ML071930548

V. C. Summer June 2007 Exam Nos. 05000395/2007301 Final RO As-Given Written Exam

ML071930548
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: ML071930548 (78)

Text

Final Submittal(BluePaper)ZW7-3t)I'3 u,"" e l3, zoo7 As c;i lIcJ Reactor Operator Written ExaminationV.C.SUMMER JUNE2007EXAMEXAMNO.05000395/2007301 JUNE4-8,2007(OP TEST)JUNE13,2007 (WRITTEN EXAM) u.s.Nuclear Regulatory Commission Site-Specific RO Written Examination Applicant Information Name: Date: Facility/Unit:

'-'" r3 tlW7\/.C.50 (Y1lrncr.)u()e Region: II Reactor Type: W Start Time: Finish Time: Instructions Use the answer sheets provided to document your answers.Staple this cover sheet on top ofthe answer sheets.To pass the examination, you must achieve a final grade of at least 80.00 percent.Examination papers will be collected 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after the examination begins.Applicant Certification All work done on this examinationismy own.I have neither given nor received aid.Applicant's Signature Results Examination Value Points Applicant's Score Points Applicant's Grade Percent Name:---------------

1.Giventhefollowing

• Theunit isat85%poweratMOL.*A continuous uncontrolledcontrolrod withdrawal occurs.WhichONE(1)ofthe followingparameterswill DECREASE?A.Steam Generator Pressure B.Main Generator Electrical OutputC.OverpowerDeltaT setpoint D.VCTLevel2007NRCExamRO 1

2007NRCExamRO2.Giventhefollowingplantconditions:*ALOCAhasoccurred.*RCS pressureis1750psigandlowering

.*Reactor Building pressureis4psigandrising.*Steam Generator pressuresare1000psigandstable

.WhichONE(1)ofthefollowing describestheactuationsthatarearesultofthis condition?

A.SafetyInjectionONLY.B.SafetyInjectionand Containment VentilationIsolationONLY.C.SafetyInjectionand ContainmentIsolationPhaseAand Containment VentilationIsolationONLY.D.SafetyInjectionand ContainmentIsolationPhaseAand Containment Ventilation Isolat ion and ContainmentIsolationPhaseB

.2 2007NRCExamRO3.Giventhe following plant conditions

• Thecrewis respondingtoanATWS lAW EOP-13.0, Response to Abnormal Nuclear Power Generation

,andis attempting an emergencyborationoftheRCS.*MVT-8104,EMERG BORATE ,valvewillnotopen.WhichONE(1)ofthe following describestherequiredactionstobe performed and why?A.Openthe ChargingPumpSuction HeaderIsolationvalvesas directed by AOP-106.1, Emergency Boration , to maximizeBoricAcid flowrate.B.Open LCV-115B/D, RWSTtoCHGPPSuet,asdirectedby AOP-106.1 , Emergency Boration , to borateviacoldleginjection

.C.Openthe ChargingPumpSuction HeaderIsolationvalvesas directedbyEOP-13.0,Responseto Abnormal Nuclear Power Generation

, to maximizeBoricAcidflowrate.D.Open LCV-115B/D

, RWSTtoCHGPPSuet,asdirectedby EOP-13.0,Responseto Abnormal Nuclear Power Generation,toborateviacoldleg inject ion.3 2007 NRC Exam RO 4.WhichONE(1)of the following describes the setpoints forthetwo(2)annunciators below?A.B.C.D.RCP AlBIC THERM BAR&BRGFLOLO 90 gpm 90 gpm50gpm 50 gpmCCBPDISCHHDRPRESSLO30psig70psig30psig70psig 4 2007NRCExamRO 5.Giventhefollowingplantconditions:*The plantisinMode5.*ThePZRissolid

.*RCS temperatureis190°F.*RCS pressureis315psig.*LetdownPressureControlValvePCV-145isinAUTO.FCV-605A,"A"BYP,and FCV-605B,"B"BYP ,arein MANUAL.WhichONE(1)ofthefollowing describesaconditionthatwill initiallycausePCV-145toCLOSE?A.Loweringtheoutputofthe controllerforthein-serviceRHRheat exchanger flowcontrolvalve

.B.Raising CCWflowthroughthe in-serviceRHRHeatExchanger.C.Loweringthe setpointofPCV-145.

D.Startingan additionalRHRPump.5 2007NRCExamRO 6.Giventhe following plant conditions:*The plantisin Mode 6.*"B"Train RHRisin service."A" Train RHRisout of service and expectedtobe returned to service in approximately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.*Refuelingisin progress.*Cavitylevelis 23.5 feet above the reactor vessel flange."B"RHRPump trips and cannot be restarted.WhichONE(1)ofthe following describes the operational restrict ion(s)associated with this event?A.Refueling Cavity level mustberaisedto greater than 24 feet above the reactor vessel flange prior to continuing refueling activit ies.B.Refueling activities are permittedforupto1 hour while repairs are initiated to"B"RHRPump.C.All containment penetrations w ith a directpathto atmosphere must immediately be verified closed.D.Suspend all activities that could resultina reduction in boron concentrationofthe RCS.6 2007NRCExamRO7.Giventhe followingplantconditions:*Theplantwasoperatingat100%power.7.2KV TransformerXTF-4waslostduetoafault.

The associated DIGdidNOTstartasdesigned.

Subsequently,aLOCAcauseda reactortripand safety injection.RCS pressure is currently350psigandtrendingdown slowly.WhichONE(1) ofthefollowing describestheoperationofRHRPumpsforthis condition?

A.RHRpumpArunningwithits miniflowvalveopen B.RHRpumpArunningwithitsmfniflowvalveclosedC.RHRpumpBrunningwithits miniflowvalveopen D.RHRpumpBrunningwithits miniflowvalveclosed 7

2007NRCExamRO8.WhichONE(1)ofthe following directly supplies power to ChargingPump"A"andRHR Pump"A"?A.B.C.D.ChargingPump"A" 1DA 1DA1 1DA 1DA1*RHRPump"A" 1DA 1DA 1DA1 1DA1 8 2007NRCExamRO 9.Giventhefollowingplant conditions

• TheplantisoperatinginMode1at100%power

.*Thefollowing indicationsarereportedbytheRO.*TI-471,PRT Temperatureistrendingupandisnowat 15SOF.*PI-472,PRT Pressureistrendingupandisnowat8psig.

Wh ichONE(1)ofthefollowingcomponents,ifleaking,will causethiscondition?

A.XVR-8708A,RHRPump"A"SuctionReliefValve

.B.XVR-8121 ,RCPSealReturn Relief Valve.C.XVR-7169,RCDTPumpsSuctionReliefValve.D.XVS-8010

, PZR Safety Valve.9 2007NRCExamRO10.WhichONE(1)ofthefollowing describes an immediateactionandthebasisfortheactionin accordancewithEOP-1.0, Reactor Trip/Safety Injection Actuation?

A.InsertcontrolrodsinManual;toinsertnegativereactivitybythemostdirectmanner possible.B.InsertcontrolrodsinManual;toreduceormaintainRCS pressuretopreventlifting the Pressurizersafetyvalves.

C.PlaceEHCPumpsin PULL-TO-LKNON-A;toprevent uncontrolledcooldownofthe RCS.D.PlaceEHCPumpsin PULL-TO-LKNON-A;tominimize secondary makeup requirements.

10 2007NRCExamRO11.Giventhefollowingplant conditions

• Areactortripandsafetyinjectionhaveoccurred.

RCS pressureis1050psigandlowering.*Tavgis550°Fandlowering

.*Pressurizerlevelis65%andrisingrapidly.*ReactorBuildingpressureis2psigandrising.WhichONE(1)ofthe followingdescribesthecauseofthis event?A.Letdownlinebreak.

B.SBLOCAonanRCScoldleg.

C.Stuckopen pressurizer PORV.D.Stuckopen pressurizersprayvalve.

11 2007NRCExamRO12.Giventhe following:*Theplantisat100%power.*All systemsarein theirnormalalignments.*Aleak occursintheLetdownHeatExchanger.Assumingnoactionbythecrew

,whichONE(1)ofthefollowing describestheeffect(s)ontheCCW System?A.RM-L2A1B indication rises.SurgeTankventvalve PW-7096closeswhentheindicationreachesthe ALERT level.B.RM-L2A1B indica tion rises.SurgeTankventvalve PW-7096closeswhentheindicationreachestheHIRADlevel.C.SurgeTank leve/lowers.

CCW Booster Pumpswilltriponlowsuctionpressure

.D.SurgeTanklevellowers

.CCWPumpswilllose suctionwhentheSurgeTank empties.1 2 2007NRCExamRO13.Giventhe following plant conditions:ALOCAoccurredandRCS pressurereached1380psig.*AllactionsofEOP-1

.0 were performedasrequired.Thecrewis performing EOP-2.1 ,Post-LOCACoo/down and Depressurization.

RCS pressure is currently1335psig.*RCS temperature is currently 496°F.TwoCharging pumpsarerunning

.Thecrewis evaluating stopping1ChargingPump

.Giventheabove conditions, whichONE(1)ofthefollowing describes whether theChargingPumpmaybe stopped ,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 2007NRCExamRO14.Giventhefollowing plant conditions

• ThePlantisinMode3.*APZR PORVbeginsleakingtothePRT.

• Pressurizer pressureis985psig.

PRT pressure is steadyat5psig.*PRT temperature is steadyat90°F.Assume:*Ambientheatlossesarenegligible.*Steamq ualityinthe pressurizeris100%.WhichONE(1)ofthe followingwouldbethe approximateMCBindicationonTI-463,RELIEFTEMP OF?C.300°F 14 2007NRGExamRO15.Giventhe following plant conditions:*The Reactor has trippedfrom100%power.*"A"and"G" Service Water (SW)pumps were running.*The crew implemented EOP-1.0, Reactor Trip/Safety Injection Actuation, then transitioned to EOP-1.1, Reactor Trip Recovery.*MDEFW pumps started on Lo-LoSGlevelsafterthetrip

.*Subsequently,anSI actuatedduetoaLargeBreakLOGA.WhichONE(1)ofthe following describes the operation of equipmentasaresultofthe SI?A.MDEFW pumpswilltripandbe restartedbythe sequencer.

Service Water Pumps"A"and"G"will continuetorun.B.MDEFW pumps will continuetorun.Service Water Pumps"A"and"G"willtripand be restartedbythe sequencer.

G.MDEFW pumpswilltripandberestartedbythe sequencer.

Service Water Pumps"A" and"G"willtripandbe restartedbythe sequencer.D.MDEFW pumps will continuetorun.Service Water Pumps"A"and"G"willcontinuetorun.15 2007NRCExamRO16.Giventhefollowingplant conditions:*Aloadrejectionhas occurredfrom100%power.*Allcontrol systems respondedasdesigned.Powerlevelisnow stableat70%.WhichONE(1)ofthe following condit ionswillexistduringthisevent?

A.Charg ingFlowControl Valve , FCV-122 ,willbethrottlingopen.B.Pressurizer Backup Heaterswillbeenergized.

C.PressurizerPORVswillbeopen

.D.Letdown Backpressure ControlValvePCV-145willbe throttling closed.16 2007NRCExamRO17.Giventhe following plant conditions

• A reactortriphas occurredfrom100%power.*Reactor Trip Breaker"B"remains CLOSED.WhichONE(1)ofthe following describes the effectontheSteamDumpSystem?A.Thesteam dump valveswillopenand maintainTavgat 55JOF.B.Thesteam dumpswillremainclosed following the reactortripduetolossofthearmingsignal.C.Thesteam dumpswillremainclosedfollowingthe reactortripduetolossofthe'planttrip' modulation signal.D.Thesteam dump valveswillopenand maintainTavgat559°F.

17 2007NRCExamRO 18.Which ONE (1)of the following describes the source of control power to Reactor Trip Breaker"B"and Reactor Trip Bypass Breaker"B"?A.B.C.D.Reactor Trip Breaker B 125 VDCBus1HB 125 VDCBus1HB 120 VAC APN-5902 120 VAC APN-5902 Reactor Trip Bypass Breaker B 125 VDCBus1HB 125 VDC Bus 1HA 120 VAC APN-5902 120 VAC APN-5901 18 2007NRGExamRO19.Giventhefollowingplant conditions

• Areactortriphas occurredcoincidentwithalossof off-site power.*While performingactionintheEOPs,thefollowing events occur:*RGS pressureis1700psigandlowering.*RB pressureis4.7psigandrisingslowly.*Three minutes aftertheseindicationsareobserved, APN-5904failsand becomes de-energized

.WhichONE(1)ofthe followingdescribestheeffect,ifany,onplant equipment aftertheAPNfailure?

A.TrainAandTrainBEGGS equipmentisoperatingasrequired;TrainAandTrainBRBSprayPump dischargevalvesareopen.B.TrainAandTrainBEGGS equipmentisoperatingasrequired;TrainAandTrainBRBSprayPump dischargevalvesareclosed.G.TrainAEGGS equipmentisoperatingasrequired;TrainBEGGS equipment isNOTrunning;TrainAandTrainBRBSprayPump dischargevalvesareopen.D.TrainAEGGS equipmentisoperatingasrequi red;TrainBEGGS equipment isNOTrunning;Tra inAandTrainBRBSprayPump dischargevalvesareclosed.

19 2007NRCExamRO20.Giventhe following plant conditions

• ALOCAhas occurred.*RCS pressureis200psig."A" Reactor Building SprayPumpisOutofService

.Containment pressure has exceededtheHigh-3setpoint.Train"B"PhaseAhasfailedto actuate.All other actuationsandTrain"A"ECCS equipmentisrunningasrequired.

The most recent Chemistry sample oftheRCSind icatedthatRCS activity is 5X10-2 microcuries/ml Dose Equivalent Iodine.Assumingnoact ionbythecrew ,whichONE(1)ofthefollowing describestheeffectontheplant?A.Containmentwillexceeditsdesignpressure.

B.Off-Sitereleaseswillexceed accident analysis assumptions

.C.Only1 Containment Isolation ValveineachPhaseA penetrationwillbeclosed.

D.Only halfofthe Containment penetrationsrequiredforisolationwillreceiveisolation signals.20 2007 NRC Exam RO 21.Given the follow ing plant conditions:*A reactor startupisin progress.*SR Channel N-31 indicates7X10 3 CPS.*SR Channel N-32 indicates 7X10 3 CPS.*IR Channel N-35 indicates 8.7X10-6%power.*IR Channel N-36 indicates 6.0X10-6%power.Which ONE (1)of the following describes(1)the existing plant cond ition ,(2)the statusofP-6 ,and(3)the action required in accordance with AOP-401.8, Intermediate Range Channel Failure?A.(1)N-36 i s undercompensated;(2)P-6 should NOT be satisfied; (3)maintain power stable until N-36 is repaired.B.(1)N-36 is overcompensated

(2)P-6 should be satisfied; (3)maintain power stable until N-36 is repaired.C.(1)N-36 is undercompensated;(2)P-6 should be satisfied; (3)place the unit in Mode3until N-36 is repaired.D.(1)N-36is overcompensated;(2)P-6 should NOT be satisfied;(3)placetheun it in Mode 3 until N-36 is repaired.21 2007NRCExamRO22.Giventhe following plant conditions

The plant is operatingat8%power.ALossof Component Cooling Waterhasoccurred

.*"A"RCP motor bearing temperatureis189°Fandrisingslowly.*"A"RCP lower seal water bear ing temperatureis226°Fandrisingslowly.Thecrewhas entered AOP-118.1 , Loss of Component Cooling Water.WhichONE(1) of the following actionsisrequ ired?A.RCP motor bearing temperature exceeds operating limits.Stop'A'RCPandinitiateaplant shutdown lAW GOP-4B, Power Operation (Mode 1-Descending).

B.RCPlowerseal water bearing temperature exceeds operatinglimits.Stop'A'RCP and initiate a plant shutdown lAW GOP-4B, Powe r Operation (Mode 1-Descending)

.C.RCP motor bearing temperature exceeds operatinglimits.Tripthereactor,stop'A'RCP,andgotoEOP-1.0, Reactor Trip/Safety Injection Actuation.D.RCP lower seal water bearing temperature exceeds operating limits.Tr ip the reactor , stop'A'RCP ,andgotoEOP-1.0, Reactor Trip/Safety Injection Actuation.

22 2007NRCExamRO 23.Giventhefollowingplant conditions:*TheplantisinMode3

.*Thefollowing wide-rangepressuresareindicated:*PT-402*PT-403*PT-455A-1335psig-1350psig-1285psig*Subcoolingindicationon TI-499AandTI-499Bindicatesthefollowing:

TI-499A TI-499BWhichONE(1)ofthe following describesthecoreexit temperatureusedtodetermine RCS subcoolingforthe 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 2007NRCExamRO24.Giventhe following plant conditions

• A Reactor Trip condition existedandthe Reactorfailedtotrip.*RCS pressure now indicates 2350 psig.Assuming no other eventsarein progress, which ONE (1)of the following describesthe1)appropriate actionandthe2)reason for that action?A.1)Verify PZR PORVs and Block Valves open2)To increase flow on FI-943 ,CHGLOOPB CLO/HOT LEG FLOW GPM B.1)Verify PZR PORVs and Block Valves open 2)To increase flow on FI-110, EMERG BORATE FLOW GPM C.1)Placeboth ESFLS A(B)Resets to NON-ESF LCKOUTS 2)To increase flow on FI-943,CHGLOOPB CLO/HOT LEG FLOW GPMD.1)Placeboth ESFLS A(B)Resets to NON-ESF LCKOUTS 2)To increase flow on FI-110, EMERG BORATE FLOW GPM 24 2007NRCExamRO25.Giventhefollowingplant conditions:*Theplantwasat100%power.*Areactortripandsafetyinjectionoccurred

.*R8CUs XFN-0064A and XFN-00648startedinSLOW.*While performingtheactionsofEOP-1.0, ReactorTrip/SafetyInjection Actuation ,thefollowingalarmsarereceivedinthecontrolroom:

• XCP-605-3-1, SW FR R8CU 18/28FLOLO*XCP-605-3-2, SWFRR8CU 18/28PRESSLOWhichONE(1)ofthefollowingchoicescontainsbothofthe conditionsthatcouldeach independentlycausethese annunciatorstoalarm?A.SW8P"8" tripped;MVG-31118, R8CU 648/658TOIND COOLINGgoingCLOSED.

8.SW8P"8" tripped;MVG-3109C, R8CU 648 OUTLETISOLgoingCLOSED.

C.XFN-00648 (18 R8CUSSFAN)tripped; MVG-3108C, R8CU 648 INLETISOLgoingCLOSED.

D.XFN-00648 (18 R8CUSSFAN)tripped; MVG-3109D, R8CU 658 OUTLETISOLgoingCLOSED.

25 2007NRCExamRO 26.WhichONE(1)ofthe following describes the power supplies that directly feed Containment Spray Header Isolation Valves XVG-3003A and XVG-3003B, respectively?A.XSW1DA1andXSW1DB1 B.XMC1DA2XandXMC1 DB2Y C.XMC1 DB2XandXMC1 DA2Z D.XMC1 DA2ZandXMC1 DB2X 26 2007NRCExamRO27.Giventhe following plant conditions:*ALOCAhasoccurred.*RCS pressureis450psig.

Reactor Building pressureis18psigandlowering.

• RWSTlevelislowering

.Reactor Building Sumplevelisrising

.*"A" Reactor Trip Breakerremainedclosed

.WhichONE(1)ofthe following describes the operationofthe ReactorBuildingSpraysystemasthe event continues?RBSprayPumpsuctiontotheRBSump Valves , MVG-3005AandB...A.are manually openedwhenRWSTlevel reaches its setpoint.RB Spray Pump suction valvesfromRWST,MVG-3001AandB,are manuallyclosedwhen MVG-3005AandBarefullyopen.

B.automaticallyopenwhen RWST level reachesitssetpo int.RB SprayPumpsuctionvalvesfrom RWST , MVG-3001AandB, automaticallyclosewhen MVG-3005A andBarefullyopen.C.are manually opened when ReactorBuildingSumplevelreachesitssetpo int.RBSprayPump suction valvesfromRWST , MVG-3001AandB,are manually closed when MVG-3005AandBarefullyopen.

D.automaticallyopenwhen ReactorBuildingSumplevelreachesits setpoint.RBSprayPump suction valvesfromRWST , MVG-3001AandB , automatically close when MVG-3005AandBarefullyopen.

27 2007NRCExamRO28.Withtheunitat100%

power ,whichONE(1)ofthefollowing describesthepotential consequence of PCV-444C, PZR Spray Valve ,failingopen?A.LossofPZR pressurecanresultinan unwarrantedOPDeltaTrunbackandreactor trip.B.PZR pressurewillremainstableasPZRheaterswill compensateforthepressure reduction.C.LossofPZR pressuremayresultinsteam formationinthe reactorvesselheadandSGtubes.D.LossofPZR pressurecanresult inan unwarrantedOTDeltaT runbackandreactor trip.28 2007NRCExamRO 29.WhichONE(1)ofthe followingdescribesthe purpose and functionofthe ReactorBuildingCharcoal Cleanup Units?Designedfor...

A.primarymeansoflongtermpost accidentiodineremovalfromtheRB atmosphere

.Dischargeis alignedtotheRBPurgesystemexhaust.

B.primarymeansoflongtermpost accidentiodineremovalfromtheRB atmosphere.Dischargeis alignedtotheRBatmosphere.C.RB pre-entry reduction of airborne contaminants

.DischargeisalignedtotheRBPurgesystem exhaust.D.RB pre-entry reduction of airborne contaminants.

DischargeisalignedtotheRB atmosphere.

29 2007 PostRetakeNRCExam Question Review FQue'stion*17rainin'g;,-R efer.en ce:f Res olutibn.',-MissedI'"*(Mes/N(>>)*onsideration I;':1¥es/No),.,".."-e., ,""c x.RO/SROI , B'tes*..Yes*3'.O, Simulator scenarios lirai liling material feed ba GI Cs tit:>m itted tochoices IA&0 to clar ifY"maximize Boric Acid flowrate".Also submitted feedback to include tliis I'-in an IRO/SRO scenario.lReviewed thls question."".._..wit heachcand idate.4 No No IB-2, Simulator Reviewed this questionwitheach candidate.

10 No No EOP-1.0 Reviewed th is questionwitheach candidate.

14 No No EOP-2.1, Simulator scenarios Rev iewed this questionwitheach candidate.

15NoNoIB-1,IB-3, GS-2, Simulator Reviewed this questionwitheach candidate.

scenarios 16NoNo IC-3, Simulator Reviewed this questionwitheachcand idate.1[8 No Y es*18-9 Feedbac k submitted to include discussion

'ofRTB I" ,f control.power in I C-;: 9.iiII 2 1"NoN o IC-8 Some examinees were confused with terminology "satisfied/NOTsatisfied"incho ices.Feedback II'.I submittedtoclarify.

Reviewed this question with-..each candidate.";,r;,&1 ,...24 Ye s*No A 0 F2-106.1...."-Il Reducing B.*S pre ssurewouldnot resultina'..I C:Jirect increasein flow on FI-11 O.Feedbacka subm ittedtoclarify.Reviewedthis questionwit h I-..B Q..,-each candida te."*g 2 7 N o I'N""....n..AlthougH technically c orrect, entire answer w as I" 0 not available.Feedback submitted to provide"..0 entire co rrect answer." 28'Q Ye s*No*10-6Some confusio n over"unwarranted".Feedback I'provide d du r.iAgexamto view"unwarranted" as I'"undesired.

" T raining fee dback submittedt o I'I;revisec hoices A&lD similar lY.a......29NoNo AB-17 Reviewed this questionwitheach candidate.

30 No No EOP-4.0 Reviewed this questionwitheach candidate.

1of4 2007NRCExamRO30.Giventhefollowing plant conditions:*Theunitwasinitially operatingatfullpower.*Alossof ALL offsite poweroccurredin conjunctionwitha steam generatortuberupture.*All safeguards equipment functionedasrequired.*The following plant conditionsnowexist:*RupturedS/G pressure=1100psig,stable*CoreexitTC

=505°F , slowly decreasing*RCS Pressure=1600psig,stable*PZRLevel=4%,stable*TotalSIFlow

=600gpmTheRCShasbeencooleddownto target temperature.*In accordancewithEOP-4.0, Steam GeneratorTubeRupture,theROopensonePZRPORV.

Soon after openingthevalve,the operatorobservesthatall channels ofPZRlevelare rapidly increasing.*ECCSflowhas increasedfrom600gpmto650gpm.WhichONE(1)ofthe followingisthecauseofthis indication?

A.PZRlevel instrumentsarenot calibrated for temperatureslessthan600°F

.B.Safety injectionflowis drivingtheRCStoawater

-solid condition.

C.Voidinginthe reactor vesselheadisforcing waterupthesurgeline.

D.Backflowhasbeen establishedfromtherupturedS/GtotheRCS.

30 2007NRCExamRO 31.Giventhe following plant conditions:*ALarge BreakLOCAhasoccurred

.*ReactorBuildingH2 concentrationwasat2%andrising

.*'A'Hydrogen Recombiner is INOPERABLE.

Wh ichONE(1)ofthe following describestheeffectontheremovalofHydrogenfromContainment?

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 Containment Sprayisplacedinservicein additiontothe Recombiner

.31 2007NRCExamRO32.WhichONE(1)ofthe following describes a featureofthe SpentFuelPooland/orCoolingsystem that will maintainradiationdoselevelsat acceptablelimitsduringplant operations?

A.SpentFuel CoolingPumpswilltriponlowsuction pressure prior to SpentFuelPoolleveldropping below 460'6".B.Boron concentration is maintainedsothat SpentFuelPool Keffislessthan0

.95andSpentFuelPool Radiationlevelsare maintained less than2.5mr/hratthesurfaceofthepool.

C.Anti-siphoningholesinthecoolingsystemsuctionand returnlines ensures thatSpentFuelPoollevelwillnotdropbelow460

'6".D.Interlocksonthe SpentFuelPool Manipulator Crane prevent spentfuelassembliesfromtravelling closerthan23feetfromthe surfaceofthe SpentFuelPool.32 2007NRCExamRO 33.WhichONE(1)ofthe followingdescribesthe initialSGLevel Response and SGWLC System Responseduringarapidincreaseinpower?SGLevel Response A.DecreasesB.DecreasesC.IncreasesD.Increases SGWLC System ResponseLagcircuitonSGlevelinput minimizes fluctuations Programmed DIPacrosstheFRV minimizes fluctuations Programmed DIPacrosstheFRV minimizes fluctuationsLagcircuitonSGlevelinput minimizes fluctuations 33 2007NRCExamRO34.Giventhefollow ing plant conditions

• TheplantisinMode6

,corereloadisinprogress.*Afuel assemblyisbeinginsertedintothecorewhen downwardmotionstops

.*TheRefuelingSROnotesthefollowing:*The SLACKCABLElightisON*The LOWER SLOWZONElightisOFF*The GRIPPERTUBEDOWNlightisOFFWhichONE(1)ofthe followingdescribesthereasonthat downward movementstoppedandthe subsequentoperationrelatedtotheinterlock?

A.Totalloadfellmorethan 150-300#belownominalfullload; bypassingtheinterlockisnotpossible.B.Thefuel assembly approached 10"fromthebottomofthecore

bypassingtheinterlockisnot possible.C.Totalloadfellmorethan 150-300#belownominalfullload

bypasstheinterlocktoallowthe assemblytobefullyinserted.

D.Thefuel assembly approached10"fromthebottomofthecore

bypasstheinterlocktoallowthe assemblytobefullyinserted.

34 2007NRCExamRO 35.Giventhefollowing plant conditions:

• Reactor poweris75%.RCSleakratedataisasfollows:*TotalRCS leakagerateis 9.1 gpm.*LeakagetoPRTis7.0gpm.

Leakagetothe ReactorCoolantDrain Tankis1.3gpm.*Total primary to secondaryleakageis0

.33 gpm.*SG1-0.09gpm*SG2-0.17gpm*SG3-0.07 gpmWhichONE(1)ofthe following describes RCS leakageinrelationto Technical Specif ication limits?A.Identified leakage exceedstheTSlimitB.Unidentified leakage exceedstheTSlimitC.Primaryto Secondary leakageexceedstheTSlimit D.AllRCS leakageiswithinTSlimits 35 2007NRCExamRO 36.Giventhe following plant conditions

Theunitisin Mode 3.*Asteamline breakhasoccurredon"A"SteamLineinthe Reactor Building.WhichONE(1)ofthe following describestheplantresponsetothisevent?

A."A"MainSteamLine pressurewilldrop."B "and"CMainSteamLinepressureswillremain constant.AllMSIVswillclosewhenatleast2 Containment pressure transmitters indicate3.6psig.B."A"MainSteamLine pressurewilldrop."B"and"C"Main SteamLinepressureswillremain constant.AllMSIVswillclosewhen"A"MainSteamLinepress ureindicateslessthan675psig.C.All3Main Steam Line pressureswilldrop.AllMSIVswillclosewhenatleast2 Containment pressure transmitters indicate3.6psig.D.All3Main Steam Line pressureswilldrop.AllMSIVswillclosewhenatleast2 Main Steam Lines indicatelessthan675psig.

36 2007NRCExamRO37.WhichONE(1)ofthe following describes the purposeofC-9 , Condenser Availability

,andC-16 , Condenser Pressure , permissive signals?A.C-9prevents2 steam dumpvalvesfrom operating during conditionsthatcoulddamagethe condensers.C-16armsALL condenserdumpvalveswhen condenser is below 4.5"Hgabsand adequate circ water pumps are available.B.C-9armsALL condenserdumpvalveswhen condense r is below 7.5"Hgabsand adequate circ water pumpsareavailable.C-16prevents2 steam dumpvalvesfrom operating during conditionsthatcoulddamagethe condensers

.C.C-9 anticipates condenserheatload problemsbyblocking2 condenser dumpvalvesat7.5"Hgabs.C-16 prevents ALL condensersteamdump valves from operatingduringconditionsthatcould damage the condensers.

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

C-16 anticipates condenserheatload problemsbyblocking2 condenser dumpvalvesat4.5"Hgabs.

37 2007NRCExamRO38.Giventhe following plant conditions:Theplantis operatingat100%power.*A FeedwaterLineBreakoccursatthepiping connectionto"A"SG.WhichONE(1) of the following describestheeffectofthis event?A.RCS temperaturerisespriorto reactortrip.SG"A" continues to depressurize afterFWIVclosure.B.RCS temperaturelowerspriortoreactortrip.SG"A" continues to depressurizeafterFWIV closure.C.RCS temperatures lowerspriortoreactortrip.SG"A" pressure stablil izes after FWIV closure.D.RCS temperature rises prior to reactortrip.SG"A" pressure stablizesafterFWIV closure.38 2007NRCExamRO 39.Giventhefollowingplant conditions:*AStation Blackouthasoccurred

.*Thecrewisrestoring off-site powertoBus1DAthroughthenormalfeed.Priortoclosingthenormal feeder breakertoBus1DA,whichONE(1)ofthefollowingsetsofactions must be performed, in accordancewithAOP-304.1

, Loss ofBus1DA with Diesel Unavailable?

A.De-energizeTrain"A"ESFLSEnsureBus1DA TRANSFERINITSwitchisinOFFB.De-energizeTrain"A"ESFLSEnsureBus1DA TRANSFERINITSwitchisinONC.Reset NON-ESF LCKOUTS&AUTO-START BLOCKSEnsureBus1DA TRANSFERINITSwitchisinOFFD.ResetNON-ESF LCKOUTS&AUTO-START BLOCKSEnsureBus1DA TRANSFERINITSwitchisinON 39 2007NRCExamRO40.Giventhefollowingplant conditions

• Alossof off-site powerhasoccurred.BothEDGshaverespondedasdesigned.

• Subsequently, safetyinjectionoccurs

.*Thefollowing conditionsexiston"A"EDG:

• Frequency59.9Hz.*Voltage7150Volts KW Output2600KWRBPressure reaches an actuation setpointrequiringthestartof"A"RBSpraypumpLoadsstabilize

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

" EDG?A.Alllisted parametersarewithinlimits.B.Frequencyis belowthelimit.C.Voltageis belowthelimit.D.Output exceeds the continuousKWrating.40 2007NRCExamRO41.Giventhefollowing plant conditions:

• lAW GOP-4A, Power Operation(Mode1-Ascending), powerhasbeenstabilizedbetween12and15%.

• PreparationsarebeingmadetorolltheMain Turbineto1800rpm.

Reactor power indicates the following:

• IRN-35-1X101%.*IRN-36-1X10 1%.*PRN-41-15%.

• PRN-42-14%

.*PRN-43-14%

.*PRN-44-14%.

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

A.APowerRangeRodStop(C-2)signal,withno change in reactor power.B.Areactortripduetothe deenergization of Intermediate Range Channel N-35.C.Areactortripduetothe deenergizationofIntermed iate Range Channel N-36.D.An IntermediateRangeRodStop(C-1)signal

,withno change in reactor power.41 2007 NRC Exam RO 42.Giventhe following plant conditions

• The plant is operating at 100%power.*The following annunciators are receivedinthe control room:*XCP-636 , 4-6 ,DCSYS OVRVOL T/UNDRVOL T*XCP-637 , 1-5, INV 3/4 TROUBLE*Inverter output voltage indicates120vac.Assuming NO other alarms are received, which ONE(1)ofthe following describes the common cause of both of the alarms?A.Loss of Alternate Source1FB.B.Loss of Normal Source 1 DB2Y.C.Loss of voltageonBus1HB.D.Inverter has transferred to Alternate Source1FB.42 2007NRCExamRO43.Giventhe following plant conditions:*The plant is operatingat100%power.*The followingalarmisreceived:

• XCP-624-1-5,SGALVLDEV*TheRO determines thatSG"A"levelisrising slowly on L1-474,475,and476

.*SG"B"and"C" levels are stable.WhichONE(1)ofthe following describesthecauseofthealarmandtheaction required?Alarmwas receivedona...A.5%deviation from programduetoa Feedwater Control Valvefailure;Place"A" Feedwater Control valve in manual and restorelevelto normal.B.5%deviat ion from programduetoaSteamFlowinputto"A"SGlevelcontrolfailing low;Select the alternatefeedflowand steamflowinputs

.C.10%deviation from programduetoa Feedwater Control Valvefailure;Place"A" Feedwater Control valve in manual and restoreleveltonormal.D.10%deviation from programduetoaSteamFlowinputto"A"SGlevelcontrolfailinglow; Select the alternatefeedflowandsteam flow inputs.43 2007NRCExamRO 44.WhichONE(1) of the following conditionswillresultinthe most Emergency FeedwaterSystemflow required to maintain SG levels constant following a reactor trip?A.B.C.D.Core Burnup 1 ,000 MWD/MTU 1,000 MWD/MTU 10 ,000MWDMTU 10,000 MWD/MTU Initial Power Level 10%100%10%100%44 2007NRCExamRO 45.Giventhefollowingplantconditions:

.*Theplantisat100%

powerduringanA1 maintenance week.*APN-5901hasbeen transferredtoAPN-1FAwhileworkisinprogresson XIT-5901.*Thenormal feeder breakerforbus1DAtripsopen.*"A" DIGfailstostart.WhichONE(1)ofthe following describes the subsequentoperationofthe"A"Train ESFLS?A.Output 1willshedloadsandtheESFLSwillgothroughitsnormal sequence.B.Output1willshedloads,butthentheESFLSwillbe preventedfromoperating.C.Output 1willNOTshedloads

,buttheESFLSwillgothroughitsnormalsequence.D.Output 1 will NOTshedloadsandtheESFLSwillbepreventedfromoperating.

45 2007 NRC Exam RO46.WhichONE(1) of the following describes the availability of Channel I (TrainA)120VACvital safeguards power duringalossofthe 115KVlinefromthe Parr Generating Complex?A.Is initially available from Battery 1A through inverter XIT-5901 , then automaticallyreturnstothe normal source after Diesel Generator"A" starts.B.The static switch initially transfers the supplyto1FA,then automaticallyreturnsto the normal source after Diesel Generator"A" starts.C.Is initially available from Battery 1A through inverter XIT-5901 ,thenis manually returned to the normal source after Diesel Generator"A" starts.D.The static switch initially transfers the supplyto1FA,thenis manually returned to the normal source after Diesel Generator"A"starts.

46 2007NRCExamRO47.Theplantisat100%power.Alossof125VDCcontrol powertothewillrequireentrytoEOP-1.0, Reactor Trip/Safety Injection Actuation.

A.FWBPbreakersB.MSIVsC.RCPbreakersD.PZRSprayValves 47 2007NRCExamRO48.Giventhe followingplantconditions:*Alossof off-site power has occurred.*BothEDGsstartasrequired.WhichONE(1)ofthe following describestheoperationoftheEDGRoom Ventilation system?Automat ically start when...A.DieselRoom temperature exceeds 88°F,tomaintainroom temperaturebelowthe Technical Specificationlimitof120°F.

B.the associated Diesel Generatorstarts,tomaintainroom temperaturebelowthe Technical Specificationlimitof88°F.c.DieselRoom temperature exceeds 72°F ,tomaintainroom temperaturebelowthe Technical Specificationlimitof88°F.D.the associated Diesel Generator starts , to maintain room temperaturebelowthe Technical Specif icationlimitof 120°F.48 2007NRCExamRO49.Giventhe following plant conditions

Emergency Diesel Generator"A"ispa ralleledtoits associated Bus.*Alagging power factorhasbeen established.WhichONE(1)ofthe following describes the operationofthediesel generator voltagecontrolswitch?

A.Loweringthe voltage control setpointwillcausethe generatortopickupalargershareoftherealload.B.Raisingthe voltage control setpointwillcausethe generatortopickupalargershareoftherealload.C.Lower ing the voltage control setpointwillcausethe generatortopickupalargershareofthe reactive load.D.Raisingthe voltage control setpointwillcausethe generatortopickupalargershareofthe reactive load.49 2007NRCExamRO 50.Giventhefollowingplant conditions:*AlossofRB InstrumentAirhasoccurred.*RB Instrument Air header pressureiscurrently94psigandlowering

.Assumingno operatoraction,whichONE(1)ofthefollowing describestheresponseoftheAirSystemandwhy?

RB Instrument Air header pressure decreasesuntil...A.PVA-2659 ,INSTAIRTORBAIR SERV , automaticallyopensat90psigtoensureanairsupplyforAOVsinsidethe Reactor Building.B.PVA-2659,INSTAIRTORBAIRSERV, automatically opensat93psigtoensureanairsupplyforAOVsinsidethe Reactor Building.C.PVT-2660

,AIRSPL YTORB,closesat90psigtoisolatetheRB headertoavoidalossof Instrument Air outside the Reactor Building.D.PVT-2660 ,AIRSPL YTORB ,closesat93psigtoisolatetheRB headertoavoidalossof Instrument Air outside the Reactor Building.50 2007NRCExamRO51.Giventhe followingplantconditions:*The plantisinMode6.

ReactorBuildingPurgeisinoperation

.Refueling activitiesareinprogress.*Aspentfuel assemblyisdroppedinthecavity.

Containment radiation monitor indicationsareallrising

.WhichONE(1)ofthefollowingdescribestheradiationmon itorsthatw ill initiateisolationofallorpartofthe Containment Purge?RM-A4 ,RBPurge Exhaust Particulate(Iodine)(Gas)Atmos monitor...A.ONLY.B.AND RM-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 2007NRCExamRO 52.Giventhe following plant conditions

• An immediate dischargetothe penstocksfromboth Waste Monitortanksis required.*Current conditionsareasfollows.RM-L5andRM-L9areoutof service*FairfieldHydroisinthe"pumping" mode.WhichONE(1)ofthe following statementswillprovidethe MINIMUM conditions necessary for monitor tank release?A.EitherRM-L5orRM-L9mustberestoredto operability priortorelease.B.BothRM-L5andRM-L9mustberestoredto operability priortorelease.

C.TheFairfieldHydro must converttothe generatingmodeand redundant samples performed priortorelease.Two independent qualified individualsmustverify release calculationsandvalve lineups.D.TheFa irfield Hydro must converttothe generatingmodepriortoreleaseandeitherRM-L5orRM-L9mustbe restored to operability.

Two independent qualified individuals must verify release calculationsandvalve lineups.52 2007NRCExamRO53.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 radiationalarmon RM-A 1, Control Bldg Supply Air?A.BothXFN-32A&BandbothXFN

-30A&Bstart,all outside air sourcesareisolated

.B.Both XFN-32A&Bandboth XFN-30A&Bstart ,returnairis mixedwithasmall amount of makeup air.C.Both XFN-32A&BtripandbothXFN

-30A&Bstart,all outside air sources are isolated.D.Both XFN-32A&Btripandboth XFN-30A&B start ,returnairis mixedwithasmall amount of makeup air.53','

2007NRCExamRO 54.Giventhe following plant conditions

• The plantisinMode5.RHRTrainAisinservice.

RCS temperatureis168°F.RCS pressureis175psig.

• Subsequently

,aLossof Service Water occurs.*Thecrewis performing actions containedinAOP-117.1

, Total Loss of Service Water.*NEITHER Service Waterloopcanberestored

.WhichONE(1)ofthe following describestheeffectontheRHRSystem,andtheprocedurethatwill mitigate the event?A.Stabilize RHR/RCS system temperatureusingsteam dumps lAW GOP-6, PlantShutdownMode 3toMode5.Goto AOP-115.3, Loss ofRHRwiththeRCSIntact

, for long-term mitigation.

B.Stabilize RHR/RCS system temperatureusingsteam dumps lAW GOP-6 , PlantShutdownMode 3toMode 5.Continue us ing AOP-117.1 , Total Loss of Service Water, for long-term mitigation.

C.RHR/RCS system temperaturewillriseasaresultofalossofcoolingto ComponentCoolingWater.Goto AOP-115.3 , Loss ofRHRwiththeRCSIntact

.D.RHR/RCS system temperaturewillriseasaresultofalossofcoolingto ComponentCoolingWater.

Continue using AOP-117.1 , Total Loss of Service Water.54 2007NRCExamRO55.WhichONE(1)ofthe following providestheelectrical powersupplytothe Supplemental Air Compressor?

A.XSW1DA1 B.XSW1DB1C.XSW1A1D.XSW1B1 55 2007NRCExamRO56.Giventhefollowingplant conditions

TheFire ProtectionSystemactuatedduetoaMain Transformer Fire.System pressuredroppedto80psigbefore recoveringduetotheactuationof necessary equipment.*Thefireisout.*The delugevalveisisolatedandreset.WhichONE(1)ofthe following describes the equipmentthatisrunning

,andthemethodofshutt ing the equipment down?A.ONLYthe MotorDrivenFirePumpisrunning;mustbe stopped locally.B.ONLYthe MotorDrivenFirePumpisrunning;maybe stoppedlocallyorinthecontrolroom

.C.TheMotorDrivenandEngineDrivenFirePumpsarerunning.Bothmustbestoppedlocally.D.TheMotorDrivenandEngineDr ivenFirePumpsarerunning

.TheMotorDrivenPumpmaybe stoppedlocallyorinthecontrolroom,theEngineDrivenPumpmustbestoppedlocally.

56 2007NRCExamRO57.Giventhefollowingplant conditions:*ALOCAhasoccurred.

SafetyInjectionis actuated.Reactor Building pressureindicates14psigandrisingslowly.*While performing actionsofEOP-1.0, Reactor Trip/SafetyInjectionActuation,thefollowingvalves indicate OPEN:*RCPSLWTRISOL 8100*LTONISOL8152*RBAIR SERVISOL2660WhichONE(1)ofthe followingdescribesthefailurethathasoccurredandtheMINIMUMaction necessary to mitigatethecondition?

A.PhaseAhas partiallyfailed.Place eitherPhaseA actuation switchesinthe ACTUATE position.B.PhaseAhas partiallyfailed.PlacebothPhaseAactuation switchesinthe ACTUATE position.C.PhaseBhas partiallyfailed.Place eitherPhaseB actuation switchesinthe ACTUATE position.O.PhaseBhas partiallyfailed.PlacebothPhaseB actuation switchesinthe ACTUATE position.57 2007NRCExamRO 58.G iventhefollowingplantcondit ions:*Thereactorhastripped.

SafetyInjectionisactuated

.*AnRCS cooldownisinprogressinaccordancewithEOP-2.1,PostLOCA Coo/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°FAtwh ich t imewastheTech SpecRCSCooldownratelimit FIRST exceeded?A.0915.B.0930.C.1000.D.1115 58 2007NRCExamRO 59.Giventhe following plant conditions

• ALOCA outside containmenthasoccurred

.Thecrewis performingtheactionsin EOP-2.5,LOCAOutsideContainment.WhichONE(1)ofthe followingactionswillbe attemptedtoisolatethebreakandwhichindicationisusedto determineiftheleakhasbeenisolatedin accordance with EOP-2.5?A.Isolatelow pressure SafetyInjectionpiping

.RCS pressure is monitored, becauseSIflowwill repressurizetheRCSwhenthebreakisisolated.

B.Isolatelow pressure SafetyInjectionpiping.PZRlevelis monitored , becausewhenthe breakisisolated

, RCS inventory willrapidlyrise

.C.Isolatehigh pressure SafetyInjectionpiping.

RCS pressure is monitored, becauseSIflowwill repressurizetheRCSwhenthebreakisisolated.

D.Isolatehigh pressure SafetyInjectionpiping.PZRlevelis monitored , becausewhenthe breakisisolated

, RCS inventory willrapidlyrise

.59 2007NRCExamRO 60.WhichONE(1)ofthe following describesthereasonthataREDconditionontheIntegrityCSFStatusTreemay developwhileperformingactionsofEOP-14.1,Responseto DegradedCoreCooling?

A.CoreExit Thermocouple temperaturewilldecreaserapidlywhenLowHeadSIPumpsarestartedandSIflowisinitiated

.B.CoreExit Thermocouple temperaturewilldecreaserapidlywhenSG depressurizationandSI Accumulatorinjectionoccur.C.RCSColdLeg temperaturewilldecreaserapidlywhenLowHeadSIPumpsarestartedandSIflowisinitiated.

D.RCSColdLeg temperaturewilldecreaserapidlywhenSG depressurizationandSI Accumulatorinjectionoccur.

60 2007NRCExamRO61.Giventhefollowingplantconditions:*ALOCAhas occurred.*Thecrewis performingactionscontainedinEOP-2.0, Loss of Reactor or Secondary Coolant.*Thefollowing conditionscurrentlyexist:Integrity-RED

• Containment-RED*Subcriticality

-ORANGECoreCooling-ORANGE Inventory-YELLOW*HeatSink-YELLOWWhichONE(1)ofthe followingdescribesthecorrect procedureflowpathforthese conditions?

A.EOP-17.0 , ResponsetoHigh Reactor Building Pressure ,followedby EOP-16.0 , Response to Imminent Pressurizer Thermal Shock Condition.B.EOP-16.0, Response to Imminent Pressurizer Thermal Shock Condition , followedbyEOP-17.0, ResponsetoHigh Reactor Building Pressure.C.EOP-14.1

, Response to Degraded Core Cooling ,followedby EOP-16.0 , Response to Imminent Pressurizer Thermal Shock Condition.

D.EOP-16.0 , Response to Imminent Pressurizer Thermal Shock Condition , followedbyEOP-14.1

, Response to Degraded Core Cooling.61 2007NRCExamRO62.Giventhefollowingplant conditions

• A reactortriphas occurredduetoalossofoffsite power.*ThecrewisperformingactionsofEOP-1.4, Natural CirculationCooldownwithSteamVoidinVessel.*Duringtheevent,RCPsealcoolingwaslost,but subsequently restored.*The operatingcrewis preparingtoinitiatetheRCScooldown.Thefollowing conditions are indicated:*RVLlSNRlevelis89%

.RCSsubcool ingis60°F.*PZRLevelis72%andstable.WhichONE(1)ofthefollowing actionsisrequiredin accordancewithEOP-1.4?

A.UsePZRHeatersas necessary to saturatePZRwaterand continueinEOP-1.4.

B.Initiate SafetyInjectionandgotoEOP-1.0

, ReactorTripOr Safety Injection.C.StartaRCPandgotothe applicableportionofthe appropriate GOP.D.ReturntoEOP-1.3

, Natural Circulation Cooldown.62 2007NRCExamRO63.Giventhefollowingplantconditions:*ALOCAhasoccurred.DuetolowRHRSumpLevel

,thecrewhas transitionedfromEOP-2.2, TransfertoColdLeg Recirculation,toEOP-2.4 , Loss Of Emergency Coolant Recirculation

.*All automatic actionsoccurredasdesigned

.*TwoCharging pumpsandtwoRHRpumpsarerunning.BothRBSprayPumpsarerunning

.RHR , Charging ,andRBSpraypumpampsandflowarestable

.RWSTlevelis approximately5%andcontinuestolower.WhichONE(1)ofthe followingdescribeshowtheCharging

,RHR,andRBSpraypumpsshouldbe operated in accordance with EOP-2.4?ChargingPumpsRBSprayPumpsRHRPumps A.StopBOTHLeaveBOTHrunningLeaveBOTHrunning B.StopONEStopBOTHStopONE C.StopBOTHStopBOTHStopBOTH D.LeaveBOTHrunningLeaveBOTHRunn ingStopONE 63 2007NRCExamRO64.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 cooldownratesabove100°Fperhourmay potentiallyresultin pressurized thermal shocktothepressurizer.C.LossofSG inventory may ultimatelyresultintheRCS Pressure SafetyLimitbeing exceeded.D.LossofSG inventorymay ultimatelyresultinthe Reactor Core SafetyLimitbeing exceeded.64 2007NRCExamRO65.WhichONE(1)ofthefollowing describesthestatusofRB ventilationandRBCU'suponcompletionoftheactions containedinEOP-17.2

, Response to High Reactor Building Radiation Level?A.RBPurgeisolatedAllRBCUfansin SLOWB.RBPurgeisolatedRBCUfansselectedonswitchRBCUTRAIN AlBEMERG,runn ing in SLOW C.RBMiniPurgeinserviceAllRBCUfansin SLOWD.RBMiniPurgeinserviceRBCUfansselectedonswitchRBCUTRAIN AlBEMERG,runningin SLOW 65 2007NRCExamRO66.Inaccordancewith OAP-100A, Communication

,whichONE(1)ofthefollowing communicationsshouldusethephoneticalphabet?

A.Communicationsinvolvingsafetysystemtrains

.(Train Alpha)B.Communications involving manipulationofplant components

.(AlphaCharging Pump)C.Communications describing Conta inmentIsolation(PhaseBravo)D.All communicationsthatarenot'informationonly'

.66 2007NRCExamRO67.Giventhefollowingplantconditions:*Theplantisat46%

power and increasing lAW GOP-4A , Power Operation (Ascending)at3%perhour.*Alossof Feedwater occurs.*AllthreeS/GNRlevelsareat5%andlowering

.*Itisnow60 seconds later.WhichONE(1)ofthefollowingistheexpectedresponseoftheATWSMitigation System Actuation Circuitry (AMSAC)?'A.AMSACwillNOT actuate becauseitisnotarmed.

B.AMSACwillTRIPthereactorand STARTtheEFWpumps.C.AMSACwillNOT actuate becausethetimedelayonreactor powerhasnottimed out.D.AMSACwillTRIPthemain turbine and STARTtheEFWpumps

.67 2007NRCExamRO68.Giventhe following plant conditions:*AnRCSleakisin progress.*Thecrewis performing the appropriate AOPforthe plant condition.

• Letdown is isolated.*Charging flow is maximized.*RCS pressure is 1990psigandlowering

.*Reactor Building pressureis1.8psigandrising.

• Pressurizerlevelis18%andlowering.

• VCTlevelis15%and lowering.WhichONE(1)ofthe following describes the statusofthe plantandtheaction required?A.AnRPS setpointhasbeen exceeded.Tripthe Reactor and initiate Safety Injection when immediate actions of EOP-1.0havebeen completed.B.AnRPS setpoint has been exceeded.Tripthe reactor and concurrently perform actionsofthe in-use AOP when immediate actions of EOP-1.0havebeen completed.

C.AnRPS setpoint has NOT been exceeded ,Tripthe Reactor , perform the immediate actions of EOP-1.0,theninitiate Safety Injection.D.AnRPS setpoint has NOT been exceeded ,Tripthe Reactor, perform the immediate actions of EOP-1.0 , continue to implement the AOP concurrently, then initiate Safety Injection when Pressurizerlevelis<12%.

68 2007NRCExamRO69.Theunitisat100%

power.Allsystemsareinnormal alignments

.WhichONE(1)ofthefollowingactivitiesrequiresentryintoa technical specificationLCOaction statement?

A.CCWPumpB mechanicalsealrepair.

B.ChargingPumpAremovalfromserviceforoilchange.

C.BoricAcid TransferPumprecircvalveleakrepair

.D.RHRHeat ExchangerDischargeflowcontrolvalverepair

.69 2007NRCExamRO 70.WhichONE(1)ofthe following describes the MINIMUM Source Range Nuclear Instrumentation requirement that mustbemet prior to off-loadingfuelfromthereactor vessel?VisualincontrolroomAud ibleincontrolroom AudibleinRB A.C.D.1 2 2 2 1 , 1 2 2 1 1 1 2 70 2007NRCExamRO71.Giventhefollowing information:*A27yearoldnewV.C Summer employeehasafully completedNRCForm4anda2007 radiation exposurehistoryasfollows:*2650milliremfrom previous employmentwithProgressEnergyin2007.*110 millirem sincebecomingaV.C

.Summer employee.WhichONE(1)ofthe followingdescribestheMAXIMUM ADDITIONALexposuretheemployeemayreceivepriortoreachinghis MAXIMUM AdministrativeDoseControl Limit,includingany applicable extensions

, lAW HPP-0153 , Administrative Exposure Limits?A.1240milliremB.1350milliremC.2240millirem D.2350m illirem 71 2007NRCExamRO72.Giventhefollowingplantconditions:*AGeneral Emergency exists.TheTSCis manned.*AvalveintheAuxBuildingmustbeclosedtoprevent damage to valuablesafetyrelated equipment.*Radiationlevelsare extremely high.WhichONE(1)ofthefollowingdescribesthemaximumdosethatisallowedtoperfo rmthisoperationandwhose permission isrequired?Anindividualmayreceive

...A.Upto10Remwith permissionfromtheDutySSB.25Rem,ormore

, w ith permissionfromtheDutySSC.Upto10Remwith permissionfromtheED D.25Rem ,ormore,with permissionfromtheED 72 2007NRCExamRO73.Giventhefollowing plant conditions:*Areactortripand safetyinjectionhaveoccurred.

Off-Site powerislost subsequent to safety injection actuation.

• Equipment failures during performanceofEOP-2.0, Loss of Reactor or Secondary Coolant,resultedinthefollowingconditions:*Bus1DAis de-energizedduetoafault.*CSF Status Trees indicateasfollows:

• Subcriticality*CoreCooling*HeatSink*Integrity*Containment Inventory GREEN ORANGE RED GREEN YELLOW YELLOWWhichONE(1)ofthe followingdescribesthe requirementforCritical Safety FunctionStatusTree Monitoring in accordance with OAP-103.04, EOPIAOPUser'sGuide?

A.Continuous monitoringisrequired.

B.Monitorevery5-10 minutesunlessachangeinstatusoccurs.C.Monitorevery10-20 minutes unless achangeinstatus occurs.D.Monitoredfor information only.73 2007NRCExamRO74.Giventhefollowing plant conditions:

T=OAfireis occurringintheAuxBuilding436'.T+2FireBrigade Leaderreportstothescene.T+15 NotificationofUnusualEventdeclared.

In accordance with EPP-013 , Plant Fire ,who,bytitle,is coordinatingthefirefightingeffortswiththeFire Brigade Leader?A.Shift Supervisor B.Emergency Direc torC.OSC SupervisorD.HealthPhysicsShift Leader 74 2007NRCExamRO75.Giventhefollowingplantconditions:*TheUnitisinMode5

.RCSDrainDowntoMidLoopisinprogressin preparationforweldingonaHotLegopening.*RHRPumpAisinservice

.*Duringthedraindown,RHRampsand discharge pressurebeginfluctuating erratically.*Thecrew enters AOP-115.1,RHRPumpVorlexing.*The drain-downisstopped.WhichONE(1)ofthefollowing describestheFIRSTactionthatwillberequiredinaccordancewith AOP-115.1?A.ReduceRHRflow.B.AligntheRHRPumptotheRWST.C.RaiseRCSlevel.D.Ventthe operatingRHRloop.75