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See also: [[followed by::IR 05000400/2008301]]
See also: [[see also::IR 05000400/2008301]]


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Revision as of 12:15, 12 July 2019

March 05000400/2008301 Final SRO Written Examination & References
ML081140054
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 03/10/2008
From:
NRC/RGN-II
To:
Duke Energy Corp
References
50-400/08-301
Download: ML081140054 (89)
v • d • e


See also: IR 05000400/2008301

Text

{{#Wiki_filter:Final Submittal(BluePaper) Zto8-3 0/IIV It-hA.t LtCeIlse.3/JO- t'512,(/241"8FINALSRO WRITTEN EXAMINATION AND REFERENCES ES-401 Site-Specific SRO Written Examination Cover Sheet Form ES-401-8 u.s.Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Certification Applicant's Signature All workdoneonthis examinationismyown.Ihave neithergivennorreceivedaid. IUsethe answersheetsprovidedto document youranswers.Staplethis cover sheetontopofthe answersheets.Topassthe examinationyoumust achieveafinalgradeofatleast80.00 percentoverall,with70.00 percentorbetteronthe SRO-only itemsifgiveninconjunctionwiththeROexam;SRO-onlyexamsgivenalonerequireafinalgradeof80.00 percenttopass.Youhave8hoursto complete the combined examination,and3hoursifyouareonly takingtheSROportion. I I I I I I , I I I I I I I I I I I I I I I I I I I I I I I 

I I I/Points I/Points//Percent Reactor Type: W[K]CE D BWD GE DFinishTime:

Instructions Facility/Unit: HARRIS PLANT Applicant Information I D II[XJ III D IV D Name: Date: 3/21/08 Region:StartTime: Results RO/SRO-OnlylTotal Examination Values Applicant's Scores Applicant's GradeES-401,Page31of33 Name: 1.Initial conditions: Harris 2008 SRO Exam Rev FINALForm:0Version:0*Theplantisat 80%Reactor powerand rampingUPat 1/2%per minute.*Tave and Tref are matched.*Rod Controlisin AUTOMATIC. Current conditions:

  • ONE (1)Control Bank0Rodhas just droppedandis stuck at 170 steps.*All Other Control BankORodsare currently indicating

206 Steps.Assuming NO operator action is taken, which ONE of the following describes the DEMAND forrod motion,andthe effect on Axial Flux Difference (AFD)for the channel NEAREST the control rod problem?ROD MOTION AFDEFFECT A.Outward Less Negative B.Outward More Negative C.Inward Less Negative D.Inward More NegativeThursday,March 20,200810:36:58AM 1 Harris2008SROExamRevFINAL 2.InitialPlant Conditions:*TheplantisSolid. Current Plant Conditions:*A controller failurehascaused1CS-38,Letdown PressureControlvalve,toshut.*Thecrewhas justenteredAOP-019, Malfunction of RCSPressure Control.WhichONEofthe following describes the effectofthis malfunctiononRCS pressure and the actions required lAW AOP-019 to mitigatethisevent?A.RCS Pressurewillincrease; EnsuretheRCPSeal WaterReturnvalvesareopen B.RCS<Pressurewillincrease; Secure the running CSIPC.RCS Pressure will decrease;EnsuretheRCPSeal WaterReturnvalvesareshut D.RCSPressure will decrease;IncreasechargingflowtoraiseRCS pressureThe plant is operatingat100%powerwhenonecontrolroddropsfullyintothecore causing PowerRangeN-41toreadlowerthanthe other powerrangechannels. WhichONEof the followingistheexpectedQPTR response overthenexttwotosixhoursandwhy? A.QPTR will increaseduetothebuildupofXenoninthe droppedrod'sfuel assembly.B.QPTR will decreaseduetothebuildupXenoninthe droppedrod'sfuel assembly.c.QPTR will increaseduetothechangein temperatureinthe droppedrod'sfuel assembly.D.QPTR*wili decreaseduetothechange*intemperature.inthe droppedrod'sfuel assembly.Thursday,March20,200810:36:58AM 2 Harris 2008SROExamRev FINAL 4.Given the following:*A plant startupisin progress.*Reactor poweris20%.*"B"RCPtrips. Which ONE of the followinq describes the effectonthe reactorand"B"loop Tave?A.Reactor remainsatpower;Loop"B" Tave lowersdueto Thot loweringtothe valueofTcold.B.Reactor remainsatpower;.Loop"B"Taverisesduetothe decreased flowinthe"B"loop. C.Reactor automatically trips;Loop"B" Tave lowersdueto Thot loweringtothevalueof Tcold.D.Reactor automatically trips;Loop"B" Tave risesduetothe decreased flowinthe"B"loop. A.Lowering the setpoint of the Letdown Temperature Control Valve, TCV-144,by10 of.B.Raising the flow settingofthe boric acid flow controllerby2 turns during a blended makeuptotheVCT.C.Raising the setting of the blended makeup flow totalizerby100 gallonstotalduring a blended makeup to theVCT.D.Lowering the setting of the boric acid batch totalizer by20 gallons total during a blended makeup to theVCT.Thursday,March 20,200810:36:58AM 3 Harris2008SROExamRevFINAL 6.Which ONE of the followingsetsof parameters and conditions will satisfy the interlockstoopenthe ResidualHeatRemoval Hot Leg Suctionvalves(1RH-1, 2,39,and40)?A.RCS temperatureis345 of, RCS pressureis365psig, RHR dischargetoCSIPvalves,1RH-25and1RH-63,areshut, RHR suction from RWSTvalves,1RH-322and1RH-323,areshut. B.ReS temperature is 335 of,RCSpressure.355psig, RHRdischarge toCSIPvalves,1RH-25and1RH-63,areshut,-RHRsuction from RWSTvalves,1RH-322and1RH-323,areshut. C.RCStemperatureis 345 of, RCS pressure 355psig, RHR suction fromRWSTvalves,1RH-322and1RH-323,areshut. RHRsuction from Containment sump valves181-300,301,310,and311areshut.D.RHR temperature is 335°F, RCSpressureis 365psig, RHR discharge toCSIPvalves,1RH-25and1RH-63,areshut, RHR suction from Containment sump valves181-300,301,310,and311areshut.Thursday,March20, 200810:36:58 AM 4 Harris 2008SROExamRev FINAL 7.Given the following:

  • The plantisin Mode 4.*RHR Train"A"is in service.*RHR Heat Exchanger Bypass Valve1RH-20isin

automaticwiththe output at 40%to maintain3750GPM.*RHRHeat Exchanger outlet valve 1 RH-30demand positionisset at30°k>.*The Instrument Air supplylineto RHRHeat Exchanger Outlet Valve 1 RH-30<becomes severed.andis completely detached.*No other air operated valves are impactedbythe failure.Which ONE of the foUowingdescribes the RHRsystemparameter changesfromthe initial steady state condition to final steady state condition? A.B.c.D.RHRHX Outlet Temp Higher Higher Lower Lower Total RHR flow Lower Higher Higher LowerThursday,March20, 200810:36:58AM 5 Harris 2008 SRO Exam Rev FINAL 8.Given the following:*A reactor trip and safety injection have occurred.*RCS pressureis1OOOpsigand lowering.*"A"*.CSIP fails to operate.*All other equipment operates as designed.Which ONE of the following describes the expected MCB Charging Flow indication (FI-122.1), and the Safety Injection flow indication (FI-943)?A.MCBCharging flow 0 gpm;Safety Injection flow is approximately 600 gpm B.MCBCharging flow0gpm;Safety Injection flow is approximately 450 gpm C.MCB Charging flow approximately150gpm;Safety Injection flow is approximately 150 gpm D.MCBChargingflow approximately 150 gpm;Safety Injection flow is approximately 450 gpmThursday,March20,200810:36:58AM 6 Harris2008SROExamRevFINAL 9.Giventhe following:*"A"Train equipmentisinservice.*A ReactorTripoccurs.*All equipment is operatingasdesigned.*Thecrewis performingactionsofPath-1.

  • Conditionsareasfollows:PZRpress.CNMTpress.

1865psig2.9psigCHII1865psig3.1psig CHIli--1845psig3.1psig CH IV NA2.9psig WhichONEofthe following describesthestatusOftheCharging Safety Injection Pumps?A.BothCSIPsarerunningduetoSIsignalonlowPZRpressure.B.BothCSIPsarefunningduetoSIsignalonhigh Containment pressure.C.Only"A" CSIPisrunning,but"B"CSIPwillbestarted automaticallyifthe additional requiredPZRpressuretransmitterreachestheSI actuation setpoint.D.Only"A"CSIPis running, but"B"CSIPwillbestarted automaticallyififthe additional requiredCNMT pressure transmitterreachestheSI actuation setpoint.Thursday,March20,200810:36:58AM 7 Harris2008 SROExamRevFINAL 10.Initial Conditions:*Withtheplantoperating.at 1000/0powerand all equipmentinitsnormal lineup, the ROtakestheReactorTripswitchtotheTRIPposition.Currentplant conditions are:*ReactorTripBreaker"A"Redindicationexists.

  • Reactor Trip BreakerB"Greenindicationexists.
  • ReactorPoweris4%andlowering.*RodbottomlightsarelitwiththeexceptionofFOURControl

BankD rods.Their positionsareasfollows:*H-8-16steps*K-2-220steps*M-12-8steps*M-8-20steps WhichONEofthefollowingdescribestheconditionofthereactor,andtheactionthatwillberequired?A.The reactoristripped;Performnormal RCSborationforthestuckrodsasdirectedbyEPP-004referencingOP-107,ChargingandVolumeControlSystem.B.The reactoristripped; Initiate emergencyborationforthestuckrodsasdirectedbyEPP-004referencing AOP-002, Emergency Boration.C.The reactorisnottripped; Manually insertcontrolrodsinaccordancewithFRP-S.1untilallrodsareon bottom.D.The reactorisnottripped; Initiate emergencyborationforthestuckrodsinaccordancewithFRP-S.1until adequate ShutdownMarginisverified.Thursday,March20,200810:36:58AM 8 Harris 2008 SROExam Rev FINAL 11.Giventhe following:

  • The plantisat 1000/0 power.*A PressurizerPORVhasa slow leak through the seatordisk.*The respective

PORV isolation valve cannotbeclosed.*ALB-009-8.-1, PRESSURIZER RELIEF TANK HIGH-LOW LEVEL PRESS OR TEMP, is actuated.*PRTLevelis73%.

  • PRT Temperatureis128 of.*PRT Pressure is6.3 Psig.Which ONEiofthefollowing

parameters is causingthealarm,andwhich ONE of the followingisthe actionrequiredtobe performed from OP-100, Reactor Coolant System, Section8,I nfrequentOperations? A.Pressure;Vent thePRT as necessarytocontrol pressure.B.Pressure;Drainthe PRTas necessarytocontrol pressure while maintaining level within the normal-band. C.Temperature; Recirculate the PRT contents through the RCDT Heat Exchanger to lower temperature. D.Temperature; Drain PRT to thelowendof the normalbandandthen refillwith demineralized water to lowertemperature.Thursday,March20, 200810:36:58 AM 9 Harris 2008 SRO Exam Rev FINAL 12.Given the following:

  • The plantisat 1000/0 power.*The temperature

input to Letdown Heat Exchanger CCW flow control valve TCV-144, fails low.Which ONE of the following describes the impactonthe plantandthe action that is requiredbythe appropriate Annunciator Panel Procedure (APP)?A.High CCW flow to Letdown Heat Exchanger; Place TCV-144in manual and adjust flow to restore normal cooling.B.High CCWfiow to Letdown Heat Exchanger; Isolate letdown and place Excess Letdown in service.C.High temperature letdown diversion to VCT;Place TCV-144 in manual and adjust flow to restore normal cooling.D.High temperature letdown diversion to VCT;Isolate letdown and place Excess Letdown in service.13.Given the following:*A reactortrip has occurred from 1000/0 power.*Pressurizer pressure is 2050psigand lowering.*Pressurizer levelisrisingrapidly.

  • Containment

pressureis1psigand slowly rising.Assuming NO operator action, whichONEofthe following could have caused the event in proqress?A.Master Pressure Controller PT-444 output failed LOWB.Both Pressurizer Spray Valves failed OPEN C.Master Pressure Controller PT-444 output failed HIGH D.Small break LOCAon an*RCSHotLegThursday,March20, 200810:36:59AM 10 Harris2008SROExamRevFINAL 14.Given*thefollow.ing:*A reactortriphasoccurred.

  • Safety Injection is actuated.*All actionsrequiredinPath-1havebeen

taken.*AllRCPsarerunning.*RCS pressureis1450 psigand stable.*Sifiowis150GPM.*Containment pressure Is4.5psigand slowly rising.*SG pressuresare1 050psigandstable. Which ONE of the following describes the plant condition upon transition from Path-1?A.RC.Ps should NOTbetripped.SGsare required for subsequentRCSheatremoval. B.RCPsshould NOTbetripped.SGsare NOT required for subsequentRCSheatremoval.C.RCPs shouldbe.tripped. SGs are-required for subsequentRCSheatremoval. D.RCPsshouldbe tripped.SGsare NOTrequiredfor subsequent RCS.heat removal.Thursday,March20,200810:36:59AM 11 Harris2008SROExamRevFINAL 15.InitialPlant Conditions:*Theplantwasat100%power. Currentplantconditionsare:*ALossof Off-sitePoweroccurs.*Bus 1A-SAislockedout.*All other equipmenthasoperatedasdesigned.

  • Diesel loading sequenceiscomplete.*RCS pressureis2180psig.

Assuming NO operatoractionhasbeentaken,whichONEofthefollowing describesthestatusofthePZRHeaters?A.ALLPZR BackupHeatersare DE-ENERGIZED.B.GroupBisthe onlyPZRh.eatergroupENERGIZED.C.GroupCis.theonlyPZR heater group ENERGIZED. D.Groups BandCaretheonlyPZRheatergroups ENERGIZED.Thursday,March20,200810:36:59AM 12 Harris 2008SROExamRev FINAL 16.Which ONE of the following describes the characteristicsofa design basis Large Break LOCA twenty (20)minutesintothe event?A.RCS temperatureisat saturation temperature for intact SG pressure;RCSpressure is stable below normal SI accumulator pressure, but above RHR pump shutoff head.B.ReS temperature is at saturation temperature for intact SG pressure;RCSpressure is stable belowRHRPump shutoff head.C.RCS temperature is below saturation temperature for intactSG pressure;Res pressure is stable below normal SI accumulator pressure, but above RHR pump shutoff head.D.RCS temperature is below saturation temperature for intact SGpressure; RCS pressure is stable below RHRPump shutoff head.*Theunitisat100 %power.*Unit electrical.aliqnmentisnormal.*Aux Bus1D deenergizesandislockedout. Which ONEofthe followingloadswill de-energize and automatically re-energize?A."A".NSW*Pump B."B" NSW PumpC."A" CSIPD."B" CSIP Thursday, March20,200810:36:59AM 13 Harris 2008SROExamRev FINAL 18.Given the following: eTheplantis operatingat30%reactor power, steady state.e I&Cotechniciansarepreparing to perform a calibration on Power Range Channel N-41..eOneI&C technician mistakenlypullsthe control power fusesonN-42.e Realizing his mistake, he reinserts the fuses forN-42andthenpullsthe control power fuses for the correctchannel,N-41. Which ONE of the following describes the statusofthe reactor aftertheN-41 fuses were pulled and which bistable(s)inN-42wouldbe tripped?A.The reactor is tripped;PRPositiveRateTripand PRNegativeRateTrip.B.The reactor is tripped;PRPostive Rate-Trip ONLY.C.The reactor is NOT tripped;PR PositiveRateTripandPR NegativeRateTrip.D.The reactor is NOT tripped;PRPositiveRate Trip ONLY 19.Giventhe following: e Pressurizer Pressure Protection Channel PT-455hasfailed off-scale HIGH.eNO Operator actionhasbeen.taken. Which ONE of the following identifies the MINIMUM additional channels required to meettheESF andRPS actuationlogicto initiate a reactortripand safety injection onPressurize rPressure?A.Reactor Trip-1;Safety Injection-1 B.ReactorTrip-1

Safetylnjection-2

C.ReactorTrip- 2;Safety Injection-1 D.Reactor Trip..2;Safety Injection-2Thursday,March20,200810:36:59AM 14 Harris 2008 SRO Exam Rev FINAL 20.Given the following:*A LOCA has occurred.*RCS.pressure is 200 psig.*"A" Containment Spray Pump is Out of Service.*Containment pressure is 12 psigand slowly increasing.

  • Train"B" PhaseAhas failed to actuate.*Normal Containment

Purge was in service atthetime of the LOCA.*The Containment Ventilation Isolation Signal (CVIS)fails to actuate.*All other ECCS equipment is running as required.Assuming no action by the crew, which ONE of the following describes the effect on the plant?A.Containment Normal.PurgeMakeup fanswilltripand their associated dampers SHUT.B.Offsite dose consequences. will exceed the guidelines of 10CFR100.C.Normal Containment Purge Makeup valves (1CP-6and9)will remain OPEN.D.Only half of the Containment penetrations required for containment isolationwillbe isolated.21.Given the following:

  • The plantisat20%

power.*Rod Controlisin AUTO.*The operating crew is preparing to stopRCP1 C'duetorising vibration. Assuming that reactor power is maintained at200JO, which ONE of the following describes the expected indications on Loop1and Loop 3 flowrates whenRCP1Cis stopped?A.B.C.D.Loop 1 Flowrate increaseto11 0°/0 increaseto110%increase to 1200/0 increase to 1200/0 Loop 3 Flowrate decreases to ooJO and stabilizes decreasesto0%then increases to 100/0 decreases to 00/0 and stabilizes decreasesto0%then increases to 10%Thursday,March 20,200810:36:59AM 15 Harris 2008SROExamRev FINAL 22.Given the following:

      • The plant is at 600/0 powerduringaplant

startup.Steam Dumpsareinthe Tave modeofcontrol. First Stage Pressure TransmitterPT-446failshigh. Assuming the reactor remains atpower,whichONE of the following describes the effectonthe steam dump system?A.Steam Dumpswillreceivean arming signal.B.Steam Dumpswillreceivea modulation(open)signal. C.Steam DumpswillNOTarmifrequired. D.Steam DumpswillNOT modulateifrequired. 23.Given the following:

  • The crew is performing

EPP-004, Reactor Trip Response.*.Natural circulation verificationisin progress.*Core Exit ThermocouplesG2and K5havefailedduetoopen circuits.With these open circuit failures,theinputfrom these thermocouplestothe Inadequate Core Cooling.Monitor(ICCM)willbeandthe subcoolng margin calculated bylCCM will be_A.failed low;higher B.failed low;unaffected C.failed high;lower D.failed high;unaffectedThursday,March20, 200810:36:59AM 16 Harris2008SROExamRevFINAL 24.Initial.Conditions:

  • Containment

Cooling isintheNormalCoolingModeofoperationwithTrain"A"inservice.

  • Containment

temperaturehasbeenslowlyrising.CurrentConditions:*ThecrewhasplacedtheContainmentCoolingsysteminMaximumCooling Mode per OP-169, ContainmentCoolingSystem.

  • Containment

temperatureisnowlowering. WhichONEofthefollowingidentifiestheMINIMUM temperatureatwhichaTechnical Specification action statementmustbeenteredandtheexpected alignmentforthe ContainmentCoolingSystem? A.118°FBOTHfans inAH-3andAH-4inhighspeedANDONE(1) faninAH-1andAH-2inhighspeed. \B.118°FBOTHfansinAH-3 andAH-4inhighspeedANDBOTHfansinAH-1andAH-2inhighspeed.C.120 OF BOTHfansinAH-3andAH-4inhighspeedANDONE(1)faninAH-1andAH-2inhighspeed.D.120 OFBOTHfans inAH-3andAH-4inhighspeedANDBOTHfans inAH-tandAH-2inhighspeed.Thursday,March 20,200810:37:00AM 17 Harris2008SROExamRevFINAL 25.Giventhe following:*The plantisat100%power.

    • VCT level ChannelLT-112 fails high.Assuming NO operator action, whichONEofthefollowing

describes the function(s) lostduetothisfailure? A.ONl YDiverttoRHTwillbe disabled B.ONLY AutoSwapover from RWSTwillbedisabled.C.Auto Swapover from.RWSTANDAutoMakeupwillbe disabled.D.Divert toRHT AND Auto Makeupwillbedisabled.Thursday,March20, 200810:37:00AM 18 Harris 2008 SROExamRevFINAL 26.Initial conditions:*The plant isat1 000/0 power.*Train"B" ContainmentFanCoolingisinservice. Current conditions:*A Safety Injectionsignalhasoccurred.*All equipmentisoperatingas designed.Which ONE of the following describes the operation of Containment Cooling?OnefanineachFan CoolerUnitis operatingin...A.LOW speed;Normal Service Water aligned.B.HIGH speed;Normal Service Water aligned C.LOW speed;Emergency Service Water alignedD.HIGH speed;Emergency Service Water alignedThursday,March20, 200810:37:00 AM 19 Harris2008 SROExamRevFINAL 27.Initial conditions:*"A"BoricAcidpumpis under clearance for motor replacement. Current conditions:*1 B-SBEmergency Safety Bus locksoutduetoan 86UV failure.*Thecrewis performing an EmergencyBorationin accordance with AOP-002, Emergency Boration, due to.a secondary load rejection.*The ROperformstherequiredvalve alignment to provideaboration source.Which ONE of the following describestheaction and/or verificationrequiredto ensurethatthe requiredborationflowis achieved?A.Verifyaminimumof30GPMon FI-110,EmergencyBorationflow. B.Verify a minimum of 30GPM on FI-113,BoricAcidflow.C.Adjust FCV-122 as necessarytoachievea minimumof30GPM onFI-122.1, Charging Header flow.D.Adjust FCV-122 as necessarytoachievea minimumof90GPMonFI-122.1, Charging Header flow.Thursday,March20, 200810:37:00 AM 20 Harris 2008SROExamRev FINAL 28.Given the following:

  • The plant is in Mode 5.*An RCSleak and lossofRHR occurs..*The crew is performing

actions of AOP-020,LossofRCS Inventory or Residual Heat Removal While Shutdown.*The crew is aligning to provideRCSMakeupusingCSIP flow in accordance with section 3.6, EstabHshingSI Following a MajorRCSLeak.Which ONE of the following describes the required actions to provide RCSmakeup in this condition? A.Start ONE (1)CSIP;initiate flow thoughtheBIT B.Start ONE(1)CSIP; Initiate flowthoughthenormal charging line C.Start TWO (2)CSIPs;Initiate flow thoughtheBIT D.Start TWO (2)CSIPs;Initiate flowthouqhthenormal charging lineThursday,March20,200810:37:00AM 21 Harris 2008SROExamRev FINAL 29.Initial Cond itions:*Surveillance testingisin progress on Containment SprayTrain"A".*"A" Containment Spray Pumpisrunning.

  • 1CT-24-SAand.1CT-25-SB, Containment

Spray Eductor Test Valves,areopen for.testing.*1 CT.:.50-SA,ContainmentSpray Pump 1A-SA Discharge Valve, is closed.Current conditions:*A LOCA occurs.*RCS pressureis600psig.

  • Containment

Pressure is 10.5psig.Which ONE of the following correctlyliststhe position of the Containment Spray Eductor Test Valvesandthe 1A-SA Discharge Valve for the current plant conditions? A.B.C.D.1CT-24-SA and 1CT-25-SB OPEN CLOSED OPEN CLOSED 1CT-50-SA OPEN OPEN CLOSED CLOSEDThursday,March20,200810:37:00AM 22 Harris2008SROExamRevFINAL 30.Giventhe following:TheplantisinMode1. 12:00 ContainmentSprayPump1A-SAdeclared INOPERABLEduetoafailed surveillance. 12:27 ContainmentSprayPump1B-SBalsodeclared INOPERABLEduetothe results ofacommoncausefailureanalysis. 14:21 ContalnrnentSprayPump1A-SAreturnedto OPERABLE status.14:40 ContainmentSprayPump1B-SBreturned to OPERABLE status.WhichONEofthefollowingdescribestheTechnical Specificationrequirementsforoperationoftheplant? Actionstoinitiateaplantshutdownmustcommencenolaterthan...A.12:27;The shutdown maybeterminatedno earlierthan 14:21.B.12:27;.The shutdownmaybeterminatednoearlierthan14:40.C.13:27;Theshutdown maybeterminatedno earlierthan14:21.D.13:27;.The shutdown maybeterminatednoearlierthan14:40.Thursday,March20, 200810:37:00 AM 23 Harris2008SROExamRevFINAL 31.Giventhe following:

  • The plant is operatingat100%power.*A failure of thePT-444 inputtoPK-444A, Pressurizer

Pressure Master Controller, caused actual pressurizer pressure to decreaseto2190psig.

  • PK-444Ahasbeenplacedin

MANUAL..Which ONE of the following describestheactionrequiredtoreturn pressureto2235 psig?A.Decrease the controller output.B.Increase the controller output.C.Lower the pressure setpoint adjustment.D.Raisethe pressuresetpoint adjustment.Thursday,March20,200810:37:00AM 24 Harris 2.008SROExamRevFINAL 32.Giventhe following:*Theunitisin Mode 6.*Refueling activitiesareinprogress.*Afuel assemblyhasbeenrupturedduringremovalfromthecore.

  • Radiation levelsarerising steadilyandare currentlyasfollows:*REM-01 LT-3502A-SA,CnmtRCSLeakDetectionMonitor,isinHIGH

ALARM*REM-01 LT-3502B-SB, Cnmt Pre-EntryPurgeMonitor,isinHIGH ALARM WhichONEof thefoHowing describesthesystemisolationsignal(s),ifany,thathave been automaticallyinitiated,andactionrequiredin' accordance with AOP-013, Fuel Handling Accident?A.ONLY a Containment Pre-EntryPurgeisolationsignalhasbeeninitiated.Performan evacuation from Containment.B.BOTHNormal ContainmentPurgeAND Containment Pre-Entry Purge isolation signalshavebeeninitiated. Perform an evacuation from Containment. C.ONLY a Containment Pre-EntryPurgeisolationsignalhasbeeninitiated. Dispatch Radiation Protection to determine if Containment Evacuationisrequired.D.BOTHNormal ContainmentPurgeAND Containment Pre-Entry Purge isolation signalshavebeeninitiated. Dispatch Radiation Protection to determine if Containment Evacuationisrequired..Thursday,March20,200810:37:00AM 25 Harris 2008SROExamRevFINAL 33.Given the following:

  • The plantisat100%power.*A transient on SGlevelrequireda reactortrip,butthe

reactordidnottrip.

  • The crew is performing

FRP-S.1, Response To Nuclear Power Generation /ATWS.*The crew notesthatthe Pressurizer pressureis2350psig.

  • Controlrodsare inserting in AUTO.*All Pressurizer

PORVvaive position indicatinggreenlightsareonandred lightsareoff.Which ONE of the following actionsarerequiredinrelationto thePZR PORVs?A.Verify ONLY ONE Pressurizer PORVandBlockvalveOPEN; reduce pressuretolessthan 2135psig.B.Verify ALL Pressurizer.PORVsand Block valves OPEN;reduce pressuretoless than2135psig.c.Verify ONLY ONE Pressurizer PORV and Block valve OPEN;reduce pressuretolessthan2235psig. D.Verify ALL Pressurizer PORVsand Block valves OPEN;reduce pressuretoless than2235psig.Thursday,March 20,200810:37:00 AM 26 Harris 2008SROExamRev FINAL 34.Given the following:

  • The plant is at40%power.
  • Intermediate

Range ChannelN-35loses compensating voltage.*I&Ciscalied to investigate.

  • Priortoany actionbyI&C,a reactortripoccurs.

Which ONE of the following describes the expected Source Range responseinthis conditionandwhy?A.Source Range Instruments wilJ automatically energize prematurely; they must be manually de-energized until approximately 5 minutes post-trip to prevent damage to the detectors. B.Source Range Instruments will automatically energize prematurely; they must be manually de-energized until approximately 15 minutes post-trip to prevent damage to the detectors. C.Source Range Instrumentswillnot automatically energizewhenrequired; they must be manually energized approximately 5 minutes post-trip to preventalossof reactor power indication. .D.SourceRanqelnstruments wilJ not automatically energizewhenrequired; they must be manually energized approximately 15 minutes post-trip to preventaloss of reactor power indication.Thursday,March20, 200810:37:00AM 27 Harris 20'08SROExamRevFINAL 35.Initialplantconditions:*Theplant isinMode.6withRefuelinginprogress. Current plant conditions are:*Fuel movementhasstoppedduetoaproblemwiththeManipulator.*TheMainControlRoomhasbeeninformedthatinitial troubleshootingisinprogressontheManipulator.*The troubleshootingteamdesirestooperateTS-5,the TROLLEY INTERLOCKBYPASSswitchtopermitforwardand reversemotionofthetrolleywithoutthe grippertubeatitstoplimit. WhichONEofthefollowingdescribesthepermissionandconcurrence,ifany,required forthisaction?A.The No concurrenceis required.B.TheSRO-FuelHandlingmustapprovewiththe concurrenceoftheSSO.C.TheSSO mustapprovewithconcurrenceof the Manager-Mechanical Maintenance.D.The SSGmustapprove.Noconcurrenceisrequired.Thursday,March20,200810:37:00AM 28 Harris2008SROExamRevFINAL 36.Giventhefollowing:*Refueling isin progress.*A spent fuel assemblyisbeingmoved intheFuelHandlingBuilding(FHB)when it's damagedbycontactinga wallofthepool.*SpentFuelPoolarearadiation monitor RM-1FR-3566A-SAisinHIGHalarm.*SpentFuelPoolarea radiation monitor RM-1FR-3567B-SBisinALERT. WhichONEof thefollowingdescribesthe effectontheplant?A.ONLY"A"trainofFuelHandlingBuildingVentilationEmergencyExhausthasreceivedan automaticstartsignal.B.BOTH"A"and"B"trainsofFuelHandlingBuildingVentilation Emergency Exhausthavereceived automaticstartsignals. c.NEITHERtrainofFuelHandlingBuildingVentilationEmergencyExhausthasreceivedan automaticstartsignal,andmanualstartisNOTrequired. D.NEITHERtrainofFuelHandlingBuilding Ventilation EmergencyExhausthasreceivedan automaticstartsignal,butmanualstartisrequired byAOP-013, Fuel Handling Accident.Thursday,March20, 200810:37:01AM 29 Harris 2008SROExamRev FINAL 37.Given the following:*A Steam Generator Tube Rupture has occurred.*Off-Site powerhasbeenlost.

  • BothDG's are operatingasrequired.
  • Pressurizer

level indicates10%and lowering slowly.*All plant equipment hasrespondedas expected for the plant conditions. Which ONE of the following describes a plant concern during the performance of Path-2 for these conditions? A.Voiding in the inactive regionsoftheRCS duringtherapidRCS cooldown to target temperature.B.Loss of RCSsubcoolingduring depressurizationusingmainor auxiliary spray.C.Voidinginthe inactive regionsoftheRCS during depressurizationusingaPZR PORV.D.Lossof RCSsubcoolingdue.to the time required to cooldown to target temperature with condenser steam dumps unavailable.Thursday,March20,200810:37:01AM 30 Harris 2008SROExamRev FINAL*A reactortriphas occurred from 100°11>power.*All systems functioned as designed.Which ONE of the following describes the position ofvalvesassociatedwiththeMain Turbine?.A.ThrottleValves-CLOSED Valves CLOSED Reheat Stop Valves-OPEN B.Governor Valves-OPEN Intercept Valves-OPEN Reheat Stop Valves-CLOSED C.Throttle Valves-CLOSED Intercept Valves-CLOSED Reheat Stop Valves-CLOSED D.Governor Valves-OPEN Intercept Valves-CLOSED Reheat Stop Valves-CLOSEDThursday,March 20,200810:37:01AM 31 Harris2008 SROExamRevFINAL 39.Giventhe following:*ASteamLinebreakhasoccurredon"C"SG.*Thecrewhas performedactionscontainedinEPP-014,FaultedSGisolation.*SG"C" pressure is 50psig._.SG"C" WRlevelis off-scale low.*SG"A"and"B">NRlevelsarebeinqcontrolledat 250/0.*SG"A"and"B" pressures are approximately900psigandstable. WhichONEofthefollowing describestheactionrequired lAWEPP-014,andthereasonforthis action?A.IsolateAFWflow to SG"C";MinimizeRCScooldownand themassandenergyreleasefromthesteamline breakB.Isolate AFW flow toSG"C";Failureof componentsin"C"SGmayoccurduetothermalshock C.InitiateAFWflowtoSG"C"attheMINIMUM verifiable rate;Feedingthe"C"SGis requiredforcooldown,buthigh AFWflowratesmaycause an excessive RCScooldownrequiringanundesiredtransitionoutof EPP-014.D.Initiate AFW flowtoSG"C"atthe MINIMUM verifiable rate;Feeding.the"C"SG isrequired forcooldown,buthigh AFW flow r(3tesmaycause failure of SG"C" componentsduetothermalshockThursday,March20,200810:37:01AM 32 Harris2008SROExamRev FINAL.40.InitialPlant Conditions:eTheplantisat 1000/0 power.Current Plant Conditions: eAspuriousturbinetripoccurs. e TheC-8 interJockfailstooperate.eAll other plant equipmentsrespondsasexpected. Which ONE of the following describestheresponseoftheSteamDumpControl System (SDCS)andtheoverall effectonthe ReS temperature?A.SDCSwillcontrol temperatureusingthe Turbine Trip Controller; RCS temperaturewillbecontrolledatnormalno-load temperature. B.SDCSwili control temperatureusingtheLoadRejection Controller; Res temperature willbecontrolledatnormalno-load temperature.C.SDCSwillcontrol.temperatureusinqthe Turbine Trip Controller; RCS temperaturewillbecontrolledat approximately 3 degreesabovenormal no-load temperature.D.SDCSwill control temperatureusingtheLoadRejection Controller; RCStemperaturewillbecontrolledat approximately 3 degreesabovenormal no-load temperature.Thursday,March20,200810:37:01AM 33 Harris 2008SROExamRev FINAL 41.Given the following:

  • The Reactor is critical atthe*POAH.*The crew is preparing to perform a turbine startup lAW GP-005, Power Operation.

Which.>ONE of the following describes the expected rod height for Control Bank"0" rods lAW GP-005andthebasis for this band?A.Between 95.and115steps;Helps.ensurelR tripandrod stop bistable setpointsarenot reached before theycanbe blocked B.Between130and150steps; Helps ensureIRtripandrod stop bistable setpointsarenot reached before theycanbe blocked c.Greater than 95 steps;Minimum height required to remain above Rod Insertion Limit o.Greater than130steps;Minimum height required to remain above Rod Insertion LimitThursday,March 20,2008*10:37:01 AM 34 Harris 2008SROExamRev FINAL 42.Initial Conditions:

  • The plant isat1 00%power.*Testing isin progressonthe AFW system,*The"A"MDAFWpumpisrunningwiththe

MDAFW FCVs 200/0 open.Current Conditions:

  • Atripofboth

MFW pumps occurs.*ThelowestSGlevelsduring the transient were:*SG"A"=18%*SG"B"=24°Jb*SG"C"=28%Assuming NO operator actions have occured, which ONE of the following describes the currentstatus of the MDAFW Flow Control Valves (FCVs)and TDAFW pump for this event?A.B.C.D.MDAFW FCVs 20 0Jb Open 20%Open Fu*1I Open Full Open TDAFW Pump Running Secured Running SecuredThursday,March 20,200810:37:01 AM 35 Harris2008SROExamRevFINAL 43.Giventhe following:*The plantisat100%power.*An ExtrerneHl-HlIevelisreceivedin Feedwater Heater 1A.Which ONE of the following describes the impactontheunitandtheaction,ifany,thatisrequiredin accordance withOP-136, Feedwater Heaters?A.ONLY FeedwaterHeaters 1Aand2Aarebypassed; Reduce Turbine Load tolessthan70%. B.ONLY Feedwater Heater1A and2Aarebypassed; Ensure reactor powerlessthan 1000/0, NO additional power restrictionsarerequired C.FeedwaterHeaters 1A,2A,1 B,and2Barebypassed; Reduce TurbineLoadtolessthan 700/0.D.Feedwater Heaters lA,2A, 1 B,and2Barebypassed; Ensure reactor powerlessthan100%,NO additional power restrictionsarerequiredThursday,March 20,200810:37:01AM 36 Harris2008SROExamRevFINAL 44.Giventhe following:*The plantwas operatingat98%powerwhenaloss of off-site power occurred.*Twenty minuteslater,the following plant conditions exist:*RCSpressureis2235psigandstable.*RCSLoop THOTis596°Finall3loopsandlowering.*RCSLoop TCOLDis552°Finall3loopsandlowering.

  • Core exit TCsindicate

approximately600°Fandloweringslowly.

  • Steam Generator pressures are approximately1048psigandstable.

Which ONE of the following describes the current plant conditions?(Steam Tables are provided.) A.Natural Circulationdoesnotexist. Heat removal must be establishedbyopeningthe condenser steam dumps.B.Natural Circulation exists.Heat removalisbeing maintained by condensersteamdumps. C.Natural Circulationdoesnotexist. Heat removal must be established by openingtheSGPORVs. D.Natural Circulation exists.Heat removal isbelnqrnaintainedbySGPORVs.Thursday,March20,200810:37:01AM 37 Harris2008SROExamRevFINAL 45.Giventhe following:

  • TheplantisinMode3.*Aloss ofDCBusDP-1B-SBhasoccurred.*Thecrewis

performingactionsof AOP-025,LossofOne EmergencyACBus(6.9kV)orONE EmergencyDCBus(125V) WhichONEofthe following describesthereasonfor ensuringthatletdown orificevalvesareshutin accordance with AOP-025?A.Prevent water hammerorflashingintheletdownline. B.Prevent RCS leakage in excess of Technical Specification limits.C.Minimize reduction in PZRlevelwithlossofchargingflow. D.Prevent damage to the RegenerativeHeatExchanger. 46.FortheSteam Generator Water Level Control System (SGWLCS),whichONEofthe following describes this system'snormaloperationand programlevelinput? A.SGWLCSisa leveld.ominantsystemthat ultimately adjustsFeedRegvalve positionbylevelerror. Program level is variablebasedoninputfrom TurbineFirstStagepressure. B.SGWLCSisalevel dominantsystemthat ultimately adjustsFeedRegvalve position by level error.Programlevelis constantat57%NR.c.SGWLCS.isaflow dominant system that ultimately adjustsFeedRegvalveposition by mismatch in steam flowvs.feedflow. Program level is variablebasedoninputfrom TurbineFirstStagepressure. D.SGWLCS isa flow dominantsystemthat ultimately adjustsFeedRegvalveposition by mismatch in steam flowvs.feed flow.Programlevelis constantat57%NR.Thursday,March20,200810:37:01AM 38 Harris 2008SROExamRev FINAL 47.Given the following:

  • The plant is at100%power.
  • The following alarm has just been received:*ALB-04-2-2, REFUELING WATER STORAGE LOW LEVEL*All otherMCR alarms are clear*The crew enters AOP-008, Accidental

ReleaseofLiquid Waste Which ONE of the following describes the setpointforthealarm received,andthe action required maccordance with AOP-008?A.94.3%;Immediately begin refilling the RWST to above the alarm setpoint B.94.3°;0;Stop all additionstothe RWSTC.23.4%,;Ensure RHRandContainment Spray Pumps are de-energized D.23.4%.EnsureCSIP suctions areisolatedfrorn the RWST 48.Which ONE of thefollowinq instruments failures will cause actual feedwater flowtothe affectedSGto INITIALLY lower?(Assume selected)A.SGlevelfailslow B.Feedwaterflow fails low C.Steam pressure fails high D.Steam flow fails lowThursday,March 20,200810:37:02 AM 39 Harris2008SRO'ExamRevFINAL 49.Giventhe following:*A Gaseous Waste release ofGasDecayTankCisinprogress.*An ALERTalarmisreceivedonREM-3546, WPBStack5PIGmonitor.

  • Activitylevelisstable

justabovethe ALERT setpoint.Which ON.E of the following describestheactionrequiredin accordance with OP-120.07?A.The release MUSTbestopped;releasemay continue underthesamerelease permit after REM-3546is determinedtobe operableandcurie contentofthereleaseis determinedtobewithinlimits.B.The release MUSTbestopped;a newrelease permitmustbe generated prior to resuming the decay tank release.C.The release maycontinue;ifactivitylevel approaches or exceedstheHIGHalarm setpoint, stop the release;release may continue underthesamerelease permit afterREM-3546 is determinedtobe operableandcurie content of thereleaseis determined. tobewithinlimits.D.The releasemaycontinue;ifactivitylevel approaches or exceedstheHIGHalarm setpoint,stoptherelease;anew release permitmustbe generated prior to resuming the decaytankrelease.Thursday,March20, 200810:37:02 AM 40 Harris2008SROExamRevFINAL 50.Giventhefollowing:*The plant isoperatingat50%power.*The Turbine Driven AFWpumpwastakenOOS12hoursagoforbearing replacement.*Both Motor Driven AFWpumpmotorshavebeen determinedtobe INOPERABLEduetoacommoncausefailureanalysis. Which ONE of thefollowingactions is required?A.Immediatelyinitiateactiontorestoreone AFWtraintooperablestatus;poweroperationis currentlyallowedwithallthree AFWPumpsInoperable.B.Restoreat least2 AFWPumpstoservicewithin1hour,orbeinHot Standby withinthefollowing6hours.C.Restoreatleast1 AFWPumptoservicewithin 1hour,orbeinHot Standby withinthefollowing6hours. D.ImmediatelyentertheactionofTS3.0.3andbeinatleastHOT STANDBYwithin7hoursfromthe time itwasdeterminedthatno AFWpumpswereoperable.Thursday,March20,2008 10:37:02 AM 41 Harris 2008 SROExam Rev FINAL 51.Given the following:

  • The plantisin mode 3*RCS heatupisin progress As AFW flow to thesteamgenerators

is increased, what will happentothe initial heat transfer rate betweenRCSandthesteamgenerators and why?The heat transferratewill... A.increase;because the cooler AFW water will increase the delta T betweentheRCSandthe steam generators. B.decrease;because the cooler AFW water will decrease the delta T betweentheRCSandthe steam generators. C.increase;because increasing SGlevel causes SG pressureand saturation temperature to increase.D.decrease;because increasingSGlevel causes SG pressure and saturation temperature to decrease.Thursday,March 20,200810:37:02 AM 42 Harris 2008SROExamRev FINAL 52.Given the following:*The, plantisat1 00%power.*RecoveryfromaLoss of Instrument Bus 1DP-1A-S1isin progress.*The crew has de-energized the associated Process Instrumentation Cabinet (PIC)in preparation for energizing Instrument Bus 1DP-1A-S1.*The crew i,s evaluating bistable status prior to energizingthebus.Which ONE of the following describesthereason for checking bistable status?A.When the lnstrurnentbusis enerqizedwiththe PICdeenergized, a reactortripmay occurdue to'de-energize to actuate'bistables becoming actuated.Checking other bistables ensures a ReactorTripwillnotoccur. B.WhenthePICis enerqized after the InstrumentBusis energized,'energize to actuate'bistables may experience a momentary inadvertent trip.Checking other bistables ensuresanESF actuationwillnotoccur. C.Bistables are checked to ensurethateach parameter for Process or Protection goes to its required state when.the InstrumentBusandPICare energized. D.Bistablesare checked to ensurethatalllightsareout, verifying thatthePIC normal and alternate supply breakersareopen prior to reenergizing the Instrument Bus.Thursday,March 20,200810:37:02AM 43 Harris2008 SROExamRev FINAL 53.lnitial Plant Conditions:

  • Yesterday,aloss ofESW Header"A"occurredduetoa

failure shaft shearofthe"A"ESW Pump.*Thecrew completed AOP-022, Attachment 1, Equipment AlignmentDuetoLossofan ESWHeader.*Thecrew implemented OWP-SW, Operations Work Procedure Service Water,duetothe extendedlossofthe"A" ESWheader. Current Plant Conditions:*Aloss of off-sitepoweroccurs coincidentwitha safety injection actuation. WhichONEof the following describes the alignment of ESW loads forthe current plant condition?A."A" EDGwillNOT automaticaHystart because implementation of OWP-SW places the diesel in MAINTENANCE MODE.B."A"EDG will automaticallystart,butmustbe manually tripped becauseitwillhave no ESW flow.C."A"EDGwillNOT automatically start because implementation of OWP-SW willhavebarredthediesel. D."A"EDG will automaticallystart,but operatorsmustrealign NSWtothe ESW header.Thursday,March 20,200810:37:02 AM 44 Harris2008SROExamRev FINAL 54.Giventhe following:

  • The plantisinMode3.
  • AFW Pump1.A-SAis operating to provide secondary inventory.*DC

becomes de-energized. Which ONE of the foHowing describes the effectonthe operating AFW pump?A.MCR control switch indication is extinguished. Pump remains runninq.MCRbreaker control is lostB.MCR control switch indication is extinguished. Pump remains running.MCR breaker control is available C.MCRcontrol switch indicationisavailable. Pump trips.MCRbreakercontrolislostD.MCR control switch indicationisavailable.Pumptrips. MCRbreaker control is availableA.6500 KWata power factorof0.8leadingB.6500 KWat a power factor of0.8laggingC.7150 KWatapowerfactor of 0.8 leadingD.7150 KWatapower factor of0.8laggingThursday,March 20,200810:37:02AM 45 Harris 2008SROExamRev FINAL 56.Given the following:

  • The unitisin Mode 4.*Maintenance

reports that the inner dooronthe Containment Emergency Airlock willnotseal properly after leaving Containment.

  • The crew has declared the inner door.INOPERABLE.and

closed the outer door.Which ONE of the foHowingdescribes the status of CONTAINMENT INTEGRITY, per Technical Specification Definitions,andthe required Technical Specification action?A.Containment IntegrityISmet;Immediately verify the outer door closed B.Containment Integrity IS NOT met;Immediately verify the outer door closed C.Containment IntegrityISmet;Verify the outer door closed within 1 hour.D.Containment Integrity.IS.NOT met;Verify the outer door closed withint hour.57.Which ONE of the following wouldbeusedto change the alarm setpoints from the Main ControtRoom of a safety related radiation monitor?A.RM-11 B.RM-23 C.RM-23P D.RM-80Thursday,March 20,200810:37:02AM 46 Harris2008SROExamRevFINAL 58.Giventhefollowing:*Thecrew enteredFRP-C.1,ResponsetoInadequateCoreCooling,withthefollowingcond itionspresent:*Lossof Offsitehasoccurred*CoreExit temperatureis737degreesF

  • RCSpressure

is 1650psig*RVLISis 360/0 WhichONEofthefollowingdescribestheconditionoftheRCSandtheactionsrequiredinresponsetothiscondition?A.Saturated,heat transferisdegraded;Establishan*RCSVentpathtolowerpressureand temperature B.Saturated ,heat transferisin jeopardy;ReinitiateHighPressureSafetyInjectiontorestorecorecooling C.Superheated, heattransferisdegraded; Establish anRCSVentpathtolowerpressureand temperature D.Superheated, heat transfer isin jeopardy;ReinitiateHighPressureSafetyInjectiontorestorecorecoolingThursday,March 20,200810:37:02 AM 47 Harris2008SROExamRevFINAL 59.Giventhe following:*The plantisoperating at55%power.*Thefollowing annunciatorisreceivedintheControlRoom:

  • APP-ALB-002-7-2, SERV WTRPUMPS DISCHARGELOWPRESS*TheROnotesthat

Cooling TowerBasinLevelis decreasing rapidly.*Service Water headerpressureis45psigandlowering.*One minutelater,Service Water headerpressureis 25psig and continues to lower.*CTMU cannotmaintainCooling TowerBasinlevel.

  • ThecrewehtersAOP-022, Loss of Service Water and completes the immediate actions.*APP-ALB-002-7-2is

stiJlinandtheCooling TowerBasinLevel continues to decrease rapidly.*RABOperatorreportsthatalargevolumeofwaterisgushingfromoverheadpipinginthe vicinity of1SW-276,HeadersA &BReturnToNormalSW Headervalve.Theareaisinaccessible.*All automaticplantsystemshavefunctionedasdesigned. Which ONE ofthefollowing describesthelocation oftheleak,andtheactionrequired? A.UnisolableleaklocatedintheNormalService Water System;Tripthe reactorandgo toPATH-1.B.UnisolableJeakIocatedinthe Emergency Service Water System;Tripthe reactorandgo toPATH-1.C.Isolableleak locatedinthe Normal Service Water System;EnsureNSW is properlyalignedto equipmentlistedin AOP-022, Attachment 1.D.Isolableleak located in the Emergency Service Water System;EnsureESW is properlyalignedto equipmentlistedin AOP-022,Attachment 1.Thursday,March.20, 200810:37:02 AM 48 Harris2008 SROExam Rev FINAL 60.Which ONE of the following describes the operation of Service Air Header IsolationValve,1 SA-506?A.Closes automatically when Instrument Air.header pressure decreases below 75 psig;Automatically reopens when pressure increases above79psig.B.Closes automatically when InstrumentAir header pressure decreases below 75 psig;Must be manually reopened.whenpressure increasesabove79psig. C.Closes automatically when Instrument Air header pressure decreases below 90 psig;Automatically reopens when pressure increases above94psig.D.Closes automatically when Instrument Airheader pressure.decreases below 90 psig;Mustbe manually reopened when pressure increasesabove94psig.Thursday,March 20,200810:37:03 AM 49 Harris2008SROExamRev FINAL 61.Giventhe following:

  • The plantisat1 000/0.power.*An inadvertent

Containment Spray actuation has occurred on Train"A".*Train"A" Containment Sprayhasbeen secured.*Containmentpressureindicates (-)2.4 inches H20.Which ONE of the following describes how Containment pressure will be restored to within limits?A.Containment Vacuum Relief system will operatetorestore containment pressure to-1.5 inchesH20.No other actions are required.B.ContainmentVacuumRelief system will operate to restore containment pressure to-1.5 inches H20.Containment purge operationisthen required to restoreto-1.0 inches H20.C.ContainmentVacuumReliefsystemwilloperate to restore containmentpressure to-1 other actionsarerequired. D.ContainmenfVacuum Relief system will operate to restore containment pressure to-1.0 inches H20.Containment purge operationisthenrequiredto restoreto-0.5 inches H20.Thursday,March 20,200810:37:03 AM 50 Harris2008SROExamRevFINAL 62."{he plant is at 1 00% Th.-z pUt fl!r;,., loo:5z, I?O"'e12-i 1-{,.\V ?iY'<U\}0"+oq'S ea-u l c.e...TheoperatingcrewhasenteredEPP-013, LOCAOutside ContainmentduetoMCB indications.WhichONEof thefollowingdescribestheleaklocationthatwouldbeisolatedfirstin accordancewithEPP-013, LOCAOutsideContainment,andthemethodfor confirmationofleakisolation?ExcessLetdownHeatExchanger; PZRlevel rising.B.ExcessLetdownHeatExchanger; RCSpressurerising. C.RHRHeat Exchanger;PZRlevelrising.D.RHRHeatExchanger;RCSpressurerisingThursday,March20,200810:37:03AM 51 Harris 2008 SRO Exam Rev FINAL 63.Given the following:

  • The reactor was tripped on simultaneous

loss of the Main Feedwater Pumps.*All AFW was subsequently lost.*RCS Bleed and Feedisin progress in accordance with FRP-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK.*Core Exit Thermocouples have stabilized atan average of 595 OF.*Main Feedwater Pump"A" hasbeen started.*Containment pressureis1.0psigand stable.Which ONE of the following describes the method-and rate of establishing feedwater flow?A.Feed one Steam Generator at the MINIMUM controllable rate untila SG WIDE range level is>15%using the respective Feedwater Control Bypass Valve.B.Feed one Steam Generator at the MAXIMUMrateuntila SGNARROW range levelis>25%using the respective Feedwater Control Bypass Valve.c.Feed all Steam Generatorsatthe MINIMUM controllablerateuntila SGWIDE range level is>15%using the Feedwater Control Valves.D.Feed all Steam Generators attheMAXIMUMrate until aSG NARROW range level is>25%using the FeedwaterControl Valves.64.Given the following:*A reactortripandlossof off-site power have occurred.*The crew is performing acooldown using EPP-007 , Natural Circulation With Steam Void in Vessel (Without RVLIS).*Off-Site powerhasbeen restored.*Preparations are being made to startanRCP.Which ONE of the following describes the minimum PZR level required for RCP restart in accordance and the reason for the level?A.25%to ensure minimum inventory for adequate pressure control.B.65%to ensure minimum inventory for adequate pressure control.C.25%to ensure adequate volume for collapsing the void D.650/0 to ensure adequate volume for collapsing the voidThursday,March20,200810:37:03AM 52 Harris2008SROExamRev FINAL 65.Which ONE of the following describesthereasonand requirements for depressurizing theRCS in accordance with EPP-012,Lossof Emergency Coolant Recirculation?A.To.minimizeRCSleakage; DepressurizetheRCSto achieve RCS subcooling between10°Fand20°F[40°Fand50°F];B.To ensure SI Accumulator injection; Depressurize theRCS to.achieveRCS subcooling between10°Fand20°F[40°Fand50°F];C.To minimize ReS leakage;Depressurize the RC,S to maintain RCS subcoolingjustabove lOaF[100°F];D.To ensureSIAccumulatorinjection; Depressurize the RCSto maintain RCS subcoolingjust above zo-r[100°F];Thursday, March.20,200810:37:03 AM 53 Harris 2008SROExamRevFINAL 66.Giventhefollowing:*Youare assigned as theROondayshift.*YouhavebeencalledforFitness forDutyscreening.*You mustleavetheControlRoomfor approximately1.5hours.*TheSSOhasgivenperm.issionanddirectednoadditionalactionsarerequired beyond those'stated°inOMM-002,Shift Turnover Package.lAWOMM-002,whichONEofthefollowingistheMINIMUMrequiredfortheshift relief?Note: (Attachment 14, Documentation of Short Term AssumptionofDuties)(Attachment5,Control Operator Shift Turnover Checklist)A.Oral turnovertotheremainingBoardOperator.Both watchstanders Initial Attachment 14.Nologentryrequired.B.Oral turnovertothe remainingBoardOperator.Both watchstanders Initial Attachment14and document reliefforgreaterthan1hourintheControl Operator log.Co.Performa turnover using Attachment5.Both watchstanders Initial Attachment 5.Nolog entry.required.D.Performa turnover using Attachment5.Enter the informationintheControl Operators log,andsignthelogover.Thursday,March 20,200810:37:03 AM 54 Harris2008SROExamRevFINAL 67.Given the following:*A power increase.isinproqress in accordancewithGP-005, Power Operation.

  • Average PowerRangeNls indicate40%power.*Main Turbine load indicates35%power.*AverageLoopDelta Tindicates

420/0 power.Which ONE of the following describestheactionsrequiredin accordance with GP-005?A.Power mustbereducedlessthan 30.%byall indicationsanda calorimetric performed to determine actual.power.B.Power increaseshouldbestoppedanda calorimetricmustbe performed to determineactualpower. C.Power increaseshouldbestoppedandthePRNlsadjustedtomatch turbine power.D.Power increase may continue using turbinepowerandno furtheractionisrequired unless turbine power and average PRNlsdeviate by 50/0orgreater. A.Lubrication ofavalvestempriortoeach scheduledtestingofthevalve. B.Periodic or occasionalventingofpumps priortotesting,not associatedwiththe surveillance being performed. C.Adjustingthebolt torqueonavalve collar prior to stroke timetestingofthevalve. D.Operation ofa pump shortly beforeatest, ifasituationcouldbeavoidedto operate the pump while maintaining plant and personnel safety.Thursday,March20,200810:37:03AM 55 Harris2008 SROExamRevFINAL 69.Giventhefollowing:*TheunitisinMode6.*Refuelingoperationsareinprogress.*The30thfuel assemblyisbeingloadedintothecore.*CurrentBoronConcentrationis2450ppm.AccordingtoGP-009,RefuelingCavityFill,Refueling,andDrainoftheRefuelingCavity,Modes5-6-5,whichONEof thefoHowingwouldrequirefuelloading operationstobestopped immediately? A.Communicationsislostbetween ContainmentandtheControlRoom. B.WaterintheSpent FuelPoolinnot.clearenoughtoviewtheFueltopNozzles without supplementalJighting.C.Boron concentrationdropsby10ppmasdeterminedby two successive samples of Reactor Coolant.D.Anunanticipatedrisein countrateby a factor of twooccurson1 of2 operableSourceRangechannelsduringanysingleloadingstep.Thursday,March 20,200810:37:03 AM 56 Harris.2008,SRO ExamRev FINAL 70.Given the following conditionsata work site:*Airborne activity-5 DAC*Radiation level-40mrem/hr.

  • Radiationlevelwith shielding-20 mrem/hr.*Time to conduct task WITH respirator-40 minutes.*Time to conduct task WITHOUT respirator

..30 minutes.Assumptions:

  • The airborne dosewitha respiratorwillbezero.*A dose rate of40mrem/hrwillbe received while placing the shielding.

Assume no benefit from shielding during placement.*All tasks will performedbyone worker.*Shieldingcanbe placedin15 minuteswithor without a respirator.

  • The shieldingwillnotbe removed.Which O.NE of the following would resultinthe lowestwhole

body dose?A.Conduct task WITHOUT respirator or shielding. B.Conduct task WITH respirator and WITHOUT shielding. C.Place shielding while wearing respirator and conduct task WITH respirator. D.Place shielding while wearing respirator and conduct-task WITHOUT respirator.Thursday,March20, 200810:37:03 AM 57 Harris2008SROExamRevFINAL A.2000mrem;Superintendent-RadiationProtectionB.2000mrem;SiteVice President c.4000mrem;Superintendent-Radiation ProtectionD.4000mrem; Site Vice PresidentThursday,March 20,2008 to:37:03 AM 58 Harris2008SROExamRevFINAL 72.Initial Conditions:*The unitis att00%power.Current Conditions:*The followingalarmis received:*ALB-001-7-1, ACCUMULATOR TANK AHI..LO PRESSURE*The RO.reportsthe following indications:*ColdLeg AccumulatorA'tpressure is 650psig and slowly increasing*ColdLeg Accumulator"A"levelis75%andslowly increasing Whichoneofthe followingistheactionrequired lAW the appropriate Annunciator Plant Procedure andlheOPERABILITY ofthe"A"Cold <Leg Accumulator (CLA)?A.Drain"A"CLAto lower pressure;CLA"A"is INOPERABLE B.Verify Nitrogentothe accumulatorsisisolatedandvent excess accumulator pressure;CLA"A"is INOPERABLEC.Drain"A"CLAto lower pressure;CLA"A" is OPERABLE D.Verify Nitrogen to the accumulatorsisisolatedand vent excess accumulator pressure;CLA"A" is OPERABLEThursday,March20,200810:37:03AM 59 Harris2008SROExamRevFINAL 73.Giventhefollowing:*At1302,asteam generatortubeleakisidentified.*At 1318,a,plantshutdownis commenced duetoexceedingTSleakagelimits.*At1319,anUnusualEventisdeclaredbytheSiteEmergencyCoordinator.(SEC)*At1321,a reactortripoccurs,*At1327,thecrew identifies SG"A"as the ruptured SG.*At1330,an ALERTisdeclaredbytheSEC. Which ONE of thefollowingdescribesthelatesttimethattheinitialnotificationto State/County officialsANDthe*NRC*is due?State/County NRC A.1334 1334 B.1334 1419 C.1345 1419 D.1345 1430Thursday,March 20,200810:37:04 AM 60 Harris2008SROExamRevFINAL 74.Given thefoHowing:*One Shutdo.wnBank-A,Group2Rodhas droppedintothecore.*Thecrew is recovering thedroppedrod.

  • ALB-13-7-1 ,RODCONT SYSTEM URGENT FAILUREisreceived.

WhichONEofthe following describesthereasonforthealarmandtheplant response?A.Withdrawingtherodwhile theremainingGroup2LiftCoilsare deenergized. Rod withdrawalisblockeduntilthealarmisreset. B.Initiation of an"out" siqnaltoSOBank"A"Rods,anditsGroup1rodsdonotmove. Rod withdrawalisblockeduntil thealarmisreset.C.Withdrawing therodwhiletheremainingGroup2LiftCoilsare deenergized. Rod withdrawal is unaffectedandrecoverymay continue.D.Initiation of an"out"signaltoSOBank"A"Rodsand itsGroup1rodsdonotmove. Rod withdrawal is unaffectedandrecoverymaycontinue.Thursday,March20,200810:37:04AM 61 Harris2008SROExamRevFINAL 75.Giventhefollowing:*TheUnithasexperienced aSBLOCA.*EPP-0'09,Post LOCACooldownandDepressurizationisinprogress.*AllRCPsarerunning.*RCS pressure is 1690psig.*An RCScooldown has-beeninitiatedbydumpingsteamtothe atmosphere. WhichONE.ofthefollowingdescribestherequiredRCPconfiguration lAW withEPP-009,andthebasisforthis configuration?A.AllRCPsshouldbestopped;minimizeRCSinventorylosswhenthebreakuncoversB.OneRCPshouldbestopped; produces effective heat transfer,providesboronmixingforRHRoperations,and providesRCSpressure control C.All RCPsshould be Jeft running: ensures symmetric heat transfertothe S/Gs,aidsin ReSpressurecontrol,andpreventssteamvoidingintheReactorvesselheadD.TwoRCPsshouldbestopped; minimizesRCSheatinputandstillproduceseffectiveheat transferandRCSpressurecontrol Thursday, March 20, 200810:37:04 AM 62 Harris<2008SROExamRev FINAL 76.Which ONE of the following describes the Technical Specification basis for the Pressurizer Code*safety valves?The basis is that the combined reHefcapacityofallthe pressurizer Code safeties is greaterthanthe maximum surge rate assuming AND_A.a complete loss of load.directlyresultingina reactortripfromthe turbine trip;no operation of the pressurizerPORVsorthe steam dumpsB.a complete loss ofloadwithno reactortripuntilthe second trip setpoint is reached;no operation. of the pressurizer PORVsorthe steam dumps C.a complete loss of load directly resultingina reactortripfromthe turbine trip;no operation of the pressurizer PORVs, steam dumps operate as designedD.a complete loss ofloadwithno reactor tripuntilthe second trip setpoint is reached;no operation of the pressurizer PORVs, steam dumps operate as designedThursday,March 20,200810:37:04 AM 63 Harris2008SROExamRevFINAL*Followinga turbinerunback,thecrewhasstabilizedtheplant.*ControlBank"O"GroupCountersareat180steps.*OnORPI,oneControlBank "0"rodindicates198steps;allothersindicate180 steps.*ThecrewhasenteredAOP-001anddeterminedtherodtobe immovable and untrippable. WhichONEofthefollowingdescribestheexpectedalarmforthegivenplantconditionsandthe technical specificationimplicationsofthisevent? RPIURGENT.ALARM;VerifyShutdownMarginwithin1 hourandbeinHot Standbywithin6hours. B.ALB-13-8-5, COMPUTER ALARM RODDEV/SEQNISPWRRANGETILTS; VerifyShutdownMarqinwithin1hour.Poweroperationmaycontinueprovidedthat accidentanalysesare revaluatedtobesatisfactory. c.ALB-13-6-1, RPJURGENTALARM; VerifyShutdownMarginwithin1hour.Poweroperationmaycontinueprovidedthat accidentanalysesarerevaluatedtobe satisfactory D..ALB-13-8-5, COMPUTERALARMRODDEV/SEQNIS PWRRANGE TILTS;VerifyShutdownMargin within 1 hour and bein Hot Standbywithin6hours.Thursday,March0:37:04AM 64 Harris2008SROExamRevFINAL 78.Giventhe following plant conditions:*A normalplantcooldownisinprogress*Both CSIPsare OPERABLE Whichofthe following is the plant temperatureatwhichTechnical Specificationsrequirea MAXIMUM of ONE(1)CSIPtobe OPERABLEandthebasisforthis requirement?A.325-r.Prevents an uncontrolledcooldownduetoamassadditionofcold waterfromthe RWST B.325°F;Provides assurance thatamassadditionpressure transientcanberelievedbythe operationofasinglePORV C.350°F;Prevents an uncontrolled cooldown duetoamassadditionofcold waterfromthe RWST D.350°F;Provides assurance thatamassadditionpressure transientcanberelievedbythe operationofasinglePORVThursday,March 20,200810:37:04AM 65 Harris 2008SROExamRev FINAL 79.Given the following:

  • The plant is.at 100%power.*Aloss of Component Cooling.Water has occurred.*The crew is performing

actions of AOP-014, Loss of Component Cooling Water.*3 minutesintotheevent, thele.ak is determinedtobe onCCWloop"A".*"A"SurgeTanklevel indicates 20/0.*"B" Surge Tank leveLindicates 38%and stable.*TheCCW Non-EssentialLoopwas isolatedfrom"A" Trainandis now aligned to the"B" Train.Which ONE of the following describes the minimum actions required by AOP-014?A.Tripthe reactor, Immediately trip RCPs, and enter Path-t.B.TripaffectedCCWpump(s) Continue attempts to locate theleakin accordance. with AOP-014.Mode 1 operations may.continue.C.Tripthe reactor, EnterPath-1andtripthe RCPs within 10 minutes.D.Trip affectedCCW pumpis)..' Enter AOP-038 fora rapid shutdown while continuing attempts to locate the leak in accordance with AOP-014.Thursday,March20,2008 10:37:04 AM 66 Harris2008SROExamRev FINAL 80.Given the following:

  • Theplantis operatingat100%power*All equipment is operatinginnormallineups.

Current conditions:*AlossofDCBus ..Which.ONE of the following describes the impactofthis failureonthe Reactor Protection Systemandthe actions required?A.RTB"A"shunt trip coilwillbe disabledbytheloss ofDCbusand directly cause a reactor trip;Perform actions ofPath-1inparallelwith AOP-025,LossofOne Emergency AC Bus(6.9kV)OrOne EmergencyDCBus(125V)B.RTB"A" shunttripcoilwillbe disabledbythe loss ofDCBusbutthiswill NOT directlyresultin areactortrip: Initiate a.manual reactortripdueto the effectonthe plantofthelossofDC Power supply and perform actionsofPath-1inparallelwith AOP-025,LossofOne Emergency ACBus(6.9kV)Or One EmergencyDCBus(125V)C.RTB"A" undervoltage coltwilllose powerduetotheloss ofDC*Busand directly cause a reactor trip;Perform actionsofPath-.t. Once Path-tisexited then enter AOP-025, Loss of One EmergencyACBus(6.9kV)Or One EmergencyDCBus(125V)D.RTB"A"undervoltagecoilwilllose powerdueto the loss ofDCBusbutthiswill NOT directly resultina reactor trip;Initiate a manual reactortripduetothe effectonthe plant.ofthelossofDC Power supply and perform actions ofPath-1 in parallel with AOP-025,LossofOne EmerqencyAt; Bus{6.9kV)OrOne EmergencyDCBus(125V)Thursday,March 20,200810:37:04AM 67 Harris 2008SROExamRevFINAL 81.Giventhefollowing:*A reactor startup isinproqressinaccordancewithGP-004, Reactor Startup(Mode3toMod.e2).

  • ThefoHowingalarmis

received: '*ALB-013-3-2, INTERMEDIATE.RANGELOSSOF COMPVOL TAGE*SRChannel N-31 indicates 7X10 3 cps.*SRChannelN-32indicates7X10 3 cps.*IRChannelN-35indicates 8.7X10-11 amps.*IRChannel N-36 indicates 7.0X10.-10 amps.WhichONE ofthefollowingdescribestheexistingplantconditionandtheassociated Technical Specificationrequirementsforcontinuedoperation?A.N-35is undercompensated; Raising power above P-6ispermittedonceOWP-RP,ReactorProtection,is implemented. B.N-35is undercompensated; Raising power above P-6is*NOTpermitteduntilthechannelisrestoredto OPERABLE.C.N-36 isundercompensated; Raisinq power aboveP-6is permittedonceOWP-RP,ReactorProtection,is implemented.D.N-36is undercompensated; Raising power above P-6isNOTpermitteduntilthechannelisrestoredto OPERABLE.Thursday,March20, 200810:37:04 AM 68 Harris 2008SROExamRevFINAL 82.Giventhefollowing:*Plantisoperatingat 1000/0 power.*Pressurizer level transmitter LI-459Aoutputhasfailed.WhichONEofthefollowingdescribestheTechnical Specificationactionsrequired,ifany,andthe TechnicalSpecificationbasisfortheHigh Pressurizer WaterLevelreactor trip?A.Enter T*.S.3.3.1, RPSlnstrumentation.Theinoperablechannelmustbeplacedinatripconditionwithin 6*hours;ProvidesabackuptriptoPZRHighPressurereactortripandensures that water relief through thePZRsafetyvalveswillnotoccur. B.EnterT.S.3.3.1 ,RPSlnstrumentation.Theinoperablechannelmustbe placedinatripconditionwithin6hours; Provides primaryprotectionforlossofloadevents'andensuresthatonaPZRlevelchannelfailure, the PZRsafetyvalveswillnot liftpriortothePZRHighPressure reactor trip.C.ActionperT.S.3.3.1,RPSInstrumentation,isNOTrequiredsince2channelsarestillavailable;ProvidesabackuptriptoPZRHighPressure reactortripandensuresthatwater relief through the PZRsafetyvalveswillnotoccur.D.ActionperT.S.3.3.1,RPSInstrumentation,isNOTrequiredsince2channelsarestillavailable; Provides primary protection forlossofloadeventsandensures thatonaPZRlevelchannelfailure, thePZRsafetyvalveswillnotliftpriorto thePZRHighPressurereactortrip. Thursday, March 20,200810:37:04AM 69 Harris2008SROExamRevFINAL 83.Giventhefollowing:*The plant isinMode4.*RHR Train"B"hasbeenplacedinservice.

  • ReS temperatureisstableat

325°F.*RCSpressureis320psigandloweringslowly.

  • Containmentsumplevel is20inchesandrisingslowly.
  • REM-01LT-3502A-SA,Cnmt

RCSLeakDetectionMonitor,isinHIGHalarm.

  • Pressurizerlevelis24%andslowlylowering.*ChargingisinMANUALwithflowof120gpm.

WhichONEofthe following-describesthecorrectproceduretoaddresstheeventin proqressandthemitigationactionsthisprocedurewillrequire? A.AOP-016, ExcessiveRCSLeakage Manuallyalignhighhead SifiowthroughtheBIT B.AOP-020, Loss of RCSlnventoryorResidualHeatRemoval While Shutdown ManuallyalignhighheadSIflowthroughtheBIT C.AOP-016, ExcessiveRCSLeakageStopallrunningRHRpumps andisolateRHR D.AOP-020, Loss of ReSInventoryorResidual HeatRemovalWhileShutdownStopalLrunning RHRpumps and isolateRHR Thursday, March 20, 200810:37:05 AM 70 Harris 2008SROExamRev FINAL 84.Given the following:

  • A LOCA occurred 45 minutes ago.*The crew is performing

actions in accordance with EPP-010, TransfertoCold Leg Recirculation*SwapovertoColdLegRecirculation is in progress.*The followinqalarrnsare received:*ALB-001-2-2, SPRAY PUMPA DISCHARGE LOW PRESS*ALB-001-2,-5,SPRAYPUMP A SUCTION LOW PRESS*Both alarmsarereceivedand clear intermittently over the course of about 1 minute.*"A" RHRpumpampsand discharge pressure are beginning to oscillate.

  • The USCOdetermines

thatTrain"A" recirculation sump performance is degraded.WhichONE of-the describes the actions performed.basedonthe determination thatthe recirculation sump is degraded?A.Remainin,EPP-010;Stop"A" Containment Spray Pump.B.Remain in EPP-010;ThrottleCSIP flowtobe slightly greaterthanthe minimum flow requirements.C.Goto EPP-012,Lossof Emergency Coolant Recirculation; Stop"A"Containment Spray Pump.D.Goto EPP-012, Loss of Emergency Coolant Recirculation; Throttle CSIP ftowto be slightly greaterthanthe minimum flow requirements.Thursday,March 20,200810:37:05AM 71 Harris2008SROExamRevFINAL 85.Giventhe following:*A SGTRisin progresson"A" S/G.*.All MSIVs failedtoclose.*All required actions of Path-2havebeen completed*A transition has been made to EPP-020, SGTRWITHLOSSOF REACTOR COOLANT: SUBCOOLED RECOVERY.*Containment sumplevelsarenormalforthe current plant conditions. Which ONE of the following conditionswouldrequire consulting plant operations staff to determine if recoveryshouldbe completed*usingEPP-021, SGTR WITHLOSSOF REACTOR COOLANT: SATURATED RECOVERY?A.RWST level of 70%B."A" SG.levelat 98%C.RWST level of20%D.RCSPressure of 360psigThursday,March 20,200810:37:05 AM 72 Harris2008 SROExam Rev FINAL 86.Initial conditions:

  • Reactor powerwasat 100°A>.*Main Steam flow indications

wererisingonall 3SGs.*Reactor power roseto103%.*The reactor was manually tripped.*SafetyJnjectionwClsmanuallyactuated.*Main SteamIsolation.was manually actuated.Current conditions:

  • ReS pressure is 1700psigandstable.*"A" and"B" SG pressuresare800psigandstable.*"C" SGpressureis50

psigand slowly lowering.*Core Exit temperatureis440degreesFandrising.

  • Pressurizerlevelis 12%andrising.*SG"A"and"B"NRlevelsare35%andrising.
  • Containment

pressure is 0.3psigand stable*The USCG has just completed the steps in EPP-014, Faulted Steam Generator Isolation, for isolatingthe"C" Steam Generator. Which ONE of the following describes current statusofSI Termination criteria and which'procedure will beusedto address SI Termination? A.Conditions are met toterminateSI; SI willbe terminated in EPP-014 B.Conditions aremetto terminate SI;SI will be terminatedonceatransition is made to EPP-008,SI Termination C.Conditio.nsareNOTmettoterminate SI;SIwillbe terminated in EPP-014 once conditionsaremet D.Conditions are NOTmetto terminate SI;SIwillbe terminated in EPP-008,*SI Termination, once conditions are metThursday,March 20,200810:37:05AM 73 Harris 2008 SROExam Rev FINAL 87.Given the following plant conditions:

  • The plant-is in Mode 1.*ALB-15-2-2,PIC

POWER FAILURE, alarms*ALB-15-1-4,60KVAUPSTROUBLE, remains clear*ALB-15-1-5,7.5KVAUPS TROUBLE, remains clear*ALB-15-1-3, PROTECTIONSYSAlBTROUBLEalarms

  • Most lights in" the bottomrowofTrip StatusLightBoxesare

energized Which ONE of the following correctly identifies the effectontheplantandthe Technical Specification implications for this event?A.Powerhasbeen losttoall"B"Train SSPSSlaveand Master relays Enter Technical Specification 3.0.3 immediately B.Ability to placeAFW Isolation bistablesina tripped conditionislost Enter Technical Specification 3.0.3 immediately C.Powerhasbeen losttoall"B"Train SS.PSSlaveand Master relays Enter Technical Specification 3.0.3 after 6 hours D.Ability to place AFW Isolation bistables ina tripped conditionislost Enter Technical Specification .3.0.3 after6hoursThursday,March20, 200810:37:05AM

  • 74

Harris2008SROExamRevFINAL 88.Given the following:*TheMCRhasbeen evacuatedandthecrewhasentered AOP-004, Remote Shutdown.*TheACPismanned.and operational. WhichONEofthe following describes how powerwillbe monitored by the Wide Range Neutron Flux Monitoring (WRFM)system afterleavingtheMCR,and whatisthe MINIMUM EmergencyClassificatio.nforthisevent? A.Neutron fluxwillbe determinedusingtwo redundant WRFM(NI-60A2, N.I-60B2)that willbothindicateacrosstheSourceand Intermediate Range.Alert.B.Neutron fluxwill be determinedinitially using.oneWRFM(NI-60B2).Onceitis off-scalelowthenthe second WRFM(NI-60A2).isusedto determine Source Range flux;Site Area Emerqency. C.Neutron flux wilLbedeterminedusingtwo redundant WRFM (NI-60A2, NI-60B2)that will both indicateacrosstheSourceand Intermediate Range.Site Area Emergency. D.Neutron flux will be determined initially using oneWRFM (NI-60B2).Onceitis off-scalelowthen the.secondWRFM(NI-60A2)isusedtodetermineSource Range flux;Alert.Thursday,March 20,20081 0:37:05 75 Harris 2008SROExamRev FINAL 89.Given the following plant conditions:

  • The plant is at100%power*A'Iossofpower

to Safety Bus 1B-SBoccurs

  • The"B"EDG fails to start Which one of the following describes the effectonthe plantandthe Technical Specification (T.S.)requirements

that apply?A.Will generate aContainmentVentilationlsolation Signal;ONLY"B" Train containment vacuum breaker is INOPERABLE, enterT.S.3.6.5, Containment Vacuum Relief, restorein72 hours orbeinat least HOT STANDBY within the next 6 hours.B.Will NOT generate a ContainmentVentilation Isolation Signal;ONLY"B"Traincontainmentvacuum breaker is INOPERABLE, enter T.S. Containment Vacuum Relief, restorein72 hoursorbeinat least HOT STANDBY within the next 6 hours.C.Will generate aContainmentVentiiation 'Isolation Signal;Enter T.,S.3.0.3duetoinoperabilityofboth containment vacuum breakers D.Will NOT generate a Containment Ventilation Isolation Signal;Enter 1.S.3.0.3' due to inoperabilityofboth containmentvacuum breakersThursday,March20, 200810:37:05 AM 76 Harris2008 SROExamRevFINAL 90.InitialConditions:*The plantwasat100%power.

  • Automatic SafetyInjectionoccurs.*Thecrew entersPath-1CurrentPlantConditions:
  • Pressuriz.erlevel15%

andslowlylowerinq*RCS pressure1400.psig.andslowlylowering*RAB radiationlevelsareslowlyrising*RABSumplevelsareslowlyrisingWhichONE(1)ofthefollowingdescribesthe correctactiontobetaken?A.Transitionout ofPath-1to EPP-013, LOCAOutsideofContainment,and isolate theLowHead SafetyInjectionsystem.B.Transition outofPath-1toEPP-013,LOCAOutsideofContainment,andisolatetheHighHead SafetyInjectionsystem. C.RemaininPath-1and thencooldownanddepressurize lAW EPP-009, Post-LOCA Cooldownand Depressurization. D.RemaininPath-1andthenestablishcoldlegrecirculation lAWEPP-010,ColdLeg Recirculation.Thursday,March20,200810:37:05AM 77 Harris 2008 SROExam Rev FINAL*A LOCAhasoccurredon"B"ColdLeg.

  • ECCS has NOT functioned

as required.,.All RCP's are TRIPPED.*CET'sindicate 756°F.*RVLISFull Rangeis49%.*Containment pressure is6psigandrisingslowly.

  • All SG pressuresareat 1050 psig.Which ONE of the following procedureswillthe crew implement for these conditions, and what actionswillbe taken to mitigate this event?A.Enter FRP-C.1, Response To Inadequate

Core Cooling;Depressurize allintactSGsto 80psig by dumping steam at maximum rate.B.Enter FRP-C.2, Response To Degraded Core Cooling;Depressurize all intact'SGsto80 psigbydumpingsteam at maximum rate.C.Enter FRP-C.1 ,Response To Inadequate Core Cooling;Depressurize all intact SGsto80psigby dumping steamnotto exceed a 100°F/hr cooldown rate.D.Enter FRP-C.2, Response To Degraded'Core Cooling;Depressurize all intact SGs to80psigby dumping steam notto exceed a 100°F/hr cooldown rate.Thursday,March20,200810:37:05AM 78 Harris2008SROExamRev FINAL 92.Given.the following:*A reactor trip has occurred.duetoaloss of offsitepower.

  • The operating crew is performing

actions of EPP-005, Natural Circulation Cooldown.*"A" Train RVLIS is outofservice.*The crew has commenced RCScooldown and depressurization.

  • RCSpressureis1780psigand

trending DOWN.*RCS Tave is 448 of and trending DOWN.*All SGpressuresareat960.psiqand trending DOWN slowly.*Pressurizerlevelis 350/0 and trendingUPslowly.*Plant management determines that RCS cooldown rate MUST be performed at approximately 60°F/hrdue to secondary inventory concerns.Which ONE of the following actionswillbe required in accordance with EPP-005?A.Remain in EPP-0.05and continue cooldownand depressurization. B.Actuate safety injectionandgo toPath-1, entry point A.C.Transition to EPP-006, Natural Circulation Cooldown With SteamVoidIn Vessel (With RVLIS).D.Remain in EPP-005, stop depressurization and re-establish required subcooling .Thursday, March20,200810:37:06AM 79 Harris 2008SROExamRev FINAL 93.Initial Conditions:*A LOCA has occurred.*The crew is performing actions of EPP-012, Loss of Emergency Coolant Recirculation,basedon plant conditions upon transitionfromPath-1.

  • RWSTlevelis3%andlowering.

Current Conditions:

  • Integrity CSF Status Tree indicates Orange.Which ONE of the following describestheactionand

procedure usage required?A.StopaH pumps taking suctionfromthe RWST;Remain in EPP-012 because actions in EPP-012 are expected to cause an Orange conditionon*Integrity. B.Reduce ECCSflow from the RWST toONE(1)trainrunning; Remain in EPP-Ot2 because actions in EPP-012 are expected to cause an Orange condition on Integrity.C.Stopall pumps taking suction from the RWST;Goto FRP-P.1, Responseto.Imminent Pressurized Thermal Shock.D.Reduce ECCS flowfromthe RWSTto ONE (1)train running;Go toFRP-P.1 ,Response to Imminent Pressurized Thermal Shock.Thursday,March20,200810:37:06AM 80 Harris 2008 SRO Exam Rev FINAL 94.Given the following:

  • The Unit experienced

aStearn Generator Tube Rupture (SGTR)*on the"B" Steam Generator (SG).*The.crew is currently performing actions ot Path-z.*After completing the initial cooldown using"A"and"C" Steam Generators, the RO reports that"C"SG.pressurecontinuestolower.Which ONE of the following correctly describes the NEXT action the crew should take in accordance with Emergency Operating Procedures? A.Immediately transitiontoEP.P-014, Faulted Steam Generator Isolation, to isolate"C" SGand thengoto EPP-020,SGTR With Loss Of Reactor Coolant: Subcooled Recovery B.'Immediately transition to EPP-014, Faulted Steam Generator Isolation, to isolate the"C"SG and then return toPath-2 Entry Point J C.CompletethedepressurizationinPath-2 to restore pressurizer.level,and thengoto EPP-020,SGTRWith Loss Of Reactor Coolant: SubcooledRecovery. D.Complete the depressurization in Path-2 to restore pressurizerlevel,and thengoto EPP-014, Faulted Steam Generator Isolation.Thursday,March20, 200810:37:06 AM 81 Harris2008SROExamRevFINAL' 95.Initial Plant Conditions:*Theplantis at100%.power.

  • Chemistry, reports thefoHowing:
  • Primary specific activity is 0.76microcuriespergramdose

equivalent 1-131.*Secondary specific activityis0.03 microcuriespergramdose equivalent 1-131.*Secondary conductivity isS micromhos. Current Plant Conditions are:*Chemistryreportsthe following:

  • Primary specific activityis0.85 microcuriespergramdose

equivalent 1-131.*Secondary specific.activityis0.62 microcuriespergram dose equivalent 1-131.*Secondary conductivityis12 micromhos.*Thecrew enters AOP-033, Chemistry Out of Tolerance. WhichONEofthe following actionsisrequiredin accordance with AOP-033?Remainin AOP-033 and checkforCondensertubeleakage.Initiate Turbine load red uctiontolessthan30%.B.Goto AOP-032, HighRCS Activitybasedupon direction of AOP-033.C.Remainin AOP-033andisolate Auto-Chlorination of Service Water andCirc Water, initiate Turbine load reductiontolessthan 30°/0.D.Goto AOP-016, Excessive ReSLeakage,as directed by AOP-033.Thursday,March 20,200810:37:06 AM 82 Harris2008SROExamRevFINAL 96.In Mode1,whichONEofthefollowing correctly states the basis for the Technical Specification SafetyLimitsonthe ReactorCoreandthe parameters thatareusedto ensure that the SafetyLimitisnot violated?A.Ensures Departure from Nucleateboilingdoesnotoccurby restricting operation towithinthe nucleate b'oiling regime..Reactor Thermal Power,HighestOperatingLoopRCS Average Temperature, and Pressurizer Pressure.B.EnsuresDeparture from Nucleate boilingdoesnotoccurby restricting operation towithinthe. nucleateboilingregime. ReactorThermal Power, HighestCoreExit Thermocouple, and Pressurizer Pressure.C.Ensures Peak Centerline Temperatureofthe fuel is maintainedlessthan2200°F. Reactor Thermal.Power,HighestOperatingLoop RCS Average Temperature, and Pressurizer' Pressure.D.Ensures Peak Centerline Temperatureofthefuelis maintained less than2200°F.Reactor Thermal Power, HighestCoreExit Thermocouple, and Pressurizer Pressure.97.Given the following plant conditions:

  • Afuelshuffleisinpro,gressfollowinga

refueling lAWFHP-014,FuelandInsert ShuffleSequence.

  • You.are.thE3.SRO-FueIHandling

forthefuelshuffle,*A fuelassemblyhasjustbeenlatchedandraisedfor visual inspection.

  • The Refueling Engineer reportsto you thattheserial number on Attachment

1 does NOT matchthevisuallyverified serialnumberonthefuel assembly.Which ONE(1)ofthefolJo.wingliststheactionsrequiredbyFHP-014,FuelandInsert Shuffle Sequencewithregardtothelatchedfuel assembly?A*.Lowerthefuel assemblyinthelocationitwasremovedfromandunlatchB.Movethe fuel assemblytoa temporary storagelocationandunlatch C.Lower the fuel assemblyinthelocationitwasremovedfrombutdoNOTunlatchD.Movethe fuelassembly toa temporary storagelocationbutdoNOTunlatchThursday,March 20,200810:37:06AM 83 Harris 2008SROExamRev FINAL 98.Given the following plant conditions:*The operatingcrewislining up.to discharge the contentsofthe Treated L&HS TankA to Cooling Tower Discharge IAWOP-120.1 0.04.*Itis also determined that a release is*required from the Secondary Waste Sample Tank (SWST).WhichONE(1}of the following provides the minimum approval requirements for this release and what release of the SWST can occur simultaneouslywiththe discharge of the Treated L&HSTank IAW*OP-120.10.04? A.Manager-Operations permission required;ONLY a ContinuQusReleaseofSWSTmay occur simultaneously. B.S-SO permission required;ONLY a Continuous Release of SWSTmayoccur simultaneously. C.Manager-Operations permission required'BOTHa Continuousora Batch Release of SWST may occur simultaneously. D.S-SOpermission required;BOTHa ContinuousoraBatch Release of SWST may occur simultaneously.Thursday,March20,2008 10:37:06 AM 84 Harris 2008SROExamRevFINAL 99.Initial plant conditions:*"A" Train Equipment in service*"B"*ESWPumpis under clearance for motor replacement

  • TDAFW Pump is under clearance fortappet nut replacement

TimeLogEntry 1230 SBLOCA inside containment (-200gpm)1231 ReactorTrip&Safety Injection initiated 1236 Containment Pressure3.3psigandrising1238Lossof Offsite Power occurs 1240 Crewnotes"A" CCWPumphastrippedandcan not be restarted 1242 CURRENT TIME All other plant equipment responds as expectedforthe event in progress.Which ONE(1)of the followingisthe HIGHEST Emergency Classification entered for this event asof CURRENT TIME?A.ALERT, EAL5-1-2 B.ALERT, EAL8-2-2C.SITE AREA EMERGENCY,EAL2-1-3D.SITE AREA EMERGENCY,EAL8-2-3Thursday,March20, 200810:37:06 AM 85 Harris2008SROExamRevFINAL 100.Given the following:*The plantisinMode6,Core Alterationsinprogress.

  • Battery 1 B-SBisoutofservice.
  • Maintenance

reports that Battery tA-SAelectrolyteisoverflowingin several cells.WhichONEof thefollowinqis.theTechnical Specificationactionrequiredandits bases?A.Restore an EmergencyBatteryto Operablestatuswithin 1 Hour;A subsequent loss ofoff-sitepowerwouldresultinlossofallDC subsystems with attendant 10ssofESF functions. B.lmmediatelY suspendatloperationsinvolvlnqCore Alterations, positive reactivitychanges,or movementofirradiatedfuel; A subsequentlossofoff-sitepowerwouldresultinlossofallDC subsystems with attendantlossofESFfunctions. C.Restore an EmergencyBatteryto Operablestatuswithin 1 Hour;Sufficientcontroland instrumentation capabilityisno longeravailableto monitor and maintaintheunitstatus D.Immediptely.suspendalloperationsinvolving Core Alterations,positivereactivity changes,or movementofirradiatedfuel; Sufficientcontroland instrumentation capabilityisnolongeravailableto monitor and maintain theunitstatus Thursday, March 2Q, 200810:37:06 AM You have completed the.test!86 Harris2008-301SROInitialLicense Examination References1.EALFlowpath06-1SideOneOnly2.SteamTables }}

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