollowingplantconditions:*Areactortriphas occurredduetolossofoff-sitepower.

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

,(>4hours)whichONE(1)ofthefollowing describes the event mitigation strategyuponexitfrom EOP-1.0, Reactor Trip/Safety Injection Actuation?

A.GotoEOP-1.1, Reactor Trip Recovery;cooldowntheRCSusing EOP-1.3 , Natural Circulation Cooldown.B.GotoEOP-1.1, Reactor Trip Recovery;stabilizetheprimaryand secondary plants ,andremaininEOP-1.1until powerisrestored.C.GoToGOP-5

, Reactor Shutdown From StartuptoHot Standby (Mode 2toMode 3);referto AOP-304.3, Loss of All Balance of Plant Buses ,torestoreservicebus power.D.GoToGOP-5, Reactor Shutdown From StartuptoHot Standby (Mode 2toMode3);referto SOP-211, Emergency Feedwater System ,toswap EFWtoService Water.88 2007NRCExamSRO 89.Giventhefollowing plant conditions:*Theplantisina normal service water system alignmentwith'A'and'B' SWpumpsrunning.

• XCP-604-1-2"SWP A/C TRIP" alarms.*Annunciator XCP-604-1-4"SWP AlC DISCH PRESSLO"alarms.

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

• AOP-117.1, Total Loss of Service Water,hasbeen entered.WhichONE(1)ofthe following describes the actions that shouldbetakento mitigate this event?A.Referto SOP-117, Service Water System, and ensurethe'C'SW pump automatically startedonlow header pressure.B.Continue in AOP-117.1,TotalLoss ofServiceWater,tripthereactor,andtr ip all RCPs.C.Referto SOP-117'.Service Water System, and startthe'C'SWpumponthe'A' train.D.Continue in AOP-117.1,TotalLoss ofServiceWater, and isolateall CCW loads.89 2007NRCExamSRO90.Giventhe following plant conditions

• The plantisin Mode 5.*Welding activitiesinthe Cable SpreadingRoomarein progress.*The Simplex Panel indicates actuation of Fire Protectionintheroom.*Maintenance reports that Fire Suppression is actuated, but thereisnoactual fire.WhichONE(1) of the following describesthefire suppression actuationandtheactiontobe taken?A.C02;Evacuate personnelfromtheareaandstopthe discharge in accordance with the associated Fire Emergency ProcedureandFire Pre-Plan.B.C02;Evacuate personnelfromtheareaandstopthe discharge in accordance with SOP-509, Fire Suppression System.C.Pre-Action Sprinkler; Terminate the actuation in accordancewiththe associated Fire Emergency ProcedureandFire Pre-Plan.D.Pre-Action Sprinkler; Terminate the actuation in accordance with SOP-509, Fire Suppression System.90 2007NRCExamSRO91.Giventhefollowingplant conditions:*ASteam GeneratorTubeRupturehasoccurred.*Dueto equipment failures ,thecrewisperformingactionscontainedinEOP-4.3

,SGTRwithLoss of Reactor Coolant-Saturated Recovery.*TheShift Engineer informsyouthatallCSFStatusTreesareGREENwiththeexceptionofthe following:*CoreCooling-YELLOWduetoRVLlSlevel

• Inventory-YELLOWduetoRVLlSlevelWhichONE(1)ofthe following describesthecorrect implementationofproceduresforthisevent?

A.Select another post-SGTR cooldown method lAW EOP-4.0.Implementation ofYellowPath proceduresisnotallowedwhileinEOP-4

.3.B.RemaininEOP

-4.3 while addressingBOTHYellowPath procedures

.Youmaychooseto implement the actions of eitherYellowPath procedure.C.Select another post-SGTR cooldown method lAW EOP-4.0andaddressONLYtheCoreCoolingYellowPath

,duetoitshigherpriority.D.Remainin EOP-4.3 and addressONLYthe InventoryYellowPathduetoconflictbetweentheCoreCooling YellowPathandEOP-4

.3 actions.91 2007NRCExamSRO 92.Giventhe following plant conditions.*0547A Reactor Trip occurred*0548Tavg=552°FandRCS pressureis2080psig*0748Tavg=379°FandRCS pressureis1550psig*0948Tavg=248°FandRCS pressureis1850psigWhichONE(1) of the following describesthelimit thathasbeen exceededandthereasonwhy?(REFERENCE PROVIDED)Limit A.Plant Operational Limits Curve T1B.Plant Operational Limits Curve T1C.TS CooldownLimit(Figure 3.4-3)D.TS CooldownLimit(Figure 3.4-3)Reason RCS pressureistoohigh RCS temperatureistoolow RCS pressureistoohigh RCS temperatureistoolow 92 2007NRCExamSRO93.Giventhefollowingplant conditions:*ALOCAhasoccurred.*Thecrewhas completed EOP-1.0, Reactor Trip/Safety Injection Actuation,tothepointof transition to another procedure.*AllESF equipment is operatingasdesigned.*Thefollowing conditionsexistinthe Reactor Building:*RB Pressure 10.5psigandrisingslowly

.*RHRSumpLevel424feetandrisingslowly.WhichONE(1) of the following describestheconditionthatexists,theproceduretransitionthatwillbemade

,andthe strategyforrecovery?

A.ORANGEconditiononHigh ReactorBuildingPressure

.Enter EOP-17.0, Response to Reactor BuildingHighPressure, and attempttolocateandisolatethesourceoftheleak;notifyplant stafftoobtain recommendedactionfor disposalofwaste.B.ORANGEconditiononRHRSumpLevel.EnterEOP-17.1, Response to Reactor Building Flooding , and attempttolocateandisolatethe sourceoftheleak;notify plant stafftoobtain recommendedactionfor disposal of waste.C.ORANGE conditiononHigh ReactorBuildingPressure

.Enter EOP-17.0, Response to Reactor BuildingHighPressure,andensureRBIsolationandHeatRemovalfunctionsare satisfied.D.ORANGE conditiononRHRSumpLevel.EnterEOP-17

.1, Response to Reactor Building Flooding , and ensureRBIsolationandHeatRemoval functions are satisfied.

93 2007NRCExamSRO94.Giventhefollowingplant conditions:*TheplantisinMode1.*Makeupto'A'SI Accumulator was just completed.*'A'SI Accumulator parametersareasfollows:*Boron Concentration*Pressure*Level2197ppm650psig 67%WhichONE(1)ofthe followingdescribestheactionrequiredin accordance with Technical Specificationsandwhy?A.Restoreboron concentrationtowithinlimitswithin1hour.Tominimizethe potentialforreaching unacceptable peak cladding temperaturesduringaLOCAwith postulatedfailureof1otherSI Accumulator.B.Restoreboron concentrationtowithinlimitswithin1hour.Tomaintainthe calculatedDNBRinthecoreatorabovethedesignlimitduring short-term transientsuntilcoreisreflooded

.C.Restore pressuretowithinlimitswithin1hour.

To minimize the potentialforreaching unacceptable peak cladding temperaturesduringaLOCAwith postulatedfailureof1otherSI Accumulator

.D.Restore pressuretowithinlimitswithin1hour.Tomaintainthe calculatedDNBRinthecoreatorabovethedesignlimitduring short-term transientsuntilcoreisreflooded.

94 2007NRCExamSRO95.G iventhefollowingplant conditions:*Youarethe ControlRoomSupervisor.*An explosion occursresultingin significant damageintheunit.*TheShift Supervisorwasseriouslyinjuredinthe explosionandisincapacitated.*Thereareno proceduresordirectivesthatprovide adequate directiononcontroloftheplantandrescueofinjuredpeopleforth is situation.*Immediateactionisrequired.WhichONE(1)ofthe following describes the requirement for performingthisaction?

A.Youmayapprovethisactionin accordance with 10CFR50.54(x)and(y).B.Youmustobtain concurrencefromoneotherSROpriortoperformingtheaction.C.TheNRCmustbenotifiedpriortotheactionandshould concurwiththeactiontobetaken.D.ThePlant Managermustbenotifiedandshould concurpriortotakingtheaction.

95 2007NRCExamSRO96.Giventhefollowingplant conditions:*100%power.*AllmajorcontrolsareinAUTO.*ChargingPump"A"isrunning.*ChargingPump"B"hasbeen out-of-service for AuxiliaryOilPumpreplacement.*ChargingPump"C"isalignedtoTrain "B".*ChargingPump"B"isreadyfor post-maintenance testing.WhichONE(1)ofthe choicescorrectlycompletesthefollowing statement regardingtheoperabilityofTrain"B"duringthe post-maintenance testing?Train"B"mustbe declared inoperable when_A.ChargingPump"B" breakerisrackedup

.B.ChargingPump"B" control powerisrestored

.C.ChargingPump"C" breakerisrackeddown.D.ChargingPump"C"controlpoweris de-energized

.96 2007NRCExamSRO 97.TheplantisinMode1.

RCS TemperaturehasgonebelowtheTechnical Specification MinimumTemperatureforCriticality.Ifthe conditions CANNOTbecorrected,whichONE(1)ofthe followingdescribestheMAXIMUMtimeallowedpriortoplacingtheplantinMode3andthebasisfortheactioninaccordancewith Technical Specifications?

A.30minutes;RPS Instrumentationisno longeroperatinginitsanalyzedrange.B.30minutes; Analysis assumptions for calculationofMode1 ShutdownMarginare no longer valid.C.1hour;RPS Instrumentationisnolongeroperatinginits analyzed range.D.1hour;Analysis assumptions for calculationofMode1 ShutdownMarginarenolongervalid

.97 2007NRCExamSRO98.Giventhefollowingplant conditions:*Theplantiscomingoutofarefuelingoutage.OperationsDept.is performingsystemvalvelineups.*Avalve alignmentinthe ReactorBuildingshouldtake approximately30minutesinaradiationfield of 6 Rem/l-it.WhichONE(1)ofthe following descrtibestheMINIMUMreview requirements thatmustbemetpriorto performing the alignment?

A.APre-Job Briefandreviewof RWP/SRWP forvalvelineupsONLYB.Areviewofthe RWP/SRWPforvalve lineups and ALARA CommiteereviewONLYC.APre-Job Brief and ALARA CommiteeReviewONLYD.APre-JobBrief, ReviewofRWP/SRWP

, and ALARA Commitee Review 98 2007NRCExamSRO 99.Giventhefollowingplantconditions:*Mode5withRHRTrain "A"runninginthe shutdowncoolingmode.*RCS subcoolingis45 of.*SG"B"and"C"are availableforheatremoval.*Atotalloss of CCWflowhasoccurred

.*Seal Injectionflowisnormal.*The operatingcrewisinAOP-118.1

, TOTALLOSSOF COMPONENT COOLING WATER,andhasreferredto AOP-115.3,LOSSOFRHRWITHTHERCSINTACT.WhichONE(1)ofthe following describesthecorrectactionandthereasonforthat action?A.StopanyrunningRCPandRHRPump"A

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

" immediatelyandalignforRCSBleedandFeedtoprovide cooling.D.Within90 minutesstop"A"RHRpumpto preventsystemdamage.

99 2007NRCExamSRO 100.Giventhefollowing plant conditions

• Theplantis operatingat100%power.*EDG"B"isout of serviceandis expectedtoreturnto serviceintwo(2)hours.

• Subsequently, the following events occur:*Alossof offsite power.*The reactor is trippedandthecrewenters EOP-1.0 , Reactor Trip or Safety Injection.*SIisNOT actuated.*Thecrewmadea transitiontoEOP-15.0, Loss of Secondary Heat Sink ,basedona CSFSTREDPath.*EDG"A" output breaker subsequentlytripsona differentia/lockoutonBus 1DA.WhichONE(1)ofthe following describestheactionsthatwillbe takenanditsbases?

A.Immediately transitiontoEOP-6.0 , Loss Of AllESFAC Power.All other proceduresintheERG network assumeboth7.2KVESFbussesare available.B.Immediately transitiontoEOP-6.0, Loss Of All ESFACPower.All other proceduresintheERG network assume a minimumofONE(1)7.2KVESFbusisavailable.

C.Remainin EOP-15.0untilfeedisrestoredandtheRED conditioniscleared , and then transitiontoEOP-6.0 , Loss of All ESF AC Power.REDpath Function Recovery procedures must be performeduntilthe conditioniscleared.

D.Remainin EOP-15.0 until directedtoreturnto procedure i n effect ,andthentransitiontoEOP-6

.0 , Loss of AllESFACPower.REDpath Function Recovery procedures must be finished to completion.

100 INTEGRIT Y EO P-12.0 REVI SION 12 ATTACHM ENT 4 PAGE2of 2 PLAN T OPERATIONAL LIMITS CUR VE 400 350 300 200250 RCS T c ol d (o F)1 50 0 I I.'._P SIG I (PZR SAFETY VALVE S A S SUMED FULL O P EN)I-10-----R EGION OF ACC EPTABLE OPERATION-----01 LIMIT T2 LIMIT T1 I---I I LIM IT At--.II- I o 100 RCS PR ESSURE (PSIG)300 2500 500 2000 1500 1000 PAGE 9 OF 12 REACTOR COOLANT SYSTEM MATERIAL PROPERTY BASIS LIM ITING MATERIAL: INTERMEDIATE SHELLPLATEA9154-1 LIMITING ART VALUES@56EFPY: 1/4T , 153°F 3/4T , 138°F Q 5 0 10 0 150 20 0 250 300 35 0 400 45 0 500 550 Moderator Temperature (0 F)FIGURE 3.4-3 V.C.Summer Unit 1 Reactor Coolant System Cooldown Limitations (Cooldown Ratesupto100 oF/hr)Applicablefor56 EFPY (Without Margins for Instrumentat ionErrors)Using1998 Appendix G Methodology SUMMER-UNIT 1 3/44-32 AmendmentNo.53 , 113 , 133,143,174