ML080720490

Feb Exam 05000327-08-301, 05000328-08-301 Final Simulator Scenarios

ML080720490
Person / Time
Site:	Sequoyah
Issue date:	02/29/2008
From:	- No Known Affiliation
To:	Office of Nuclear Reactor Regulation, NRC/RGN-II
References
ER-08-301
Download: ML080720490 (341)

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{{#Wiki_filter:Final Submittal(BluePaper) FINAL SIMULATOR SCENARIOS c§E4)uoy/lH I Appendix 0ScenarioOutlineFormES-D-1 I Facility: SequoyahScenarioNo.:1OpTestNo.:NRC Examiners: Operators:InitialConditions:100%PowerBOLTurbineDriven AuxiliaryFeedwaterPumpOOSfor Maintenance Turnover:ReducePowerTo93%forturbinevalvetesting. Target CTs:InitiateFeedandBleedPerFR-H.1IncludingmanualstartofSIPump1B-Bpriorto10%WideRange S/G level.Establish FeedwaterflowfromCondensateorAFWpriortoexitingFR-H.1. EventMalf.No.EventType*EventDescription No.1 N/A R-ATCReducePowerfrom100% N-SRO/BOP2NI07A TS-SRONISPowerRangeinstrumentChannelIfailshighandrequires I-SRO/ATCtakingrodstomanualdueto inadvertentinsertion.TechSpec Evaluation. 3 CV01BTS-SROChargingPump1BTripRequiresplacing Standbypumpin C-ATCserviceandrestoringletdown.TechSpecEvaluation.4RX26A TS-SROSteamGenerator#1PressureChannelfailslowrequiringmanual I-SRO/BOPcontrolofloop1 S/GLevelControlvalve.TechSpecEvaluation.5CN09 C-SRO/BOPCondenserVacuumleak.6FW11AM-AIIMFPATripFromSpuriousLowVacuumresultsinplantrunback. ZDISIC46MFPTurbBSpeedController (SIC-46-20B)-SpeedDemand 20BOutputFailsto0%3MinutesafterMFPATriprequiringReactorTripifRxTripnot alreadyinitiatedduringrunback. 7 FW21B C-SRO/BOPAFWPump1B-BAirboundmay eventuallyberestoredbyventingPumpcasing. 8 ED06A C-SRO/BOP1AShutdownboardDifferentialFault5minafterRxTripresultsinlossof2ndChargingPump,lossoflastAFWpump1A-A,andmanualshutdownof DIG1A-Aduetoalossofcoolingwater.Initiateslossofall Feedwaterflowto S/Gs and ultimately RCSFeedandBleedduetolossof secondaryHeatSinkwithbothChargingPumpsunavailable. 9 SI13A C-SRO/ATCSafetyInjectionpump1B-BAutoStartfailurerequiringmanualstarttoprovideinjectionflowforRCSFeedandBleed.*(N)ormal,(R)eactivity,(I)nstrument, (C)omponent, (M)ajor Appendix 0NUREG1021Revision9 I Appendix 0ScenarioOutline Scenario 1 SummaryFormES-D-1 I (TheCrewwill assumeshiftat100%powerwithdirectiontoreducepowerto -93%forMainTurbineValvetesting.The Turbine Driven AuxiliaryFeedwaterpump (TDAFW)outofservicefor maintenanceandwillnotbereturnedtoserviceduringthescenario.Followingthepowerreduction,NISpowerrangechannelIwillfailhighresultinginrodinsertionandmanualcontroltostoptheinsertion.TheSROwillenter AOP-1.01anddirectactionstodefeatthefailedchannelandreturnrodcontroltoautomatic.TheSROwillalsoevaluateandenterapplicable Technical Specifications.AftertheNISChannelfailurehadbeenaddressed,ChargingPump1Bwilltriprequiringplacingthe standbypumpinserviceandrestoringletdown.TheSROwillevaluateandenterapplicable Technical SpecificationsandTechnicalRequirements.Afterletdownisrestored,SteamGenerator#1Pressure Transmitterwillfaillowresultingintheassociatedsteamflowchannelfailinglowduetodensity compensationinputrequiringmanualcontrolofLoop1 feedwatercontrolvalve.SROwilldirect performanceofAOP-S.01(Optional)andAOP-1.06toselectunaffectedsteamflowchannelforcontrolandreturning feedwatercontrolvalvetoAuto. Technical specificationsmayalsobeaddressedforthefailedpressurechannel.Asmall condenservacuumleakwilloccurthatrequiresperformanceofAOP-S.02butisnotlargeenoughtorequireReactorand Turbine Trip.After condenservacuumleakis adequatelyaddressed,MainFeedwaterPumpAwilltripduetospuriouslowvacuumtripresultinginplantrunback.Crewmayelectto conservativelytripduringrunbacksince TDAAFWisnot availableand1B-BMDAFWPumpisairbound(Seebelow).ThreeminutesafterMFPAtrip,MFPBspeed controllerwillfailtozeroresultinginlossofallMain feedwaterflow.ReactortripwillberequiredduetolossofSteamGeneratorlevelifnot already initiatedduringrunbackandcrewwillenterEmergency procedure E-OandtransitiontoES-0.1.WhenAFWpump1B-BstartsduetoMainFeedwaterpumpAtrip,itwillbeairbound.Crewmay eventuallyinitiateventingofthepumpcasingandthepumpmayberestoredfollowingventing.Severalminutes (-5)aftertheRxTrip,adifferentialfaultwilloccuron6.9KvShutdown1A-AresultinginlossofthelastChargingpumpandthelastMotordriven AuxiliaryFeedwaterpump1A-Aresultingin transitiontoFR-H.1forlossof secondaryheatsink.Scenario Failure/EventtimingshouldensureallS/Glevelsarelessthan10%atthistimeorcloseenoughtoensuretimelyentryintoFR-H.1.AfterenteringFR-H.1thecrewwillinitiatemanualSlandRCSfeedandbleedsincetherearenochargingpumpsavailable.UponinitiatingSIforFeedandBleed,thecrewwillberequiredto manuallystartthe1BSafetyInjectionpumpthatfailedtoautostartasthesourceofRCSFeed.TheCrewwillcontinueinFR-H.1torestore feedwaterflowbyeitherventingtheairboundAFWpumpor establishing condensateflowtoatleastoneS/G.Thescenariomaybeterminatedafter feedwaterflowisestablishedtoatleastoneSteamGenerator. Appendix 0NUREG1021Revision9 Page1of3 NRC08ARev0 CONSOLE OPERATOR INSTRUCTIONS (Sim.SetupTheseremote functionsareactivewhentheSCENSfileisloaded.Event#1:DecreasePowerasdeterminedbyNRCExaminer. Event#2:WhenPowerDecrease complete as determinedbyNRCExaminer,Insertthis Malfuinction using Key 1 Event#3:When DeterminedbyNRCExaminer,insertthis Malfunction using.<ey 2.IPerformswitchcheck.Allowthe simulatortorunforatleast3minutesbeforeloadingSCENfileorstartingtheexercise.ThiswillinitializeICS. Load SCENS: NRC08A Place simulatormomentarilyinRUN,PlaceOOSequipmentinrequiredpositionwithtags,ClearalarmsandReturntoFREEZE.IMFFW07Cf:1 lOR ZLOHS151A_GREEN f:O lOR ZLOHS117A_GREEN f:O lOR ZLOHS118A_GREEN f:OlORZLOHS3136AA_GREEN1 f:O lOR ZLOHS3136AA_GREEN2 f:OlORZLOHS3136AA_RED1 f:O lOR ZLOHS3136AA_RED2 f:O lOR ZDIHS3136AA f:OlORZLOHS3179AA_GREEN1 f:O lOR ZLOHS3179AA_GREEN2 f:OlORZLOHS3179AA_RED1 f:O lOR ZLOHS3179AA_RED2 f:O lOR ZDIHS3179AA f:OIMFNI07Af:120 k:1IMFCV01Bf:1k:2 Initialize simulator atRTPBOL.Place Mode_1_placard on panels.Place..A.Train Week sign on the simulator. Ensure1B-B Charging Pumpisin operation.TDAFWPUMPISINOPERABLE. Close FCV-1-17&18&place Hold Notice on1-17&18 and FCV-1-51.Also place Hold order on TDAFW Pump ERCW supply valves.Place Protected Equipment tags on MD AFW pumps.-100%DECREASEPOWERTO93%FORTURBINEVALVETESTING.NISPOWERRANGECHANNEL1(N41)OUTPUTSIGNALFAILUREHIGH. Acknowledge request to Reactor Engineering to perform O-S/-NUC-OOO-011.0, Moveable Detector Determination of Quadrant Power Tilt.WhenIMs or MSS contacted to Remove failed power range channel from service per AOP Appendix, inform the crew thattheIMs will reporttotheMCRin -45 minutes.CHARGINGPUMPBTRIPWhenthe Support SROIAUO are dispatched to investigate, wait-5 min.and report that the relay target is instantaneous overcurrent and the motor smells hot. CONSOLE OPERATOR INSTRUCTIONS Page2of3 NRC08ARev0 (Event#4:WhenIMFRX26A f:O k:3STMGEN#1PRES TRANSMITTER FAILURE,DeterminedbyNRCCHNLIPT-1-2AFAILSLOWExaminer,insertthisMalfunctionusingWhenMSS or IMs contacted, then inform the Key 3.crew that IMs willbeupinthe MeR within 45 minutes.Event#5:WhenIMFCN09 f:O.15 k:4LOSSOFCONDENSERVACUUM-SMALLLEAKDeterminedbyNRCExaminer,insertthis IF personnel are dispatched to look for theMalfunctionusing vacuum leak wait-5 min THEN report a noise in Key 4.the Turbine Building.near A and B main condenser north sideonel685.Event#6:WhenIMFFW11Af:1k:5MFPATRIPFROMSPURIOUSLOWVACUUMDeterminedbyNRC SIGNALExaminer,insert these Malfunctions If dispatched to check pump locally, wait-5 min using and report no obvious problem locally.KeyS.TimeDelayed3minlORZDISIC4620Bf:2d:180k:5MFPTURBBSPEED CONTROLLER(SIC-46-20B)- ifterMFPAtripSPEEDDEMANDOUTPUT FAILSTO0%.(key-5)Event#7:ThisMalfIMFFW22Bf:1AFWPUMP1B-BAIRBOUNDisactivewhentheSCENSfileisloaded. When personnel are dispatched to check pump, wait5 minutes and report:(IFRUNNING) that 1B-B MDAFW pump casing is hot and pump does not sound normal.(IFNOTRUNNING) that 1B-B MDAFW pump casing is hot.Event#8:EventIMFED06Af:1d:300e:1DIFFERENTIALFAULTON6.9KVSDBD1A-A Trigger5minafterReactorTrip. If dispatched, wait-4 minutes and report a board differential relay operation. You cannot determine the cause but will continue to investigate. Event#9:ThisMalfisIMFSI13Bf:1SIPUMPAAUTOSTARTFAILURE(ALLSIGNALS)activewhenthe-PUMPWILLMANUALLYSTARTSCENSfileisloaded CONSOLE OPERATOR INSTRUCTIONSPage3of3 NRC08ARev0 (If DispatchedtoVentDMFFW22BRESTORESAFWPUMP1B-B AIRBOUND TO1B-BAFWPump, SIMULATE VENTING COMPLETE.DELETE malfunction only AFTER RCS If directed to Vent and Restore AFW pump 18-8,feedandbleedis stall until after ReS feed and bleed hasstartedoras commenced per FR-H.1, ensure malfunction has DeterminedbyNRC been deleted.and report that venting is complete.Examiner.If Dispatched toIRFCNR06f:1k:6 1-FU2-6-21D &147DDISABLE INTERMEDIATEperformEA-2-2HEATERISOLATION AppendixAPart1to removefusesto If dispatched to pull fuses, ensure remote disable intermediate function is entered and wait-5 min to reportheaterstringisolation fuses removed.insertRemote functions using Key 6 If Dispatched toIRFRPR11f:1k:7BLOCKAUTOSIONHIGH CONTAINMENTperformEA-99-1to PRESSURE (EA-99-1)BlockAutoSIsignals,nsertRemote If dispatched as MIG to perform EA-99-1, wait-function using 10 minutes, enter remote function and report Key 7 complete.If RequestedtoIRF EDR66Af:1k:8120VAC INSTRUMENT POWERRACKA Transfer 1-M7 TRANSFER SWITCH InstrumentRackA to Alternate, Use KEY-8 NOTE: Evaluator will need to intercept personnel dispatchedtoM-7 back panel to Operate Transfer switch and then request Console operator to enter KEY-B. I Appendix D Required Operator ActionsFormES-D-2 IReducePowerForTurbineValveTesting (OpTestNo.:EventDescription:NRCScenario

1. 1Event#Page1of45-----""";';;"'-..,1 Time II Position IIApplicant'sActionsorBehaviorBoothInstructor:NoactionrequiredforEvent1 Indications available:

None ApplicableDirectaloadreductioninaccordancewith0-GO-5NormalSROPowerOperations,Section5.3,and 0-SO-62-7 Boron ConcentrationControl,Section6.4. Evaluator Note:FollowingStepsarefrom 0-SO-62-7 Boron Concentration Control, Section 6.4 CAUTION:ReturningtheBoricAcidBlendertoserviceafterunplugging,cleaning,or maintenanceonBoricAcidSystemcouldintroducedebris,sludge,airorsolidifiedboronintoCCPsuctionresultinginpumpdamage.ExtremecaremustbeexercisedtoproperlyflushtheBoricAcid pipingfollowinganoutage. NOTE:Ifalarge amountofborationisrequired(plantshutdown),pzrheatersshouldbe energizedtocausesprayoperationforequalizingboronconcentrationinRCSand pressurizer. ENSUREmakeupsystemalignedfor AUTO operation RO in accordancewithSection5.1. NOTESteps2and3are NIA for minorpowerchangesORifimmediateborationisrequiredtomaintainshutdownmargin,tomaintainrodsabovetheinsertionlimit,duringan emergency shutdown (AOP-C.03),duringrecoveryofa dropped/misalignedrod(AOP-C.01),orat Chemistry recommendationinmode3,4,5or6. RECORD the quantityofboricacidrequiredtoachievedesiredboronconcentrationusingAppendixD. RO gals PERFORMAppendixIIndependentVerificationofCalculationforAmountofBoricAcidorPrimaryWater. Crew(N/AifApp.DwasperformedbySROtoverifydatafromRx Engineering) I Appendix 0 Op Test No.: Event

Description:

Required Operator Actions NRC Scenario#1 Event#Reduce Power For Turbine Valve TestingFormES-D-2 IPage2of Tim Position II Applicant's Actions or Behavior (DETERMINE availableboricacidvolumein in-service BAT.RO gals PLACE[HS-62-140A],BoricAcidto Blender Flow Control ROSwitchtothe STOP position.PLACE[HS-62-140B],CVCSMakeup SelectorSwitchtothe RO BORATE position.ADJUST[FC-62-139],BoricAcidFlow Controllertothe ROdesiredflowrate. SET[FQ-62-139], Batch Integratortothedesiredquantity. RO PLACE[HS-62-140A],BoricAcidto Blender Flow Control ROSwitchtothe START position.ENSUREBoricAcidPumpalignedto blenderinFASTspeed RObyrightredlight LIT on[HS-62-230A] OR[HS-62-232A]. NOTE Flow oscillations and/or erratic controller response may require manual operation ofBoricAcidFlow Controller [FC-62-139]untilstable conditions exist.VERIFYBoricAcidFlow established. RO NOTE It may take approximately 15 minutesbeforeany changes to reactivity are indicated on nuclear instrumentationorRCS temperature indication. IF reactoriscritical, THEN MONITOR nuclear instrumentation and reactor coolant temperature to ensure proper response ROfromboration. NOTE BAT operabilitylimitsare prescribedbyTRM 3.1.2.6(Modes1-3)or3.1.2.5 (Modes 4-6). I Appendix D Required Operator ActionsFormES-D-2 IOpTestNo.:NRCScenario

1. 1Event#Page3of45......;...----EventDescription:ReducePowerForTurbineValveTesting Time Position ROApplicant'sActionsorBehavior IFVolume'ControlTanklevel increasesto63percent,THENENSURE

[LCV-62-118], VolumeControlTankDivert Valve OPENStodivertexcess watertotheHoldupTank. NOTE SamplemaybeobtainedatnormalRCSsampleintervalsprovidedtheunitisatpowerandtheunit responsefollowingtheborationisasexpected. WHENborationiscomplete, THEN RO*PLACE[HS-62-140A],BoricAcidto Blender FlowControlSwitchtothe STOP position.*CHECK no primary waterflowoneither [FI-62-142A] OR[FQ-62-142].*ENSURE[FC-62-142], Primary Water to Blender Flow*Controllerisin AUTOpositionandthe potentiometer (dial indicator)issetat35%.

• ADJUST[FC-62-139],BoricAcidFlow Controllertothedesiredblendsolutionin accordancewithTI-44Boron Tables.*ENSURE[FCV-62-128]

is CLOSED.*PLACE[HS-62-140B],CVCSMakeup Selector Switchtothe AUTO position.*PLACE[HS-62-140A],BoricAcidto Blender FlowControlSwitchtothe START position.*IFRCSboronsamplerequired, THEN NOTIFY ChemLabtoobtainRCSboronsample. NOTE Borationisdoneinbatchesuntilthetotalboronand/orpowerchangeiscompleted. REPEATthissectionasrequiredto completetotalboronROchange.WHENtotalborationiscomplete, THEN: RO*REALIGNtheblendercontrolsfor AUTO makeuptotheCVCSin accordancewithSection5.1.

• NOTIFYChemLabtoobtainRCSboronsample.

IFinmodes1,2,or3, THEN ENSURE requirementsofTRM US 3.1.2.6aremet. I Appendix 0 Required Operator ActionsFormES-D-2 IOpTestNo.:NRCScenario

1. 1Event#......;..Page4 of 45 Event

Description:

ReducePowerForTurbineValveTesting Time II Position II Applicant's ActionsorBehavior Evaluator Note:FollowingStepsarefrom0-GO-5, Normal Power Operation, Section 5.3 BeginningatNotespriortostep7. NOTES 1)GuidanceonrestorationofEHCControlsafteraBOPrunbackiscontainedin Appendix B, Turbine Runback Restoration.2)Forcore operating recommendations for situationssuchasendofcorelifecoastdownorunusualpowermaneuvers,contact ReactorEngineeringfor guidance.3)Itis recommendedthatAFDbecontrolledwithinthetargetband.4)The following general approachshouldbeusedduringpowerreduction: (a)borateRCStoreduceRCSTAVGwithinlimits ofTREF,(b)reduceturbineloadto match TREFwithTAVG(c) periodicallytakerodcontroltoMANUALfrom AUTO and insertthebanktomoveAFDnearthetargetvalue,(d)returnrodcontrolto AUTO whennotusingthebanktocontrolAFD,and(e)repeattheaboveas necessary to accomplishtheloadchange. 5)Actions effecting reactivityaredirectedinthefollowingstep.0-SO-62-7 requirementsshallbe adheredtofor reactivity changes(i.e.reactivitybalance,amountsofboricacidorwater).All appropriate verificationsandpeerchecksshallbeutilizedduring performance. INITIATEaloadreduction. BOP BOP MONITORturbineloaddecreasing. CAUTIONDoNOT exceed a load change rate of plus or minus 5%/minute or a step change of 10%NOTETAVGis programmedfrom578.2°Fat100%powerto 54rFatzeropoweratarateof 0.312°Fper%power. MONITORthefollowingduringtheloadreduction:TAVGfollowing TREF program.CrewAllRPls,groupstepcountersforrodinsertionlimitsand inoperablerodsorrod misalignment, LoopT,andNISforcorrectpower distribution and quadrantpowertilts.CoreAFDwithin -5%controlbandaroundthepowerlevel dependenttargetvalue. I Appendix DRequiredOperatorActionsFormES-D-2 IOpTestNo.:NRCScenario

1. Event#.....;..Page5 of 45 Event

Description:

ReducePowerForTurbineValveTesting Time Position II Applicant'sActionsor Behavior (NOTEValvepositionlimitand governorcontrolmeteraredisplayedonEHCDisplaypanel1 ,2-XX-047-2000 (M-2).Valvepositionlimit approximately10%abovethecurrent BOP governorcontrolindicationasturbineloadischanged. Lead Examiner may direct initiation of the next event at his discretion I Appendix DRequiredOperatorActionsFormES-D-2 IOpTestNo.:NRCScenario

1. 1Event#2EventDescription:NISPowerrangeChannelI(N41)FailsHighTimePositionApplicant'sActionsorBehavior (Booth Instructor:

When directed, initiate Event 2 Indications available: Control Rods Inserting M-4 Indicator Full Scale 1-AR-M4-B.D31PRSNISPOWERRANGEOVERPOWERROD WITHDRAWAL STOP 1-AR-M4-B.E3NC-46BNISPOWERRANGE CHANNEL DEVIATION 1-AR-M6-A.B1NC-41U1NC-41-KNISPOWERRANGEHIGHNEUTRONFLUXRATE 1-AR-M6-A.01NC-41RNISPOWERRANGEHIGHSETPOINTHIGHFLUX LEVELRecognizes,announcesunexpectedControlRodsinsertionROandtakesImmediateactiontoplacerodcontrolinmanual. Crew us RORefertoalarmresponseprocedures.DetermineNISInstrumentFailurehasoccurredanddirectentryto AOP-1.01,NuclearInstrumentMalfunction,section2.3 PLACErodcontrolinMAN. EVALUATEthefollowingTechSpecsfor applicability:*3.3.1.1(3.3.1), Reactor Trip System Instrumentation (Action 2 Applies)SRO*3.3.3.5,RemoteShutdownInstrumentation(N/A)*3.3.3.7,AccidentMonitoringInstrumentation(N/A)*SR4.2.4.2,QPTR withonePR Channel Inoperable (Surveillance requirement Applies) I Appendix D Required Operator Actions Form ES-D-2 IOpTestNo.:NRCScenario

1. 1Event#2EventDescription:

NIS PowerrangeChannelI(N41)FailsHigh Time II Position IIApplicant'sActionsorBehavior (PLACE following switcheslocatedon Detector Current Comparator drawer[M-13,N50]inposition corresponding tofailedPowerRangeChannel(N41):

• Upper Section RO*LowerSection
• AppropriateRodStop Bypass switch*Appropriate Power Mismatch Bypass switch DEFEATfailedPowerRangechannel USING Comparator Channel Defeat switch: RO*ComparatorandRate Drawer[M-13,N37]

RESTORETavgwithin1.5°Fof TrefUSINGoneofthe following:

• manualrodcontrol OR Crew*RCS boration/dilution OR*turbineloadreduction ENSURE OPERABLEPowerRangechannelselectedtothe following:
• Nuclear Power Recorder[M-4,NR-45]

RO*Nuclear Power Recorder-(.6.1)[M-4,NR-45]

• RCSTemp.6.T recorder-(greenpen)

[M-5, XS-68-2B]RETURNrodcontrolto AUTO if desired.RO RO CHECKreactorpower greaterthan75%. I Appendix D Required Operator Actions Form ES-D-2 IOpTestNo.:NRCScenario

1. Event#2 of 45EventDescription:

NIS PowerrangeChannelI(N41)FailsHigh Time II Position II Applicant'sActionsor Behavior NOTIFY Reactor Engineering to Crew PERFORM O-SI-NUC-OOO-011.0, Moveable Detector Determination of Quadrant PowerTiltRatio. NOTIFY 1Mtoremovefailed power range channelfromserviceUSING appropriate Appendix: POWER RANGE PROT APPENDIX CHANNEL CH SRO N-41!A N-42 II B N-43 III C IV D (N41 Requires Appendix A)SROGOTO appropriate plant procedure. When technical specificationshavebeen identifiedorat discretionoftheLead Examiner, proceedtothenextevent I Appendix D Required Operator Actions Form ES-D-2 IOpTestNo.:EventDescription:NRCScenario

1. 1Event#ChargingPump1BTrip 3TimePosition Applicant'sActionsorBehavior

((BoothInstructor: When directed,initiateevent 3 Indications available: MotortripoutAlarm,PanelM-1 Motortripout Buzzer White Disagreementlighton1BCCPHandswitch 1-AR-M6-C, 0-3,FS-62-93A1BCHARGINGLINEFLOWABNORMAL Crew Refertoalarm response procedures Perform Alarm Response procedure forCharginglineflow RO Abnormaltoplace standby ChargingPumpin service andrestoreletdown. RO CHECK charginglineflowon [1-FI-62-93A]. Evaluator Note: Steps 2 through4ofARPareNot applicableStep5c follows below.Note If sufficient time existstoobtainalocal inspectionofthe Standby pump,thenhaveanAUO conduct inspectionpriortostartingpump. IFCCPtrippedorfailed,THENPERFORM the following:1.IF Thermal Barrier flowispresent, THEN A.VERIFY 1-LCV-62-132and-133 OPEN and VCT level>8%OR RO 1-LCV-62-135 AND/OR 1-LCV-62-136 OPEN.B.ANNOUNCEpumpstart over PA AND START the standbyCCPand check for proper operation. I Appendix D Required Operator ActionsFormES-D-2 IOpTestNo.:EventDescription:NRCScenario

1. 1Event#ChargingPump1BTrip 3 Time II Position IIApplicant'sActionsorBehavior

((CautionStartingthe standbyCCPwithRCPseal temperature greaterthan230°Fcouldleadto seal damage.2.IFthermalbarrierflowisNOTpresentorislostafterpumptrip,THENA.ENSUREsuctionpathandVCTLevelarenormal. B.VERIFYallRCPSealslessthan230°F.ROC.ANNOUNCEpumpstartoverPA AND START the standbyCCPandcheckforproper operation.(Step Should Be N/A)3.REESTABLISHchargingandletdownin accordancewith1-RO SO-62-1, Chemical&Volume Control System.EvaluatorNote:Followingstepsarefrom 1-S0-62-1 Note This Instructionistobeusedifletdownhasbeentakenoutofserviceorhasisolated, charging still remainsinserviceandCVCSdeminstatusisunchanged. Note Following Instruction closelymaypreventopeningletdownreliefvalve.ENSUREfollowingorificeisolationvalvesare CLOSED:*1-FCV-62-72 RO*1-FCV-62-73

• 1-FCV-62-74 RO PLACE[1-HIC-62-78]

in MANUAL,ANDOPEN[1-TCV-70-192]to-50%.ENSUREfollowingletdownisolationvalvesareOPEN: RO*1-FCV-62-69

• 1-FCV-62-70
• 1-FCV-62-77 I Appendix D Required Operator ActionsFormES-D-2 IOpTestNo.:EventDescription:NRCScenario

1. 1Event#ChargingPump1BTrip 3 of 45 Time PositionApplicant'sActionsorBehavior (CautionFlashinginletdownlinemayoccurif1-PCV-62-81isopenedexcessively.

RO PLACE[1-HIC-62-81A]inMANUAL,AND ADJUST[1-PCV-62-81]to50-60%OPEN(40-50%output). CautionStep[6]needstobe performed immediately afterstep[5]is completed to prevent flashing in letdown line.OPENoneoftheletdownorificeisolation valves (N/A one(s)notused): RO*1-FCV-62-72

• 1-FCV-62-73
• 1-FCV-62-74 Note Normalletdownpressureis325psigatoperatingtemperature.

RO ADJUST[1-HIC-62-81A]toobtaindesiredletdownpressureasindicatedon [1-PI-62-81]. RO PLACE[1-HIC-62-81A]inAUTO.NoteNormalletdown temperature is-100°F.ADJUST[1-HIC-62-78A]toobtaindesiredletdown ROtemperature,asindicatedon [1-TI-62-78]. RO PLACE[1-HIC-62-78A]inAUTO.Note Letdown temperaturemayswingduetorepeatedactuationof TIS-62-79B/Aonhigh temperature causing TCV-70-192tofullyopen. I Appendix D Required Operator ActionsFormES-D-2 IOpTestNo.: Event

Description:

NRCScenario

1. 1Event#ChargingPump1BTrip 3of45 Time II Position II Applicant'sActionsor Behavior RO IF necessarytostabilizeletdown temperaturedueto oscillationsinCCSflow, THEN PERFORM followingtogaincontrolofCCSflow throughletdownheat exchanger:Openthefollowingbreaker:*Vital Instrument Power Bd 1-111 1-BKRA-250-NG/15-F WHENletdownheat exchanger outlet temperature is stabilized at approximately 100°F, THEN CLOSEfollowingbreaker:*Vital Instrument Power Bd 1-111 1-BKRA-250-NG/15-F (Step Should Be N/A)Note 1-TCV-62-79 (letdown temperature divertvalve)shouldbeinbypasspositionifthe temperature reaches 140°F.IFMixBedHI TemperatureBypassvalve

[1-HS-62-79A] auto bypassesDIonhigh temperature, THEN RO RO ENSURE letdown temperaturereturnsto NORMAL AND PLACEdemininserviceusing [1-HS-62-79A].(Step Should Be N/A)IFPZRlevelisonprogramandauto operationisdesired, THEN[a]IF[1-HIC-62-93A] deviation meterisoffscalehighor off scale low THENPLACE[1-L1C-62-339] in MANUAL AND ADJUSToutputuntil [1-HIC-62-93A] deviation meter is approximately mid-scale.[b]PLACE[1-L1C-62-339] in AUTO.[e]PLACE[1-HIC-62-93A] in AUTO. I Appendix 0RequiredOperatorActionsFormES-D-2 IOpTestNo.:EventDescription:NRCScenario

1. 1Event#ChargingPump1BTrip 3 Time II Position II Applicant'sActionsorBehavior PERFORMIndependentVerificationforfollowingvalve(s)thatwere OPENED: (N/Aone(s)notused).

VALVE NO.DESCRIPTION IV INITIALS'I-FCV-132-69 Letdown Isolation RO/BOP'1-FCV-62-70 Letdown lsotation'1-FC'V-62-11 letdown Flow Isolation 1-FCV-62-72 letdown Orifice tsos.rrcv-62-73 letdo\,vi1 Orifice 11501.'l-FCV-62-14 letdown Orifice l:sot.Evaluator Note:ThefollowingTechSpecevaluationisnot specificallydirectedbythe ARP orSO performed.EvaluateTechSpecsandTechnicalRequirementsManualfor ChargingPumptrip.SRO*Tech Spec LCO3.5.2-ECCS Subsystems (72 Hour Action Applies)*TRM3.1.2.4-Charging Pumps-Operating (72 Hour Action applies)When technical specifications and Tech Requirementshavebeen identified, standby charging pumphasbeen placed in service, and letdown restored, or at Lead Examiner's discretion, proceed to the next event. I Appendix D Required Operator ActionsFormES-D-2 IOpTestNo.:NRCScenario#1Event# 4 Event

Description:

SteamGenerator#1SteamPressurechannelfailslow(PT-1-2A) Time II Position II Applicant'sActionsorBehavior (" Booth Instructor: When directed,initiateEvent 3 Indications available:

• Loop2 Feedwater Flow Decreasing
• 1-AR-M5-A-A7,STEAMGEN FEEDWATERFLOWHIGH*1-AR-M6-B,A2,LOWSTEAMLINE PRESSURELOOP1*1-AR-M6-B, A3,HIGHNEGATIVERATESTEAMLINE PRESSURELOOP1 CrewRefertoalarmresponse proceduresDirectentrytoAOP-S.01,LossOfNormalFeedwater,Sect2.1 SROSteps1-4IfSROgoes directly to AOP-1.06,thengotonext page.RESTORE steam generatorlevel(s)toprogram:

BOPa.PLACEaffectedlevel controller(s)inMANUAL: BOP*FIC-3-35A,S/G-1 b.CONTROL feedwaterflowonaffectedS/G(s) USING main BOP feedwaterregulatingvalve controller(s)torestorelevelto program.2.CHECKSteamFlowandFeedFlow BOPChannelsNORMAL.[M-4] RNO: TRANSFERassociatedSteamFlow selectorswitchto alternate channel: BOP LOOP TRANSFER SWITCH FLOW INDICATORS/G1 XS-1-3D (FI-1-3A)FI-1-3B I Appendix DRequiredOperatorActionsFormES-D-2 IOpTestNo.:NRCScenario#1Event# 4of45EventDescription:SteamGenerator#1SteamPressurechannelfailslow(PT-1-2A)TimePositionApplicant'sActionsorBehavior (Caution:FeedFlow transients may impactcorethermalpower. BOP 3.MAINTAIN steam generatorlevel(s)onprogram. BOP 4.CHECK S/G pressure instruments NORMAL.GOTO AOP-1.06, Steam Generator Instrument Malfunction. SRO Evaluator Note: SRO may directly enterAOp*1.06at next step.Directentryto AOP-1.06, Steam Generator Instrument SRO Malfunction,section2.1 NOTES: ChannelsIandII compensatetheirrespectivesteamflowsignalswhichinputtothe STEAM/FEEDWATERFLOWMISMATCHalarmsand S/G WaterLevelControl. ChannelsIIIandIVinputtotheSTEAM GENERATORLOOPSPRESSLOWalarm. VERIFYunaffectedsteamflowchannel SELECTED:*S/G-1 , XS-1-3D BOP PERFORMthefollowing:

• PLACEaffectedlevel controller(s)inMANUAL: 0 FIC-3-35A, S/G 1MATCHsteamflowand feedwaterflowonaffected S/G USING BOP main feedwaterregulatingvalve controller(s).

I Appendix D Required Operator ActionsFormES-D-2 IOpTestNo.:NRCScenario#1Event# 4EventDescription:SteamGenerator#1SteamPressurechannelfailslow(PT-1-2A) Time II Position II Applicant'sActionsorBehavior TRANSFERassociatedSteamFlow selectorswitchto alternate channel: BOP LOOPS/G1 TRANSFER SWITCHXS-1-3D(FI-1-3A) FLOW INDICATOR FI-1-3B (BOP BOP SROMAINTAINsteam generatorlevel(s)onprogram.PLACEmain feedwaterregulatingvalve(s)inAUTO.EVALUATEthefollowingTechSpecsfor applicability:*3.3.1.1(3.3.1),ReactorTripSystem Instrumentation*3.3.2.1(3.3.2), Engineered Safety Feature Actuation System Instrumentation.(Action 17 Applies)*3.3.3.5,RemoteShutdown Instrumentation*3.3.3.7, Accident Monitoring Instrumentation.(Action 1 Applies)NOTE1: MegawattthermalindicationonICS(U1118andU2118)maybeimpactedbythisfailure.NOTE2: If performingAOPinconjunctionwith AOP-1.11foranEagleLCPfailure,thenactionstohardtripbistablesshouldbedelayeduntilEaglesystemresetisattempted.Actionstohardtripbistablesmustbecompletedwithin6hoursUNLESSaffectedloopisrestored to operablestatusbyresettingEaglerack. NOTIFY 1MtoremovefailedS/Gpressure instrumentfromserviceUSING appropriate Appendix: SRO SRO LOOP INSTRUMENT NUMBERPROTCH1P-1-2A(P-514)IGOTO appropriateplantprocedure. APPENDIX A When Technical Specifications have been addressed, Lead Examiner may cue the next event I Appendix DRequiredOperatorActionsFormES-D-2 IOpTestNo.: Event

Description:

NRCScenario

1. 1Event#CondenserVacuumLeak 5of45TimePosition Applicant'sActionsor Behavior ((BoothInstructor:

When directed,initiateEvent5 Indications available:

• O-M-12A, C-2, 1-RA-90-119BCONDVACPMPLORNGAIREXH MaN INSTR MALFUNC*1-AR-M2-C, C6, CONDENSERVACUUMLOW*CondenserVacuumdegrading(MonitoredonrecorderorICS),Airinleakage increasing CrewRefertoalarmresponse procedure EvaluatorNote:Crewmayrecognizevacuumleakearlyandenterabnormal procedure AOP-S.02, Loss Of Condenser Vacuum,priortoalarm.IfAOPEntered DirectlygotoNextpageatNOTE.

VERIFYalarmvia[1-P/TR-2-2] recorder.BOP VERIFY required numberofCCWpumpsareinservice. BOP CHECK condenser vacuum exhaustonICSusingeither: BOPa.1F2700Aif 1-FCV-2-255isclosedb.1F2263Aif 1-FCV-2-255isopen.IF condenser vacuum exhaust flow>45CFM,THENENSURE BOP 1-FCV-2-255 OPEN.IFalarmisvalid,THENGOTO AOP-S.02, Loss of Condenser SRO Vacuum.NOTE:Useofthe highestreadingoperable condenser pressure instrument is conservative and recommended by engineering. I Appendix D Required Operator ActionsFormES-D-2 I (OpTestNo.:EventDescription:NRCScenario

1. 1Event#CondenserVacuumLeak 5 of 45TimePosition Applicant'sActionsorBehavior (MONITOR condenserpressureforturbinetripcriteria.

BOP*CHECKturbineload greaterthanorequalto30%.(MTLow CondenserVacuumTrip @3.9psia increasing) CHECK condenserpressurelessthanorequalto2.7psia. BOP (1-AR-M2-C, C-G, CONDENSER VACUUM LOW@2.7psia increasing.) ENSURE condenservacuumpumpsRUNNING. BOP (Operatorstarts1B CondenserVacuumPump) ENSURE condenser vacuum breaker CLOSED.BOP CHECKrequiredCCWPumpsRUNNING[M-15]. BOP NOTE:ICSpointsF2700AandF2263Awillalarmif Condenser Vacuum ExhaustFlowis45 cfm.DETERMINEvolumeof condenserinleakage USING thefollowingplant computer points: BOP*F2700A*F2263A*F2260A I Appendix D Required Operator ActionsFormES-D-2 I Op Test No.: Event

Description:

NRC Scenario#CondenserVacuumLeakEvent#5Page19of45TimePosition Applicant's Actions or Behavior (VERIFYinleakagevalueis <45cfmasindicatedbybothF2700AandF2263A. RNO:PERFORMthefollowing: BOP*ENSURE FCV-2-255, Condenser Vacuum ExhaustBypass,isOPEN.

• IF greaterthan5%RTP,THEN NOTIFYChemLabtoreevaluateVentFlowRateMonitor setpoint in accordance with 0-SI-CEM-030-415.0.

DISPATCH an operatortoPERFORMthefollowing: a.CHEC'Kloopsealonvacuumbreaker[TurbineBldg,706' elev].b.CHECKthefollowingcomponents:

• MainTurbinerupturediscsintact Crew*Condensershellintact
• Main FeedwaterPumprupturediscsintact
• MainTurbine exhaust hoods c.VERIFYMainSteamDumpDrainTanklevelcontroloperatingproperly.ENSUREcontrolrods controllinginAUTO.RO CHECK condenserpressureSTABLEorDROPPING.IFNOT:REDUCEturbineloadtomaintain condenservacuumUSINGoneofthefollowing:

BOP*AOP-C.03,RapidShutdownorLoadReduction.(preferred) OR*ValvePositionLimiter. Power Change not required, On Lead Examiner's cue, proceed to the next event I Appendix DRequiredOperatorActionsFormES-D-2 IOpTestNo.:NRCScenario

1. 1Event#6,7,8Page20of45EventDescription:

Main FeedwaterPumpAtrip,MDAFWpump1B-BAirbound,Main FeedwaterPumpBSpeedcontrollerfailsto0%.TimePositionApplicant'sActionsorBehavior (Booth Instructor: When directed, initiate Event 6 (Events7,and8 previously activated or automatically initiated) Indications of Main Feed Water Pump A Trip:*Main feedwater Pump tripped Alarms*Decreasing Feedwater flow to all Steam generators.

• Turbine and Reactor Runback Indications of MDAFW Pump 1B-B airbound:*Pump running with proper valve alignmentandno indicated AFW flow to loops 3 and 4.*Low discharge pressure and pump amps.Indications of Feedwater Pump B Speed control Fails to 0%.*Main Feedwater Flow rapidly decreasing
• Main feedwater pump B speed rapidly decreasing CrewAnnounceMFPtripandMonitor Turbine/Reactorrunback,S/GlevelsandRunningMainFeedwaterpumpresponse.

Evaluator Note: Crew may only complete a small portion of AOP-S.01, if any, prior to second MFP Speed Control failure (3 min afterMFPA trip)resulting in reactor trip.Also, crew may elect to trip the reactorasa conservative action during runback since TDAFW pump is not available and if they note the condenser vacuum spike during runback due to main steam entering from steam dump.If Rx Tripped crew will not enter AOP-S.01.SRODirectEntryintoAOP-S.01,section2.3. VERIFYturbinerunbackBOPtolessthan72 %load (-880 Mwe). I Appendix D Required Operator ActionsFormES-D-2 IOpTestNo.:NRCScenario

1. 1Event#6,7,8of45 Event

Description:

MainFeedwaterPumpAtrip,MDAFWpump1B-BAirbound,Main FeedwaterPumpBSpeedcontrollerfailsto0%.TimePositionApplicant'sActionsorBehavior (VERIFYcontrolrodsinserting automatically ROtomatchT-avgandT-ref. ENSURErunningmain feedwater pump FULLY LOADED: Speed controller outputatmaximum. BOP[M-3, SIC-46-20A or SIC-46-20B] EvaluatorNote:CrewshouldidentifyAirboundAFWPumppriortoorduring performanceofthefollowingstep.Whenidentified,crewmaystopthepumpor dispatch personneltocheckthepumplocallypriortostoppingit. Followingfieldreportonpumpstatus,crewshouldalsoinitiateventingofthepumpcasing. ENSUREAFWpumpsstarted: a.MDAFWPumpsRUNNING.[M-4] b.TDAFWPumpRUNNING.[M-3]BOPc.TDAFWPumpLCVsOPEN.[M-3] d.MDAFWPumprecirculationvalvesCLOSED:[M-4]

• FCV-3-400*FCV-3-401 EvaluatorNote:SecondMain FeedwaterPumpspeedcontrolfailurewilllikely occurpriortooraroundthisstep.

Recognize main feedwater flow decreasing and attempt ROmanualspeedcontrol SRO Direct/Ensure Reactortripbasedon decreasingS/Glevels. Reactor trip terminatesthisseriesofevents. I Appendix D Required Operator Actions Form ES-D-2 IOpTestNo.:NRCScenario

1. Event#9&10 Event

Description:

LossofHeatSinkFeed/Bleed-1AshutdownBoarddifferentialFault,SIPump1Bautostartfailure. Time II Position II Applicant'sActionsor Behavior Booth Instructor: Remaining Events Automatically initiated. Indications available: 1A shutdown board differential Fault (5 minutes after Rx Trip)*Loss of Train A Equipment including: o Last Aux Feedwater Pump 1A.o Last Charging Pump 1A.*Emergency DIG Start (Cooling water not available)

• Multiple alarms1B safety I njection Pump auto start failure (When 51 actuatedinFR-H.1)*Green Light on Handswitch*No Pump flow or amps SRO RO Directs transition to E-O, ReactorTripor Safety Injection VERIFY reactor TRIPPED:*Reactor trip breakers OPEN*Reactortripbypass breakers DISCONNECTED or OPEN*Neutronflux DROPPING*RodbottomlightsLIT*Rodposition indicatorslessthanorequalto12steps.

(VERIFYturbineTRIPPED:BOP*Turbinestopvalves CLOSED.VERIFYatleastonetrainof shutdown boards ENERGIZED. BOP EVALUATOR Note: 51 not required at this point crew will transition to ES-O.1 in the next step and continue untilFR-H.1is required following SO Board Differential fault.The exact Transition is crew dependent therefore steps may be included that are not performed in ES-O.1. I Appendix DRequiredOperatorActionsFormES-D-2 IOpTestNo.:NRC Scenario#1Event#9&10 (Event

Description:

LossofHeatSink Feed/Bleed-1AshutdownBoard differentialFault,SIPump1Bautostartfailure. (Time II Position II RO Applicant'sActionsor BehaviorDETERMINEifSIactuated:*ECCSpumpsRUNNING.*AnySIalarmLIT[M-4D](RNO)DETERMINEifSIRequired:a.IFanyofthefollowingconditionsexist:*S/GPressurelessthan600psig OR*RCSpressurelessthan1870psig, OR*Containmentpressuregreaterthan1.5psig THEN ACTUATE SIb.IFSInotrequiredTHENPERFORMthefollowing:*MONITORStatusTreesGOTOES-0.1,ReactorTripResponse EVALUATOR Note: During performance ofES-0.1,at some point Shutdown board 1A will be lost.Crew should note that the 1A DIGhasno cooling water and emergency stop it.If not addressed by crew early, if will be addressedinP.05as discussed below.Crew may designate one of the ROs (most likely the BOP)to performAOP-P.05 for Loss of Shutdown Board when it occurs.Details ofAOP-P.05areat the end of this event guide just prior to event guide for ES-0.5.(SRO RO BOPEnteranddirectES-0.1,ReactorTripResponseMONITORSINOTactuated:*SIACTUATEDpermissiveDARK[M-4A,D4] VERIFY generatorbreakersOPEN. I Appendix D Required Operator ActionsFormES-D-2 I (OpTestNo.:EventDescription:NRCScenario

1. 1Event#LossofHeatSinkFeed/Bleed-1AshutdownBoarddifferentialFault,SIPump1Bautostartfailure.

({\Time II Position II RO BOP Applicant'sActionsorBehaviorMONITORRCStemperatures:IFanyRCPrunning, THEN CHECKT-avgstableatortrendingto between 54rFand552°F.(RNaNextPageIfRequired)(RNaIfRequired) IF temperature less than and dropping.THEN PERFORM the following: a.ENSURE steam durnps and atmospheric reliefs CLOSeO.b.ENSURE S/G blQwdowniSolation valves CLOSeO.c.IF cooldown contin,ues, THEN PERFORM thefolowlng: 1)CONTROL total feed flow USING;&\..3-8, Manual Cmtro1 of AFWFlow.2)MAINTAIN total feed flow greater than 440 gpm UNTIL narrow range level greater than 10%in at IHst one SlG, 3)DEPR.ESS RESET on MSR control panel" 4)IF any MSR temp contrOl valve fails to dose.THEN ISOLA TE HP steam to MSRs.d.IF cooktovJn still continues, THEN CLOSE MSIVs and bypass valves. I Appendix D Required Operator Actions Form ES-D-2 ILossofHeatSink Feed/Bleed-1A shutdown Board differentialFault,SIPump1B auto start failure.(Op Test No.: Event

Description:

NRC Scenario#1 Event#9&10 (Time II Position II BOP RO Applicant's Actions or Behavior MON,rORfeedwater status: a. Ie:ssthan 650°F, b.MFWreglJlatlng valves CLOSED.c,MFW Tegwlating bypass valve controller outputs ZERO.d, MFW isolatio'!'l valves CLOSED.e, MFW pumps TRIPPED.f, MFW ftow ZERO.g.Tofm feed now to S/Gs greater than 440 gpm.CHECK if emergency boratJon is required: a.VERIFY all control rods fully inserted:..Rod bottom lights LIT*Rod position indicators less than or equaJ to 12 steps.b.MONITOR RGS temperature:*T greater than 5400 F if any Rep runnl\ng OR*T",cojd greater than If all Reps stopped. I Appendix D Required Operator Actions Form ES-D-2 ILossofHeatSinkFeed/Bleed-1AshutdownBoarddifferentialFault,SIPump1Bautostartfailure. (OpTestNo.: Event

Description:

NRCScenario

1. 1Event#9&10 Time II Position II BOP Applicant'sActionsor Behavior ANNOUNCE reactor trip USING PA system., MONITOR pressurIzer level control: a.CHECK pressurizer level greater than 17%, RO b.VERIFY charging IN SERVICE, c.VERIFY letdown IN SERVICE, d.CHECK pressunzerl&vel trending to 25%(normal range 20%to 30%).MONITOR pressurizer pressure control: (RO BOP BOP a, PRiissurizer pressure gfeaterfhan 1870 psig.b.Pressurizer pressure stable at or trending to 2235 psig (normal range 2210 psig to 2260 psig).MAINTA&N SlG narrow range levels: a.Greater than 10%.VERIFY AC busses ENERGIZED from start busses.CAUTION Annlng steam dumps in pressure mode with demand signal presen.t could result in rapid R.CS cooldown.

I Appendix 0 Required Operator Actions Form ES-0-2 IOpTestNo.:NRC Scenario#1Event#9&10Page27of45 ---';'----ii Event

Description:

LossofHeatSinkFeed/Bleed-1AshutdownBoard differentialFault,SIPump1Bautostartfailure. Time II Position II BOP Applicant's Actions or Behavior DETERMJNE if steam dump to condenser available: a, CHECK condenser AVAILABLE:

• c-s CONDENSER INTERLOCK permlulve UT[M-4A.E6],.At least one Intact SlG MSIV OPEN, b.PLACE strtam dumps in STEAM PRESS mode: 1)PLACE steam dumps in OFF..2)ENSURE steam dumps in steam pressure mode.3)ENSURE zero output (demand).4)PLACE steam dumps In ON, 5)ADJUST steam dump controller setpoint to 84%(1005 psig)in AUTO, Evaluator Note: It is assumed that transitiontoFR-H.1 will occur prior to or at this step.Transition shouldbebasedonRed Status tree path when the last AFW pump is lostdueto the loss of the shutdown board.EnteranddirectactionsofFR-H.1, loss of Secondary HeatSROSink.(CAUTION Feeding an Intact or Ruptured S/G is preferred to feeding a Faulted SIG.Thermal stresses from feeding a Faulted SIG could rupture tubes, resulting i'n a Fautted-AND-Ruptured S/G.

I Appendix D Required Operator ActionsFormES-D-2 I Op TestNo.:NRC Scenario#1 Event#9&10 Event

Description:

LossofHeatSink Feed/Bleed-1A shutdown Board differentialFault,Sl Pump1B auto start failure.Time Position Applicant's Actions or Behavior DETERMlNE procedure appIkability: a.CHECK the following:

• Total feed flawless than 440 gpm due to operator action BOP directed by another procedure.

AND*Total feed flow capabiliity of greater than 440 gpm AVAilABLE. (RO MONITOR RWST greater than 27%.CHECK if secondary heat sink.required: 8.RGS pressure greater than any BOP non-Faulted SIG pressure.D.RCS temperature greater than 3.50 QF.RO RO MON'ITOR at least one CCP available.(RNORequiredsinceLastCCPwaslostwiththeSDBoardDifferentialFault.)(RNO)STOP ail RCPs.Evaluatornote:This shouldbedone prior to openinq PORV's (RNO)SRO GO TO Caution prior to Step 1 EL I Appendix D Required Operator Actions Form E8-D-2 ILossofHeatSink Feed/Bleed-1A shutdown Board differentialFault,SI Pump1Bautostartfailure. (Op Test No.: Event

Description:

NRC Scenario#Event#9&10 Time Position Applicant's Actions or Behavior CAUTION Any delay in completing Steps 16 through 19 could result in fuel damage.ACTUATESL RO Evaluator Note: Crew should identify and start 51 Pump 1 B that failed to auto start from 51 signal prior to or during this step.CRITICAL Task1 Part 1 RO VERIFY RCSfeed path: R CHECK ECGS pump status:*At least one GGP R.UNNING OR., At least one SI pump RUNNING.CriticalTask"Priorto10%Wide Range S/G level" ((RNOrequiredif 81Pumpnot previously started)START pumps.IF NO GCP or SI pump can be started, RO THEN PERFORM the following:(RestofstepN/A 81pumpshouldbe started) I Appendix 0RequiredOperatorActionsFormES-D-2 ILossofHeatSink Feed/Bleed-1AshutdownBoard differentialFault,SIPump1Bautostartfailure. (Op Test No.: Event

Description:

NRC Scenario#1Event#9&10Page30of45 (Time CRITICALTask1Part2 Position RO RO Applicant's Actions or Behavior VERIFY EGGS valve alignment for ftJl1mng pumps: 1)CCP suction ali!gned to RWST:*LCV-62-'135 or LCV-62-136 OPEN*LC\I-62-132 Of LCV-62-133 CLOSED 2)CCPIT valves OPEN:*FC\I-63-25 or FGV-63-2B*FCV-63--39 or FGV-63-40 3}Sl Pump suction valves OPEN:*FCV-63-5*FCV-63-47 (Train A)*FCV-63-48{Train B}4)SI Pump injection valves OPEN:*FCV-63-22*FCV-63--152 (Train A)*F CV-63-153 (Train B)ESTABLISH RCS bleed path: a.CHECK power to pressurizer POHV block valves AVAILABLE b.CHECK pressurizer PORV block valves OPEN.c.OPEN both pressurizer PORVs.(Powerwillbeavailabletoonlyoneblockvalvebutitshouldbeopen)CriticalTask"Priorto10%WideRanaeS/G level" I Appendix D Required Operator ActionsFormES-D-2 I Loss of Heat Sink Feed/Bleed-1A shutdown Board differentialFault,SI Pump1B auto start failure.(Op Test No.: Event

Description:

NRC Scenario#1 Event#9&10 of 45 Time Position RO Applicant's Actions or Behavior CHECK Res bleed path ADEQUATE:*Both Pressurizer PORVs OPEN*Both Pressurizer PORV block valves OPEN.EvaluatorNote:SROshoulddirectROstoperformsubstepsofthe following step.PERFORM the following WHILE continuing with this procedure: (SRO a.E-O, Reactor Trip or Safety Injection, Steps 1 through 4.b.ES-O.5, Equipment Verifications.(ES-O.5IncludedattheendoftheEvent Guides)MAINTAIN RCS heat removal: RO-ECGS flow*Pressurizer PORVs OPEN.RO RO RO RESET SI signaL RESET Phase A and Phase R MONnOR control air to containl'Ilient (Pane!oK and 6L]*1-FCV-32-80 Train A essential air OPEN-1-FCV-32-102 (2-FCV-32-103) Train 8 essenaat aif OPEN-1-FCV-:32-110 (2-FGV-32-111) Non-essential air OPEN I Appendix D Required Operator Actions Form ES-D-2 I Op TestNo.:NRC Scenario#Event#9&10 Event

Description:

LossofHeatSink Feed/Bleed-1A shutdown Board differentialFault,SIPump1B auto start failure.(Time Position RO Applicant's Actions or Behavior MONITOR if containment spray required: a.CHECK the following:

• Phase B ACTUATED OR*Conulinment pressure greater than 2.13 psig.(IfNO,proceedtosteptocheckRHR status)(IfYES, Continue)b.ENSURE containment spray INITIATED:

1J Containment spray p!umps RUNNING.2)Containment spray header isolation valves FCY-72-39 and FC\I-72-2 OPEN.3)Containment spray rea:rculation valves to RWST FGV-72-34 and FCY-72-13 CLOSED.4}Containment spray header fto\"\I'greater than 4750 gpm per train.(c.WHEN to minutes have elapsed THEN BOP VERIFY containment eur return fans RUNNING. I Appendix D Required Operator ActionsFormES-D-2 IOpTestNo.:NRCScenario

1. 1Event#9&10of45 Event

Description:

LossofHeatSinkFeed/Bleed-1AshutdownBoarddifferentialFault,SlPump1Bautostartfailure.TimePosition Applicant'sActionsor Behavior (CAUTION Operation of RHR pumps for greater than 100 minutes with miniflow valves open and NO CCS flow to RHR heat exchangers could result in pump damage.CHECK RHR status: RO a.CHECK RHR pumps RUNNING BOP D.CHECK ccs ALIGNED to RHR heat exchangers. MONITOR if containment spray should be stopped: d.CHECK any containment spray pump RUNNING_D_CHECK containment pressure less than 2.0 psig.(IfNO,ProceedtoMonitor Containment Vacuum Control)(IfYES, Continue)RO C.CHECK containment spray suction aligned to RWST d.RESET containment spray.e.STOP containment spray pumps and PLACE m A-AUTO.f.CLOSE containment spray discharge valves:*FCV-72-39, Train A*FCV-72-2, Train R I Appendix DRequiredOperatorActionsFormES-D-2 IOpTestNo.:NRCScenario

1. 1Event#9&10EventDescription:LossofHeatSinkFeed/Bleed-1AshutdownBoarddifferentialFault,SIPump1Bautostartfailure.

Time II Position II Applicant'sActionsorBehavior MONITOR if containment vacuum control should be returned to normal: (CRITICAL TaskOption1 a.CHECK containment pressure less than-1.0 psj'g..RO b.VERIFY conta:inment vacuum relief isolation valves OPEN:[paneI6K]*FCV-30-46 OPEN*FCV-30-47 OPEN*FCV-30-48 OPEN_A TIEMPT to establish AFW flow to at least one SIG in the following order of pliority-- Intact, Ruptured, Faulted: a.CHECK SIG blowdown isolanon valves CLOSED_b.CHECK control room indications for BOP cause of APiV failure:*CST level*AFW pump power supply*AFW valve alignment(StepContinuednextpage) CriticalTask:"Priorto exiting FR-H.1".EvaluatorNote:Ifnot previouslyperformedcrewmayinitiateventingofAFW pumpatthispoint. I Appendix 0 Required Operator Actions Form ES-D-2 I Op TestNo.:NRC Scenario#1Event#9&10 Event

Description:

Loss ofHeatSink Feed/Bleed-1A shutdown Board differentialFault,SIPump1Bautostart failure.Time II Position II Aoolicant's Actions or Behavior (c.ESTABLISH MD APW pump flow: 1)ENSURE MD AFWpumps RUNNING.2}ENSURE AFVV level contmj BOP valves OPEN.3)ENSURE MD AFW recirculation valves FCV-3-400 and FG\l-3-401 CLOSED.O.ESTABUSH TO AFW pump flow: (TDAFWFlownot availabledueto tacout)e.MONITOR AFVVflow available to at least one SlG.BOP (If Yes, Proceedtosteptocontrol ControlFeedFlow)(If NO.Continue)EvaluatorNote:IfAFWflow established byventingAFWpump,crewwillgotothelaststep in thiseventguide toControlFeed Flow to S/G.Steps beginning on thenextpagewillnotbe required. I Appendix DRequiredOperatorActionsFormES-D-2 IOpTestNo.:NRCScenario

1. 1Event#9&10of45 Event

Description:

LossofHeatSinkFeed/Bleed-1AshutdownBoarddifferentialFault,SIPump1Bautostartfailure. Time II Position II Applicant'sActionsor Behavior ((NOTE CRITICAL TasKOption2 Containment pressure greater tnant.S psig will prevent opening RN isolation valves until 51 signal is blocked using EA-9!J*i, BlockingAutoSl Signals.A.TTEMPT to establish feed flow from condensate system: a.NOTIFY MliG to perform EA-99-'l, Blocking Auto SI signals.b.CHECK condensate system IN SERVICE:BOP*Hotwell pumps*Condensate booster pumps c.BlOCKsignals:*Low pressurizer pressure SI*Low stearruine pressure SI.Critical Task:Prior to exiting FR-H.1".d.CHECK the following indications:

• PRESSURIZERSITRAINSA&B BLOCKED permissive UT[M-4A, 84]BOP*STEAr",1l1NE PRESS ISOllSI BLOCK RATE ISOL ENABLE permissive LIT[M-4A, A4].ROe.CHECK Containment pressure less than 1.5 psig.BOP (IfNO,SkipnextstepuntilautoSIsignalsBlocked)

I Appendix 0 Required Operator Actions Form ES-D-2 I Op Test No.: NRC Scenario#1Event#9&10 Event

Description:

Loss ofHeatSink Feed/Bleed-1A shutdown Board differentialFault,SI Pump1Bautostartfailure. Time Position Applicant's Actions or Behavior f.CHECK FV'V isolation valves OPEN.(RNOif Required)PERFORM the foUowing: 'l}ENSURE MFW reg valve controllers in MANUAL and output ZERO.2)ENSURE MFW bypass reg controllers In MANUAL and output BOP/RO ZERO.3)RESET SI signal.4)CYCLE reador trip breakers.5)RESET F'V'-/lsolation. 6)OPEN FWisolation valves for intact S/Gs.(BOP BOP g.AUGN condensate flow path to S/Gs USING EA-2-2, Establishing Secondary Heat Sink Using Main Feedwaier or Condensate System.h.CHECK Condensate flowpath established: ..At least one Feedwater Isolation Valve OPEN..Condensate flowpath to SiG aligned. I Appendix D Required Operator Actions Form ES-D-2 IOpTestNo.:NRCScenario

1. 1Event#9&10of45EventDescription:LossofHeatSinkFeed/Bleed-1AshutdownBoarddifferentialFault,SIPump1Bautostartfailure.

Time II Position II BOP BOP Applicant'sActionsorBehavior L DEPRESSURIZE one SIG USING SIG atmospheric relief val've UNTil condensate flow established: 1)ENSURE ail MS'(Vand MSIV bypass valves CLOSED.2)DUMP steam from one Intact SIG at maximum rate USING SfG atmospheric relief valve.J.CONTINUE depressurization UNTil condensate flow'established. k.WHEN condensate fi,ow established, THEN PERFORM the following: 1:)STOP SIG depressurization. 2)CONTROL pressure III selected S/G as necessary to maintain condensate flow.CONTROL feed flow to SfG: a.CHECK Core Exit TCs STABLE or DROPPING.b.CHECK wide range level BOP on selected SfG greater than [30%ADY]c.CONTROL S/G feed flow as necessary to restore narrow range level 111 selected SfG between 10%[25%ADV]and Scenario may be terminated whencrewhas established feedwaterflowfrom either AFW or Condensate. (((Appendix D Required Operator Actions Form ES-D-2OpTestNo.:NRCScenario

1. 1 Event#AOP-P.05 Page 39of45--EventDescription:EquipmentVerifications I Time II Position IIApplicant'sActionsorBehavior I AOP-P.05 Actions Evaluator Note: Operator may discontinue early to assist with loss of heat sink BOP Enter and perform AOP-P.05 Section2.1 Reader-Doer.

NOTE: Indicating lights for the turbin:e throttle, governor, intercept&reheat-stop valves are de-energized. MONITOR 1 B-B 6900V Shutdown Board BOP ENERGIZED. CAUTION 1:: Restoring seal cooling to an overheated Rep seal could result in RCP seal damage or steam vo-iding in CCS..CAUTION 2: Operati:on of Reps for greater than 2 minutes without CCS cooling to oil coolers will result in bearing temperatures greater than 200°F.CHECK RCP sea!cooling available: ,.seal injection flow BOP OR*therrna!barrier flow CAUTION: CCP and SI Pumps may experience bearing failure 10 minutes after loss of ERCW cool:ing.ENSURE tHO Train A ERCW Pumps IN SERVICE: BOP K-A ERGW Pump*..R-A ERCW Pump Appendix D NUREG 1021 Revision 9 Appendix 0 Required Operator Actions Form ES-D-2OpTestNo.: NRC Scenario#1Event#AOP-P.05Page40of45 --Event

Description:

Equipment Verifications I Time II Position II Applicant'sActionsor Behavior I ENSURE Diesel Generators RUNNING and ERC\tV ALIGNED to all DIGs.BOP (RNO if not previously performed) EMERGENCY STOP any DIG with NO ERCW cooling available. BOP ENSURE 1 8-B CCS Pump supplying Train A ccs.MONITOR REACTOR COOlANT PUMPS BOP MOTOR THRUST BEARING TEMP HIGH alarm DARK[1i-M-SB, E-3l CHECK ERCW supply header pressure NORMAL: BOP*1 (2}-PI-67-493, between BO psig and 120 pSJ:g CHECK dlarging IN SERVICE: BOP a.CHECK 18-B CCP RUNNING.If Reactor is critical, THEN BOP EVALUATE CLOSING TDAF\fV LCV'S to prevent ReS cooldQwn BOP CHECK letdown IN SERVICE.PERFORM Appendix AA, Potential Tech BOP Spec Impacts..(May be performed later)NOTE 1 1-M-l Instrument Rack A is normally powered from 4BOV Shutdown Bd 1A1-A.Power loss results in loss of varrous rad monitors, boric add flow indication , and other MeR indications and controls.NOTE 2: Restoration of power to Instrument Rack A may cause leV-&-1 06B to open, resulting In condensate system fjow changes.Appendix 0 NUREG 1021 Revision 9 (((Appendix 0 Required Operator Actions Form ES-D-2OpTestNo.:NRCScenario

1. 1Event#AOP-P.05Page41of45

--Event

Description:

EquipmentVerifications Time II Position II Applicant'sActionsorBehavior RESTORE power to 1-Mq Instrument Rack A by pla£ing Instrument Rack A Transfer Svvitch to ALTERNATE position. middle switch]Evaluator Note: remainderofprocedurewillmostlikelynotbecomplete due toLossofHeatsinkandisthereforenotincluded.. Appendix 0NUREG1021Revision9 ((Appendix D Required Operator ActionsFormES-D-2OpTestNo.:NRCScenario

1. 1 Event#ES-O.5Page42of45

--Event

Description:

Equipment Verifications Time II Position II Applicant'sActionsor Behavior ES-O.5 Actions CHECKERCWsystem operation: BOP*VERIFYatleast fourERCWpumps RUNNING.*VERIFY DIG ERCW supplyvalvesOPEN. VERIFYCCSpumpsRUNNING:

• Pump1A-A(2A-A)

BOP*Pump1B-B(2B-B)

• PumpC-S.VERIFYEGTSfansRUNNING.

BOP VERIFY generator breakers OPEN.BOP VERIFYAFWpumps RUNNING: BOP*MDAFWpumps

• TDAFWpump.

Appendix D NUREG1021Revision9 (Appendix D Required Operator ActionsFormES-D-2OpTestNo.:NRCScenario# 1Event#ES-O.5Page43of45 --Event

Description:

Equipment Verifications Time II Position II Applicant'sActionsor Behavior NOTEAFWlevelcontrolvalvesshouldNOTberepositionedifmanualactionhasbeentakentocontrolS/Glevels,toestablishflowduetofailure,ortoisolateafaultedS/G. CHECKAFWvalvealignment: a.VERIFYMDAFWLCVsinAUTO. BOP b.VERIFY TDAFWLCVsOPEN. c.VERIFYMDAFWpumprecirculationvalvesFCV-3-400andFCV-3-401CLOSED. VERIFYMFWIsolation:

• MFWpumpsTRIPPED
• MFWregulatingvalvesCLOSED BOP*MFWregulatingbypassvalve controlleroutputsZERO
• MFWisolationvalvesCLOSED
• MFWflowZERO.

MONITORECCSoperation: VERIFYECCSpumpsRUNNING: BOP*CCPs*RHRpumps*SIpumps Appendix DNUREG1021Revision9 (Appendix D Required Operator ActionsFormES-D-2OpTestNo.:NRCScenario

1. 1 Event#ES-O.5Page44of45--Event

Description:

Equipment Verifications Time II Position II Applicant'sActionsor Behavior VERIFYCCPflowthroughCCPIT.

• CHECK RCS pressurelessthan1500psig.

BOP*VERIFYSIpumpflow.

• CHECK RCS pressurelessthan300psig.
• VERIFYRHRpumpflow.

VERIFY ESF systems ALIGNED:*PhaseA ACTUATED: 0 CONTAINMENT ISOLATIONPHASEA TRAINAalarmLIT[M-6C,B5]. 0 CONTAINMENT ISOLATIONPHASEATRAINBalarmLIT[M-6C,B6].

• Containment Ventilation Isolation ACTUATED: 0CONTAINMENTVENTILATION ISOLATIONTRAINAalarmLIT[M-6C,C5].

0 CONTAI NMENTVENTILATION ISOLATIONTRAINBalarmLIT[M-6C,C6]. BOP*Status monitor panels: 06CDARK 0 6D DARK 06ELIT OUTSIDE outlined area 0 6H DARK 06JLIT.*TrainAstatuspanel6K: 0 CNTMT VENT GREEN 0PHASEA GREEN*TrainBstatuspanel6L: 0 CNTMT VENT GREEN 0PHASEAGREEN Appendix DNUREG1021Revision9 (Appendix D Required Operator ActionsFormES-D-2OpTestNo.:NRCScenario

1. 1 Event#ES-O.5Page45of45

--Event

Description:

Equipment Verifications Time It Position II Applicant'sActionsor Behavior MONITOR containmentsprayNOTrequired:

• PhaseBNOT ACTUATED BOP AND*Containmentpressurelessthan2.81psig
• Ensure ContainmentSprayis actuated VERIFY pocketsumppumps STOPPED:[M-15,upperleft corner]*HS-77-410,RxBldgAuxFloorand Equipment Drain BOPSumppumpA*HS-77-411,RxBldgAuxFloorandEquipmentDrainSumppumpB.

DISPATCHpersonneltoperformEA-0-1, Equipment Checks BOPFollowingESFActuation. Appendix DNUREG1021Revision9 SHIFT TURNOVER CHECKLISTPage1 of 3 Today (D SM D US/MCR Unit 1 D UO Unit 1Off-going-Name D AUO Station SQN DSTA(STA Function)AUOCompActionsOn-coming-Name Part1-Completed by Off-going Shift/Reviewed by On-coming Shift: Abnormal Eauioment Lineuo/Conditions: " tI'Jf,JEfJ , TrainA Week**All Equipment normal*TDAFW pump was tagged 2 hours ago for repair to theT&T valve.The packing was blowing excessively. Expected Return to service is 8 hours.(WO 07-080025-000 Total 0.03 gpm I Identified 0.02gpm I Unidentified 0.01 gpm.(Today 0600) SHIFT TURNOVER CHECKLISTPage2of3 Today (SI/Test in Progress/Planned: (Including Need for New Brief)Dailyand ShiftlySisperwork schedule Major Activities/Procedures in Progress/Planned:

• Reduce to<93%turbine power for Turbine Valve Testing.Initiate boration and rod insertion per Rx Engineering Spreadsheet.

Spreadsheet has been verified bytheSRO/STA.0-SO-62-7 Appendix E and D have been performed. Radiological Changes in Plant During Shift: None TS LCO 3.7.1.2.a: TDAFW pump was tagged 2 hours ago for repairtotheT&Tvalve.The packing was blowing excessively. Expected Return to service is 8 hours.TS3.3.3.7.18b action 1;Accident Monitoring Instrumentation, ERCW to AFW Valve Position, Turbine Driven Pump.Part2-Performed by on-coming shift oReviewofOperatingLogSinceLastShiftHeldor3Days,WhicheverisLess(N/AforAUO's) oReviewofRounds Sheets/AbnormalReadings(AUO'sonly)ReviewtheFollowingProgramsforChangesSinceLastShiftTurnover: oStandingOrders 0LCO(s)inActions(N/AforAUOs) oImmediateRequiredReading 0TACF(N/AforAUO's) Part3-Performed by both off-going and on-coming shift oWalkdownofMCRControlBoards(N/AforAUO's) Relief Time:ReliefDate: today (TVA40741[03-2001]OPDP-1-1[03-14-2001 SHIFT TURNOVER CHECKLISTPage3of3 Disabled Annunciators Today PANEL WINDOW ANNUNCIATOR Equipment Off-Normal (Pink Tags)WO I PER Number ((UNID And Noun Name ID And Noun Name Panel Panel Problem Description MCRWO List Problem Description WO I PER Number WOlPER Number (UNITONE REACTIVITY BRIEFDate:TodayTime:NowRCSBoron: 1093 ppm Today I BA Controller Setpoint: 27%*IRCSB-10Depletion:2ppm Operable BAT: A IBATABoron: 6850 ppm IBATCBoron: 6850 ppm IRWSTBoron: 2601 ppm Nominal Gallonsperrodstepfrom219: 7 gallonsofacid, 36 gallons of water*Verifyboricacidflow controller ISsetatAdjustedSAController Setting law 0-SO-62-7 section 5.1 Gallonsofacid: 26Gallonsofwater: 138RodSteps: 4 Power reduction amount EstimatedFinalRod Position Estimated boron addition 10%198StepsonbankD 101 gallons 30%174StepsonbankD 295 gallons 50%152StepsonbankD 485 gallons**Thesevaluesare approximationsandnotintendednorexpectedtobeexact.Thevaluesmaybesupercededby Rx Engineering or SO-62-7calculatedvalues.Thesevaluesarecalculatedassuming100%steadystatepower operation only.Engineeringdatalastupdatedoneweekago.DataValiduntiloneweekfrom now.Number of dilutions: 0***Numberofborations: aRodstepsin: a Gallons per dilution: aGallonsperboration: aRodstepsout: a Total amount diluted: a Total amount borated: aNetchange: a IN/Out Number of dilutions: a Numberofborations: aRodstepsin: a Gallons per dilution: a Gallonsperboration: aRodstepsout: a Total expected dilution: aTotalexpectedboration: aNetchange: a In/Out Remarks: Rx Power-100%MWD/MTU-1000Xenon &SamariumatEquilibrium

• • • Theboronletdowncurveisflatforthenext25EFPD.NextUnit1FluxMapis scheduled-threeweeksfromnow Unit Supervisor:

Name/Date Operations Chemistry Information Sample PointUnitsBoronDate/TimeGoal LimitU1RCS ppm 1093Today/NowVariableVariableU2RCS ppm 816Today/NowVariableVariableU1RWST ppm 2601Today/Now2550 -26502500-2700U2RWST ppm 2569Today/Now 2550-26502500-2700BATA ppm 6850Today/NowVariable Variable BATB ppm 6850Today/NowVariableVariable BATC ppm 6850Today/NowVariableVariableU1CLA#1 ppm 2556Today/Now 2470-2630 2400-2700U1CLA#2 ppm 2575Today/Now2470-26302400-2700U1CLA#3 ppm 2591Today/Now 2470-2630 2400-2700U1CLA#4 ppm 2589Today/Now2470-26302400-2700 U2 CLA#1 ppm 2531Today/Now2470-26302400-2700 U2 CLA#2 ppm 2650Today/Now 2470-2630 2400-2700 U2 CLA#3 ppm 2522Today/Now2470-26302400-2700 U2 CLA#4 ppm 2526Today/Now 2470-2630 2400-2700 (SpentFuelPool ppm 2547Today/Now 2.18-2.48 2.33 IndicatorUnitsU1Date/TimeU2 Date/TimeSI50S/GLeakage?Yes/NoNoToday/Now NoToday/NowSI137.5CVELeakrategpd <0.1Today/Now<0.1Today/Now5gpdleak equivalent cpm 380Today/Now 68Today/Now30gpdleak equivalentcpm1980Today/Now 83Today/Now50gpdleak equivalent cpm 3250Today/Now 206Today/Now75gpdleak equivalent cpm4850Today/Now 455Today/Now150gpdleak equivalentcpm9750Today/Now 870Today/NowCVEAir Inleakage cfm 10Today/Now 12.5Today/NowBkgdon99/119 cfm 50Today/Now 40Today/Now ( ,,,,..-..,.,_"" unit 1 DELTA REACTOR POWER ASSUMED INSERTEDEXPECTEDDELTA RHO BORON DELTARECOMMENDRECOMMEND IODINE TIME POWER DEFECT ROD HT WORTH XENON BORON CONC PPM DILUTION BORATION CONC (hrs)(%)(pcm)(steps)(pcm)(pcm)(pcm)(ppm)(ppm)(gal)(gal)(%eq)0.0 100.0 1732.0 216.0-24.5-2728.0 1093.0 100.0 1.0 93.0 1608.0 204.0-83.7-2742.5-50.4 1100.8 7.8 a 87 99.7 2.0 93.0 1604.5 204.0-83.7-2764.3 18.4 1098.0-2.9 168 a 99.0 3.0 100.0 1729.6 216.0-24.5-2762.9 64.4 1087.9-10.0 594 a 98.8 4.0 100.0 1734.4 216.0-24.5-2747.7-10.4 1089.6 1.6 a 18 98.9 5.0 100.0 1733.7 216.0-24.5-2736.8-11.7 1091.4 1.8 a 20 99.0 6.0 100.0 1732.8 216.0-24.5-2729.0-8.6 1092.7 1.3 a 15 99.1 7.0 100.0 1732.2 216.0-24.5-2723.7-6.0 1093.7 0.9 a 10 99.2 8.0 100.0 1731.7 216.0-24.5-2720.1-4.1 1094.3 0.6 a 7 99.3 9.0 100.0 1731.4 216.0-24.5-2717.8-2.6 1094.7 0.4 a 4 99.3 10.0 100.0 1731.2 216.0-24.5-2716.4-1.5 1094.9 0.2 a 3 99.4 11.0 100.0 1731.1 216.0-24.5-2715.7-0.8 1095.1 0.1 a 1 99.5 12.0 100.0 1731.0 216.0-24.5-2715.6-0.2 1095.1 0.0aa 99.5 13.0 100.0 1731.0 216.0-24.5-2715.7 0.1 1095.1 0.0 1 a 99.6 14.0 100.0 1731.0 216.0-24.5-2716.1 0.4 1095.0-0.1 4 a 99.6 15.0 100.0 1731.1 216.0-24.5-2716.7 0.6 1094.9-0.1 5 a 99.6 16.0 100.0 1731.1 216.0-24.5-2717.3 0.7 1094.8-0.1 6 a 99.7 17.0 100.0 1731.2 216.0-24.5-2718.0 0.7 1094.7-0.1 7 a 99.7 18.0 100.0 1731.2 216.0-24.5-2718.7 0.8 1094.6-0.1 7 a 99.7 19.0 100.0 1731.3 216.0-24.5-2719.4 0.8 1094.5-0.1 7 a 99.8 20.0 100.0 1731.3 216.0-24.5-2720.1 0.7 1094.3-0.1 7 a 99.8 21.0 100.0 1731.4 216.0-24.5-2720.7 0.7 1094.2-0.1 6 a 99.8 22.0 100.0 1731.4 216.0-24.5-2721.4 0.7 1094.1-0.1 6 a 99.8 23.0 100.0 1731.5 216.0-24.5-2721.9 0.6 1094.0-0.1 6 a 99.8 24.0 100.0 1731.5 216.0-24.5-2722.5 0.6 1093.9-0.1 5 a 99.9 25.0 100.0 1731.6 216.0-24.5-2723.0 0.5 1093.8-0.1 5 a 99.9 26.0 100.0 1731.6 216.0-24.5-2723.4 0.5 1093.8-0.1 5 a 99.9 27.0 100.0 1731.6 216.0-24.5-2723.9 0.5 1093.7-0.1 4 a 99.9 28.0 100.0 1731.7 216.0-24.5-2724.2 0.4 1093.6-0.1 4 a 99.9 29.0 100.0 1731.7 216.0-24.5-2724.6 0.4 1093.6-0.1 4 a 99.9 30.0 100.0 1731.7 216.0-24.5-2724.9 0.4 1093.5-0.1 3 a 99.9 31.0 100.0 1731.8 216.0-24.5-2725.2 0.3 1093.5 0.0 3 a 99.9 32.0 100.0 1731.8 216.0-24.5-2725.5 0.3 1093.4 0.0 3 a 99.9 33.0 100.0 1731.8 216.0-24.5-2725.7 0.3 1093.4 0.0 2 a 99.9 .-............."c., f....-......, Unit 1 34.0 100.0 1731.8 216.0-24.5-2725.9 0.2 1093.3 0.0 2 0 99.9 35.0 100.0 1731.9 216.0-24.5-2726.1 0.2 1093.3 0.0 2 0 100.0 36.0 100.0 1731.9 216.0-24.5-2726.3 0.2 1093.3 0.0 2 0 100.0 37.0 100.0 1731.9 216.0-24.5-2726.5 0.2 1093.3 0.0 2 0 100.0 38.0 100.0 1731.9 216.0-24.5-2726.6 0.2 1093.2 0.0 1 0 100.0 39.0 100.0 1731.9 216.0-24.5-2726.8 0.1 1093.2 0.0 1 0 100.0 40.0 100.0 1731.9 216.0-24.5-2726.9 0.1 1093.2 0.0 1 0 100.0 41.0 100.0 1731.9 216.0-24.5-2727.0 0.1 1093.2 0.0 1 0 100.0 42.0 100.0 1731.9 216.0-24.5-2727.1.0.1 1093.2 0.0 1 0 100.0 43.0 100.0 1731.9 216.0-24.5-2727.2 0.1 1093.1 0.0 1 0 100.0 44.0 100.0 1732.0 216.0-24.5-2727.3 0.1 1093.1 0.0 1 0 100.0 45.0 100.0 1732.0 216.0-24.5-2727.3 0.1 1093.1 0.0 1 0 100.0 46.0 100.0 1732.0 216.0-24.5-2727.4 0.1 1093.1 0.0 1 0 100.0 47.0 100.0 1732.0 216.0-24.5-2727.5 0.1 1093.1 0.0 1 0 100.0 48.0 100.0 1732.0 216.0-24.5-2727.5 0.1 1093.1 0.0 1 0 100.0 49.0 100.0 1732.0 216.0-24.5-2727.6 0.1 1093.1 0.0 0 0 100.0 50.0 100.0 1732.0 2 6.0-24.5-2727.6 0.0 1093.1 0.0 0 0 100.0 51.0 100.0 1732.0 216.0-24.5-2727.6 0.0 1093.1 0.0 0 0 100.0 52.0 100.0 1732.0 216.0-24.5-2727.7 0.0 1093.1 0.0 0 0 100.0 53.0 100.0 1732.0 216.0-24.5-2727.7 0.0 1093.0 0.0 0 0 100.0 54.0 100.0 1732.0 216.0-24.5-2727.7 0.0 1093.0 0.0 0 0 100.0 55.0 100.0 1732.0 216.0-24.5-2727.8 0.0 1093.0 0.0 0 0 100.0 56.0 100.0 1732.0 216.0-24.5-2727.8 0.0 1093.0 0.0 0 0 100.0 57.0 100.0 1732.0 216.0-24.5-2727.8 0.0 1093.0 0.0 0 0 100.0 58.0 100.0 1732.0 216.0-24.5-2727.8 0.0 1093.0 0.0 0 0 100.0 59.0 100.0 1732.0 216.0-24.5-2727.8 0.0 1093.0 0.0 0 0 100.0 60.0 100.0 1732.0 216.0-24.5-2727.9 0.0 1093.0 0.0 0 0 100.0 Total 884 166 Hold Tavg=Tref+/-1.SF Small hourly boration/dilution 6820 BAT ppm volumes may be accumulated for larger single additions Reason for Downpower Unit 1 TV test DateRxENGName Beeper 70808 Comments SQN 0-SO-62-7 1,2 BORON CONCENTRATION CONTROLRev.46Page161of199APPENDIX0Page1of1 CALCULATIONFORAMOUNTOFBORICACIDORPRIMARYWATER(TI-44)NOTE1 NOTE 2 One calculationisrequiredforeachmajorchange.BoricacidamountstoachieverequiredRCSboronconcentrationmaybe significantlyhigherthancalculatedamountsifCVCSdeminresinsareremovingboron.AmountofboronremovalbymixedbedresinswilldependonRCSboron,resinage, whetherdeminbedwas previouslyborated,andletdowntemperature.Chemistryshouldbeconsultedifrequiredtoevaluateresinbedremoval.[1]IFREACTFnotused, THEN CALCULATE amountofprimarywaterorboricacidrequiredusingTI-44. RCS BORON I ()q 3 ppm Current PPM CHANGE AMOUNT PRIMARY WATERORBORICACID (I 7 TOTAL GAL(s)NOTE REACTFdatasheetsaretobesignedbythepreparerandreviewer.[2]IFREACTFusedattachprintouttoprocedure. o NOTEIVisnotrequiredif appendixisperformedbyanSROtoverifydataprovidedbyRx.Eng. [3]ENSURE independentlyverifiedbyanSROin accordance with Appendix I.ENDOF TEXT Initials (NRC08A Borate.txt 0[REACTF-VERS SQ2.1]BORATION/DILUTION CALCULATION SEQUOYAH UNIT 1 CYCLE 15 RCS AVG TEMP 578.2 DEG F RCS PRESSURE 2235.0 PSIG PZR LEVEL 60.0%MAKEUP WTR CONC.0 PPM BORIC ACID CONC 6850.0 PPM INITIAL CONC FINAL BORIC ACID MAKEUP WTR BORON CONC CHANGE BORON CONC ADDITION ADDITION (PPM)(PPM)(PPM)(GAL)(GAL)

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1093.0 6.8 1099.8 74.9.0 0 page 1 NOTE1NOTE2 SQN BORON CONCENTRATION CONTROL 0-SO-62-7 1,2Rev.46Page162of199 APPENDIX EPage1of18 REACTIVITY BALANCE CALCULATION One calculationisrequiredforeach major change.Calculationisan approximation of requiredBoronchange.Eyeball interpolation of graphs is expected.Dilution or Boration value for power change from P1%to P 2%powerintimeperiodTwithrods movingfromsteppositionR 1toR 2.(Subscript convention: 1=currentpoint,2=target point)[1]ENTER the following data:DATA REQUIRED DATAWhereToGet Current RCS Boron loCf3 ppmChemLaborEstimateusing Appendix 0 Core Burnup 1t200 MWO/MTUICSU0981 Current Reactor power I t:J 0%NISorICS Final Reactor power 93%Asrequiredfor plant conditions Total Reactor Power change 7 11%11 Currentandfinal Reactor powerRateof Reactor power change 7%/hrAsrequiredforplant conditions Number of hours to change power/hr(s)Asrequiredfor plant conditions Zit::,ICSorMCRBoard Current Rod Position steps 201./Estimate numberofrodstepsrequiredtoFinalRod Position steps control 111androd withdrawal requirements for power change. SQN 1,2 BORON CONCENTRATION CONTROLAPPENDIXEPage2of 18 0-80-62-7Rev.46Page163of199 -CAUTION Follow sign conventions explicitly.(See Example Power Increase and Power decrease.) [2]CALCULATEchangeinboronconcentrationbyperformingthefollowing: Parameter WhereToGet Calculation Value Attached Power Defect Curves:/b7S" pcm PD 1-/05 (negative[a]POWERDEFECT Unit 1: Figure1,2,or3 pcm PD 2=pcmforpower (current)L'1pPOWERDEFECT increase)Unit 2: Figure8,9,or10.Xenon., From ICS*or REACTF(eithercurrent NOTE: Xenon reactivity must be negative (negativeconditionsorprojectiontoinitialcondition).forrisein[b] XENON Xenon-,FromICS*or REACTF pcm XE 2-(-Zl2.t3)pcm XE 1=-12-pcm Xenon (projection overtimeperiodT).-Z74 V cone)*(ICSXenonvaluesmustaddnegativesign).(current)L'1p XENON[c] RODS Attached Rod Worth Curves:-7S-pcmRods,-(-z, s-)pcm Rods,=-50 (negative Unit 1: Figure4,5,or6 pcmforrod (current)L'1p RODS insertion) Unit 2: Figure11,12,or13. [d]POWERDEFECT +XENON+RODS (CHANGE IN REACTIW DUE TO POWER DEFECT, XENON, AND RODS)'-13 pcm[a]pcm L'1pPOWERDEFECT +[b]pcm L'ip XENON+[c]pcm L'ip RODS=[e] BORON (CHANGE IN BORON REACTIVITY)-Y3 pcm ([d]pcmPOWERDEFECT +XENON+RODS)X (-1)=L'1p BORON[f]Apprn BORON (CHANGE IN BORON CONCENTRATION)(negative-0-:'1'-fordilution, ([e]pcni L'1p BORON)-:-(pcm/ppm Boron Worth)=6.8 ppmpositiveforfromFig.7 (U-1)orFig.14(U-2) boration)[3]ENSUREindependentlyverifiedbySROinaccordancewithAppendix J.(N/Aifperformedbyan8ROtoverifydataprovidedbyRx.Eng) ((SequoyahNuclearPlant Unit1&2GeneralOperating Instructions O-GO-5 NORMAL POWER OPERATIONRevision0052QualityRelatedLevelofUse: Continuous Use EffectiveDate:10-27-2007 ResponsibleOrganization:OPS,OperationsPreparedBy:Judy R.VarnerApprovedBy:W.T.Leary Current Revision DescriptionRevisedtoremovereferencestoDCN22190whichwasnotimplementedU1C15. PERFORMANCEOFTHIS PROCEDURE COULD IMPACT REACTIVITY. SQN NORMAL POWER OPERATION 0-GO-5 Unit1&2Rev.0052Page2 of 93 Table of Contents 1.0 1.1 1.2 2.0 2.1 2.2 3.0 3.1 3.2 4.0 5.0 5.1 (5.2 5.3 5.4 5.5

6.0 INTRODUCTION

...........................*.............................................................................. 3 Purpose 3 Scope 3 REFERENCES 4 Performance References 4 Developmental References 5 PRECAUTIONS AND LIMITATIONS 6 Precautions 6 Limitations 11 PREREQUiSiTES 14 INSTRUCTIONS 16 Power AscensionFrom30%to100% 17 At Power Conditions 58 PowerReductionFrom100%to30% 64 Power CoastdownatEndofLife 77 LOAD FOLLOW OPERATIONS 82 RECORDS 86 Appendix A: DELETED 87 Appendix B: TURBINE RUNBACK RESTORATION 88 Appendix C: ISOLATIONOFMSR STARTUP VENTS 90 Appendix D: RECOMMENDED POWER VALUES BASED ON CONDENSATED PRESSURE 91 Source Notes 92 ATTACHMENTS Attachment 1: NORMAL POWER OPERATION (SQNNORMALPOWEROPERATION 0-GO-5Unit1&2Rev.0052Page3of93

1.0 INTRODUCTION

1.1PurposeThisGeneralOperating(GO)Instructionprovides guidanceforpower ascension from approximately30to100%power,atpowerconditions,powerreductionfrom100to30%power,PowerCoastdownatEndofLifeoperations,andLoadFollow operations. This instructionprovidesadditional guidanceforturbinecontrol restoration following a turbine runback.1.2ScopeThisGOcontainsthefollowingsections: 5.1 PowerAscensionFrom30%Powerto100%5.2At Power Conditions 5.3 PowerReductionFrom100%to30% 5.4 PowerCoastdownatEndofLife5.5LoadFollow Operations (SQN NORMAL POWER OPERA lION 0-GO-5 Unit1&2Rev.0052Page4of93

2.0 REFERENCES

2.1 Performance References 0-SI-NUC-000-038.0,ShutdownMargin Boron Concentration Control 0-SO-58-1. Main GeneratorBusDuctCoolingSystem 1,2-S0-62-9, CVCS Purification System 0-SO-35-4, Monitoring Generator Parameters 0-SO-12-1, Auxiliary Boiler System 1,2-S0-2-9, CondenserVacuumandTurbineSteamSeal Systems Operation 1 ,2-S0-5-1, FeedwaterHeatersandMoisture Separator Reheaters 1,2-S0-5-2, NO.3 HeaterDrainTankandPumps 1,2-S0-5-3, NO.7 HeaterDrainTankandPumps 1 ,2-S0-2/3-1, Condensate and Feedwater System 0-SO-68-3, PressurizerSprayand Heater Pressure Control SystemM.0-SO-85-1,ControlRodDriveSystem N.0-PI-OPS-000-666.0, RiverTemperatureLimits SpecifiedbyNPDES permit O.0-SI-OPS-092-078.0, PowerRangeNeutronFlux ChannelCalibrationByHeat Balance Comparison A.B.C.D.E.F.G.H.I.('J.\K.L.P.0-SI-CEM-000-050.0, 72-Hour Chemistry Requirements Q.0-SI-CEM-030-407.2, RadioactiveGaseousWaste Effluent Particulate and Iodine DoseRatesfromShieldand AuxiliaryBuildingExhausts (Weekly/Special) and Condenser Vacuum Exhausts (Special)R.0-SI-CEM-030-415.0, Gaseous Effluent Requirements (GrossAlpha,Noble Gas and Tritium S.0-SI-OPS-000-001.0,InitialStartupSystemParameterLog T.TI-40, Determination of Preconditioned Reactor Power (SQN NORMAL POWER OPERATION 0-GO-5 Unit1&2 Rev.0052Page5of93 2.2 Developmental References A.MemorandumfromSystem Engineering concerningMSRoperation-RIMSS57 880322999 B.MemofromReactorEngineering-RIMSS57941219934 C.S57-880322-999andS57-880808-851D.WLetter GP89-076(RIMSNo.S53890427984)E.W LetterGP89-155(RIMSS57 891026972)F.W LetterGP86-02(B44861112002) G.SSP-2.3, Administration of Site Procedures H.TVA-NQA-PLN89-A I.GOI-10, Reactivity ControlatEnd ofCycleLife(TrojanNuclearPlant)J.FSAR,Section13.5 K.Memo from Reactor Engineering -August6,1996(GBair) (SQN NORMALPOWEROPERATION0-GO-5 Unit 1&2Rev.0052Page6 of 93 3.0 PRECAUTIONS AND LIMITATIONS 3.1 PrecautionsA.To ensurethatNIS ReactorPowerlevel indicationsremainwithin2%oftrue power during powerlevelchanges,acheckshouldbe performed about every 20%powerlevelchange,when greaterthan15%power,by comparing calorimetricpowertoeachNISPowerRangedrawer.The20% power levelcheckdoesnot preclude the operatingcrewsfrommaking necessary changes in responsetochangingplantconditions.B.TRM 3.3.3.15requiresLEFMcorethermalpower (U2118)tobeusedto perform 0-SI-OPS-092-078.0above15%reactorpower.LEFM indication is availableifthe followingconditionsaremet:*LEFMstatus NORMALonICS CalorimetricDatascreen.*LEFMcore thermal power(ICSpointU2118)showsgood (green)data.*LEFMMFW headertemp(ICSpoint T8502MA)greaterthanorequalto250°F.IfLEFM indicationisNOT available above15%reactorpower,thenTR 3.3.3.15actionmustbeentered.C.The followingshouldbeusedto determinethemost accurate reactor power indication for comparisonwithNIS:*When reactor power is greater than15%,useLEFM calorimetric power indication (U2118).*IfLEFMisNOTavailable,thenuse average loop (U0485orM-5 indicators)upto40%.Above40%,use computerpointU1118.D.The turbineshouldbeoperatedin"IMPOUT"controlduring normal unit operation."IMPIN" operationresultsinsystemswingsand shouldonlybeusedduringthe performanceofvalvetests.(WLtrGP89-155;RIMSS57 891026 972)E.Pressurizer heatersandspraysmaybe operatedasrequiredto maintain pressurizerandRCSboron concentrationwithin50ppm.Ifloopboron concentrationischangedby20ppmorgreater,usethe pressurizer backup heaters to initiate automatic spray. (SQN NORMAL POWER OPERATION 0-GO-5 Unit1&2Rev.0052Page7of93 3.1 Precautions (continued) F.Condensate 01 polishing operationsduringpowerascensionarecontrolledbystayingwithinsystem parametersandby recommendationsfromthe Chemistry Section.G.Thevalvepositionlimitershouldbe periodically positioned approximately 10%above the current governor control indications (keeps governorvalvesoffofthe limiter)as turbineloadischanged.Thisprevents inadvertent load increases by limiting governorvalveopeningandallowsafasterresponseoftherunback featurewhichensuresmain feedwatersystemwillsupplytherequired amountofflow.H.Any off-frequency turbine operationistobereportedto Engineeringforrecord keeping.Thereportwillincludedurationand magnitude of off-frequency operation. I.Operation at off-frequenciesistobeavoidedinordertopreventtheprobable occurrenceofturbinebladeresonance.Prolongedperiodsof operation at certain off-design frequenciescouldcause excessive vibratory stresseswhichcould eventually generate fatiguecrackingintheblades. Off-frequency operationispermittedtothedegreeandtimelimitspecifiedonthechart"Off-FrequencyTurbineOperation",FigureA.26ofTI-28.J.The potentialexistsfor condensationformationinsteam extractionlineswhen feed waterheatersareisolated. K.InitialStartupAfterRefueling-Afterrefuelingoperations,theNIS indicationsmaybe inaccurate until calibrationathigherpowerlevels.TheNIScalibration procedureswilladjustthePRMtrip setpointstoensurethattheexcore detectorsdonot contributetoan overpowerconditionatthefollowingRTPhold points.Reactor Engineering and/or SystemsEngineeringwill determine procedure performance. [C.3]1.At<50%RTPafluxmapandsinglepointalignment,ahotchannel factor determination,anaxial imbalancecomparison,and aPRNIScalibrationwillbeperformed.ThePRhighrangetrip setpointwillthenbeincreasedtoitsnormalvalueof109%.2.At<75%RTP, calorimetric calculationsandRCSflow verificationmaybeperformed,EAGLE-21updatedpriortoincreasingpower,afluxmap,ahotchannelfactor determination,anaxial imbalancecomparisonmayberequiredifnotperformedat <50%,a detectorcalibration(ifAFO3%),andaPRNIScalibrationmaybeperformed. (SQNNORMALPOWEROPERATION0-GO-5Unit1&2 Rev.0052Page8of93 3.1 Precautions (continued)3.Ifnotperformedat75%holdpoint,anaxial imbalance comparisonanda detector calibration (ifAFD3%)shouldbe performed at-100%RTP.Engineering will determineifPRNIS calibration must be performed. Calorimetric calculations,RCSflowverification,ahotchannel factor determination,anda reactivitybalancewillbe performedandEAGLE-21 updated.Reactor Engineeringwillnotify Operations thatnormalfull power operationsmayproceed. 4.PreconditionedPowerLevelsandMaximum AllowableRatesof Power IncreasearespecifiedinTI-40, Determination of Preconditioned Reactor Power.5.Duringinitialstartups,basedon Westinghouse recommendations, a lowerpowerrampratelimithasbeen implementedforpowerlevels above the intermediatepowerthreshold.The Intermediate Power Threshold is unit/cycle dependentandis determinedbythe Vendor.RefertoTI-40.6.ICSwill automatically monitor pre-conditioned powerlevelasfollows:a.PointU1127isreactorpowerin percentofRTPbasedon either secondary calorimetricorRCST dependingonpowerlevel.b.Point U0103isa20minuterolling average of reactor power rate-of-changefittedovera20minuteperiod. U0103isa leading indicator of%/hourpowerramprateandcanbeusedin deciding tospeeduporslowdowntheramprate.Point U0104isa1hourrolling average of reactor power rate-of-changefittedovera1hourperiod. U0104isusedin demonstratingcompliancewithfuel pre-conditioning powerramprate limits.d.PointK0058isthe currentlyqualified(or pre-conditioned)powerlevel. e.ThesepointscanallbemonitoredwiththeICSgroup display1140.AppendixAmaybeusediftheICSis unavailable.L.TI-40 power increaselimitsthatareexceeded,in anyonehour,are evaluated in accordance with SPP-3.1. f\.(, (SQN NORMAL POWER OPERATION 0-GO-5 Unit 1&2Rev.0052Page9 of 93 3.1 Precautions (continued)M.PowerCoastdownAtEndOfLife:1.Reactorpowerchangesshouldbelimitedtolessthanorequalto1%perhourtoavoidcausingxenonpeakingwhichcouldforceaplant shutdown.2.Donotperform unnecessaryunitpowermaneuversortesting(e.g.,turbinevalvetesting).Suchtestingcouldresultinan uncontrollable Xenon oscillation. 3.Nonessentialworkonsystemswhichcouldcauseaplantupsetshouldbe deferred.4.SecondaryPlantrunbackssuchasMainFeedPump Turbinetripor#3HeaterDrainTankrunbackwillrequireaunitshutdownifReactorpowerisnotpromptlyreturnedto pre-transientlevelduetotheresultingsevereXenontransient.Ifasystempoweralertisineffect,andelectricalgenerationiscritical,unitloadshouldbereducedas necessary keeping T AVGonprogram.ContactReactorEngineeringforanevaluationand guidanceconcerningunitshutdownorreductionofload. 5.Managementshouldbeconsultedtoevaluatethe feasibilityofaunitrestartifareactortripoccurswithRCSequilibriumboron concentrationlessthan50ppm.Ifthereactoristoberestarted,thepowerlevelshallbelimitedtonominalpre-trippowerlevel.N.AxialFluxDifference Management:Whenthereactorisoperatingatasteadypowerorduringnormalloadchanges, maintain L'11withintheoperatinglimitsoftheCoreOperatingLimitsReport(COLR).Itisrecommendedthatthecoreaxialfluxdifference(AFD)bemaintainedwithin +/-5%ofthetargetbandatalltimes,excludingthe performance of 0-PI-NUC-092-036.0,"Incore-ExcoreCalibration,"andEndoflifepowercoastdowns.Operatingtimeoutsidetheband,whichisgivenin TI-28 Attachments1and2,shouldbeminimized.Reactor Engineering shouldbecontactediftimeoutofthe +/-5%targetbandexceeds approximately30minutes.O.Theposition ofcontrolbank 0shouldnormallybe215stepswhenpowerlevelissteadystateatorabove85%RTP.Atsteadystatepowerlevelsbelow85%,controlbank 0shouldnormallybe165steps.Ifrodpositionismorethan2stepsbelowthis guidanceforlongterm,thenimpactmayoccurtosafety analysis assumptions.P.Duringheatupandcooldowntransients,RCSdensitychangeswillcausechangesinNISindicatedpower.At constantreactorpower,a1°Fchangein TAVGmaycauseasmuchasa1%(ormore)changeinindicatedNISpower. ('SONNORMALPOWEROPERA liON 0-GO-5Unit1&2Rev.0052Page10of93 3.1 Precautions (continued)Q.Operationofmaingeneratorwithout automaticvoltagecontrolcouldimpactgridvoltagerequirements.TheSouthEastAreaLoad Dispatcher(SELD)shouldbe notified immediatelyifgeneratorisinservicewithout automatic voltageregulator.Also,refertoSectionEofGOI6forMVARlimits. R.Main Generatoroperationwithout AutomaticVoltagecontrolrequiresthat NarrativeLogentriesbemade(time,date,reason &duration)andthatnotificationbemadetoOperationsDuty Specialist(ODS)withintwentyfour(24)hours.S.Main GeneratoroperationoutsideoftheVoltageScheduleinGOI-6requires that NarrativeLogentriesbemade(time,date,reason &duration)andthat notificationbemadetoSouthEastAreaLoadDispatcher(SELD)withinone(1)hour.1.ThefollowinglimitationsareapplicabletoUnitTwoONLY.1.Inwintermonths#7HDTPcapacityisnotadequatetopump#6HeaterdrainswhenallCondensate Demineralizerpumpsareinservice.CurrentpracticeistoruntwoCond 01Pumpsand/orthrottlethe condensatesystemtoreducebackpressure.Thepreferredmethodistothrottle condensatepressureinsteadofrunningonlytwo Condensate Demineralizerboosterpumpsatfullpowerduetopumprunoutconcerns. 2.Siemens-WestinghouseanalysishasdeterminedthatthemaximumunitpowerwithoneMFPoperationis65%underworstcaseconditions.Theplantcouldoperatehigherifplantconditionspermit.3.MFPflowfromtheleadMFPshouldnotexceed53.7%ofthetotalflow.FlowratesabovethiswouldresultinHPsteamflowtotheleadMFP1. Computer points 1(2)U0504 and U0505canbeusedtomonitor. (SQN NORMAL POWER OPERATION 0-GO-5 Unit1&2Rev.0052Page11of93 3.2 LimitationsA.Whentheaxialflux differencemonitoralarmisinoperable,theAFDmustbeloggedeveryhourbyperforming 0-SI-NUC-000-044.0.(SR4.2.1.1.a.2 &4.2.1.1.b)B.WhenboththeplantcomputerandNISQPTRalarmsystemsareinoperable,theQPTRmustbecalculatedevery12hoursbyperforming 0-SI.,NUC-000-133.0.(SR4.2.4.1.b)C.Donotexceedaloadchangerateofplusorminus5%perminuteorastep change of1 0%.D.Riverwater temperaturesshallbemaintainedwithinthe limitationsoftheNPDESpermitasspecifiedin 0-PI-OPS-000-666.0. NOTE Westinghouseshouldbecontactediftheturbineisoperatedoutsideofitsoperatinglimitsasstatedbelow. E.To preventhighvibratorystressesandfatiguedamagetothelaststageturbineblading,donotoperatetheturbineoutsideoflimitslistedbelow: [W Ur GP86-02 (844861112002)]1.Atloadslessthanorequalto30%(350MW),themaximumpermissible backpressureis1.72psia.(3.5"Hg)2.Atloadsgreaterthan30%,themaximumpermissible backpressure is2.7psia(5.5"Hg)witha5minutelimitationbeforetrippingtheturbine.F.Donotallowthe generatortobecomeunderexcited.G.Intheeventofachangeintheratedthermalpowerlevelexceeding15%inonehour,notifyChemistrytoinitiatetheconditionalportionsof 0-SI-CEM-000-050.0, 0-SI-CEM-030-407.2 and 0-SI-CEM-000-415.0duetothethermalpowerchange. ((SQN NORMAL POWER OPERATION 0-GO-5 Unit1&2Rev.0052Page12 of 93 3.2 Limitations (continued)H.The following Main Turbine vibration limitationsandactionsshouldbeadhered to: 1.Vibrationlevelswhichexceed7mils(alarmsetpoint)shouldbeverifiedby Predictive Maintenance Group.2.Vibrationlevelsgreaterthan7milsandlessthan14milsshouldbe continuouslymonitoredbyPredictive Maintenance Group.3.IFvibrationlevelis greaterthanorequalto14mils,THENTRIPthe turbine.I.Westinghouse recommendsthatifanythrottlevalveisheldclosedformorethan10minutes,thenitshouldbere-tested immediately upon reopening in accordance with 1,2-PI-OPS-047-002.0.J.The generatormaybeoperatedwithoutabusductcoolerupto approximately729MWturbineload.K.To ensure sufficientvoltageforasafeshutdownafterlossofbothunits,voltage and reactivepowershouldbemaintainedwithinthelimitsofGOI-6. L.WithLEFM calorimetricpowerindicationavailable,fullpower operation isdefinedas approximately3455MWTnottoexceed3455.0MWTaveragedover a 8-hourperiod.[C.1]IfLEFMisavailable,powershallbemonitoredusing plant computerpointU2118 InstantaneousValue.DONOTallow average thermalpowertoexceed3455MWthermalfortwo consecutive hours.M.The followingrestrictionsapplyifLEFM calorimetricpowerindication (U2118)is unavailable: 1.ApplicableactionofTRM3.3.3.15mustbeentered.2.AFDlimitsinCOLRandTI-28mustbemademore restrictiveby1%.3.RodinsertionlimitsinCOLRmustberaisedby3steps.4.Ifreactorpoweris greaterthan40%,powershouldbemonitoredusingU1118.IfU1118isalsounavailable,usethehighestreadingNISchannel.5.Ifreactorpowerislessthan40%,usetheRCSaverageTasthepreferredmethodfor determiningpowerlevel.N.IF equilibrium conditionsareachieved,after exceedingby10%ormoreofratedthermalpowerthethermalpoweratwhichtheheatfluxhotchannelfactorwas last determined, THEN conditional performance of 0-SI-NUC-000-126.0, HotChannelFactor Determinationisrequired. (SQN NORMAL POWER OPERATION 0-GO-5Unit1&2Rev.0052 Page13of93 3.2 Limitations (continued)O.Atlow powerlevels,theLPHeaters may be unbalanced in extraction steam supply use andheatpickupacrossthe condensatesideofthe heater string.This condition should correct itselfastheunit approaches 45-50%TurbinePower.(Ref:PER 99-003789-000)P.WithoneLP heaterstringoutof service (isolated),powerislimitedto86% .(Unit1)or90%(Unit2).ThisisbasedonLP turbine blading limitations.(Ref: DeN E21203A). SQN NORMAL POWER OPERATION 0-GO-5 Unit 1&2Rev.0052 Page 14 of 93 4.0 STARTUPNo._PREREQUISITES Unit--NOTES Date----1)Throughout this Instruction where an IFITHEN statementexists,thestepshouldbe N/A'difthe conditiondoesnotexist. 2)Prerequisites may be completedinanyorder.[1]ENSURE Instructiontobeusedis acopyof effective version.[2]TAVGisbeing maintainedwithin1.5°FofT REF.0[3]SGlevel controlsarebeing maintained in AUTO (N/AifautocontrolNOT available). 0[4]Controlrodsarebeing maintained within the operatingbandof Core Operating Limits Report (COLR)(N/A if shuttingdowndueto dropped or misaligned rod).0 ([5]SteamdumpcontrolsystemisintheT AVG mode (N/AifTavgModeNOT available). 0[6]TheEHCsystemshould bein OPER AUTO (pushbutton lit).0[7]Generator pressurized with hydrogen according to capability curve.(TI-28,Fig.A14) 0 NOTE During start up afteracold shutdown the Condensate 01 normallywillbe alignedforfull flow polishinguntiltheMSRsarein service.[8]ENSURE Condensate 01 polishing operation in accordancewithRCL recommendations. SQN NORMALPOWEROPERATION0-GO-5 Unit 1&2Rev.0052Page15 of 93 4.0 STARTUP No._....,.....- __PREREQUISITES (continued) Unit--Date_[9]ENSURE each performer documentstheirnameandinitials: (Print Name Initials SQN NORMALPOWEROPERATION 0-GO-5 Unit 1&2Rev.0052 Page 64 of 93 STARTUPNo,_5.3 Power Reduction From 100%to 30%Unit__Date----NOTES1)Thissectionmaybeusedtoreducepowerto -30%duringplantshutdownORaportionofthissectionmaybeperformedtoreducepowerasrequiredbyplantconditions.StepswhicharenotrequiredforpartialloadreductionmaybemarkedN/AwithSMconcurrenceasspecifiedbySPP-2.2. 2)Appendix0providesguidanceonrecommendedpowervaluestomaintain condensatepressureifsecondaryplantequipmentmustberemovedfromservicefor maintenance.3)Steps5.3[2]through5.3[6]maybeperformedoutofsequence. [1]ENSURESection4.0,Prerequisitescomplete.[2]REVIEWofPrecautionsandLimitationsSection3.0hasbeen completed. 0 ([3]NOTIFYRADCONofimpendingloadreduction. 0[4]NOTIFYCON 01operatorsofloadreductionandtoremovebedsasneeded. 0[5]NOTIFYLoadDispatcherofimpendingloadreduction. 0 NOTELoweringloadontheMainGeneratorwillcauseVARstotrendinthepositivedirection(towardoutgoing).Thiswillrequireloweringgeneratorvoltage.RefertoGOI-6SectionEforMVARlimitsforgeneratorstability.[6]PERFORMthefollowingasrequired:[6.1]IFAutomaticVoltageControlisinservice, THEN ADJUSTMainGeneratorVARsUSING [HS-57-221ExciterVoltageAutoAdjusterasnecessaryduringpowerescalation.[6.2]IFAutomaticVoltageControlisNOTinservice, THEN ADJUSTMainGeneratorVARsUSING [HS-57-231ExciterVoltageBaseAdjusterasnecessaryduringpowerescalation. SQN NORMAL POWER OPERATION 0-GO-5 Unit 1&2Rev.0052Page65 of 93 STARTUP No.,_Unit__Date_(5.3 Power Reduction From 100%to 30%(continued) NOTES 1)GuidanceonrestorationofEHCControlsafteraBOPrunbackiscontainedin Appendix B, Turbine Runback Restoration. [C.4]2)Forcore operating recommendationsforsituationssuchasendofcorelifecoastdownorunusualpowermaneuvers,contactReactorEngineeringforguidance.[C.5]3)Itis recommendedthatAFDbecontrolledwithinthetargetband.4)Thefollowinggeneralapproachshouldbeusedduringpowerreduction:(a)borateRCStoreduceRCST AVGwithinlimitsofT REF,(b)reduceturbineloadtomatchT REFwithT AVG (c)periodicallytakerodcontroltoMANUALfromAUTOandinsertthebanktomoveAFDnearthetargetvalue,(d)returnrodcontroltoAUTOwhennotusingthebanktocontrolAFD,and(e)repeattheaboveasnecessarytoaccomplishtheloadchange.5)Actionseffectingreactivityaredirectedinthefollowingstep.0-SO-62-7requirementsshallbeadheredtoforreactivitychanges(i.e.reactivitybalance,amountsofboricacidorwater).All appropriate verificationsandpeerchecksshallbeutilizedduring performance. [7]INITIATEaloadreduction. D SQN NORMAL POWER OPERATION 0-GO-5 Unit1&2Rev.0052Page66of93 5.3 STARTUP No.Unit__Power Reduction From 100%to30%(continued)Date_[8]MONITORturbineload decreasing. CAUTION o Do NOT exceedaload changerateofplusor minus 5%/minuteorastep change of 10%.NOTE T AVG is programmedfrom578.2°Fat100%powerto 54JOFatzeropoweratarateof 0.312°Fper%power. [9]MONITORthefollowingduringtheloadreduction: ([9.1][9.2][9.3]TAVGfollowingTREFprogram.AllRPls,groupstepcountersforrodinsertionlimitsand inoperablerodsorrodmisalignment,LoopandNISforcorrectpower distribution and quadrantpowertilts.CoreAFDwithin +/-5%controlbandaroundthepower level dependenttargetvalue. NOTE o D D Valvepositionlimitand governorcontrolmeteraredisplayedonEHCDisplaypanel1 ,2-XX-047-2000(M-2). [9.4]Valvepositionlimit approximately10%abovethe current governorcontrolindicationasturbineloadischanged. D[10]IFAFDremainsoutsidetheAFDtargetbandfor approximately30minormore, THEN CONTACT Reactor EngineeringastowhyandwhentheAFDmightbereturnedtothe target band.D SQN NORMAL POWER OPERATION 0-GO-5 Unit1&2Rev.0052Page67of93 STARTUPNo._Unit__Date_5.3 Power Reduction From 100%to30%(continued) NOTES 1)Shutdownofthe condensate demineralizer boosterpumpsshouldbebasedon header pressure, the abilityofthedraintank pumpstopumpforward,orSystem Engineering evaluation.2)The followingstepmaybemarkedN/Aifreducingpowerasspecifiedby AOP-S.04, Condensate and HeaterDrainsMalfunction,orasspecifiedby AppendixD.Inthiscase,all available condensate and heaterdrainpumpsshouldremainin service to maintain adequate condensate pressure.[11]WHENreactorpoweris approximately85to90%, THEN PERFORM the following: [11.1]IF three condensate demineralizer boosterpumpsarein service, THEN EVALUATEremovingone(1) condensate demineralizer boosterpumpin accordance with 1,2-S0-2/3-1. [11.2]IF two condensate demineralizer boosterpumpsarein service, THEN EVALUATEremovingboth condensate demineralizer boosterpumpsin accordance with 1,2-S0-2/3-1. [11.3]STOPone(1)condensate boosterpumpin accordancewith1 ,2-S0-2/3-1. SQN NORMALPOWEROPERATION0-GO-5 Unit 1&2Rev.0052Page68 of 93 5.3 STARTUP No.Unit--Power Reduction From 100%to 30%(continued) NOTEDate_0-SI-OPS-092-078.0maybeperformedatthediscretionoftheOperatorifoneormorePRMsisindicatingclosetothe +/-2%tolerance.[12]PERFORMthefollowingatapproximately80%reactorpower:[12.1]IFLEFMindicationisavailable,THEN CALCULATECalorimetricpower: Calorimetricpower=U2118 =34.55%---D[12.2]IFLEFMindicationisNOTavailable,THEN (CALCULATEreactorpower: Calorimetricpower=U1118 =34.11%---D[12.3]VERIFYthatallNISPowerRangeAchanneldrawersarewithin+/-2%ofthecalculatedcalorimetricpower. N-41 N-42 N-43 N-44 (XI-92-5005B)(XI-92-5006B)(XI-92-5007B)(XI-92-5008B) YESD YESD YESD YESD NOD NOD NOD NOD[12.4]IFanyoftheabovestepsarecheckedNO,THENPERFORM0-SI-OPS-092-078.0. SQN NORMAL POWER OPERATION 0-GO-5 Unit 1&2Rev.0052Page69 of 93 5.3 STARTUP No.Unit__Power Reduction From 100%to 30%(continued) NOTE Date_(Turbine Impulse pressurerelaylightsarelocatedon L-262.RelaylightsaredarkwhenrelaysareNOTarmed.Relay NO.4isaspare.[13]WHEN turbineloadlessthan71%(Unit1)72%(Unit2), THEN PERFORMoneofthe following (N/A substep not performed): [13.1]VERIFY Turbine RunbackcircuitsareNOTarmedby performing the following: A.ENSURE(TurbinerunbackfromMFPloss)isNOTLIT. 8.ENSURE[PIS-47-13RLY2L (Turbinerunbackfrom NO.3HOT)isNOT LIT.C.ENSURE(Closure of LCV-6-1 068fromLossofany#3HOTP)isNOT LIT.[13.2]VERIFY Turbine Runback circuitsareNOTarmedby performing the following:A.ENSURE[FU2-47-13AL (TurbinerunbackfromMFPloss)REMOVED(AuxInstRm.R71). 8.ENSURE[FU2-500-R071(Turbine runback from NO.3 HOT)REMOVED(AuxInstRmR-75). C.ENSURE jumper betweenP18-1andP18-2inPnl262, (Closure of LCV-6-1068fromLossofany#3HDTP)REMOVED. SQNNORMALPOWER OPERATION 0-GO-5Unit1&2Rev.0052Page70of93 STARTUP No.,_Unit__Date_(5.3Power ReductionFrom100%to30%(continued) CAUTION ValvesLCV-6-106Aand 1068shallbeverifiedtobe controlling properly during unit load reduction. NOTES1)OneMFWPis normallyremovedfromserviceat45%turbineloadbut,ifnecessary,mayberemovedfromserviceatpowerlevellessthan55%(Unit1)or65%(Unit2)ifapprovedbytheOperationsSuperintendent.2)Ifholdingatapowerlevellessthan60%thecondensate demineralizerboosterpumpsmaybeleftrunning.3)Shutdownofthecondensate demineralizerboosterpumpsand#3heaterdrainpumpsshouldbebaseduponheaderpressureandabilityofthedraintankpumpstopumpforward. [14]WHENbetween55to70%turbineload, THEN PERFORMthefollowing: [14.1]SIMULTANEOUSLY STOPbothoperating condensate demineralizerboosterpumpsinaccordancewith 1,2-S0-2/3-1(N/AifNOTinservice). [14.2]VERIFY#3HOTrunbackNOTarmedbyensuringeither(N/AmethodNOTused) Step 5.3[13.1]8 completed OR Step 5.3[13.2]8 completed. SQN NORMAL POWER OPERATION 0-GO-5 Unit 1&2Rev.0052 Page 71 of 93 STARTUPNo._Unit__Date_5.3 Power Reduction From 100%to 30%(continued) [14.3]STOPoneofthe three#3 heaterdraintankpumpsin accordance with 1,2-80-5-2. [14.4]DISPATCHanAUOtoperformoneofthe following toalignsteamsealstotheunit:A.IF Auxiliary Stearn Header is available and otherunitis greaterthan55%load,THEN ALIGN oppositeunits#3 Extraction to supply steamsealsin accordance with 0-80-12-1. DB.IFthe#3 Extractiononthe oppositeunitisNOT available THEN PLACE the AuxiliaryBoilerin service in accordance with 0-80-12-1, OR (ENSUREsteamsealsarebeing suppliedfromtheunit'smainsteamsupply. NOTE D 0-81-0P8-092-078.0maybe performed at discretion of OperatorifoneormorePRMsis indicating closetothe+/-2%tolerance. [15]PERFORM the following at approximately60%reactorpower:[15.1]IFLEFM indication is available, THEN CALCULATE Calorimetric power: Calorimetricpower=U2118 =34.55%---D[15.2]IFLEFM indicationisNOT available, THEN CALCULATE reactor power: Calorimetric power=U1118=34.11%---D SQNNORMALPOWER OPERATION 0-GO-5Unit1&2Rev.0052Page72of93 (5.3 STARTUP No.Unit--Power ReductionFrom100%to30%(continued) [15.3]VERIFYthatallNIS Power Range A channel drawersarewithin+/-2%ofthe calculated calorimetric power.N-41 (XI-92-5005B) YESD NOD N-42 (XI-92-5006B) YESD NOD N-43 (XI-92-5007B) YESD NOD N-44 (XI-92-5008B)YESD NOD[15.4]IFanyofthe abovestepsare checked NO, THEN PERFORM O-SI-OPS-092-078.0.Date_ saN NORMAL POWER OPERATION 0-GO-5Unit1&2Rev.0052 Page73of93 5.3 STARTUP No.Unit__Power Reduction From 100%to30%(continued)Date_NOTE Steps 5.3[16]through5.3[18]maybeperformedoutofsequence. [16]WHENbetween40%and65%turbineload, THEN STOPoneofthetwo#7heaterdraintankpumpsin accordance with 1,2-S0-5-3. [17]WHEN reactorpoweris approximately 50%, THEN VERIFY annunciator XA-55-4A, window E-4: (P-9 LOW POWER TURB TRIP-REAC TRIP BLOCK is LIT.o ([18]WHEN approximately45%turbineload, THEN PERFORMthefollowing: [18.1]IF operatingwithtwomain feedwaterpumpsinservice, THEN SHUTDOWNonemain feedwaterpumpin accordance with 1,2-S0-2/3-1. [18.2]STOPthesecond#7heaterdraintankpumpin accordance with 1,2-S0-5-3. SQN NORMALPOWEROPERATION0-GO-5 Unit 1&2Rev.0052 Page 74 of 93 STARTUPNo._Unit__Date---5.3 Power Reduction From 100%to 30%(continued) NOTE 0-SI-OPS-092-078.0maybeperformedatthediscretionoftheOperatorifoneormorePRMsisindicatingclosetothe +/-2%tolerance.[19]PERFORMthefollowingat approximately40%reactorpower:[19.1]IFLEFMindicationisavailable, THEN[19.2]IFLEFMindicationisNOTavailable, THEN (CALCULATE Calorimetric power: Calorimetricpower=U2118 =34.55 CALCULATEreactorpower: Calorimetricpower=U1118 =34.11%---%---D D[19.3]VERIFYthatallNISPowerRange Achanneldrawersarewithin+/-2%ofthecalculatedcalorimetricpower. N-41 N-42 N-43 N-44(XI-92-5005B)YESD(XI-92-5006B)YESD (XI-92-'5007B)YESD(XI-92-5008B)YESD NOD NOD NOD NOD[19.4]IFanyoftheabovestepsarecheckedNO, THENPERFORM0-SI-OPS-092-078.0. SON NORMAL POWER OPERATION 0-GO-5Unit1&2Rev.0052Page75 of93 5.3 STARTUP No.Unit__Power ReductionFrom100%to30%(continued) Date---NOTE AMSACisblockedwhenlessthan40%turbineloadfor greaterthan360seconds(time delay).[20]WHENlessthan40%turbineload, THEN VERIFY annunciator XA-55-4A, window E-7:C-20AMSAC ARMED is DARK.o ([21]WHEN approximately35%reactorpower, THEN VERIFY annunciator XA-55-4A, window C-5:P-8LOW POWERLOWFLOWTRIP BLOCK is LIT.o[22]WHEN approximately30%turbineload, THEN[22.1]STOPthetwooperating#3heaterdrainpumpsin accordance with 1,2-S0-5-2. [22.2]STOPoneofthetwooperating condensate boosterpumpsin accordance with 1,2-S0-2/3-1. [22.3]STOPoneofthethree operatinghotwellpumpsin accordance with 1,2-S0-2/3-1. SQN NORMAL POWER OPERATION O-GO-5 Unit1&2Rev.0052 Page 76 of 93Date_(5.3 STARTUP No.Unit__Power Reduction From 100%to30%(continued) [23]STABILIZEtheplantat approximately30%reactorpowerwithreliablesteamflow/feedflowindications. D[24]IF further load reductionisrequired,THENGOTO 0-GO-6, PowerReductionfrom30% Reactor Power ToHotStandby. [25]IFmainturbine shutdownisdesiredwhileholdingreactorpowerat approximately 30%, THENGOTO 0-GO-11,TurbineShutdownWithout Reactor Shutdown.[26]IFreactorshutdownandturbineshutdownisrequired THENGOTO 0-GO-6, PowerReductionfrom30% Reactor Power ToHotStandby. [27]IFunitistoreturnto100%poweroperation, THENGOTOSection5.0ofthisinstruction.ENDOF TEXT I Appendix 0 Scenario OutlineFormES-D-1 I ((Facility: SequoyahScenarioNo.:2OpTestNo.:NRC Examiners: Operators:InitialConditions:100%PowerBOLTurbineDriven AuxiliaryFeedwaterPumpOOSformaintenance. Turnover:MaintainCurrentPlantconditions. TargetCTs:IsolateSteamflowandFeedwaterflowtorupturedS/GpriortoinitiationofRCSCooldowntotargettemperature. CooldownRCStolessthanorequaltotarget temperaturepriortoRCS depressurization. DepressurizeRCStomeetE-3 depressurizationcriteriapriortoS/Goverfill(100%S/Gdomelevelfrom simulator computer variable).EventMalf.No.EventType*EventDescription No.1ED16ATS-SRO125DCVitalBattery ChargerIfailure.TechSpecevaluation.CrewinitiatesplacingSpare ChargerinServicetoVitalBattery.2RW01ETS-SROERCWpumpN-Btrips.Requiresplacing standbypumpinservice C-SRO/BOPandAOPM.01performance.TechSpecEvaluation.3RX11BI-AllImpulsepressure transmitterPT-1-73failslowresultinginrodinsertionandmanualrodcontrol.SROwilldirect AOP-1.08 toremovefromserviceand transfersteamdumpsystemtopressurecontrol. 4 TH05A TS-SRO Steam generator#1tubeleakof approximately15gpmrequiring C-AIIrapidplantshutdown.TechSpecEvaluation. 5N/AR-ATCPerformrapidplantshutdownusingAOP-C.03.ManualRod N-SRO/BOPcontrolwillberequired. 6 ZDIHS621 C-SRO/ATC Emergencyborationvalve (FCV-62-138)willnotopenfrom 38Acontrolroomhandswitch.Normalborationrequiredforshutdown. 7 TH05A M-AII Steam generatortubeleakincreasestotuberupture (-400 gpm)requiringRxTripandSafetyinjection. 8 FW09A C-BOPMotorDriven Auxiliary Feeedwaterpump1A-AfailstoAutostartrequiringmanualstart. 9 RC06A C-SRO/ATC PressurizerSprayvalvefailsfullopenduringRCS depressurizationinE-3.StoppingRCPs(atleast#1 &#2)to terminate depressurization required.*(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajorAppendix0NUREG1021Revision9 I Appendix 0 Scenario OutlineScenario2 SummaryFormES-D-1 I (Shortly after assumingshift,125VoltDCVitalBatteryChargerIwillfail.Crewwill diagnosethefailureandinitiateVitalbatteryItransfertothesparecharger.SROwillevaluateandenter applicable Technical Specifications. After addressing the chargerfailure,EssentialRawCooling WaterpumpN-Bwilltrip.Crewwillstartthe standbypumpandperformtheAOPwhichwillrequirerealigningtheStandbypumpfor Emergency startalso.SROwill evaluateTechnicalSpecifications,LOCisapplicableuntilselectorswitchforautostartisalignedtothe operablepumpthenitmaybeexited I.AftertheERCWpumpAOPiscompleteTurbineImpulse TransmitterPT-1-73willfaillow.Thiswillresultin inadvertentrodinsertionwhichwillrequireplacingrodcontrolinmanualforthe remainderofthescenario.Thisfailurewillalsorequiretransferringsteamdumpcontrolsystemtosteampressuremode.S/GlevelprogramandTavgreferenceprogram(Tref)willbealsobeaffected.SROmayagain evaluate Technical Specifications;however,LCOentrywillnotberequiredsincethelowfailuredoesnotaffecttheassociated interlockinsuchawayastopreventtheassociatedreactorprotectionsystemfunctionsfromoperating.AfterthisAOPhasbeenaddressed,asteam generatortubeleakof approximately15gpmwilloccurin Steam Generator#1.Sincethisleakiswithinthe capacityofthenormalchargingsystem,theassociatedAOPwillrequireinitiationofarapidshutdown.RCSleakageTechSpec.isapplicable.Whenstartingthe rapid shutdown, the emergencyborationvalvewillnotopenfromthecontrolroomhandswitchrequiring performanceofthealtenatepathtoinitiateborationusingnormalboration.Rodcontrolduringthe shutdownwillbemanual.Aftertherapidshutdownhasresultedinasufficientpowerreduction,thesteam generatorTubeleakwill propagatetoa significantruptureof approximately400gpm.Thisleaksizewillrequireinitiationofa ReactorTripand SafetyInjection.MotorDriven Auxiliary FeedwaterPump1A-AwillfailtoautostartfromtheSIsignalandwillrequiremanualstart.Thecrewwillprogressthrough E-OandtransitiontoE-3wheretheywillcooldowntotargetRCS temperature and depressurizetheRCS.During depressurization a Pressurizersprayvalvewillfailopen requiring stoppingofatleastRCPs1and2tostopthe depressurization. The scenariomaybeterminatedwhencrewhascompletedRCS depressurizationinE-3.Appendix 0 NUREG1021Revision9 Page1of3 NRC08BRev0 CONSOLE OPERATOR INSTRUCTIONS (Sim.SetupTheseremote functionsareactivewhentheSCENSfileisloaded.Event#1:WhenDeterminedbyNRC Examiner Examiner,insertthisMalfunction using Key 1.If requestedtoplacesparecharger1-SonVitalBatteryBdIinsertremotefunction using KEY-2.Performswitchcheck.Allowthe simulatortorunforatleast3minutesbeforeloadingSCENfileorstartingtheexercise.ThiswillinitializeICS. LoadSCENS:NRC08B Place simulatormomentarilyinRUN,PlaceOOS equipmentinrequiredpositionwithtags,ClearalarmsandReturntoFREEZE.IMFFW07Cf:1 lOR ZLOHS151A_GREEN f:OlORZLOHS117AGREEN f:O lOR ZLOHS118A GREEN f:O lOR ZLOHS3136AA GREEN1 f:O lOR ZLOHS3136AA_GREEN2 f:OlORZLOHS3136AA_RED1 f:O lOR ZLOHS3136AA_RED2 f:O lOR ZDIHS3136AA f:O lOR ZLOHS3179AA GREEN1 f:O lOR ZLOHS3179AA GREEN2 f:O lOR ZLOHS3179AA RED1 f:O lOR ZLOHS3179AA_RED2 f:O lOR ZDIHS3179AA f:OIMFED16AF:1K:1IRFEDR65A F:1 k:2Initializesimulatorat100 %RTPBOL.Place Mode_1_placard on panels.Place-A-Train Week sign on the simulator.TDAFWPUMPISINOPERABLE. Close FCV-1-17&18&place Hold Noticeon 1-17&18 and FCV-1-51.Also place Hold order on TDAFW Pump ERCW supply valves.Place Protected Equipment tagsonMD AFW Pumps.125DCVitalBatteryChargerIfailure. After dispatched, wait I::t 2 minutes then report that the batterychargerwassmokingbadlybutnoflames,andthatyouhaveopenedthe ACinputand DC output breakers.Role playas Fire OPS as needed.PlaceSpareCharger1-SonVitalbatteryBdI. When dispatched, wait-20 min to insert the remote function and then report the transfer complete. CONSOLE OPERATOR INSTRUCTIONS Page 2 of 3 NRC08B Rev 0 (Event#2: WhenIMFRW01E F:1 K:3ERCWpumpN-Btripsonovercurrent. DeterminedbyNRCExaminer,insertthis When dispatchedtocheckthebreaker, wait RI 3 Malfunction using minutes then reportthatthereisan instantaneous Key 3.overcurrentrelayonthe pump breaker.When dispatched to check Motor wait-5 min andreportsmell of overheated insulation. Role playasAUOto close tripped pump discharge valve asneeded,noconsoleactionsareneeded. Event#3: WhenIMFRX11B f:O k:4IMPULSEPRESSURE TRANSMITTER 1-PT-1-73DeterminedbyNRCFAILSLOWExaminer,insertthis Malfunction usingWhenIMs or MSS contacted to trip bistables, Key 4.inform the crew that the IMs will report to theMCRin-45 minutes.Event#4: WhenIMFTH05A f:O.3 k:5 STEAM GENERATORTUBEFAILURESG#1 DeterminedbyNRCAPPROXIMATELY15GPMREQUIRINGRAPIDExaminer,insertthisPLANTSHUTDOWN. Malfunction using (ey 5.WhenChemLab contacted for RM-90-119 limit, inform the crew of the limit on the Ops chemistry information report (turnover information). Report that other Chemistry actions will take-45 minutes to complete.When RADCON/Chem Lab are requested to survey/sample S/Gs, wait-10 min then report as RADCON that#1S/Ghas slightly higher background than the others.Wait 45 minutes and report asChemLab that rupturedS/Gis#1 S/G.Event#5:AsDirected Initiate rapid plant shutdown using AOP-C.03.byS/Gtubeleak AOP.Event#6:ThislOR ZDIHS62138A f:OEMERGENCYBORATIONFLOWCONTROLOverrideisactive VALVE (FCV-62-138)WILLNOTOPENFROMwhentheSCENSfile HANDSWITCH.isloaded If Dispatched to check locally wait-3 min and report valve closed but you cannot determine why it won't open.If requested to operate the valve locally, report that it will not open locally either. CONSOLE OPERATOR INSTRUCTIONS Page3of3 NRC08BRev0 (Event#7: WhenMMFTH05Af:8.6r:300LOOP1S/GTUBELEAK INCREASING TOPowerhasbeen RUPTURE (-400GPM)OVER5MIN. REQUIRING adequatelyRXTRIPAND SAFETY INJECTION.Decreasedas DeterminedbyNRC Examiner, Modify this Malfunction.Event#8: ThisIMFFW09Af:1DEFEATAUTOSTARTOF MDAFWP1A-A-PUMPOverrideisactive CAN BEMANUALL Y STARTwhentheSCENSfileisloadedEvent#9:WhenIMFRC06Af:100k:6 PRZ SPRAY VALVE PCV-68-340BFAILSFULLCrewbeginsRCSOPEN(LOOP2) DepressurizationinE-3,insertthis Malfunction using Key 6. I Appendix D Required Operator ActionsFormES-D-2 IOpTestNo.:EventDescription:NRCScenario

1. 2Event#125VoltDCVitalBatteryChargerI

.....;..Page1of Time II Position II Applicant'sActionsorBehavior (Console Operator: When directed, initiate Event 1 Indications Available: 1-AR-M1-C,A4,125DC VITALCHGRI FAILURE OR VITAL BAT I DISCHARGE Upscale Deflection of ofEI-57-92onM-2. BOPRefertoalarmresponse procedure 1-AR-M1-C window A4 SELECT channell on[1-XS-57-96]125VVital Battery voltage, BOP AND CHECK batterybdvoltage. IFfailureof125VDCVital Battery Bd, THEN CREWGOTO AOP-P.02, Loss of 125V DC Vital Battery Board.(StepisN/ABoardVoltaqeNormal) NOTE Downscale(zeroorbelow) deflectionofEI-57-92 indicatescurrentflowfromnormal power supply (charger). Upscale (greaterthanzero)deflection of EI-57-92 indicates currentflowfromthebattery. CHECK[1-EI-57-92]VitalBatteryBdIamps. BOP (Ampmetershowsupscale deflection indicating battery discharge) DISPATCHpersonnelto INSPECT AND CHECKforlocal alarmsonthe125VDCVital ChargerIand125VDCVital BOP Battery bd I.Next5 Steps of Annunciator Response ProcedureareNAfor BOPthisfailure. I Appendix DRequiredOperatorActionsFormES-D-2 IOpTestNo.:EventDescription:NRCScenario

1. 2Event#125VoltDCVitalBatteryChargerI Page 2 of 37-.;...----TimePosition Applicant'sActionsorBehavior (IFchargerfailure,THEN EVALUATEneedtoplacesparechargerinserviceinaccordancewith0-SO-250-1,125Voltde Vital Battery Board CREW(CrewshouldinitiateplacingsparechargerinservicetoVitalBattBd I.Crewcouldalsodecidetoplacethe s"Batteryin service.)EVALUATEEPIP-1EmergencyPlanClassificationMatrix.

CREW(CrewshouldnotifyShiftManagertoevaluateREP) EVALUATETSLCOs3.8.2.3.(2Hr Action b.Applies)SRO When Technical Specifications have been identified or at discretion of the Lead Examiner, proceed to the next event. I Appendix D Required Operator ActionsFormES-D-2 IOpTestNo.:NRCScenario

1. 2 Event#2EventDescription:ERCWPumpN-BTrips Time II Position IIApplicant'sActionsorBehavior Console Operator: When directed,initiateevent2 Indications available:

• MotorTripoutBuzzerandWhiteLightonPumpHandswitch.
• LowERCW HeaderPressureAlarm RespondBackpanelAlarm,PlaceFailedPumpswitchinPullto BOPLock,andPerform Annunciator Response Procedure.

EnterandDirect performanceofAOP-M.01,Section2.1 SRO ERCWPumpFailure. IDENTIFY andLOCKOUTfailedERCWpump. BOP START additional ERCWpumpsasrequiredtomaintain supply headerpressurebetween78psigand124psig. BOP (Pressure shouldbeinthe band (-82psig)however,Crew may start standbypumpto provide additional margin since 4pumpswere initially running)CHECKtwoTrainAERCWPumps AVAILABLE. a.Supply headerpressures[between78psigand124psig]:

• 1-PI-67-493A
• 2-PI-67-493A BOP b.Supply headerflows[expectedvalue]:
• 1-FI-67-61

(-2700 gpm acceptable)

• 2-FI-67-61

(-13,500 gpm acceptable) I Appendix 0 Required Operator ActionsFormES-D-2 IOpTestNo.:EventDescription:NRCScenario

1. 2Event#ERCWPumpN-BTrips 2 Time Position IIApplicant'sActionsorBehavior (CHECK 1 Band2BERCWsupplyheaderpressuresandflows NORMAL:a.Supplyheaderpressures[between78psigand124psig]:

• 1-PI-67-488A BOP*2-PI-67-488Ab.Supply headerflows[expectedvalue]:
• 1-FI-67-62

(-1500gpmacceptable)

• 2-FI-67-62

(-11,500gpmacceptable DISPATCHpersonneltoINSPECTfailedpump(s)and Crewdeterminecauseforfailure. NOTIFYSTAtoevaluateTechSpecLCO3.7.4,ERCW System.SRO (SRO shouldevaluateTechSpecs -LCOAppliesuntil selectorswitchis repositionedtooperablepump.This mayresultinLCOentryandexit) CHECKERCWpumploadingampsNORMAL. RO TRANSFER emergency power selectorswitchawayfrom ROfailedpump. EVALUATEneedtocloseandplace Crewclearanceonmanualdischargevalveforfailedpump. SROGOTO appropriateplantprocedure. When Technical Specificationshavebeenidentifiedorat discretionoftheLead Examiner, proceedtothenext event. I Appendix DRequiredOperatorActionsFormES-D-2 IImpulsePressure TransmitterPT-1-73failslow (OpTestNo.:EventDescription:NRCScenario

1. 2Event#3 Time II Position II Console Operator: When directed, initiate event 3 Applicant'sActionsorBehavior Indications available:

• Control Rod insertion*1-AR-MS-A, CG, TAVG/TREF DEVIATION*1-AR-MS-A,B7,STEAMGENLVL HIGH-LOW DEVIATION (Crew SRORefertoalarmresponseproceduresDirectentryto AOP-1.08,TurbineImpulsePressureInstrumentMalfunction OR MAYentertoAOP-C.01,Sect2.1,Continuousrodbank movement:1.CHECKrodcontrol:

a.ENSURErodcontrolinMAN.(YES) b.CHECKrodmotionSTOPPED.(YES)SRO2.CHECKforsteamlineorfeedwaterlinebreak:(NO)3.CHECKforinstrumentationmalfunction: a.CHECKnuclearinstrumentationOPERABLE.(YES) b.CHECKRCSRTDsOPERABLE.(YES) c.CHECK turbine impulse pressure channels OPERABLE.(NO)Transitions to AOP-1.08 from 3.c I Appendix D Required Operator ActionsFormES-D-2 IImpulsePressure TransmitterPT-1-73failslow (OpTestNo.:EventDescription:NRCScenario

1. 2Event#3 Time II Position II Applicant'sActionsorBehavior (NOTE:Lossof Instrument PowertoSteam Generator level setpointprograminputwilldrivethe setpointbelow33%Steam Generator level.CHECKPI-1-73indicatesnormal.(RNOSteps)

• PLACErodsinMAN.
• EVALUATEplacingMainRegValvesinMANtomaintainSGlevelonprogram.

Operators may electtoleave FWRegvalvesinauto, S/G will control at a lower level.*PLACESteamDumpsinSteamPressureModeUSING0-SO-1-2,SteamDumpSystem. [1]PLACE[HS-1-103A]SteamDumpAFSVand [HS-1-103B]SteamDumpBFSV handswitchestoOFF.RO/BOP[2]PLACE[HS-1-103D]SteamDumpMode selector toSTEAMPRESS. [3]VERIFY[XI-1-103A1B]SteamDumpsArmedwhitelightis LIT.[4]IF[PIC-1-33]SteamDump ControllerinMANUAL, THEN ENSUREdemandisZerooncontroller. [5]IF[PIC-1-33]SteamDump controller in AUTO, THEN ADJUST setpointtoobtainzero output (demand).[6]PLACE[HS-1-103A]SteamDumpA FSVand[HS-1-103B]SteamDumpBFSV handswitches to ON.[7]ADJUST[PIC-1-33]SteamDump controller tomaintaindesiredsteampressure. I Appendix D Required Operator Actions Form ES-D-2 IOpTestNo.:NRCScenario

1. 2 Event#3 Event

Description:

ImpulsePressure TransmitterPT-1-73failslow Time II Position II RO/BOP BOP Applicant'sActionsorBehavior

• DETERMINE ProgramT-avgfor current reactor power USING TI-28FigureA.9orICS (NSSS I BOP, Program Reactor Average Temperature).*WHENplantstable,THEN RESTORET-avgto within 3 degrees of program:*POSITIONcontrolrods.

OR*ADJUST turbine load.OR*ADJUSTRCSboron concentration CHECK PI-1-72 indicates normal.(NOTE: If performing AOP in conjunction with AOP-1.11foranEagleLCPfailure,then actions tohardtrip bistables should be delayeduntilEagle systemresetis attempted. Actions tohardtrip bistables must be completedwithin6hours UNLESS affectedloopis restored to operable status by resettingEaglerack. CREW SROIFPI-1-72orPI-1-73hasfailed, THEN NOTIFY 1M to remove failed channel from service USING AppendixA,P-1-72506)OR AppendixB,P-1-73 (P-505)EVALUATE the following Tech Specs for applicability:*3.3.1.1(3.3.1), Reactor Trip System Instrumentation(ACTION B.b applies, affected channels are operable)When Technical Specifications have been determined, the Lead Examiner may cue the next event (Appendix DRequiredOperatorActionsFormES-D-2OpTestNo.:NRCScenario# 2Event#4 Page 8 of 37----EventDescription:S/G#1Tube Leak Time II Position IIApplicant'sActionsorBehavior Console Operator: When directed, initiate Event 4 Indications available: 0-AR-M12-A,C1,CNDSVACPMPLORNGAIREXHMONHIGHRAD 0-AR-M12-A,B5,STMGENBLDN L1QSAMPMONHIRAD (-10-12mindelay)Refertoalarmresponseprocedure, Condenser Vacuum Crew ExhaustHiRad.CHECK 1-RM-90-119ratemeterand 1-RR-90-119on0-M-12 BOPforindicationofincreasedradiation. NOTE Alarm validitymaybe determinedbasedonabsenceof instrumentmalfunctionalarm, indicatedresponseoftheradmonitor, and,ifpossible, other indicationssuchas blowdown monitor (recognizing the differenceinresponsetimeduetoblowdown transport time).IFalarmisvalid,THEN NOTIFYRCLtoperform 1-CEM-068-BOP 137.5 Primary to SecondaryLeakageviaSteam Generators.IFalarmisvalid,THENGOTO AOP-R.01, Steam Generator BOPTubeLeak.SRODirectentrytoAOP-R.01,Steam GeneratorTubeLeak EVALUATEthefollowingTechSpecs SRO for applicability: Appendix DNUREG1021Revision9 (Appendix D Required Operator ActionsFormES-D-2OpTestNo.:NRCScenario# 2Event#4 Page 9 of 37----EventDescription:S/G#1TubeLeak Time II Position II Applicant'sActionsorBehavior Evaluator Note:SROmayreferto Operations ChemistryInformationSheetin turnover package.*3.4.6.2, Operational Leakage.Enters action b.*3.7.1.2, Auxiliary Feedwater System*3.7.1.3, CondensateStorageTank SRO*3.7.1.4, Secondary Coolant Activity (May Address TS Later, as required)*3.2.5,DNBTechSpec:Pzr heateroperationto control/restoretowithinlimits. EVALUATE EPIP-1, Emergency Plan ClassificationMatrixornotifiestheSM. SRO NO Classification: RCS Identified leakage (Primary to Secondary leakage)is less than 25 gpm.High Secondary Radiation AND SRO PressurizerleveldroppingORChargingflowrisingwithstable Pressurizer level*Gotosection2.1 NOTE: This sectionshouldbeusediftubeleakagehasan observableeffectupon charging flow and/or PressurizerlevelORif directedbySection2.2duetoleakrate exceeding 75 gallonsperday(notdueto temporary spike).CONTROLchargingflowUSING FCV-62-89 and FCV-62-93 RO as necessarytomaintainpzrlevelonprogram. MONITOR Pressurizer level STABLEorRISING.RO Appendix DNUREG1021Revision9 ((Appendix D Required Operator ActionsFormES-D-2OpTestNo.: NRCScenario#2Event#4Page10of 37----EventDescription:S/G#1TubeLeak Time II Position II Applicant'sActionsorBehavior(RNO-Maybeperformedlaterwhenleak increases)PERFORMthefollowing:

• START additionalCCPasnecessary.
• IF pressurizerlevelcontinuestodrop,THENENSUREletdownisolated:
• FCV-62-72CLOSED RO/SRO*FCV-62-73CLOSED
• FCV-62-74 CLOSEDIFlossof Pressurizerlevelisimminent,THENPERFORMthefollowing:
• TRIPthereactor.
• INITIATE Safety Injection.
• GOTO E-O, ReactorTripor Safety Injection.

MAINTAINVCTlevel greaterthan13%using automatic or ROmanualmakeup. INITIATErapidshutdownbyperformingthefollowing:

• ANNOUNCES/GtubeleakonPAsystem.
• PERFORMrapidshutdownUSING AOP-C.03 WHILE continuing in this section.*ENSURE powerreducedtolessthan50%withinone Crew hour.*ENSUREunitinMode3withinthefollowing2hours.(SRO May handoff AOP-R.01 topBOPto perform reader Doer while directing rapid shutdown)Appendix DNUREG1021Revision9 (Appendix 0 Required Operator ActionsFormES-D-2OpTestNo.:NRCScenario#

2Event#4Page11of 37--EventDescription:S/G#1TubeLeak I Time II Position IIApplicant'sActionsorBehavior EvaluatorNote:The followingstepsfromAOP-R.01should continueinparallelwithplantrapid shutdown using AOP-C.03 directed by SRO.Refertothenexteventguideforrapid shutdown.NOTIFYRADCONto monitorTurbineBuildingandsite environment:BOP*Steamlines*S/G blowdown NOTIFYChemLabtoperformthe following: a.EVALUATE Primary to Secondary Leakage USINGSI-CEM-068-137.5: (BOP BOP*Method1,Rapid IdentificationofLeakingSteam Generators (S/Gs)[Identifies S/Gviablowdown sampling*Method3, Condenser Vacuum Exhaust (CVE)Sampling for Determination of Primary-to-Secondary (PIS)Leakage.[providesleakrateby comparison of RCS activityandCVE.Steady State conditions increase accuracy]b.DETERMINEnoblegasreleaserate,and particulate &iodinedoseratesfor condenser vacuum exhaust USINGSI-CEM-030-415.0 and 0-SI-CEM-030-407.2. c.ALIGN steam generatorsampledrainlinestoFDCT USING 0-TI-CEM-000-016.4. BYPASS condensate 01.NOTE Closure of FCV-15-44 or FCV-15-43willisolateblowdownflowto RM-90-120/121. Steam GeneratorBlowdownmustbere-alignedtoCon 01using1(2)-SO-15-1to establishflowtoradmonitors. Appendix 0NUREG1021Revision9 Appendix 0RequiredOperatorActionsFormES-D-2OpTestNo.:NRCScenario# 2Event#4Page12of 37----EventDescription: S/G#1TubeLeakTimePosition Applicant'sActionsorBehaviorTERMINATESteamGeneratorSlowdowntoCooling Tower Slowdown:a.ENSUREFCV-15-44S/GblowdowntoCooling TowerSOPSlowdownCLOSED.b.ENSURES/GblowdownALIGNEDtoCon 01USING1 SO-15-1.NOTE CondenserVacuumExhaustandS/GblowdownRadiationMonitorsshouldbemonitoredat approximately15minuteintervalsforindicationsofrisingleakrate. AppendixAperformanceisnotrequired.MONITORindicationsofleakingsteam generator: (SOPa.IDENTIFYleakingS/G(s)USINGanyofthefollowing:*UnexpectedriseinanyS/Gnarrowrangelevel.*S/Gsampleresults.*RADCONsurveyofmainsteamlinesandS/Gblowdown lines.*Highradiationonanymainsteamlineradiationmonitor.b.MONITORCondenserVacuumExhaustandS/GSlowdownRadiationMonitorsforriseinleakrate. CAUTION ClosingTOAFW pump steam supply from SIG#1 will impact AFW operability. Refer toLCO3.7.1.2. Appendix 0NUREG1021Revision9 Appendix DRequiredOperatorActionsFormES-D-2OpTestNo.:NRCScenario# 2Event#4Page13of37 --EventDescription: S/G#1TubeLeak Time II Position II Applicant'sActionsorBehavior WHENleakingS/GIDENTIFIED,THENPERFORM the following: a.ADJUSTleakingS/G atmospheric relief controllerto87%inAUTO.(1040psig) b.ENSUREblowdownvalvesonleakingS/GCLOSED.BOPc.CLOSETDAFWpumpsteamsupplyfromleakingS/G*FCV-1-15(S/G#1) Or*FCV-1-16(S/G#4). d.ENSURETDAFWpumpsteamsupplyfromintactS/G OPEN (BOP MINIMIZESpreadofcontamination. a.PERFORMEA-0-3,Minimizing Secondary Plant Contamination. b.EVALUATE Appendix C, ContingencyPlanforControlandProcessingofLargeVolumesof Contaminated Water NOTEStepspriortoStep21maybeperformedinparallelwithES-0.1. CHECKreactorSHUTDOWN.DONOTCONTINUEthissectionUNTILreactorshutdown. Sectionwillbe terminatedwhenReactorTripandSI have been actuated.Appendix DNUREG1021Revision9 ((Appendix D Required Operator ActionsFormES-D-2OpTestNo.:NRCScenario

1. 2 Event#5&6 Page 14 of 37--Event

Description:

RapidShutdown, EmergencyBorationValveFailure Time II Position II Applicant'sActionsor Behavior Console Operator:Noactionrequiredforevent5or 6.Indications Available:

• RapidShutdown:N/A
• EmergencyBorationValvecontinuestoindicateclosedwith0flowwhentakentotheopenposition.

EnterandDirect performance of AOP-C.03, Rapid Shutdown or SRO Load Reduction. ENSUREcrewhasbeenbriefedon reactivity management SRO expectations USING Appendix E.NOTIFY following personnelofrapid shutdownorload reduction:

• Load Coordinator Crew*Chemistry*RADCON*Plant Management MONITOR reactor/turbinetripNOTrequired USING Appendix BOP/RO A, Reactor and TurbineTripCriteria.

CHECK VALVE POSITIONLIMITlight DARKonEHCpanel. BOP/RO[M-2]NOTE:BATis preferredborationsource.Boration volume and flowratesinthe followingstepare recommendationsandmaybe adjusted as necessary. Appendix D NUREG1021Revision9 (Appendix D Required Operator Actions Form ES-D-2OpTestNo.:NRC Scenario#2 Event#5&6 Page 15 of 37--Event

Description:

RapidShutdown,EmergencyBorationValveFailure Time Position Applicant'sActionsor Behavior{IFboratingfromBAT, THEN PERFORM the following: a.DETERMINE recommended boration volume:*-800galtoreduce powerfrom100%to20% RO/SRO OR*10galforeach1% power reduction b.DETERMINE recommended boration flowrate and volumefromtablebelow: TURBINE LOAD BORATION REDUCTION RATE (%Jmin)fLOWRATE SRO 1% 2%-3:0gpm 3% 4% (SRO discretion may be used to determine reduction rate)c.PLACE boric acid transfer pump aligned to blender in ROFASTspeed. ADJUST FCV-62-138 to establish desired flow rate.(Valvewillnotopen,RNOrequired-AppendixDnext page)RO INITIATE normal boration USING Appendix D.Appendix D NUREG 1021 Revision 9 (Appendix D Required Operator ActionsFormES-D-2OpTestNo.:NRCScenario

1. 2 Event#5&6Page16of 37----Event

Description:

RapidShutdown, EmergencyBorationValveFailure Time II Position II Applicant'sActionsor Behavior APPENDIXD-NORMAL BORATION PLACE[HS-62-140A]MakeupControltoSTOPposition. PLACE[HS-62-140B]Makeupmode selectorswitchin BORATE position.NOTEBoricAcid controllersettingistwicethedesiredflowrate.MaximumBoricAcidflowis -45 gpm.ADJUST[FC-62-139]BAflowcontrollersetpointfordesiredflowrate. ADJUST[FQ-62-139]BAintegrator(batch counter)todesiredboricacidvolume. PLACE[HS-62-140A]MakeupControlSwitchmode selector switchtoSTART.IFdesiredboricacidflowrateNOTobtained,THEN ADJUSToneorbothofthefollowingasnecessary:

• [FC-62-139]BAflow controller RO*recirculationvalveforBATalignedtoblender.ENSUREdesiredboricacidflowindicatedonFI-62-139.WHENrequiredboricacidvolumehasbeenadded,THENPERFORMthefollowing:

a.PLACE[HS-62-140A],MakeupControltoSTOPposition b.ENSURE[FC-62-142], Primary Water to Blender Flow ControllerinAUTOwithdialindicatorsetat35%. c.ADJUST[FC-62-139],BoricAcidFlow ControllertodesiredblendsolutionUSINGTI-44BoronTables. d.PLACE[HS-62-140B],MakeupMode Selector e.SwitchinAUTOposition. f.PLACE[HS-62-140A],MakeupControltoSTART. Appendix DNUREG1021Revision9 ((Appendix 0 Required Operator ActionsFormES-D-2OpTestNo.: NRC Scenario#2 Event#5&6 Page17of37--Event

Description:

RapidShutdown, EmergencyBorationValveFailure Time II Position II Applicant'sActionsor Behavior CONTROLborationflowasrequiredtoinjectdesiredboricacid RO volume.INITIATEloadreductionasfollows: a.ADJUSTloadratetodesiredvalue:

• between1%and4%perminuteifboratingvia FCV-62-138 OR*between 1%and 3%per minute if borating via normal boration (App.DJ b.ADJUST setterfordesiredpowerlevel:

DESI'RED RECOMMENDED RX POWER LEVEL SETTER VALUE 90%70 SRO/RO 80%60 50 60 0/0 40 50%3.5 30 30%25 20%or less 15 INITIATEturbineloadreductionby depressing GO pushbutton. BOP CONTROLturbineloadreductionas necessarytoreduce BOPpowertodesiredlevel. Appendix 0NUREG1021Revision9 Appendix 0 Required Operator Actions Form ES-D-2OpTestNo.:NRCScenario

1. 2 Event#5&6 Page 18 of 37----Event

Description:

RapidShutdown,EmergencyBorationValveFailure Time 11 Position II Applicant'sActionsor Behavior MONITOR T-avg/T-ref mismatch: a.CHECK T-ref indication AVAILABLE. (ROIBOP ROIBOP BOP RO (Tref Indicationisnot availabledueto PT-1-73 failure)-RNO Required-NextStep)PERFORMthefollowing: 1)MONITORProgramT-avgfor current reactor power USINGTI-28FigureA.9orICS(NSSS IBOP,Program Reactor Average Temperature). 2)USEprogramT-avginplaceofT-ref. 3)MAINTAINT-avgwithin3°FofprogramT-avg USING manualrodcontrol. 4)ADJUSTturbineloadrateas necessary. 5)IF mismatchbetweenT-avgandprogramvalue CANNOT be maintainedlessthan5°F, THEN TRIPthereactorandGOTO E-O, ReactorTripor Safety Injection. STOP secondary plant equipment USING Appendix B, Secondary Plant Equipment. MONITORcontrolrodsabove low-low insertion limit USINGICSorCOLR. Evaluator Note: Additional AOP-C.03Stepsnotincludedasrequired power changeshouldbe completeatoraroundthisstep. Whendesired,theLead Examinermaycuethenextevent. Appendix 0 NUREG1021Revision9 Appendix D Required Operator ActionsFormES-D-2OpTestNo.:NRCScenario#2Event# 7,8,&9EventDescription:#1S/GTubeRupture,AFWPump1AAutostartfail,PrzrsprayValvefailsopen. TimeAlicant'sActionsorBehavior (Console Operator: Increase SGTRto8.6 severity (400 gpm)with 300 second ramp.Fail Pressurizer loop 2 spray valvefullopen afterithasbeen fully openedforRCS depressurizationinE-3.Indications Available: Steam Generator tube Rupture:*Pressurizer pressure decreasing

• Pressurizer level decreasing and charging flow increasing
• Loop 1 Main SteamLineRad Monitor Increasing AFW Pump1A auto Start Failure:*Pump Not running with 51 Signal present Pressurizer Spray valve failed open:*Red Control panel light lit with 0 controller demand*Pressurizer Pressure Stable or slightly decreasingDirectManual Reactortripand SafetyInjectionbasedonloss of pressurizer level imminentfromAOP-R.01Step1RNO.

(Appendix D SRO RO SROAstimeallows,mayalsoperformthefollowingas directed bysameRNO:*start additionsl CCP*isolateletdown Manually Trip ReactorandinitiateSI.EnterandDirect performance of E-O, ReactorTripOr Safety Injection. NUREG1021Revision9 (Appendix 0RequiredOperatorActionsFormES-D-2 Op Test No.: NRC Scenario#2Event#7,8,&9 Page 20 of 37 Event

Description:

1. 1S/G Tube Rupture,AFWPump1AAutostartfail,Przrspray Valve fails open.Time II Position II Applicant's Actions or BehaviorNOTE1: Steps 1 through 4 are immediate action steps.NOTE2: This procedurehasa foldout page.Evaluator Note:AFWPump1Aautostartfailureshouldbeidentifiedandpumpstartedduringperformanceofprudent operator actions immediatelyfollowingperformanceofImmediate Operator Actions.VERIFY reador TRIPPED: Rod bottom lights LIT Reactor trip bypass breakers DISCONNECTED or OPEN Reactor trip break&ts OPEN Rod position indicators less than or equal to 12 steps.*..(RO*....Neutron ftux DROPPING BOP VERIFY turbine TRI PPED:..Turbine stop valves CLOSED.BOP VERIFY at least one train of shutdown boards ENERGIZED, DETERMINE ifSlaciuated:

RO..ECCS pumps RUNNING,..Any 81 alarm LIT[M,.,4DJ, Appendix 0NUREG1021Revision9 Appendix 0 Required Operator ActionsFormES-D-2OpTestNo.:NRCScenario#2Event# 7,8,&9Page21of 37 Event

Description:

1. 1S/GTubeRupture,AFWPump1AAutostartfail,PrzrsprayValvefailsopen.

I Time I Position I Applicant'sActionsor Behavior Evaluator Note:Ifnot previouslyIdentified,AFWPump1Aautostartfailureshouldbeidentifiedduring performanceES-0.5.WhenIdentified,thepumpshouldbe immediately started.BOP BOP BOP/RO PERFORM Equipment Verifications VVtU LE continuing in this procedure,(ES-0.5Atendof Scenario)DETERMINE if secondary heat sink available: a, CHECK total AFW flOvv gt'estertlan 440 gpm.b.CH,ECK narrow rangegreater than 10%[25%ADV]in at least one S/G.C.CONTROl feed flow to maIntain narrow r.ange level between 10%[25%ADV]and 50%in intact Of ruptured 8/Gs.CHECK if main steam lines should be isolated: a.CHECK if any of the following conditions have occurr&d;*Any SlG pressure less than 600 psig.OR*Any SiG pressure dropping UNCONTROLLED. OR Appendix 0NUREG1021Revision9 (Appendix D Required Operator ActionsFormES-D-2OpTestNo.:NRC Scenario#2 Event#7,8,&9 Page 22 of 37 Event

Description:

1. 1S/GTubeRupture,AFWPump1AAutostartfail,PrzrsprayValvefailsopen.

Time II Position II Applicant'sActionsor Behavior CHECK RCP trip criteria: a.CHECK the following:

• RCS preS$ure RO less than 1250 psig AND*At least ona COP OR 81 pump RUNNING.MONnOR RCS temperatures:

(Appendix D RO RO/SOP-IF any Rep running, THEN CHECK T..avg stable at Of trending to betwaen 547 tiF and(IfNoPerformRNO)(RNO)IF tem perature less than 547°F and dropping, THEN PeRfORM the following: a.ENSURE steam dumps and atmospheric relIefS Cl.OSED.b.IF cooldown continues t THEN CONTROL total med flow USING Manual Control ofAFWFlow, (AFW Flow to Ruptured SIG#1 may be isolated during performance of EA-3-B.Level shouldbe>10%)NUREG1021Revision9 Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario#2 Event#7,8,&9 Page 23 of 37--Event

Description:

1. 1S/G Tube Rupture,AFWPump1AAuto start fail, przr spray Valve fails open.Time II Position II Applicant's Actions or Behavior (RO BOP BOP CHECK prElssuriz.er PORVs, safeties, and spray valves: a, Pressurizer PORVs CLOSED.b.Pressurizer safety valves CLOSED, e, Normal spray valves CLOSED, d, Power to at least one block vaive AVA1LABLE., e.At.

one block valve OPEN.DETERMINE if SlG secondary pressure boundaries are INTACT:*CHECK atl SIG pressures CONTROLLED or RISING.*CHeCK all S/G pressures greater than 140 psi;, DETERMINE if BIG tubes'are INTACT: a.CH.ECK the following:

• all SIG narrow range levels CONTROLLED or DROPPING.seoondary radiation NORMAL USING AppendiX A,$eeondary Rad Monitors..

{App.A is also contained in ES-O.5).(Crew will Transition to£-3 at this Step)Appendix D Enter and direct performanceofE-3Steam Generator TubeSROrupture. MONITOR at leut one Rep RUNNING, RONUREG1021 Revision 9 Appendix D Required Operator ActionsFormES-D-2OpTestNo.: NRC Scenario#2Event#7,8,&9 Page 24 of 37 Event

Description:

1. 1S/GTubeRupture,AFWPump1AAutostartfail,PrzrsprayValvefailsopen.

Time II Position II Applicant's Actions or Behavior ((Appendix D RO BOP MONITOR Rep trip criteria: a.CHECK the following:

• ReS pressureless than 1250 psig AND IF At least one CCP OR SI pump RUNNING.MONITOR indications of Ruptured SlG(s): a.IDENTIFY Ruptured SJG(s)as indicated by any of the follOWing:
• Unexpected rise in any SJG narrow range level.OR..High radiation from any SIG sample.OR*MCCON survey Qf main steam fines and SIGUnes...High radiation 00 any main steamlfne radiation monitor.NUREG1021Revision9 Appendix 0 Required Operator ActionsFormES-D-2OpTestNo.:

NRC Scenario#2Event#7,8,&9 Page 25 of 37--EventDescription:#1S/GTubeRupture,AFWPump1AAutostartfail,PrzrsprayValvefailsopen. Time II Position II Aoolicant'sActionsor Behavior CAUTION Isolating both steam supplieltothe TO AFW pump when it is the only scums of feed now wUI result in loss Of secondary heat sink.Critical Task1 Part 1 BOP ISOLATE flOw from Ruptured SlG(s}: a, ADJUST Ruptured SIG(5)atmospheric relief controller setpoint to 87%in AUTO.(1040 psig)b.CHECK Ruptured SlG(s)almo$'pheric relief hand switch in P..AUTO and valve(s)CLOSeD.c.CLOSE TO AFW pump steam suPPly from Ruptured SlG ..15 (81<3#1)or FCV-1..16{OO#4}, (RealigningTDAFWtoS/G

1. 4 not required since TDAFW pumpisTagged out of service)d.VERIFY Ruptured SlG(s)blowdawn isolation valves CLOSED.e.CLOSE RU,pWred SIG{s)MSIV and MSIV bypass valve..(Crew will close Loop#1 MSIV)CriticalTask:PriortoInitiationofRCSCooldownto Target Temperature.

(CAUTION Appendix 0 Feeding a SlG that Is Faulted and Ruptured increases the potential for an uncontroiledRCS cooldown and SlG overfill.This option sbould NOT be considered UNlESS needed forRCS cooldovm.NUREG1021Revision9 Appendix D Required Operator ActionsFormES-D-2OpTestNo.:NRCScenario#2Event#7,8,&9 Page 26 of 37--Event

Description:

1. 1S/GTubeRupture,AFWPump1AAutostartfail,PrzrsprayValvefailsopen.

Time II Position II Applicant'sActionsor Behavior I I (Critical Task1 Part 2 Appendix D BOP BOP MONITOR Ruptured S/O(.s)l&Vel: CI.CHECK narrow range Jevel greater than 1'0%(25%ADV].b.WHEN ruptured SlG lwei is greater than 10%125%A.DV], THEN'PERFORM the following: 1)STOP feed flew to ruptured$/G.2:)ENSURE Tutb&na Driven AFW Lev for ruptured SlG In CLOSE PULL TO LOCK.(Crew will isolate or verify isolated AFW to Loop 1 S/G)CriticalTask: PriortoInitiationofRCS Cooldown to Target Temperature. VER1FY Ruptured SlG ISOLA TED from Intact SlG(s): a.CHECK either of tha following conditions SATISFIED:

• Ruptured SlG MSiVs and MSIV bypass valves CLOSED OR*MSlV{s)and MSIV bypass valve(s)CLOSED on Intact 8/G(s)to be used for ReS cooldown.b.CHECK SIG#1 or SlG#4 ruptured.c.CHECK TOA.FW pump steam supply from ruptured SIS ISOlATED:*FCV-1-15 (SlG#1)or (SIG#4)CLOSeD NUREG1021Revision9 (Appendix D Required Operator ActionsFormES-D-2OpTestNo.:

NRC Scenario#2Event#7,8,&9Page27of37 --Event

Description:

1. 1S/GTubeRupture,AFWPump1AAutostartfail,PrzrsprayValvefailsopen.

Time II Position II Applicant'sActionsor Behavior CHECK Ruptured SIG pressure BOP greater than 550 p$ig UJnit t)or 425 pslg (YOU)*Determine Target Temperatureusingtableon next page.SRO Appendix DNUREG1021Revision9 (Appendix 0 Required Operator ActionsFormES-D-2OpTestNo.: NRCScenario#2Event#7,8,&9Page28of37 Event

Description:

1. 1S/GTubeRupture,AFWPump1AAutostartfail,PrzrsprayValvefailsopen.

Time" Position II Applicant'sActionsor Behavior NOTE..BIOOklng loW steamline pressure Sl as soon as pressurizer pressure is less than 1 960 psig wil prevent an inadvertent MSIV closure and keep the condenser available for stearn dump...After the low stea,mline pressure SI signal is blocked, main steamiine isolation wm occur if the high steam pressure rate setpoint is exceeded.*The 1250 ps,ig Rep mp criterion is NOT applj,cable after RCS cooldown is initiated in the fOiIONlng step.INITIATE RCS cooldown: 8.DETER" INE target core exit TIC temperature, based on Ruptured SlG pressure: Lowett Ruptured Target Core Exit SIG pressure{psig}TIC Temp (oF)1 1 00 or greater 497 1 050-1099 492 1 000-1 049 486 950999 480 900-949 473 S!30-S99 467 600<iii 849 460 750-799 453 700-749 445 650--699 437 600..649 4,28 550-599 41 9 500""" 549 410 450-499 399 425-449 393 Appendix 0NUREG1021Revision9 Appendix D Required Operator ActionsFormES-D-2 Op TestNo.:NRC Scenario#2 Event#7,8,&9Page29of 37--Event

Description:

1. 1S/GTubeRupture,AFWPump1AAutostartfail,PrzrsprayValvefailsopen.

Time II Position II Applicant'sActionsor Behavior b.WHEN RCS prMisure less than 1960 pmg, THEN PERFORM the following: (Appendix D BOP BOP 1)BLOCK low steamline pressure 51, 2)CHECK STEAMUNE: PR.ESS ISOUSI BLOCK RA T5.ISOL ENABLE: parmisstve UT,[M-4A, A4)e.DUMP steam to condenser from IntactSIG(s) at maximum achievabf'e rate: 1)CHECK condenser available:

• e.g condenser interlock permissive UT.(M-4A,.EGl*Intad: SlG MSIVs OPEN.2)PLACE steam dumps in OFF, 3)ENSURE steam dumps in steam pressure mode with demand tess tMn 25*%.4)PLACE sk1am dumps in ON, 5)ADJUST steam dump demand to FULLY OPEN three cooldoYm valves.G)WHEN T-avg is lea than 540 cF, THEN BYPASS steam, dump interlock.

7)RAISE AFW flow to intact SlGs as necessary to support cooIdown,NUREG1021Revision9 Appendix 0 Required Operator ActionsFormES-D-2 Op TestNo.:NRC Scenario#2 Event#7,8,&9 Page 30 of 37--Event

Description:

1. 1S/G Tube Rupture, AFW Pump1AAuto startfail,Przr spray Valve fails open.Time II Position II Applicant's Actions or Behavior (BOP BOP d, WHEN core exit TICs less than target temperature determined in Substep B,a, THEN PERFORM the.fofJowing; 1)CLOSE sleam dumps or SlG atmospheric reliefs to stop cooIdown, 2)REDUCE AFW flow as necessary to stop oooldown.MAINTAIN total1eed flow greater than 440 gpm UNTIL laval greater than 10%[25%ADV]in at least one Intact GIG.3)MAINTAIN core exit T!Cs less target temperature USING steam dumps or atmospheric reliefs.MAINTAIN rntactSlG narrow range levels: a.Greater than 10%(25%ADV]b.Between 200/0[25%AOV)and 50%.CAUTION Any time a pressurizer PORV opens t'tIleN is a possibility that it ma.y stiCk open.Appendix 0 RO RO BOP MONITOR pressurizer PORVs and block valves: a.Power to block valves AVAILABLE b.Pressurizer PORVs CLOSED e.At leas,t one block valve OPEN.RESET SI signal.MONITOR.AC bussesenergimd from start busses.NUREG1021Revision9 (Appendix 0 Required Operator Actions Form ES-D-2 Op TestNo.:NRC Scenario#2 Event#7,8,&9Page31 of 37--Event

Description:

1. 1S/G Tube Rupture,AFWPump1AAutostartfail,Przrspray Valve fails open.Time II Position II Applicant's Actions or Behavior RO ENSURE Phase A and Phase B RESET.CHICK control air established to containment 6K and aLl*

(2-FCV,.32--81) Train A essential air OpeN RO*1..FCV..s2-102 (2-FCV..32..103)Train B essential air OPEN*1..FCV-32;.110 (2-FCV111)non-ess$Otial air OPEN.(Appendix 0 RO DETERMINE if RHR pumps should be a.CHECK RHR pump suction algned from RWSr.b.CHECK RCSpressure greater than 300 psig.e.STOP RHR pumps and PLA.CE in A-AUTO.d.MONITOR RCS pressure greater than 300 psig.NUREG 1021 Revision 9 (Appendix D Required Operator ActionsFormES-D-2OpTestNo.:NRCScenario#2Event# 7,8,&9Page32of37EventDescription:#1S/GTubeRupture,AFWPump1AAutostartfail,PrzrsprayValvefailsopen. I Time II Positi Applicant'sActionsorBehavior (Critical Task 2 BOP BOP RO CHECK if ReS cooldown should be slopped: a.CHECK coree exit TICs le$$1ha1'l target temperature in SUbstep a,a, DO NOT CONTiNUE this procedure UNTIL core exit T lOs less than target temperature. b.CLOSE steam dumps or atmoSpheric reliefs to stop cooIdown.c.REDUCEAFW flow as necessary to stop cooldown.MAINTAIN totalfaed flow greater than 440 gpm UNTlllevel greater than 10%[25%AD\']in at least one Intact.stG, d.MAINTAIN core exit TICs less tha1'l target temperature USING steam dumps or atmospheric reliefs.CriticalTask:PriortoRCS Depressurization. CHECK Ruptured S/G(s)pressure STABLE or CHECK RCS subcooling based on core exit T<<>>girea!erthan eOG F.Console Operator Note:Whenloop2sprayvalveis completelyopeninnextstep, insert malfunctiontofailLoop2sprayvalvefullopen (Key 6).Appendix DNUREG1021Revision9 Appendix D Required Operator ActionsFormES-D-2OpTestNo.:NRCScenario# 2Event#7,8,&9 Page 33 of 37EventDescription:#1S/GTubeRupture,AFWPump1AAutostartfail,PrzrsprayValvefailsopen. I Time I Position II Applicant'sActionsorBehavior Critical Task 3 DEPRESSURIZE ReSto minimize break floW and to refill pressurizer. a, CHECK normal pressurizer spray AVA.ILABLE. b.INlnATE maximum available pressurizer spray.c..CHECK depressuri2stiion rate ADEQUATE, d.CONTINUE depressurization UNTIL any of the following conditions SATISFIED: (RO*Both of the folowing: 1)ReS pressure less than Ruptured SJG(s)pressure AND 2)Pressurizer level greater than 1 0%[20%ADV], OR Appendix D.?ressurizer level greater than 65%.OR*ReS subcooUng based on core exit TICs less than 4O"F.e.CLOSe spray valve(s): 1)Normal spray valves.(RNOsincesprayvalvewillnotclose-NextPage)CriticalTask:PriortoS/GOverfillNUREG1021Revision9 (Appendix 0 Required Operator ActionsFormES-D-2 Op TestNo.:NRC Scenario#2 Event#7,8,&9 Page 34 of 37 Event

Description:

1. 1S/GTubeRupture,AFWPump1AAutostartfail,PrzrsprayValvefailsopen.

Time II Position II Applicant's Actions or Behavior (RNO)1)STOP Reps#1and2.RO IF ReS pressure continues to drop, THEN STOP additional Rep as necessary. Scenario may be terminated when crew has completed ReS cooldown and depressurizationatlead examiner discretion. Appendix 0NUREG1021Revision9 (Appendix D Required Operator Actions Form ES-D-2OpTestNo.:NRCScenario

1. 2 Event#ES-O.5Page35of37

--Event

Description:

Equipment Verifications I Time II Position II Applicant's Actions or Behavior I ES-O.5 Actions CHECK ERCW system operation: BOP*VERIFYatleast fourERCWpumpsRUNNING.

• VERIFY DIG ERCW supplyvalvesOPEN.

VERIFYCCSpumpsRUNNING:

• Pump1A-A(2A-A)

BOP*Pump1B-B(2B-B)

• PumpC-S.VERIFYEGTSfansRUNNING.

BOP VERIFY generator breakers OPEN.BOP VERIFYAFWpumpsRUNNING:

• MDAFWpumps BOP*TDAFWpump.(If Not previously identified and started, 1A-A MDAFW pump start failure should be identified during performance of this step and pump immediately started)Appendix D NUREG1021Revision9 (Appendix 0 Required Operator ActionsFormES-D-2OpTestNo.:NRCScenario

1. 2 Event#ES-O.5Page 36of37--Event

Description:

Equipment Verifications Time II Position II Applicant'sActionsor Behavior NOTEAFWlevelcontrolvalvesshouldNOTberepositionedifmanualactionhasbeentakentocontrolS/Glevels,toestablishflowduetofailure,ortoisolateafaultedS/G. CHECKAFWvalvealignment: a.VERIFYMDAFWLCVsinAUTO. BOP b.VERIFYTOAFWLCVsOPEN. c.VERIFYMDAFWpumprecirculationvalvesFCV-3-400andFCV-3-401CLOSED. VERIFYMFWIsolation:

• MFWpumpsTRIPPED
• MFWregulatingvalvesCLOSED BOP*MFWregulatingbypassvalve controlleroutputsZERO
• MFWisolationvalvesCLOSED
• MFWflowZERO.

MONITORECCSoperation: VERIFYECCSpumpsRUNNING: BOP*CCPs*RHRpumps*SIpumps*VERIFYCCPflowthroughCCPIT.

• CHECKRCSpressurelessthan1500psig.

BOP*VERIFYSIpumpflow.

• CHECKRCSpressurelessthan300psig.
• VERIFYRHRpumpflow.

VERIFYESFsystemsALIGNED:

• PhaseAACTUATED:

BOP 0 CONTAINMENTISOLATIONPHASEATRAINAalarmLIT[M-6C,B5]. 0 CONTAINMENTISOLATIONPHASEATRAINBalarmLIT[M-6C,B6). Appendix 0NUREG1021Revision9 (((Appendix 0 Required Operator ActionsFormES-D-2OpTestNo.:NRCScenario

1. 2 Event#ES-O.5Page 37 of 37--Event

Description:

Equipment Verifications Time II Position II Aoolicant'sActionsorBehavior

• Containment Ventilation Isolation ACTUATED: 0 CONTAINMENT VENTILATION ISOLATIONTRAINAalarmLIT[M-6C,C5].

0 CONTAINMENT VENTILATION ISOLATIONTRAINBalarmLIT[M-6C,C6].

• Status monitor panels: 06CDARK 0 60 DARK 06ELIT OUTSIDEoutlinedarea 06HDARK 06JLIT.*TrainAstatuspanel6K:

0 CNTMT VENT GREEN 0PHASEAGREEN

• TrainBstatuspanel6L:

0 CNTMT VENT GREEN 0PHASEAGREEN MONITOR containment sprayNOTrequired:

• PhaseBNOT ACTUATED BOP AND*Containment pressurelessthan2.81psig
• Ensure Containment Sprayisactuated VERIFYpocketsumppumps STOPPED:[M-15,upperleft corner]*HS-77-410,RxBldgAuxFloorand Equipment Drain BOPSumppumpA*HS-77-411,RxBldgAuxFloorand Equipment DrainSumppumpB.

DISPATCHpersonneltoperformEA-0-1, Equipment Checks BOPFollowingESFActuation. Appendix 0NUREG1021Revision9 SHIFT TURNOVER CHECKLISTPage1of3 Today (0 SM 0 US/MCR Unit 1 0 UO Unit 1Off-going-Name 0 AUO Station SQN 0STA(STAFunction)AUOCompActionsOn-coming-NamePart1-Completed by Off-going Shift/Reviewed by On-coming Shift: Abnormal Eauioment Lineuo/Conditions: " s TrainA Week*All Equipment normal*TDAFW pump was tagged 2 hours ago for repair to theT&T valve.The packing was blowing excessively. Expected Return to service is 8 hours.(WO 07-080025-000 Total 0.03 gpm I Identified 0.02gpm I Unidentified 0.01 gpm.(Today 0600) SHIFT TURNOVER CHECKLISTPage2of3 Today (31ITest in Progress/Planned: (Including Need for New Brief)Dailyand ShiftlySisperworkschedule Major Activities/Procedures in Progress/Planned: None Radiological Changes in Plant During Shift: None TS LCO 3.7.1.2.a: TDAFW pump was tagged 2 hours ago for repair totheT&T valve.The packing was blowing excessively. Expected Return to service is 8 hours.TS 3.3.3.7.18b action 1;Accident Monitoring Instrumentation, ERCW to AFW Valve Position, Turbine Driven Pump.Part2-Performed by on-coming shift DReviewofOperatingLogSinceLastShiftHeldor3Days, WhicheverisLess(N/AforAUO's) DReviewofRounds Sheets/AbnormalReadings(AUO'sonly)ReviewtheFollowingProgramsforChangesSinceLastShiftTurnover: DStandingOrders DLCO(s)inActions(N/AforAUOs) D ImmediateRequiredReading DTACF(N/AforAUO's) Part3-Performed by both off-going and on-coming shift D WalkdownofMCRControlBoards(N/AforAUO's) Relief Time:ReliefDate: todayTVA40741[03-2001]OPDP-1-1[03-14-2001 SHIFT TURNOVER CHECKLISTPage3of3 Disabled Annunciators Today PANEL WINDOW ANNUNCIATOR Equipment Off-Normal (Pink Tags)WO I PER Number (UNID And Noun Name ID And Noun Name Panel Panel Problem Description MCRWO List Problem Description WO I PER Number WOlPER Number (UNITONE REACTIVITY BRIEF Date: TodayTime:Now RCS Boron: 1093 ppm Today I BA Controller Setpoint: 27%*IRCSB-10 Depletion:2ppm OperableBAT:A IBATABoron: 6850 ppm IBATCBoron: 6850 ppm I RWST Boron: 2601 ppm Nominal Gallons perrodstepfrom219: 7 gallonsofacid, 36 gallons of water*Verifyboricacidflow controllerissetatAdjustedSAControllerSettingiaw 0-SO-62-7section5.1 Gallonsofacid: 26 Gallons of water: 138 Rod Steps: 4 ((Power reduction amount EstimatedFinalRodPosition Estimated boron addition 10%198 Steps on bank D 101 gallons 30%174 Steps on bank D 295 gallons 50%152 Steps on bank D 485 gallons**Thesevaluesare approximationsandnotintendednorexpectedtobeexact.Thevaluesmaybe superceded by Rx Engineering or SO-62-7calculatedvalues.Thesevaluesarecalculatedassuming100% steadystatepower operation only.Engineeringdatalastupdatedoneweekago.DataValiduntiloneweekfrom now.Number of dilutions: 0***Number of borations: a Rod steps in: a Gallons per dilution: a Gallons per boration: a Rod steps out: a Total amount diluted: a Total amount borated: a Net change: a IN/Out Number of dilutions: a Number of borations: a Rod steps in: a Gallons per dilution: a Gallons per boration: a Rod steps out: a Total expected dilution: a Total expected boration: a Net change: a In/Out Remarks: Rx Power-100%MWD/MTU-1000 Xenon&Samarium at Equilibrium

• • • The boron letdown curve is flatforthenext25EFPD.

NextUnit1FluxMapis scheduled-three weeksfromnow Unit Supervisor: _Name/Date 2.18-2.48 2.33 IndicatorUnitsU1Date/Time U2 Date/TimeSI50 S/G Leakage?Yes/No No Today 1 Now No Today 1 Now SI 137.5 eVE Leakrate gpd<0.1 Today 1 Now<0.1 Today 1 Now5gpdleak equivalentcpm380 Today 1 Now 68 Today 1 Now30gpdleak equivalentcpm1980 Today 1 Now 83 Today 1 Now50gpdleak equivalent cpm 3250 Today 1 Now 206 Today 1 Now75gpdleak equivalent cpm 4850 Today 1 Now 455 Today 1 Now150gpdleak equivalent cpm 9750 Today 1 Now 870 Today 1 Now eVE Air Inleakage cfm 10 Today 1 Now 12.5 Today 1 NowBkgdon 99/119cfm50 Today 1 Now 40 Today 1 Now I Appendix DScenarioOutlineFormES-D-1 I (Facility: Sequoyah Scenario No.: 3OpTestNo.:NRC Examiners: Operators: Initial Conditions: -2%ReactorPower,AMain Feedwater Pump liS Turnover: ContinuePlantStartup. CurrentlyatO-GO-4Section5.2Step3. Target CTs:Establishatleastonetrainof containmentspraypriorto completing FR-Z.1 ManuallyalignonetrainofRHRfor Containment Sump RecirculationandEstablishECCSflowpriortoDegradedCoreCoolingConditions.EventMalf.No.EventType* Event Description No.1 N/A R-ATC ContinuePowerIncreasefrom -2%.N-SRO/BOP 2 CN01B C-SRO/BOPTriponeoftworunninghotwellpumps. Standbypumpshouldbe started.3 RX07A TS-SRO Controlling Pressurizer PressureChannelFailsHigh.Przrspray I-SRO/ATCvalvesOpenandrequiremanualactiontoclose.Techspec Evaluation. 4 RX02A2 TS-SRORTDCOLDLEG1 SENSOR2failshigh.Requiresmanualaction I-SRO/ATCtodefeatthechannel.TechSpec evaluation. 5 TH01BC-AIISmallRCSLeak-21gpminLoop2Hotleg. 6 TH01B M-AIIRCSLeakincreasetoBreakrequiresRxtripand Safety Injection. N/A TH01B N/A Following TransitiontoE-1RCSBreak IncreasestolargebreakLOCAto expedite Containment Sump Swapover.7 RP13C C-SRO/BOP Automatic FeedwaterIsolationfailsonbothtrainsrequiringmanualisolation. 8 RP16K644A C-SRO/ATC Both containment spray dischargevalvesfailtoAutoopenonHi-RP16K644B Hi Containmentpressuresignalrequiringmanualactiontoopen. ZDIHS722ATrainB Sprayvalvewillnot manually open CH08B1B ContainmentAirReturnfan OvercurrenttriponStart. 9 ZDIHS6372 C-SRO/ATCRHRsuctionvalveFCV-63-72from containment Sumpwillnot Aopen.ThisrequiresstoppingtheRHRPumpontheaffectedtrainandaligningsumprecirculationandECCSinjectionononetrainofRHR.*(N)ormal, (R)eactivity,(I)nstrument, (C)omponent, (M)ajor Appendix 0NUREG1021Revision9 I Appendix 0ScenarioOutline Scenario 3 SummaryFormES-D-1 I (Thecrewwill assumeshiftat approximately 2%reactorpowerwithfirstMain feedwaterpumpinserviceandcontinueapowerincrease.Duringthepowerincreaseoneofthetworunninghotwellpumpswilltriprequiringthe crewtoperformtheassociatedAOPandplacethethird non-operatinghotwellpumpinservice.Thepowerincreaseshouldcontinue.Followingan adequatepowerincreaseto demonstrateproficiency,thecontrolling pressurizer pressurechannelwillfailhighresultinginpressurizersprayvalvesfullyopeningandrequiringmanualactiontoclosethemandstoptheRCS depressurization.TheSROwilldirect performanceofAOPtoselectanother controllingchannelandreturnspraycontroltoautomatic.SROwillevaluateandenterapplicableReactorProtectionandESFAS instrumentation Technical specifications. When pressurizerpressureinstrumentactionsarecomplete,acoldlegRTDonloop1willfailhigh,thiswillcausetheTavgchannelforloop1tobehighandDeltaTchanneltobelow.TavgandDeltacontrolinputswillbedefeatedbyAOP performanceandprotectionchannelinputswillrequireTechnical Specificationentries.SROwill evaluateandenterapplicableTechnical specifications.Asmall unisolableRCSleakwilloccurof approximately21gpm.CrewwillattemptactionstoisolateleakusingAOP.Following determinationthattheleakisnotisolatedtheLeakwillbeincreasedtoaLargeBreakrequiring ReactorTripandSafetyInjection.Following TransitiontoE-1,RCSbreakwillbefurtherincreasedtoalargeBreakLOCAtoexpeditereachingRHR containmentsumpswapover.FollowingtheRxTripand Safety Injection, AutomaticFeedwaterIsolationwillfailrequiringmanualisolation.UponreachingtheHiHi containmentpressuresetpoint, containmentspraypumpswillstartbuttheirdischargevalveswillnotopenrequiringmanualactiontoinitiate containmentspray.TrainAsprayvalvewill open manuallybutBTrainwillnot.1B containmentAirreturnfanwilltripon Overcurrentwhenstarting10minutesafterPhaseB.Btrainsprayvalveand1BAirreturnfanfailureensure containment pressureremainshighenoughtorequirecrewtoperformFR-Z.1.TheCrewwill continuethroughtheEproceduresincludingFR-Z.1 contingencyprocedureforHi containment pressure and eventuallyreachthesetpointsforRHRsuctionto containments sump realignment.Oneofthe containmentsumpsupplyvalvesfailstoopen automatically or manually andrequirethecrewtostoptheaffectedRHRpumpandrealignonlyonetrainofRHRsuctionto containmentsump.Ifa setpoint for containment spray realignment to containmentsumpisreached,onlyonetrainof containmentspraycanbealignedtothe containmentsump,however,thedischargevalveonthattrainwillnotopenwhichresultsinno containmentspraycapability. The scenariomaybe terminatedafterECCSisalignedforRHRsumprecirculationusingonetrainofRHR Appendix 0NUREG1021Revision9 ..-----.....-.*.*,*,*,: I FCV---..------------ FCV 74*3 FCV 74-21 ,:: FCV:!,4-::.i',',',',.,' ,;!?: tf.r-.RHR U.L.I../.......

• • • , ,***Iu...FCV*63-5************************************.

___-_.._--__-----..---------------_

_-_---..,__-:*,*,*,',',*,',: RWST:*.*,','.'.*, L*.**T**....*.,.-------------___-______-__-___._------_------..-------------_ _-" LCV*.***11 LCV 62-135 LJ62.136 l j........__: o LCVy'" 62-132...LJ62.133f FCV 63*7 Page1of2 NRC08CRev0 CONSOLE OPERATOR INSTRUCTIONS Sim.Setup Event#1:IncreasePowerasdeterminedbyNRCExaminer.ResetIC-_9_Performswitchcheck.Allowthe simulatortorunforatleast3minutesbeforeloadingSCENfileorstartingtheexercise.ThiswillinitializeICS. LoadSCENS:NRC08C Place simulatormomentarilyinRUN,PlaceOOSequipmentinrequiredpositionwithtags,ClearalarmsandReturntoFREEZE.Initializesimulatorat -2%%RTPBOL.Place Mode.-l....placard on panels.Place....A-Train Week sign on the simulator. Ensure 1 PowerRangeand1 Intermediate Range are selected for displayonM-4NIS Recorder45.-2%POWERCONTINUEPLANTSTARTUP. (Event#2:WhenIMFCN01Bf:1 k:1Powerhadbeen Increased-2%-3%orasdeterminedbyNRCExaminer,InsertthisMalfuinctionusing '(ey 1 Event#3:WhenIMFRX07Af:1k:2 determinedbyNRCExaminer,InsertthisMalfuinctionusing Key 2 Event#4:WhenIMFRX02A2f:630k:3DeterminedbyNRCExaminer,insertthisMalfunctionusing Key 3.Event#5:WhenIMFTH01Bf:0.0025k:4DeterminedbyNRCExaminer,insertthisMalfunctionusing Key 4.Event#6:WhenMMFTH01Bf:5r:300Crewhasevaluated whetherleakisisolated(Step12 AOP-R.05), ModifythisMalfunctionat \lRC Lead Examiner I discretion.HOTWELLPUMPBTRIP When the Support US/AUO are dispatched to investigate, wait-5 min.and report that the relay target is instantaneous overcurrent and the motor smells hot.CONTROLLINGPZRPRESSURE TRANSMITTERPT68-340FAILSHIGHWhenIMs or MSS contacted to trip bistables, inform the crew that the IMs will reporttotheMCRin-45 minutes.RTDFAILURECOLDLEG1 SENSOR 2WhenIMs or MSS contacted to trip bistables, inform the crew thattheIMs will reporttotheMCRin-45 minutes.LOOP2RCSHOTLEGLEAK-21GPM.INCREASELOOP2RCSHOTLEGLEAKTOBREAKOVER5MINTOREQUIREREACTORTRIPANDSAFETYINJECTION. CONSOLE OPERATOR INSTRUCTIONSPage2of2 NRC08CRev0 (FollowingTransitionMMFTH01Bf:35INCREASELOOP2RCSHOTLEGBREAKTOtoE-1, ModifyHotlegLARGEBREAK.Breaksizeagainto expedite sump swapover.Event#7:ThisIMFRP13Cf:1FAILUREOFTHEAUTOFEEDWATERISOLATION MalfunctionisactiveSIGNAL-BOTHTRAINS.whentheSCENSfileisloaded.Event#8:TheseIMFRP16K644Af:11A-ACNTMTSPRAYVALVE,FCV-72-39,FAILSTO Malfunctions areAUTOOPENONHIHI CONTAINMENT PRESSUREactivewhentheSIGNAL.WILLMANUALLYOPEN.SCENSfileisloaded.IMFRP16K644Bf:11B-BCNTMTSPRAYVALVE,FCV-72-2,FAILSTOAUTOOPENONHIHI CONTAINMENT PRESSURESIGNAL.WILLMANUALLYOPEN. lOR ZDIHS722A f:OTRAINB CONTAINMENTSPRAYVALVEWILLNOTOPENMANUALLY.IMFCH08Bf:1AIRRETURNFAN1BTRIPON OVERCURRENTWHENSTARTED.(10MINUTESAFTERPHASEB) If dispatched to check ARF breaker, wait-5 min and report overcurret trip.Event#9:This lOR ZDIHS6372A f:OTRAINARHRSUMP SWAPOVERVALVEFCV Malfunctionisactive72FAILSCLOSED.whentheSCENSfileisloaded.When RequestedtoIRFRHR14f:1k:5RWSTTORHRPMPFLOWCNTLVLVPOWER,placepoweronFCV-FCV-63-1.63-1insertthisremotefunctionusing KeyS I Appendix D Required Operator ActionsFormES-D-2 IOpTestNo.: Event

Description:

NRCScenario

1. 3Event#PowerincreasePage1of46---'----------II Time II Position II Applicant'sActionsorBehavior (ConsoleOperator:Noactionrequiredforevent1 Indications Available:

None Applicable Direct load increase in accordance with 0-GO-4 Section 5.2,SROStep3.Reactor Power Ascension To Between 13%And 15%RTP.NOTES 1.Actions effecting reactivity are directedinthe following step.0-SO-62-7 requirementsshallbe adheredtofor reactivity changes(l.e,reactivitybalance, amountsofboricacidorwater).All appropriate verificationsandpeerchecksshallbeutilizedduring performance. 2.Recommendeddilutionrateis50to75gallon batches every12to15 minutesfora steady power increase.Rod movementshouldbelimitedto1/2step increments approximately every11/2minutes.Dilutionandrod movementratesmaybe adjusted dependingonSGlevelcontrolstability. 3.Control Rod withdrawaland/ordilution requirementsmaybe significantly impactedbythe changeincore reactivityduetochangingXenon concentration. INITIATE a methodical and deliberate reactor power increase CREWbymanual adjustmentofthecontrolbanksorby diluting the RCS.CREW WHEN reactor powerisabove5%,THENLOGMode1 entry intheUnit Narrative LOQ.MAINTAINtheSGlevelsonprogramby periodically adjusting CRO the feedwaterbypassreg controller level setpoints using Appendix Band C.Evaluator Note: The followingStepsarefrom 0-SO-62-7 Boron Concentration Control, Section 6.2, Dilute I Appendix D Required Operator Actions Form ES-D-2 IOpTestNo.:EventDescription:NRCScenario

1. Powerincrease 3 Event#Page2of46-.;..----

Time II Position II Applicant'sActionsorBehavior (CAUTION 1: When makinganRCS dilution of L3000 gallons, it should be done in batcheswithanRCSboron concentration verificationatthe halfway point(e.g.,1500 gallons).Allow at least 15 minutes between batches.CAUTION 2;ReturningtheBoricAcid Blender to service after unplugging, cleaning, or maintenanceontheBoricAcid System could introduce debris, sludge,airor chunks of solidified boronintotheCCP suction resulting in pump damage.Extreme care must be exercised to properlyflushtheBoricAcid Blender system following an outage.NOTE1:Ifan excessive amount of dilution is required (plant startup), the pressurizer heaters should be energizedtocause pressurizer spray operation for equalizing boron concentrationinRCSand pressurizer. NOTE 2: Dilute modewillbeused anytime a long-term positive reactivity addition is desired.The operator shouldusethe normal dilute mode whenever conditions permit.RO ENSUREunitisNOTina Tech SpecorTRM action that prohibits positivereactivityadditions. NOTE: HUT level increaseof1%isequalto1380 gallons (TI-28 fig.C.21)ENSURE sufficIent capacity avaiiabl,e in the HUT selected to receive expecteeamounts of eves letdown: (N/A IT not used)RO HUT lEVEL INITl.ALS A%B%RO ENSURE makeup system is aligned for AUTO operation in accordance with Section 5.1.RECORD the quantity of dilution water required to achieve RO desired boron concentration using Appendix D.(N/A for minor power changes)NOTEDueto eyeball interpolation the verified calculation may slightly differfromthe initial calculation. The following signoff indicates that any differencesinthetwo resultshavebeen discussedandare close enoughtobe considered validated. I Appendix D Required Operator ActionsFormES-D-2 IOpTestNo.:EventDescription:NRCScenario

1. 3Event#PowerincreasePage3of46.....;...----

Time II Position IIApplicant'sActionsorBehavior ((., PERFORM Appendix I Independent Verification of Calculation SRO for AmountofBoricAcidorPrimaryWater.(N/AifApp.DwasperformedbySROtoverifydatafromRx Engineering)(Step not required provided in shift turnover package)ROPLACE[HS-62-140A],BoricAcid Supply to Blender FlowControlSwitchtothe STOP position.ROPLACE[HS-62-140B],CVCSMakeup SelectorSwitchtothe DILUTE position.ROENSURE[HS-62-140D],BoricAcidValvetothe Blender is CLOSED(GreenlightisLIT). ROSET[FQ-62-142], Batch Integratorforthedesiredquantity. NOTE: Primary Water Flow Controller [FC-62-142]receivesitsreferencesignal(70 gpm)from setpoint potentiometer (dial indicator)locatedonpanelM-6.A setpoint of 35%correspondstoa70gpm primary waterflowrate.RO ADJUST[FC-62-142],PrimaryMakeup Water Flow Controllerforthedesiredflowrate. RO PLACE[HS-62-140A],BoricAcid Supply to Blender FlowControlSwitchtothe START position.NOTE: Flow oscillations and/or erratic controllerresponsemayrequiremanual operation of Primary Water Flow Controller [FC-62-142]untilstable conditions exist. the following; RO[a)Inlet to top ofVCT[FCV-6:2-12SJ is OPEN.[b)Primary Water flow by IFMi2-14ZA) OR IFQ..:62-142l NOTE: Alternate dilutioninsmall amounts is acceptableona regularbasis,providedno significantchangesinseal water temperatureorseal leakoffareindicated. Batchesof5to10 gallonsmaybeaddedthrough FCV-62-144ona frequencynottoexceedonceper30minutes.ICSpointsforNO.1 sealleakoffsandseal water temperaturesontheRCPsshouldbe monitoredduringand after dilution. I Appendix 0 Required Operator ActionsFormES-D-2 I (OpTestNo.:EventDescription:NRCScenario

1. 3Event#PowerincreasePage4of46.....;...----

'-;";'---11TimePositionApplicant'sActionsorBehavior (IF primary water addition to the bottom of the VeT[I=C\I-62-144]Is desired, THEN[a]CLOS:E[Fey-62-128}\iliittl [HS-62-128]. RO[b]OPEN[FCV-62-U4) with[HS-62-M41 [e]VERIFY Primary'Water{IDev" by[H.62-142A] OR (FQ-62-142]. NOTE: It may take approximately 15minutesbeforeanychangesto reactivity areindicatedon nuclear instrumentationorRCS temperature indication. RO MONITOR nuclear instrumentation and reactor coolant temperaturetoensuretheproperresponse from dilution.IF[1I-62-129] ,VolumeControlTankLevel, increases to 63ROpercent,THENENSURE [LCV-62-118],VolumeControl TankDivertValve OPENStodivert excess watertothe Holdup Tanks.WHEN dIlution is complete, THEN[a]PLACE[HSc62-140A], Boric Acid to Blender Flow Control Switch to the STOP position.[b]IF[FC\L62-1441 was previously OPENED, THEN RO CLOSE[FCV-62-1441 with[HS-62-144). Ee]VERIFY no prima.ry waterflow' on either (H-62-142A] OR (FQ-62-14.2]. Ed]ENSURE is CLOSED.Lead Examiner may direct initiation of the next event at his discretion. Steps on the next two pages are associated with performance of repetitive dilutions or may not be performed until all dilutions are complete. I Appendix D Required Operator Actions Form ES-D-2 I Op Test No.: Event

Description:

NRC Scenario#Power increase 3 Event#Page5of46 Time II Position II Applicant's Actions or Behavior (RO[17]IF power increase in progress and additional dilutions will be required,THENusethis table to re-perform steps[4]through[1 8].STEP3'"[4]RECORD the quantity of dilution water required to achieve desired boronconcentration usma Appendix D.[5]PERFORM Appendix I, IV af Cakulation for amount afBA or PW.'[6]PLACE[HS-62-140A), Boric Acid Supply to Blender Flow Control to the f i f STOP position. 1it f::i.l 1"" C\I[1]PLACE[HS..;62-1408], eves Makeup Selector Switch to the mLUTE position.00 0[8]ENSURE[HS-62-140D] Boric Acid Valve to Blender;1S CLOSED (GreenEght LIT}.00 0[9]SET[FQ-62-1411, Batch Integrator for the desired quantity.!!fcvCV 7'" Gil[10]ADJUST[fC-fil-141], Primar:'1 Makeup I"Vater Flow Controller for the desired i!I now ratR 7'cv fa W[H]PLACE[H S-li2-140AJ, SA Supply to Blender Flow Control Switch to START.j J f lto;C'lJ'CV:::tv[12]VERIFY the following: [a]Inlet to top ofVCT !S OPEN.D00[b]Primary Waterflcrw by[R62-142A] or[FQ-62-142].000 f13]IF PV.J addition to top of VeT (FCV-6.l-118] 15 not warranted, but PW addition to the bottom oftlle VCT'rFCV-62-144] is desired, THEN[a]CLOSE[FCV-62-1281'llith [I-1S-62-128]000[h]OPEN[FCV-62-144] with[HS-61-1441.000[c]VERIFY Primary Water ftow by[FI-62-141A ]or[Hl-61-142l 0 0 0[14]MONITOR nuclear instrumentation and reactor coolant temperature to ensure D00 the praper reseense from dilution.[15}IF[U-62-1191 VCT level, increases to 63 percent, THEN ENSURE 0 D 0 (lCV-62-118], VCT Divert Valve, OPENS to divert excess water to the HUTs.[16]WHEN dilution is compJete, THEN!!f[a]PLACE[HS-6L-140Al, Boric Acid to Blender How Control Switch to STOP 7:ev 7 cv T ,cv[h]IF was previOUSly OPENED, THEN CLOSE[FCV-62-144] '¢;,ith[HS-61-144].000[e]VERliFY no primary waterfkrw 00 either[FI-61-142A) or[FQ c61-142].000[d]ENSURE[FCV-61-118],1S CLOSED.000[18]IF step[17]wilt be repeated, THEN PERFORM the following: [a]PLACE[HS-62-14013], eves Makeup Selector SWitch to the AUTO posmon.[13]PLACE[HS-61-140A] , SA to Blender Flow Control SWitcb to START position.[e]ENSURE dilution is fiogged in Ufltt Narrative log. I Appendix DRequiredOperatorActions Form ES-D-2 IOpTestNo.:EventDescription:NRCScenario

1. 3Event#Powerincrease

.....;...Page6 of 46 Time II Position IIApplicant'sActionsorBehavior (RO REALIGNtheblendercontrolsfor AUTOmakeuptotheCVCSin accordancewithSection5.1. RO ENSURE dilution(s)isloggedinUnitNarrativeLog. NOTE SamplemaybeobtainedatnormalRCSsampleintervalsprovidedtheunitisat powerandtheunitresponsefollowingthedilutionisasexpected. IFRCSboronsampleisrequired, THEN NOTIFYChemLabtoobtainRCSboronsample. I Appendix 0 Required Operator Actions Form ES-D-2 IOpTestNo.:NRCScenario

1. 3 Event#2EventDescription:Triponeoftworunninghotwellpumps(BPump)

Time II Position Applicant'sActionsorBehavior (Console Operator: When directed, initiate event 2 Indications available: Motor TripoutalarmPanelM-1 White disagreementlightonHotwellPumpB handswitch. BOPPlacefailedpumpswitchin STOP Position.Refer to Annunciator Response Procedure. SRO Enter and direct actions of AOP-S.04,section2.4. ENSUREtwohotwellpumps RUNNING.BOP (Should Start Non-Operating Pump)MONITOR Steam generator levels BOPreturningtoprogram.[M-4] ENSURE the following conditions:

• Reactor power STABLE CREW*Turbine load STABLE DISPATCH operator to investigate cause BOPofHotwellPumptrip.

CAUTION: Reducing turbineloadtoorapidlycouldresultin furtherdropin condensate pressuredueto reduction in heaterdrainflow. Recommendedloadrateis1%per minute if turbine load reductionisneeded.NOTE: SevereMFWpump cavitationislikelyifinlet pressureislessthan250psig. I Appendix D Required Operator ActionsFormES-D-2 I Op Test No.: NRC Scenario#3Event#2of46 Event

Description:

Triponeoftworunninghotwell pumps(BPump)Time II Position II Applicant's Actions or Behavior (MONITOR Feedwaterpumpinletpressure BOP greaterthan320psig.[M-3,PI-2-129] CHECK reactor power greater than 75%.RO NOTE:WithonlytwoHotwellpumpsinserviceat100%power,cavitationmay occur and overtimecouldleadtopumpdamage.Powerreductionto75%providesmarginfor additional failures.IFHotwellPumpcannotberestoredwithin24hours, THEN EVALUATE reactorpowerreductiontolessthan75%at1%perminute USING 0-80-5,NormalPowerOperation. NOTIFY Maintenance to investigateandrepairpump malfunctionasnecessary.GOTO appropriateplantprocedure. Proceed to next eventatlead examiners discretion. I Appendix DRequiredOperatorActionsFormES-D-2 I Op Test No.: NRC Scenario#3Event#3 of 46 Event

Description:

Controlling Pressurizer Pressure channelFailsHigh Time Position Applicant's Actions or Behavior (Console Operator: When directed, initiate event 3 Indications available: PressurizerHiPressure,AlarmPanel(M-6a,C-S) Pressurizer Pressure above Setpoint,AlarmPanel(M-SA,B-3) Both Pressurizersprayvalvesfullopen. ROManuallyclosebothsprayvalves.(Immediate Action)SROEnteranddirectactionsof AOP-1.04,Section2.3. NOTEStep1isanIMMEDIATEACTION. CHECKnormalsprayvalvesCLOSED. RO (RNO)IFRCSpressureislessthan2260psig, THEN CLOSEaffectedsprayvalve(s) USINGthefollowing:PIC-68-340A,MasterPressureController. OR ROPZRSpraycontrollers PIC-68-340D(Loop1)and/or PIC-68-340B(Loop2).MONITORpressurizerpressurestableortrendingtodesired RO pressure.CHECK PI-68-340A NORMAL.RO (RNO) I Appendix 0 Required Operator Actions Form ES-0-2 IOpTestNo.:NRCScenario

1. 3Event#3EventDescription:ControllingPressurizerPressurechannelFailsHigh Time II Position II ROApplicant'sActionsorBehavior PERFORM the following:

a.ENSURE PRESS CONTROL SELECTOR switch3400 in PT-68-334&323.b.ENSURE LOOP TAVG T REC/SEL selector switch2Bin LOOP2,3,or4.c.ENSURE PRESS REC CHANNEL SELECTOR340B in PT-68-334, PT-68-323, or PT-68-322. d.GOTO Caution prior to Step 8.CAUTION: RCS pressure changes and changesinRCSboron concentration(dueto differences betweenpzrandRCS boron)maycausesmall changeincore reactivity. MONITOR reactor power: a.CHECK reactorinMode1or2. RO b.MONITOR core thermal power for unexpected changes.(SRO RO RO EVALUATE the following Tech Specs for applicability:

• 3.2.5 ONB Parameters

-(N/A unlessRCSpress decreased below 2205 psig)*3.3.1.1(3.3.1),ReactorTripSystem(Action6applies)*3.3.2.1(3.3.2), ESF Actuation System Instrumentation(Action17applies)

• 3.3.3.5 Remote Shutdown Instrumentation

-(N/A)*3.4.4 Pressurizer Heaters (may beapplicablewhile heaters are unavailabledueto instrument failure)-(N/A)CHECK PZR PRESSandPZR SPRAY controllers in AUTO.(RNO)WHEN malfunctionhasbeen identified AND isolated or corrected,THENPERFORM the following: a.ENSURE Master Pzr Pressure Controller PIC-68-340A Output Percent Meterislessthan40%. b.ENSURE PZR PRESS Controller, PZR SPRAY controller, and PZR HTRS in AUTO.(NOTE: If performingAOPin conjunctionwithAOP-1.11foranEagleLCP failure, then actionstohardtrip bistables should be delayeduntilEagle systemresetis attempted. Actionstohardtrip bistables must be completed within 6 hours UNLESS affectedloopis.restored to operable status by resettingEaglerack. I Appendix 0 Required Operator ActionsFormES-D-2 IOpTestNo.:NRCScenario

1. 3 Event#3 of 46EventDescription:ControllingPressurizerPressurechannelFailsHigh Time II Position Applicant'sActionsorBehavior

((REMOVE failed pressurizerpressurechannelfromservice: SRO CHECK any pressurizerpressurechannel INOPERABLE. RO CHECK setpointonaffectedchannelNORMAL. RO (RNO)GOTO Substep t t.d.IFanyofthefollowingconditionsexists:

• transmittersignalfailed(entire instrument loop affectedincludingOTTpressureinput)

SRO OR*OTTpressureinput potentiallyaffectedorstatus CANNOT be determined,THENPERFORM applicable appendix: PZR PRESSURE CHANNEL APPENDIX P-68-340 (P-455)I A SRO P-68-334 (P-456)Iii B P-68-323 (P-457]nl C P-68-322 (P-458)IV oGOTO appropriateplantprocedure. SROIfTech Specshavebeen evaluated,Proceedtonexteventatlead examiners discretion. (Appendix DRequiredOperatorActionsFormES-D-2OpTestNo.:NRCScenario# 3Event#4Page12of 46--Event

Description:

RTDfailureColdLegLoop1 Sensor#2FailHigh. Time II Position II Applicant'sActionsor Behavior Console Operator: When directed, initiate Event 4 Indications available: Alarm"Narrow Range RTD failure Loop1"(PanelXA-555A,D-6) Alarm"TS-68-2D Reac Cool Loops Overtemp 11 T Trip Alert"(PanelXA-556A,A-2) Loop 1 Tavg indicatingHIand Loop 1 11 T Indicating Low(PanelM-5)RORefertoAnnunciatorResponseProcedureEnteranddirectActionsof AOP-1.02 SRO PLACErodcontrolin MANUAL.RO(N/ARodsalreadyinManualat2%Power) CAUTION:ControlrodsshouldNOTbemanuallywithdrawnduringaplanttransient.RESTORETavgwithin1.5°FofTrefUSINGoneofthe following:

• manualrodcontrol OR SRO*RCSboration/dilution OR*turbineloadreduction(StepisN/AsinceTrefnotavailablewithTurbineoffline)CHECKloop1temperaturechannelOPERABLE.

RO (RNO)PERFORMthefollowing: a.PULL-TO-DEFEATTAVGCHANNELDEFEATswitchtoLOOP1 b.PULL-TO-DEFEAT ilTCHANNELDEFEATswitchto ROLOOP1 c.PLACELOOPTAVG ilTREC/SELswitchinLOOP 2,3, or 4 d.GOTOStep7.AppendixDNUREG1021Revision9 ((Appendix 0 Required Operator ActionsFormES-D-2OpTestNo.:NRCScenario#3Event# 4Page13of 46--Event

Description:

RTDfailureColdLegLoop1 Sensor#2FailHigh. Time II Position II Applicant'sActionsor Behavior EVALUATEthefollowingTechSpecsfor applicability:

• 3.3.1.1(3.3.1),ReactorTripSystem Instrumentation

-(OT Ii.TAction 6 alreadyineffect, SIG Level Ii.TAction10alsoapplies.) SRO*3.3.2.1(3.3.2),Engineered SafetyFeatureActuation System Instrumentation-(Action37for SIGLevelAFWstartapplies). NOTE: If performingAOPin conjunction with AOP-1.11foranEagleLCPfailure,then actionstohardtripbistablesshouldbedelayeduntilEaglesystemresetis attempted. Actionstohardtripbistablesmustbecompletedwithin6hours UNLESSaffectedloopisrestoredto operablestatusbyresettingEaglerack. RO NOTIFY 1MtoremovefailedTAVG L\T instrumentloopfrom service USING appropriate Appendix: ReS INSTRUMENT PROT LOOP APPENDIX LOOP NUMBER CH 1 T-68-2'I: A (T-4*t114"12)2 T-6H-25 a B (T-4211422)3 II!'I:!C (T-4311432)4 T-6&-67 IV D (T-4411442)IF automaticrodcontrolisavailable, THEN RESTORErodcontroltoAUTO.USING 0-SO-85-1.(StepIsN/A)GOTO appropriateplantprocedure. WhenTechSpec Evaluation is completeproceedtothenext eventatlead examiner's discretion. Appendix 0NUREG1021Revision9 ((Appendix D Required Operator ActionsFormES-D-2OpTestNo.:NRCScenario

1. 3 Event#5 Page 14 of 46--Event

Description:

SmallRCSLeakinside containment(HotLegLoop2) Time II Position II Applicant'sActionsorBehavior Console Operator: When directed, initiateEvent5 Indications available: Containment Pressure Small IncreaseonM-6 Recorder PDIR-30-133 Containment Radiation monitors106,and112 increase Charging flow increase&VCTLevel Decrease Alarm (1st one after-12min):ReactorBuildingAUXFL&EQDrainSumpHi SROWhenRCSLeakIdentified enteranddirectactionsofAOP-R.05.EVALUATEthefollowingTech SpeclTRMLCOsfor applicability:

• 3.2.5,DNB parameters
• 3.4.3.1,SafetyandReliefValves-Operating
• 3.4.3.2,Relief Valves-Operating
• 3.4.6.2,RCSLeakage SRO*TRM 3.4.11, ReactorCoolantSystemHeadVents
• 3.4.12,Low TemperatureOverPressureProtection Systems*3.6.1.4, Containment Pressure*3.6.1.5, Containment Air Temperature(TechSpecsmaybeevaluatedlateratLead Examiners discretion)

EVALUATE EPIP-1, Emergency Plan Classification Matrix.SRO (DirectSMtoEvaluateREP) IFleakresultsin radiologicalhazardorsafetyhazard, THEN SRO EVACUATE unnecessarypersonnelfromaffectedareas. DIAGNOSEthefailure: SRO (EnterSection2.1) CONTROLchargingflowas necessarytomaintain pressurizer ROlevelonprogram. Appendix DNUREG1021Revision9 (Appendix D Required Operator ActionsFormES-D-2OpTestNo.:NRCScenario

1. 3 Event#5 Page 15 of 46--EventDescription:SmallRCSLeakinsidecontainment(HotLegLoop2)

Time II Position II Applicant'sActionsor Behavior MONITOR pressurizer level:*greaterthan10%RO*STABLEorRISING.(MayReturntoperformRNOToTripRXandInitiateSIlaterwhenLeakincreases) NOTE:VCTleveltovolumeconversionis approximately20gal/%.Achangein indicatedlevelof0.5%inoneminuteequalsthe10 gal/minEPIP-1criteria. MAINTAINVCTlevel greaterthan13%USING automatic or ROmanualmakeup. MONITOR containmentpressureSTABLEorDROPPING. RO(RNOtoTripandSImayalsoapplylaterwhenleak increases) MONITOR ReS pressure STABLE or RISING.RO CHECK secondarysideradiation NORMAL:*S/Gblowdownrad monitor BOP*Condenser vacuum exhaust rad monitor*Mainsteamlineradmonitors. CHECKleakinsidecontainment:

• containmentpressureRISING ABNORMALL Y OR*containment temperature or humidity abnormal CREW OR*containmentairborneactivity abnormal (RM-90-106 or 112).CHECK containmentairborneactivityRISING.(RM-90-106 or BOP 112)Appendix DNUREG1021Revision9 (Appendix D Required Operator ActionsFormES-D-2OpTestNo.:NRCScenario#3Event#5 Page 16 of 46----Event

Description:

SmallRCSLeakinside containment(HotLegLoop2) Time II Position II Applicant'sActionsorBehavior NOTE: ContainmentpurgingandventingshouldNOTberesumeduntil Chemistry has evaluated off-sitedoseinalaterstep. ENSURE containmentpurgingandventing STOPPED:BOPa.CHECK containmentpurgingorventinginprogress. DETERMINE leakage source: ((Appendix D CREW RO a.CHECK leakage source UNKNOWN.D.ISOLATE I,etaown and charging: 1)CLOSE letdown orifice valves:*FCV-82-72*FCV-62-73*FCV-62-74 2)CLOSE letdown isolation valves:*FCV-62-69*FCV-62-70*FCV-62-77 3)CLOSE FCV-62-90 and-9'1, Charging header isolation valves.4)ENSURE FGV-62-B3, RHR Letdownlisolafj,on CLOSED.NUREG 1021 Revision 9 Appendix 0RequiredOperatorActionsFormES-D-2 Op TestNo.:NRC Scenario#3Event#5Page17 of 46----Event

Description:

SmallRCSLeakinside containment(HotLegLoop2) Time II Position II Applicant's Actions or Behavior RO c.CHECK pressunzer PORVs NORMAL*T aj,ipipe temperature

• Acousbe monitors d.CHECK pressunzer safety valves NORMAL RO*Tailpipe temperature
• Acoustic monitors e.CHECK PRT conditions NORMAL:*level RO (f.RO g.BOP*Pressure*Temperature NOTIFY Chemistry to ensure aU pnmary side sample valves CLOSED.[Hot Sample Room]CHECK CCS parameters NORMAL*CCS radiation monitors NORMAL*COS surge tank.level STABLE.h.CHECK excess letdown heat exchanger NORMAL (if applicable):BOP*Temperature
• Pressure Appendix 0 NUREG1021Revision9 (Appendix 0RequiredOperatorActionsFormES-D-2OpTestNo.:NRCScenario#

3Event#5 Page 18 of 46----EventDescription:SmallRCSLeakinside containment(HotLegLoop2) Time II Position II Applicant'sActionsorBehavior L CHECK TI-6B-398, Reador Vessel RO Head Vent Temperature NORMAL.[M-4]J.CHECK TI-68-21, reactor vessel RO flange leakoff temperature NORMAL[M-B]BOP MONITOR auxiliary building radiation and HElB recorders NORMAL CREW 12.CHECK leak IDENTIHED and ISOLATED.AfterCrewhasevaluated whetherleakis isolated, (Step 12 of AOP-R.OS)theleak canbeincreasedtorequireReactor TripandSafetyInjectionatLead Examiners discretion. Appendix 0 NUREG 1021 Revision 9 AppendixDRequiredOperatorActionsFormES-D-2 Op TestNo.:NRC Scenario#3 Event#6,7,8,&9 Page 19 of 46--Event

Description:

Large BreakLOCA,AutoFWIsolfailure, Cntmt SprayVlvsAutoopenfail,ATrainRHRsump suctionvlvfails closed.Time Position Applicant's Actions or Behavior ((Console Operator: When directed,initiateEvent Indications available:LargeBreak LOCA*RCS Pressure and Pressurizer level decreasing

• ContainmentPressureIncreasing Auto FeedwaterIsolationFailure(Manualisolationisavailable)*Main FeedwaterPumpsdonotautotripon 51*Main FeedwaterIsolationvalvesdonotautocloseon 51 Containment Spray dischargevalvesfailtoAutoOpen(Valveswillmanuallyopen)*SpraypumpsrunningduetoHiHi containmentpressure(2.81Psi)withnosprayflow indicated.*SpraypumprecirculationvalvesopenATrainRHRsumpsuctionvalveFCV-63-72failsclosed(Willnotmanuallyopen)*Valveremainsclosed(greenlightlit)whenautosump swapovercriteriaismetandwillnot manually open.DirectManualReactorTripandSafetyInjectionbasedononeSROofseveralmonitorstepsinAOP-R.05foreitherPressurizerlevel,ContainmentPressure,OrRCSPressure.ROManuallyTriptheReactorandInitiateSI.EnterandDirectperformanceof E-O,ReactorTripOrSafetySROInjection.AppendixDNUREG1021Revision9

((Appendix 0 Required Operator Actions Form ES-D-2 Op TestNo.:NRC Scenario#3Event#6,7,8,&9 Page 20 of 46 Event

Description:

Large Break LOCA,AutoFWIsolfailure, Cntmt SprayVlvsAutoopenfail,ATrain RHR sump suctionvlvfailsclosed. I Time II Position II Applicant's Actions or Behavior Evaluator Note: Immediately following performance of Immediate actions for Rx trip and 51, the Feedwater isolation failure may be identified and manually isolated.Also,aHiHi containment pressure condition may occur shortly after the trip and the containment Spray valve failures may be identified and corrected at this time.These actions may be performed as prudent actions prior to reaching the applicable procedure steps.ES-0.5, initiated at Step 5 ofO, procedurally address each of these failures and will be performed by the BOP operator.NOTE1: Steps 1 through 4 are immediate action steps.NOTE2: This procedurehasa foldout page.VERIFY reactor TRIPPEO;*Reader trip breakers OPEN..Reaetor trip bypass breakers DISCONNECTEO or OPEN RO*Rod bottom lights LIT..Rod position indicators less than or equal to 12 steps...NeutrOfl flux DROPPING Appendix 0 BOP BOP VERiFY turbine TRIPPED;*Turbi,,&stop valves CLOSED.VERIFY at feast one train of Shutdown boards ENE.RGIZED, NUREG1021Revision9 Appendix D Required Operator ActionsFormES-D-2 Op TestNo.:NRC Scenario#3 Event#6,7,8,&9Page21of 46 Event

Description:

LargeBreakLOCA,AutoFWIsolfailure,CntmtSprayVlvsAutoopenfail,ATrainRHRsumpsuction vlvfailsclosed. Time II Position II Applicant'sActionsor Behavior DETERMIN'EifSI actuated: RO..ECCS pumps RUNNING.*Any 81 alarm LIT[M..4D], ((Appendix D BOP RO RO PERFORM ES-C15}Equipment Verifications\t\IHl LE continuing in this procedure.(ES-0.5Atendof Scenario)DETERMINE if$8eOndary heat sink available: a.CHECK total AFW flOYI greater than 440 gpm...b.CHECK narrow range level greater than 10%[25%ADV]in afleast one S/G.c.CONTROL feed flow to maintain narrow range leV'fM between 10%[25%ADV]and 50%in intact or ruptured 51Ga.CHECK if main steam lines should be iso1Jated: a.CHECKFf any of the following conditions have occurred;*Any SlG pressure less than 600 p.sig, OR*Any SlG pressure dropping UNCONTRQU..ED.OR*Phase B actuation,NUREG1021Revision9 Appendix 0 Required Operator ActionsFormES-D-2OpTestNo.:NRC Scenario#3 Event#6,7,8,&9 Page 22 of 46 Event

Description:

LargeBreakLOCA,AutoFWIsolfailure,CntmtSprayVlvsAutoopenfail,ATrainRHRsumpsuctionvlvfailsclosed. Time II Position II Applicant's Actions or Behavior RO SRO b.ENSURE MSIVs and MSIV bypass valves CLOSED, c.ENSURE applicable Foldout Page actmJ'lS COMPLETED. Evaluator Note: Reps will probably be stopped prior to the next step due to Phase B actuation.(E-O Foldout page action)CHECK RCP trip criteria: a.CHECK the fOllowing: {Appendix 0 RO RO/BOP*ReS pressure Jess than 1250 psig AND Wi At least one: CCPOR St pump**RUNNING. b.STOP Reps.MONITOR Res temperatures:

• IF RCPs stopped, THEN CHECK T-eold stable at or trending to betINeM 547°F and 552 QF.(IfNoPerformRNO)NUREG1021Revision9 Appendix 0RequiredOperatorActionsFormES-D-2 Op Test No.: NRC Scenario#3 Event#6,7,8,&9 Page 23 of 46--Event

Description:

Large Break LOCA, AutoFWIsol failure, Cntmt Spray Vlvs Auto openfail,A Train RHR sump suction vlv fails closed.Time Appendix 0 Position RO/BOP RO RO/BOP Applicant's Actions or Behavior (RNO)IF temperature Jes$than 547°F and dropping, THEN PERFORM the following: a, ENSURE steam dumps and atmospheric reHefs CLOSED, D.IF oooidown continues, THEN CONTR.OL total feed flow USINGManual Control of AfW FIO\V.CHECK pressurizer PORVs, safeties, and spray valves: a.Pressurizer PORVs CLOSED.b, Pressurizer safety valves CLOSED, e, Normal spray valvas CLOSED.d.Power t.oat least one block valve AVAU.ASlE. e, At teast one block valve OPEN, DETERMINE. if gJG secondary pressure boundaries are INTACT:..CHECK all SlG pressures CONTROllED or RISING.*CHECK aU SiG pressures greater than 140 p$ig.NUREG1021Revision9 (Appendix D Required Operator ActionsFormES-D-2OpTestNo.:NRCScenario

1. 3 Event#6,7,8,&9Page24 of 46--Event

Description:

LargeBreakLOCA,AutoFWIsolfailure,CntmtSprayVlvsAutoopenfail,ATrainRHRsumpsuctionvlvfailsclosed. Time II Position II Applicant'sActionsorBehavior DETERMINE if S/G*Wbes'are INTACT: a.CHECK the following: II all SIG natfOW range levels CONTROLLED 0*1'DROPPING II sacondary radiation NORMAL RO/BOP USING Appendix A,Secondary Rad Monitors, (App, A is also contained\n E$..O",5).b.CHECK Appendix A COMPLETED.(RNO)b, 00 NOT CONTINUE this procedure UNTiL App, A has been completed or attempted. DETERMINE if ReS is INTACT: a.CHECK the folfowing;

• Containment pressure NORMAL..Containment sum p ievet NORMAL (Appendix D RO..LOVVER, CQMPT TEMP HIGH alarm DARK{M-5C,81](RNO)PERFORM the following:

1)MONITOR status trees.2)GO TO E-1!Loss of Reactor or Secondary CoolantNUREG1021Revision9 (Appendix D Required Operator Actions Form ES-D-2OpTestNo.:NRC Scenario#3 Event#6,7,8,&9 Page 25 of 46--Event

Description:

Large BreakLOCA,AutoFWIsolfailure,CntmtSprayVlvsAutoopenfail,ATrainRHRsumpsuctionvlvfailsclosed. Time II Position II Applicant's Actions or Behavior Ensure Status Trees are monitored (STA will perform if SRO availableatthistime)and TransitiontoE-1 Evaluator Note: Orange Paths may already be presentatthispointto perform FR-P.1 and/orFR-Z.1When verified,SROwillleaveE-1 after performing onlyafewsteps. SRO Enter and direct actionsofE-1 NOTE This procedure has a foldout page.CHECK Rep trip criteria: ((Appendix D RO a.CHECK the following:

• At least one CCP OR SI pump R.UNNING AND*R.CS pressure less than 1250 pStg.b.STOP RCPs.(Step Previously performed)

MONITOR if hydrogen i;gniters and recornbiners should be turned on: a.CHECK containment conditions NOT normal:*containment pressure high OR*containment sump level high.b.DISPATCH personnel tocpen Ice condenser AHU breakers USING EA-201-1, 480 V Board Room Breaker Alignments. NUREG 1021 Revision 9 Appendix D Required Operator Actions Form ES-D-2 Op TestNo.:NRC Scenario#3 Event#6,7,8,&9 Page 26 of 46--Event

Description:

LargeBreakLOCA,AutoFWIsolfailure,Cntmt SprayVlvsAutoopenfail,ATrainRHRsumpsuctionvlvfailsclosed. Time II Position II Applicant'sActionsor Behavior c.CHECK hydrogen concentration measurement AVAILABLE:

• Hydrogen analyzers have been in ANALYZE for at least 5 minutes.(RNO)PERFORM the following:

"1)DISPATCH operator to place hydrogen analyzers In service USING Appendix lD (also contained In ES-O.5}.2}WHEN hydrogen analyzers have been In ANALYZE for at least 5 minutes, THEN PERFORM substeps 2.d f Enter and Direct actions of FR-P.1, Pressurized thermal Shock if orange path present.SRO (If FR-P.1 not required at this point continue on next page with FR-Z.1)Appendix D RO BOP MONITOR RW8T level greater than 27%.MONITOR CST level grea.ter tha.n 5'%, NUREG 1021 Revision 9 Appendix DRequiredOperatorActionsFormES-D-2 Op Test No.: NRC Scenario#3Event#6,7,8,&9 Page 27 of 46--Event

Description:

LargeBreakLOCA,AutoFWIsolfailure,CntmtSprayVlvsAutoopenfail,ATrainRHRsumpsuctionvlvfailsclosed. Time II Position II Applicant's Actions or Behavior CHECK ReS pressure greater than 300 psig.(RNO)IF any of the folbwfng conditions exist:*(RO SRO RHR injection flow greater than 1000gpn1 OR..bothRHR pumps STOPPED AND sump raciro capability has been lost THEN RETUR.N TO procedure and step in effect.TransitiontoandDirectactionofFR-Z.1 Evaluator Note:AtsomepointduringtheperformanceofFR-Z.1,RHRAuto Containment Sump swapovercriteriamaybemet.Atthispoint,crewwillleaveFR-Z.1andenterES-1.3.ES-1.3willdirectResumeFRPimplementationtoreturntoandcompleteFR-Z.1.AllofFR-Z.1iscontainednextinthiseventguide.ES-1.3begins immediatelyfollowingFR-Z.1. NOTEIfthisprocedurehasbeenenteredforanorangepathandperformanceofECA-1.1(LossofRHRSumpRecirculation)isrequired,FR-Z.1maybeperformed concurrentlywithECA-1.1.AppendixD ROMONITORRWSTlevelgreaterthan27%.NUREG1021Revision9 ((Appendix DRequiredOperatorActionsFormES-D-2 Op TestNo.:NRCScenario

1. 3 Event#6,7,8,&9Page28of46 Event

Description:

LargeBreakLOCA,AutoFWIsolfailure,CntmtSprayVlvsAutoopenfail,ATrainRHRsumpsuctionvlvfailsclosed. I Time II Position II Applicant'sActionsor Behavior I VERIFYPhaseBvalvesCLOSED.

• Panel6KPHASEBGREEN RO*Panel6LPHASEBGREENENSURERCPsSTOPPED.

RO(RCPswillbeoffdue E-Ofoldoutpageactions) DETERMINEifthisprocedureshouldbeexited: a.CHECKforfaultedS/G: RO*AnyS/GpressureDROPPINGinanuncontrolledmannerOR

• AnyS/Gpressurelessthan140psig.

Appendix DNUREG1021Revision9 Appendix D Required Operator Actions Form ES-D-2 Op TestNo.:NRC Scenario#3 Event#6,7,8,&9 Page 29 of 46--Event

Description:

Large BreakLOCA,AutoFWIsol failure, Cntmt SprayVlvsAutoopenfail,ATrain RHR sump suction vlv fails closed.Time II Position II Applicant's Actions or Behavior I VERIFY containment spray operation: a.CHECK RHR sump redrculation capabi;!ity AVAILABLE b.VERIFY containment spray pumps RUNNiiNG.c.CHECK RWST level'greater than 27%.d.VERIFY containment spray suctio ALIGNED to RWST:*FC\I-72-22 OPEN*FC\I-72-21 OPEN_(Critical Task Appendix D RO e.VERIFY containment spray discharge valves OPEN:*FCY-12-39*FCY-12-2.(Evaluator Note: FCV-72-2 will not manually open)f.VERI:FY containment spray reese valves CLOSED:*FGV-72-34*FCY-12-13. g.VERIFY containment spray flow greater than 4150 gpmoneach train.CriticalTask"Priorto completing FR-Z.1" NUREG 1021 Revision 9 Appendix 0 Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario#3Event#6,7,8,&9 Page 30 of 46 Event

Description:

LargeBreakLOCA,AutoFWIsolfailure,Cntmt Spray VlvsAutoopenfail,ATrain RHR sumpsuctionvlvfailsclosed. Time II Position II Applicant's Actions or Behavior II MONITOR containment air return fans:*WHEN at least 10 minutes have ellapsed from Phase B, BOP THEN ENSURE containment aIr return fans (Evaluator Note: B Train AirreturnFanTripson overcurrentwhenitstarts) VERIFY containment ventilation dampers CLOSED: (RO*Panel 6K CNTMT VENT GREEN..Panel 6L CNTMT VENT GREEN..VERIFY Phase A vaJves CLOSED: RO*Panel'6K PHASE A GREEN..Panel 6L PHASE A GREEN.BOP VERIFY MSIVs and lMSIV bypass valves CLOSED.DETERMllNE if any SIGlntad: a.CHECK at least one SiG pressure: (Appendix 0 BOP*CONTROLLED or RIS1NG AND..Greater than 140 pslg.NUREG 1021 Revision 9 (Appendix D Required Operator Actions Form ES-D-2OpTestNo.:NRCScenario# 3Event#6,7,8,&9Page 31 of 46--Event

Description:

LargeBreakLOCA,AutoFWIsolfailure,CntmtSprayVlvsAutoopenfail,ATrainRHRsumpsuctionvlvfailsclosed. Time II Position II Applicant'sActionsor Behavior CAUTION Isolating al,1 SIGs will result in a loss of secondary heat sink.DETERMINE if any SiG Faulted: 6:-CHECK S/G pressures:

• Any S/G pressure DROPPING BOP In an uncontroll,ed manner OR*Any S/G pressure less than 140 pSig.MONITOR if hydrogen ,igniters and recombjners should'be turned on: a.DISPATCH personnel to open ice condenser AHU breakers USING EA-201-1 , 480 V Board Room Breaker Alignrnents.

BOP b.CHECK hydrogen concentration measurement A'VAllABLE:

• Hydrogen analyzers have been In ANALYZE for at least k minutes.;.).Appendix D NUREG 1021 Revision 9 Appendix D Required Operator Actions Form ES-D-2 Op TestNo.:NRC Scenario#3 Event#6,7,8,&9 Page 32 of 46--Event

Description:

LargeBreakLOCA,AutoFWIsolfailure,CntmtSprayVlvsAutoopenfail,ATrainRHRsumpsuctionvlvfailsclosed. Time II Position II Applicant's Actions or Behavior (RNOMaybe previously performed) b.PERfORM the following: 1)DISPATCH operator to place hydrogen analyzers in service USING Appendix D.(also BOP contained lin ES-R5)2)WHEN hydrogen analltzers have been m ANALYZE for at least 5 minutes, THEN PERFORM sebsteps 12.c through 12.e.(Appendix D RO RO SRO MONITOR if RHR spray should be placed In service: MONITOR if containment spray should be stopped: a.CHECK any containment spray pump RUNNING.b.CHECK containment pressure less than 2.0 pSig.c.CHECK containment spray suction aligned to RWST.d.RESeT Containment Spray.e.STOP containment spray pumps and PLACE In A-AUTO.f.CLOSE containment spray discharge valves:*FCV-12-39, Train A*FCV...72...2, Train B.RETURN TO procedure and step In effect NUREG 1021 Revision 9 Appendix 0 Required Operator Actions Form ES-D-2 Op TestNo.:NRC Scenario#3 Event#6,7,8,&9 Page 33 of 46 Event

Description:

Large Break LOCA,AutoFWIsolfailure, Cntmt SprayVlvsAutoopenfail,ATrain RHR sump suctionvlvfails closed.II Time Position Applicant's Actions or Behavior Evaluator Note: As previously discussed,ES-1.3maybeenteredpriorto completion of FR-Z.1 Enter and directactionsofES-1.3whenSump SwapoverSROcriteriaismet (RWSTLevellessthan27%). CAUTION Transfer to sump reci:n:ulati'on may cause high radiation in AUK Building.((Appendix 0 SRO RO SUSPEND FRP implementation. MONITOR RHR automatic switdlOver: a.CHECK containment sump level greater than 1, 1b.CHECK containment sump valves FCV-63-72 and FCV-'o3-73 OPEN.(RNO FCV-63-72Failedtoopen) IF any sump valve IS CLOSED, THEN A lTEMPT to open affected sump valve from fvlCR (Valvewillnotopen) c.CHECK RHR suction valves FCV-74-3 and FC\f-74-21 CLOSING.(RNO FCV-74-3willnotbeclosingsince FCV-63-72willnot open, howevervalveshouldnotbeclosedbasedonRNO) IF sump valve 00 affected train is cpeninq, THEN A lTEMPT to dose RHR sudion valve from MeRNUREG1021 Revision 9 (Appendix 0 Required Operator ActionsFormES-D-2OpTestNo.: NRC Scenario#3Event#6,7,8,&9 Page 34 of 46--Event

Description:

Large BreakLOCA,AutoFWIsolfailure, CntmtSprayVlvsAutoopenfail,ATrainRHRsumpsuctionvlvfails closed.I Time II Position II Applicant's Actions or Behavior (Appendix 0 RO DETERMINE if contaimnent spray should be stopped: a.CHECK any containment spray pump RUNNING.b.CHECK containment pressure greater than or equal to 201)pSlg.(RNOiflessthan2.0psig) STOP containment spray pumps as follows: 1)RES:ET containment spray signal.2)STOP containment spray pumps and PLACE m A-AUTO.3)CLOSE cntmt spray discharge valves FCV-72-39 and FGV-72-2.GO TO Step 4.(IfRNONotrequired,i.e.greaterthan2.0psi) c.CHECK BOTH cntmt spray pumps RUNNING.d.STOP one cntrm spray pump and PLACE In PUll-TO-LOCK.

• .MONITOR one cntmt spray pump RUNNING and delivering flow.NUREG1021Revision9 Appendix D Required Operator Actions Form ES-D-2 Op TestNo.:NRC Scenario#3 Event#6,7,8,&9 Page 35 of 46 Event

Description:

Large Break LOCA,AutoFWIsolfailure,Cntmt SprayVlvsAutoopenfail,ATrain RHR sump suctionvlvfails closed.Time II Position II Applicant's Actions or Behavior MONITOR RWST supplytoECGS pumps:*R\t'VST t Vt LO-LO alarm DARK (r...1-6E, E4].(RO RO NOTE*RWST level greater than 8%.(RNOifRequiredatsomepoint) WHEN RWST level is less than or equal to H%, THEN PULL TO LOCK any pumps taking suction from RWST: a.Containment spray pumps.b.SI pumps.c.CCPs.MONITOR RHR pumps RUNNING.Step 6 should be handed off to a Unit Operator.(Appendix D 6.PE:RfORM the foH:owing: a, DiSPATCH personnel to restore power to USING EA-201-1, 480 V Board Room Breaker Alignments. BOP b.OPENRHR heat exchanger outlet valves FCY-I0-156 and FCV-70-t53. c.VERIfY cos flow FI-70-159A and FI-I0-165A greater than 5050 gpm.d.MONITOR ecs temperature and surge tank level.NUREG1021Revision9 Applicant'sActionsor Behavior Position Appendix D Required Operator ActionsFormES-D-2OpTestNo.:NRCScenario

1. 3 Event#6,7,8,&9Page36of46 Event

Description:

LargeBreakLOCA,AutoFWIsolfailure,CntmtSprayVlvsAutoopenfail,ATrainRHRsumpsuctionvlvfailsclosed. ..VERIFY RHR automatic switchover: RO a.VERIFY containment sump valves FCV-63-72 and FCV-63-73 OPEN.(RNO)IF any containment sump valive(s)CANNOT be opened, THEN PULL TO LOCK RHR pump on affected train(s).(ATrainRHRPumpshouldbestopped)(RNOcontinuednextpage) (IF Train A containment sump valve FCV-63-72 CANNOT be opened, THEN PERFORM the following: RO 1)CLOSE FCV-74-3 Train A RHR suction valve to satisfy interlock. 2)WHEN FCV-14-3!S CLOSED, THEN A TIEMPT to OPEN FCV-63-12.(ContinueAERforstep 6)b.ENSURE RWST to RHR sudion valves FCV-14-3 and FCV-74-21 CLOSED.CAunON 51 pum,p operation with miniflow j'solatedand ReS pressu.re above shutoff head wHI result in 51 pump damage.NOTE The following continuous acton applies even after this procedure IS exited.(RO MONITOR RCS pressure less than 1-500 PSJ9*Appendix DNUREG1021Revision9 Appendix 0 Required Operator Actions Form ES-D-2 Op TestNo.:NRC Scenario#3 Event#6,7,8,&9 Page 37 of 46 Event

Description:

Large Break LOCA,AutoFWIsol failure, Cntmt SprayVlvsAutoopenfail,ATrain RHR sump suctionvlvfails closed.Time II Position II Applicant's Actions or Behavior I CLOSE SI pump miniflow to R\"'JST valves: RO (Step 9)RO (Step 10)*FCV-63-3*FCV-63-4*FCV-63-175 CLOSE RI-IR crosstie valves:*FCV-14-33*FGV-14-35..OPEN CCP and SI pump suction valves fromRHR: (RO (Step 11)- -FC\!-63-6. RO (Step 12)Critical Task SRO/RO Appendix 0 AUGN RHR discharge to CCP and SI pump suction: 3.OPEN RHR discharge to CCP suction FCV-63-8.(RNO since FCV-63-8willnotopendueto interlockwith 63-72 Sump valve thatwillnot open)ENSURE operation of Train E RHR:*Train B RHR pump RUNNING*FCV-63-11 OPEN.D.OPEN RHR discharge to SI pump suction FCV-63-11 VERIfY Steps 9 through 12 COMPLETED. CriticalTask"Priorto degradedCoreCoolino conditions" NUREG 1021 Revision 9 Appendix D Required Operator ActionsFormES-D-2 Op TestNo.:NRC Scenario#3 Event#6,7,8,&9 Page 38 of 46--Event

Description:

Large Break LOCA,AutoFWIsolfailure, Cntmt SprayVlvsAutoopenfail,ATrainRHRsump suctionvlvfails closed.1 Time II Position I Applicant's Actions or Behavior Evaluator Note: ECCS Alignment to containmentsumpis completeatthispoint.Lead Examiner may evaluate terminatingscenarioif critical taskshavebeen addressed and sufficient actions from contingency procedureFR-Z.1havealsobeencompleted. CHECK EGCS pump status: 3.MONITOR BOTH RHR pumps RUNNING.(RNOsinceonlyBRHRPumpisrunning) PERFORM the following: (RO 1)ENSURE the foltowing:

• one CGPRUNNING (same train as running RHR pump preferred)
• other CCP In PUll TO LOCK(RNO2)isN/A) 3)IFRCS press IS less than 150G pSl9, THEN ENSURE the following:
• one 51 pump RUNNING (same train as running RHR pump preferred)
• other SI pump ln PUll TO lOCK CAUTION Appendix D Momentary loss of shutdown power whUe aligned for sump reckculation could result in CCP damage since the bl,ackout sequencer will start the CCPs but will NOT start the RHR pumps.NUREG1021Revision9 Appendix D Required Operator Actions Form ES-D-2OpTestNo.:NRCScenario#3Event#

6,7,8,&9Page39of46 Event

Description:

LargeBreakLOCA,AutoFWIsolfailure,CntmtSprayVlvsAutoopenfail,ATrainRHRsumpsuctionvlvfailsclosed. Time II Position II Applicant'sActionsor Behavior ((Appendix D BOP RO BOP RO RO MONITOR shutdown boards continuously energized. RESETsignal.ALIGN ElRCW System USING EA-67-'1, ERC\N Operation. ISOLATE CCP suction from RWST: a.CLOSE RWST suction valves LCV-62-135 and LC"l-62-136 WHILE monitoring CCPIT flow.b.PLACE RWST suction valve bandswitches In A-AUTO (pushed in):*HS-62-135*HS-52-i3S c.ENSURE at least one VCT outlet valve CLOSED:*LCV-62-132 OR*LCV-62-133. ISOLATE RHR suction from RWST: a.CHECK power RESTORED to FCV-63-1 b.CLOSE FCV-53-1 WHILE monitori:ng

RHR flow.ISOLATE SI pump suction from RWST:*CLOSE FCV-133-5 WI-ULE monitoring SI pump flow.NUREG1021Revision9 (Appendix 0 Required Operator Actions Form ES-D-2OpTestNo.:

NRC Scenario#3 Event#6,7,8,&9Page 40 of 46--Event

Description:

LargeBreakLOCA,AutoFWIsolfailure,CntmtSprayVlvsAutoopenfail,ATrainRHRsumpsuctionvlvfailsclosed. Time II Position II Aoolicant'sActionsor Behavior ALIGN containment spray suction to containment sump: a, CHECK any of the following conditions met*RWST level less than orequal to 8%OR (Appendix 0 RO*containment sump level greater than or equal to 56%.0_ENSURE containment spray pumps in PUlL-TO-lOCK c.CHECK FCV-63-72 Train A containment sump valve OPEN.(RNO FCV-63-72 failed closed)GO TO Suostep 21 J.(Step Continuednextpage)L CHECK FC\L63-73 Train B containment sump valve OPEN.J.CLOSE FCV-72-21, Train B cntmt spray suction from RWST Ie OPEN FCV-72-20 Train B cntmt spray suction from containment sump.L CHECK containment pressure greater than 2.0 pstg.(RNOif pressurelessthan2.0psi)(Step Continuednextpaqe)NUREG1021Revision9 (Appendix D Required Operator Actions Form ES-D-2 Op TestNo.:NRC Scenario#3 Event#6,7,8,&9 Page 41 of 46 Event

Description:

Large BreakLOCA,AutoFWIsolfailure, Cntmt SprayVlvsAutoopenfail,ATrain RHR sumpsuctionvlvfails closed.I Time II Position II Applicant's Actions or Behavior PERfORM the followtng: 1)RESET Train B Containment Spray signal.2)WHEN containment sump ievel IS greater than-1 B'%[22%ADY], THEN PLACE Train B containment spray pump In A-AUTO.3)ENSURE FCV-72-2 Train B cntmt spray iso!valve CLOSED.(Continue step if pressure greaterthan2.0psi) rn.CHECK containment sump level greater than 1 [22%ADY].(Continue step next page)fl.ESTABLISH Train B Cntmt Spray: 1)CHECK Train B containment spray pump suction aligned to containment sump.(Appendix D RO 2)START Cntmt spray pump B-EL 3)ENSURE FCV'-72-2 Train B Cntmt Spray isol valve OPEN.o.ENSURE reorc valves CLOSED for running Containment Spray pump(s}:*FCV-72-34 Train A*FGV-72-13 Train B.p.CHECK containment spray flow greater than 4750 gpm on each train In service.NUREG 1021 Revision 9 (Appendix DRequiredOperatorActionsFormES-D-2OpTestNo.:NRC Scenario#3 Event#6,7,8,&9Page42of46 --Event

Description:

LargeBreakLOCA,AutoFWIsolfailure,CntmtSprayVlvsAutoopenfail,ATrainRHRsumpsuctionvlvfailsclosed. I Time II Position II Applicant'sActionsor Behavior I MONITOR if RHR spray should be placed in service: RESUME FRP implementation. Evaluator Note:CrewmayreturntoFR-Z.1atthispointifnotcompletedearlier. Scenariomaybe terminatedatlead examiner discretion when critical taskshavebeen addressed and sufficientactionsinFR-Z.1andES-1.3havebeencompleted. Appendix D NUREG1021Revision9 ((Appendix D Required Operator ActionsFormES-D-2OpTestNo.: NRCScenario#3Event#ES-O.5Page 43 of 46--Event

Description:

Equipment Verifications Time II Position II Applicant'sActionsor Behavior ES-O.5 Actions CHECKERCWsystemoperation: BOP*VERIFYatleastfourERCWpumpsRUNNING.

• VERIFY DIGERCWsupplyvalvesOPEN.

I VERIFYCCSpumpsRUNNING:

• Pump1A-A(2A-A)

BOP*Pump1B-B(2B-B)

• PumpC-S.VERIFYEGTSfansRUNNING.

BOP VERIFY generatorbreakersOPEN. BOP VERIFYAFWpumpsRUNNING: BOP*MDAFWpumps

• TDAFWpump.

, Appendix DNUREG1021Revision9 ((Appendix 0RequiredOperatorActionsFormES-D-2OpTestNo.:NRC Scenario#3 Event#ES-O.5Page 44 of 46----Event

Description:

Equipment Verifications Time II Position[Applicant'sActionsor Behavior I NOTEAFWlevelcontrolvalvesshouldNOTberepositionedifmanualactionhasbeentakentocontrolS/Glevels,toestablishflowduetofailure,ortoisolateafaultedS/G. CHECKAFWvalvealignment: a.VERIFYMDAFWLCVsinAUTO. BOP b.VERIFYTOAFWLCVsOPEN. c.VERIFYMDAFWpumprecirculationvalvesFCV-3-400andFCV-3-401CLOSED. VERIFYMFWIsolation:

• MFWpumpsTRIPPED
• MFWregulatingvalvesCLOSED
• MFWregulatingbypassvalve controlleroutputsZERO BOP*MFWisolationvalvesCLOSED
• MFWflowZERO.(Evaluator Note:Ifnot previouslycompletedAuto FeedwaterIsolationFailureshouldbeaddressedatthispoint.)

MONITORECCSoperation: VERIFYECCSpumpsRUNNING: BOP*CCPs*RHRpumps*SIpumps Appendix 0NUREG1021Revision9 ((Appendix 0 Required Operator ActionsFormES-D-2 Op Test No.: NRC Scenario#3 Event#ES-O.5 Page45of46--Event

Description:

Equipment Verifications Time II Position II Applicant's Actions or Behavior VERIFYCCPflowthroughCCPIT.

• CHECKRCSpressurelessthan1500psig.

BOP*VERIFYSIpumpflow.

• CHECKRCSpressurelessthan300psig.
• VERIFYRHRpumpflow.

VERIFYESFsystemsALIGNED:

• PhaseA ACTUATED: 0 CONTAINMENT ISOLATIONPHASEATRAINAalarmLIT[M-6C,B5].

0 CONTAINMENT ISOLATIONPHASEATRAINBalarmLIT[M-6C,B6].

• ContainmentVentilationIsolation ACTUATED: 0 CONTAINMENT VENTILATION ISOLATIONTRAINAalarmLIT[M-6C,C5].

0 CONTAINMENT VENTILATION ISOLATIONTRAINBalarmLIT[M-6C,C6]. BOP*Status monitor panels: 06CDARK 0 60 DARK 06ELITOUTSIDEoutlinedarea 06HDARK 06JLIT.*TrainAstatuspanel6K: 0CNTMTVENTGREEN 0PHASEAGREEN

• TrainBstatuspanel6L:

0 CNTMTVENTGREEN 0PHASEAGREEN Appendix 0NUREG1021Revision9 (Appendix 0 Required Operator ActionsFormES-D-2OpTestNo.:NRCScenario

1. 3 Event#ES-O.5Page 46 of 46----Event

Description:

Equipment Verifications Time II Position II Applicant'sActionsor Behavior MONITOR containmentsprayNOTrequired:

• PhaseBNOT ACTUATED AND*Containmentpressurelessthan2.81psig BOP*Ensure ContainmentSprayisactuated (Evaluator Note:Ifnot previously addressed Containment Spray dischargevalveautoopenfailuresshouldbe addressedatthispoint,onlyATrainvalvecanbe manually opened)VERIFYpocketsumppumpsSTOPPED:[M-15, upper left corner]*HS-77-410,RxBldgAuxFloorand Equipment Drain BOPSumppumpA*HS-77-411,RxBldgAuxFloorand Equipment DrainSumppumpB.

DISPATCH personneltoperformEA-0-1, Equipment Checks BOPFollowingESF Actuation. Appendix 0NUREG1021Revision9 /{SHIFT TURNOVER CHECKLISTPage1of3 Today ((0 SM 0 US/MCR Unit 1 0 UO Unit 1Off-going-Name 0 AUO Station SQN 0STA(STAFunction)AUOCampActionsOn-coming-NamePart1-Completed by Off-gOing Shift/Reviewed by On-coming Shift: Abnormal Eauipment Lineun/Conditions:

pjJiJU/JJ TrainA Week

• All Equipment normal*All equipment normalTotal0.03gpm I Identified 0.02gpm IUnidentified0.01gpm.(Today0600)

SHIFT TURNOVER CHECKLISTPage2of3 Today (31/Test in Progress/Planned: (IncludingNeedforNewBrief) 0-SI-SXX-068-127.0inprogress. Major Activities/Procedures in Progress/Planned:PlantStartupinprogress.Currentlyin0-GO-4Section5.2,Step3at -2%power.Continueplantstartupper Rx Engineering Spreadsheet. SpreadsheethasbeenverifiedbytheSRO/STA.0-SO-62-7AppendixDandEhavebeen completed. Pre-conditionedPowerlevelis100%.Turbinerollinparallelwithpowerincreaseisnotdesired. Radiological ChangesinPlantDuringShift:ReactorpowerincreasewillincreasedoseratesinsidecontainmentandvariouslocationsintheAux.Bldg.See applicableRadConRWPsfordetailsandentryrequirements. Part2-Performed by on-coming shift DReviewofOperatingLogSinceLastShiftHeldor3Days, WhicheverisLess(N/Afor AUO's)DReviewofRounds Sheets/Abnormal Readings (AUO's only)ReviewtheFollowing ProgramsforChangesSinceLastShift Turnover: D Standing Orders DLCO(s)inActions(N/AforAUOs) D ImmediateRequiredReading DTACF(N/AforAUO's) Part 3-Performed by both off-going and on-coming shift D WalkdownofMCRControlBoards(N/Afor AUO's)Relief Time: Relief Date: today TVA40741[03-2001]OPDP-1-1[03-14-2001 SHIFT TURNOVER CHECKLISTPage3of3 Today (PANEL WINDOW Disabled Annunciators ANNUNCIATOR Equipment Off-Normal (Pink Tags)WO I PER Number ((UNID And Noun Name 10 And Noun Name Panel Panel Problem Description MCRWO List Problem Description WO I PER Number WOlPER Number UNITONE REACTIVITY BRIEF Date: TodayTime:NowRCSBoron:1703ppm Today I BA ControllerSetpoint:47.5%* IRCSB-10Depletion:2ppm OperableBAT:A IBATABoron:6850ppm IBATCBoron:6850ppm IRWSTBoron:2601ppm Nominal Gallonsperrodstepfrom219: N/Agallonsofacid,N/A gallons of water*Verifyboricacidflowcontroller ISsetatAdjustedSAController Settinglaw0-SO-62-7section5.1 Gallonsofacid:N/AGallonsofwater:N/ARodSteps:4 (Power reduction amount Estimated Final Rod Position Estimated boron addition 10%N/AStepsonbank 0 N/A gallons 30%N/AStepsonbank 0 N/A gallons 50%N/AStepsonbank 0N/Agallons

• • Thesevaluesare approximationsandnotintendednorexpectedtobeexact.Thevaluesmaybesupercededby Rx EngineeringorSO-62-7calculatedvalues.Thesevaluesarecalculatedassuming100%steadystatepoweroperationonly.

Engineeringdatalastupdated one weekago.DataValiduntil one week from now.Number of dilutions:

• • • Numberofborations:

aRodstepsin: a Gallonsperdilution: aGallonsperboration: aRodstepsout: a Total amount diluted: a Total amount borated: aNetchange: a IN/Out Number of dilutions:

• • • Numberofborations:

aRodstepsin: a Gallons per dilution: a Gallonsperboration: aRodstepsout: a Total expecteddilution:*** Total expected boration: aNetchange: a In/Out Remarks: Rx Power--2%MWO/MTU-1000Xenon &Samarium at Equilibrium

• • • As Required by Reactor Engineering startup spreadsheet.

NextUnit1FluxMapis scheduled-Unit Supervisor: Name/Date N/A 2.18-2.48 2.33 Operations Chemistry Information (Sample PointUnitsBoronDate/Time Goal LimitU1RCS ppm 1703 Today/Now Variable VariableU2RCS ppm 816Today/NowVariable Variable U1 RWST ppm 2601Today/Now2550-26502500-2700 U2 RWST ppm 2569 Today/Now2550-26502500-2700BATA ppm 6850 Today/Now Variable VariableBATB ppm 6850Today/NowVariable Variable BATC ppm 6850 Today/NowVariable VariableU1CLA#1 ppm 2556Today/Now 2470-2630 2400-2700U1CLA#2 ppm 2575Today/Now 2470-2630 2400-2700U1CLA#3 ppm 2591Today/Now 2470-2630 2400-2700U1CLA#4 ppm 2589 Today/Now 2470-2630 2400-2700U2CLA#1 ppm 2531Today/Now 2470-2630 2400-2700 U2 CLA#2 ppm 2650 Today/Now 2470-2630 2400-2700 U2 CLA#3 ppm 2522Today/Now 2470-2630 2400-2700U2CLA#4 ppm 2526 Today/Now 2470-2630 2400-2700 (SpentFuelPool ppm 2547 Today/Now Indicator Units U1Date/TimeU2 Date/TimeSI50S/G Leakage?Yes/NoNo Today/NowNo Today/NowSI137.5CVE Leakrate gpd<0.1Today/Now <0.1 Today/Now5gpdleak equivalentcpm380 Today/Now 68 Today/Now30gpdleak equivalent cpm 1980Today/Now 83 Today/Now50gpdleak equivalentcpm3250 Today/Now 206 Today/Now75gpdleak equivalentcpm4850 Today/Now 455 Today/Now150gpdleak equivalentcpm9750 Today/Now 870 Today/NowCVEAir Inleakage cfm 10 Today/Now 12.5 Today/NowBkgdon99/119cfm50 Today/Now 40 Today/Now ( ,,--,'-'-., Unit 1 DELTA REACTOR POWER ASSUMED INSERTEDEXPECTEDDELTA RHO BORON DELTA RECOMMEND RECOMMEND IODINE TIME POWER DEFECT ROD HT WORTH XENON BORON CONC PPM DILUTION BORATION CONC (hrs)(%)(pcm)(steps)(pcm)(pcm)(pcm)(ppm)(ppm)(gal)(gal)(%eq)0.0 2.0 35.6 173.0-327.8-118.3 1702.9.9 1.0 14.0 240.3 195.0-163.7-125.9 48.1 1695.3-7.6 290 0 2.5 2.0 26.0 427.1 200.0-125.1-143.6 166.0 1669.1-26.2 1018 0 4.2 3.0 38.0 605.0 205.0-89.7-176.3 175.1 1641.5-27.6 1091 0 7.0 4.0 50.0 779.2 210.0-58.3-226.7 193.2 1611.0-30.5 1226 0 10.6 5.0 62.0 954.0 216.0-27.9-295.5 213.1 1577.4-33.6 1378 0 15.1 6.0 74.0 1133.0 216.0-26.9-381.4 264.0 1535.9-41.6 1747 0 20.3 7.0 86.0 1320.8 216.0-25.9-482.0 287.3 1490.7-45.2 1951 0 26.2 8.0 98.0 1519.1 216.0-24.7-593.9 309.1 1442.1-48.6 2170 0 32.7 9.0 100.0 1570.9 216.0-24.5-716.0 173.7 1414.9-27.3 1241 0 39.2 10.0 100.0 1582.9 216.0-24.5-845.9 141.9 1392.6-22.3 1029 0 45.2 11.0 100.0 1592.7 216.0-24.5-979.0 143.0 1370.2-22.4 1054 0 50.6 12.0 100.0 1603.0 216.0-24.5-1111.2 142.4 1347.9-22.3 1067 0 55.4 13.0 100.0 1613.2 216.0-24.5-1239.7 138.7 1326.2-21.7 1056 0 59.8 14.0 100.0 1623.1 216.0-24.5-1362.8 132.9 1305.3-20.8 1026 0 63.8 15.0 100.0 1632.6 216.0-24.5-1479.2 125.9 1285.6-19.7 987 0 67.3 16.0 100.0 1641.6 216.0-24.5-1588.3 118.2 1267.2-18.5 940 0 70.5 17.0 100.0 1650.1 216.0-24.5-1689.9 110.1 1250.0-17.2 888 0 73.4 18.0 100.0 1657.9 216.0-24.5-1784.0 102.0 1234.0-15.9 832 0 76.0 19.0 100.0 1665.2 216.0-24.5-1870.7 94.0 1219.4-14.7 776 0 78.4 20.0 100.0 1672.0 216.0-24.5-1950.3 86.3 1205.9-13.5 720 0 80.5 21.0 100.0 1678.2 216.0-24.5-2023.2 79.1 1193.5-12.3 666 0 82.4 22.0 100.0 1683.9 216.0-24.5-2089.7 72.3 1182.3-11.3 615 0 84.2 23.0 100.0 1689.3 216.0-24.5-2150.4 66.1 1171.9-10.3 566 0 85.7 24.0 100.0 1694.3 216.0-24.5-2205.6 60.1 1162.6-9.4 520 0 87.1 25.0 100.0 1698.7 216.0-24.5-2255.7 54.6 1154.1-8.5 475 0 88.4 26.0 100.0 1702.8 216.0-24.5-2301.2 49.6 1146.3-7.7 434 0 89.5 27.0 100.0 1706.5 216.0-24.5-2342.5 44.9 1139.3-7.0 396 0 90.6 28.0 100.0 1709.9 216.0-24.5-2379.8 40.7 1133.0-6.3 361 0 91.5 29.0 100.0 1712.9 216.0-24.5-2413.6 36.8 1127.2-5.7 328 0 92.3 30.0 100.0 1715.6 216.0-24.5-2444.2 33.3 1122.0-5.2 298 0 93.1 31.0 100.0 1718.1 216.0-24.5-2471.9 30.1 1117.4-4.7 271 0 93.8 32.0 100.0 1720.4 216.0-24.5-2496.9 27.2 1113.1-4.2 246 0 94.4 33.0 100.0 1722.4 216.0-24.5-2519.5 24.6 1109.3-3.8 223 0 94.9 ,-<P'-""" Unit 1 34.0 100.0 1724.2 216.0-24.5-2539.9 22.2 1105.8-3.5 202 0 95.4 35.0 100.0 1725.9 216.0-24.5-2558.3 20.1 1102.7-3.1 183 0 95.9 36.0 100.0 1727.4 216.0-24.5-2574.9 18.1 1099.9-2.8 165 0 96.3 37.0 100.0 1728.7 216.0-24.5-2589.9 16.4 1097.3-2.5 149 0 96.6 38.0 100.0 1730.0 216.0-24.5-2603.4 14.8 1095.0-2.3 135 0 97.0 39.0 100.0 1731.0 216.0-24.5-2615.7 13.3 1093.0-2.1 122 0 97.3 40.0 100.0 1732.0 216.0-24.5-2626.7 12.0 1091.1-1.9 110 0 97.5 41.0 100.0 1732.9 216.0-24.5-2636.6 10.8 1089.4-1.7 100 0 97.8 42.0 100.0 1733.7 216.0-24.5-2645.6 9.8 1087.9-1.5 90 0 98.0 43.0 100.0 1734.5 216.0-24.5-2653.7 8.8 1086.5-1.4 81 0 98.2 44.0 100.0 1735.1 216.0-24.5-2661.0 8.0 1085.3-1.2 74 0 98.4 45.0 100.0 1735.7 216.0-24.5-2667.6 7.2 1084.1-1.1 66 0 98.5 46.0 100.0 1736.3 216.0-24.5-2673.5 6.5 1083.1-1.0 60 0 98.7 47.0 100.0 1736.7 216.0-24.5-2678.9 5.8 1082.2-0.9 54 0 98.8 48.0 100.0 1737.2 216.0-24.5-2683.7 5.3 1081.4-0.8 49 0 98.9 49.0 100.0 1737.6 216.0-24.5-2688.1 4.7 1080.7-0.7 44 0 99.0 50.0 100.0 1737.9 216.0-24.5-2692.0 4.3 1080.0-0.7 40 0 99.1 51.0 100.0 1738.2 216.0-24.5-2695.5 3.9 1079.4-0.6 36 0 99.2 52.0 100.0 1738.5 216.0-24.5-2698.7 3.5 1078.9-0.5 32 0 99.3 53.0 100.0 1738.8 216.0-24.5-2701.6 3.1 1078.4-0.5 29 0 99.4 54.0 100.0 1739.0 216.0-24.5-2704.2 2.8 1077.9-0.4 26 0 99.4 55.0 100.0 1739.2 216.0-24.5-2706.5 2.6 1077.5-0.4 24 0 99.5 56.0 100.0 1739.4 216.0-24.5-2708.6 2.3 1077.2-0.4 21 0 99.5 57.0 100.0 1739.6 216.0-24.5-2710.5 2.1 1076.9-0.3 19 0 99.6 58.0 100.0 1739.7 216.0-24.5-2712.3 1.9 1076.6-0.3 17 0 99.6 59.0 100.0 1739.9 216.0-24.5-2713.8 1.7 1076.3-0.3 16 0 99.7 60.0 100.0 1740.0 216.0-24.5-2715.2 1.5 1076.1-0.2 14 0 99.7 Total 29846 0 Hold Tavg=Tref+/-1.SF Small hourly boration/dilution 6820 BAT ppm volumes may be accumulated for larger single additions Reason for Power Increase Plant Startup DateRxENGName Beeper 70808 Comments SQN 0-SO-62-7 1,2 BORON CONCENTRATION CONTROLRev.46Page161of199 APPENDIX DPage1of1 CALCULATION FOR AMOUNTOFBORICACIDOR PRIMARY WATER (TI-44)NOTE 1 NOTE 2 One calculationisrequiredforeach major change.BoricacidamountstoachieverequiredRCSboronconcentrationmaybesignificantlyhigherthancalculatedamountsifCVCSdeminresinsareremovingboron.AmountofboronremovalbymixedbedresinswilldependonRCSboron,resinage, whetherdeminbedwaspreviouslyborated,andletdowntemperature.Chemistryshouldbeconsultedifrequiredtoevaluateresinbedremoval.[1]IFREACTFnotused, THEN CALCULATE amountofprimary waterorboricacidrequiredusingTI-44. (RCS BORON/703 ppm Current Ib 67 PPM CHANGE-3G AMOUNT PRIMARY WATERORBORICACID 1357 b/htle TOTAL GAL(s)NOTEREACTFdatasheetsaretobesignedbythepreparerandreviewer. NOTE[2]IFREACTFusedattachprintoutto procedure.IVisnotrequiredif appendix is performedbyanSROtoverifydataprovidedbyRx.Eng. [3]ENSURE independentlyverifiedbyanSROin accordance with Appendix I.ENDOF TEXT I//A--lnitiats ({NRC08c Dilute.txt 0[REACTF-VERS SQ2.1J BORATION/DILUTION CALCULATION SEQUOYAH UNIT 1 CYCLE 15 RCS AVG TEMP 547.0 DEG F RCS PRESSURE 2235.0 PSIG PZR LEVEL 24.7%MAKEUP WTR CONC.0 PPM BORIC ACID CONC 6850.0 PPM INITIAL CONC FINAL BORIC ACID MAKEUP WTR BORON CONC CHANGE BORON CONC ADDITION ADDITION (PPM)(PPM)(PPM)(GAL)(GAL)----------

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1703.0-36.0 1667.0.0 1357.7 0 page 1 NOTE2NOTE1 SQN BORON CONCENTRATION CONTROL 0-SO-62-7 1,2Rev.46Page162of199APPENDIXEPage1of18 REACTIVITY BALANCE CALCULATIONOnecalculationisrequiredforeachmajor change.CalculationisanapproximationofrequiredBoronchange.Eyeballinterpolationofgraphsisexpected.DilutionorBorationvalueforpowerchangefrom P1%to P 2%powerintimeperiodTwithrodsmovingfromsteppositionR 1toR 2.(Subscriptconvention:1 =currentpoint,2 =targetpoint) [1]ENTER the following data: DATA REQUIRED DATA WhereToGet CurrentRCSBoron J 703 ppmChemLabor Estimate using Appendix 0 Core Burnup IOOCJ MWO/MTUICSU0981 Current Reactor power 2%NISorICS Final Reactor power Zb%Asrequiredfor plant conditions Total Reactor Power change zLJCurrentandfinal Reactor power Rate of Reactor power change/Z%/hrAsrequiredfor plant conditions Number of hours to change power 2 hr(s)Asrequiredfor plant conditions /73ICSorMCRBoard Current Rod Position steps 200 Estimate numberofrodstepsrequiredtoFinalRod Position steps controlandrod withdrawal requirementsforpower change. SQN BORON CONCENTRATION CONTROL 0-80-62-7 1,2 Rev.46 Page 163 of 199 APPENDIX E Page 2 of 18 CAUTION Follow sign conventions explicitly.(See Example Power Increase and Power decrease.) [2]CALCULATE change in boron concentration by performing the following: Parameter Where To Get Calculation Value Attached Power Defect Curves: go t.;./[]-pcm (negative[a]flp POWER DEFECTUnit1: Figure1,2,or3 pcm PD 1-pcm PD 2=forpower (current)8.pPOWERDEFECT increase)Unit2:Figure 8,9,or10.Xenon-,FromICS*or REACTF(eithercurrent NOTE: Xenon reactivitymustbe negative (negativeconditionsorprojectiontoinitialcondition).forrisein[b]flp XENON Xenon.,FromICS*or REACTF-IC/D pcm XE 2-(-I!B)pcm XE 1=-22..-pcm Xenon(projectionovertimeperiodT). conc)*(ICSXenonvaluesmustaddnegativesign).(current)8.p XENON[C]flp RODS Attached Rod Worth Curves: ,...1 DO pcm Rods 2-(-Z(;U)pcm Rods 1=/60 (negativeUnit1:Figure4,5,or 6 pcmforrodUnit2:Figure11,12,or13.(current)8.p RODS insertion) [d]flp POWER DEFECT+XENON+RODS (CHANGE IN REACTIVYDUETO POWER DEFECT, XENON,ANDRODS)-227 pcm[a]pcm 8.p POWER DEFECT+[b]pcm XENON+[c]pcm RODS=[e]flp BORON (CHANGE IN BORON REACTIVITY) 2 2 7 pcm ([d]pcm flpPOWERDEFECT +XENON+RODS)X (-1)=8.p BORON[f]Apprn BORON (CHANGE IN BORON CONCENTRATION)(negativefordilution, ([e]pcm 8.p BORON)-:-(-biZ 7 pcm/ppm Boron Worth)= ppmpositiveforfromFig.7(U-1)orFig.14(U-2) boration)[3]ENSURE independently verified by SRO in accordance with Appendix J.(N/A if performed by an 8RO to verify data provided by Rx.Eng) SON RCS AND PRESSURIZER TEMPERATURE AND PRESSURE LIMIT O-SI-SXX-068-127.0 1&2 Rev 11 Page 37 of 38 Date vA---'APPENDIX E Page 1 of 1 Sheetv-of\U nit._--.:. __MINIMUM TEMPERATURE FOR CRITICALITY AcceptanceCriteriaFailureActions:Action1-IFAcceptanceCriteriaisnotSatisfied,THEN[a]NOTIFYSRO,[b]REFER talCO 3.1.1.4.[4][5][6]Initials D TAvg minus TRof Deviation Alarm NOT Reset_/'&T Avg less than 551°F[;II'Time(15 minute prior to Criticality trackingor30 minute (TAvg minus T Rof)Deviation Alarm NOT Reset intervals) DYesDYesDYes DYesDYesDYesDYes D No D No D No D No D No D No D No D No D No DYes DYesDYesDYesDYes DYesDYesDYesDYes Time:Time:Time:Time:Time: Time:Time:Time:Time:Date:Date:Date:Date:Date:Date: Date: No.No D No D No D No D No D No D No D No[1]RECORDreasonforthis performance. PERFORM the following sequence every 15 minutes to document prior to criticality temperature tracking or every 30 minutes until (tavg minus tref)deviation alarm is reset:[2]RECORD currenttime(24hourclock).[3]RECORD instrument(Ref.AppendixF)selectedforlowestRCStemperature(TAvg)tracking (*)AND RECORDcurrentRCS temperaturetonearestwholenumber.[4]RECORD instrument (Ref.AppendixF)selectedfornextlowestRCS(TAvg)tracking (*)ANDRECORDcurrentnextlowestRCStemperaturetonearestwholenumber.[5]VERIFYRCSTAvgisAcceptableby checkoffinrow[5].[6]RECORD whetherCriticalityisachievedor whether (TAvgminusT Ref)DeviationAlarmisResetby checkoffinrow[6]ANDRECORDDate &Timewhen accomplished. Use additionalsheetsasrequired. (*)-AdditionallnstrumentIDrecordingneedsenteringonlywhen changedwithintestprogress. (Sequoyah Nuclear Plant Unit1&2 General Operating Instructions 0-GO-4 POWER ASCENSION FROM LESS THAN 5%REACTOR POWER TO 30%REACTOR POWER Revision 0055 Quality Related LevelofUse: Continuous Use Effective Date: 09-13-2007 Responsible Organization: OPS, Operations Prepared By: BetsyParson/W.T.Leary ApprovedBy:K.A.Perkins Current Revision DescriptionAddedanotepriortoStep5.2[1]toremind performerofthepotential impactofchanging Xenon concentrationofcore reactivity (07000359). Madeaneditorialrevisionto update references to chemistry procedure (07000362). Clarified conditionaltobeappliedin AppendixFStep 1.0[14](07000147). Re-Iocated steps associated with Exciter Cooling,controlofSealOil temperatures, Core Condition Monitor and StatorCoolingfromSection5.4to Appendix F (07000359). Added informational note regarding the relationship between T AVG and Reactor PowerpriortoStep5.1[7] (07000280). THIS PROCEDURE HAS THE POTENTIAL TO IMPACT REACTIVITY. (SQNPOWERASCENSIONFROMLESS0-GO-4 Unit 1&2THAN5%REACTORPOWERTO30%Rev.0055REACTORPOWERPage2 of 104 Table of Contents

1.0 INTRODUCTION

4 1.1 Purpose 4 1.2 Scope 4

2.0 REFERENCES

5 2.1 Performance References 5 2.2 Developmental References 7 3.0 PRECAUTIONS AND LIMITATIONS 8 3.1 Precautions 83.2Limitations 11 4.0 PREREQUISITES 13 5.0 INSTRUCTIONS 145.1ActionsToBePerformedPriorToIncreasingReactorPower 145.2ReactorPowerAscensionToBetween13%And15%RTP 175.3TurbineRoll 225.4PlacingMain GeneratorInService 465.5ReactorPowerAscensionto30%RTP 65 6.0 RECORDS 77 AppendixA:MODE2TOMODE1REVIEWAND APPROVAL.78 AppendixB:FIGURE1STEAM GENERATOR LEVELSETPOINTVS REACTOR POWER 81 AppendixC:MAIN FEEDWATERREGANDREG BYPASS VALVE INSTRUCTIONS 82 Appendix D: Turbine RotorBalance 87 Appendix E: Preparations for Turbine Roll 89 Appendix F: Preparations for Generator Synch 94 Source Notes 102 (SON POWER ASCENSIONFROMLESS0-GO-4 Unit 1&2THAN5%REACTORPOWERTO30%Rev.0055 REACTOR POWERPage3 of 104 Table of Contents (continued) ATTACHMENTSAttachment1:UNITSTARTUPFROMLESSTHAN5%REACTORPOWERTO30%REACTORPOWER (((SQNPOWERASCENSIONFROMLESS 0-GO-4Unit1&2THAN5%REACTORPOWERTO30%Rev.0055REACTORPOWERPage4of104

1.0 INTRODUCTION

1.1Purpose This General Operating (GO)Instruction provides necessary instructions to performaunit startupfromlessthan5% Reactor Powerwithmain feedwater reg bypass valves in AUTOto30%Reactor Powerwithmain feedwater reg valves in AUTO.1.2Scope A.ThisGO contains the following sections: 5.1 ActionsToBe PerformedPriorTo Increasing Reactor Power 5.2 Reactor Power Ascension to Between13%and15%RTP 5.3 Turbine Roll 5.4 Placing Main Generator In Service 5.5 Reactor Power Ascensionto30%RTP ((SQNPOWERASCENSIONFROMLESS 0-GO-4Unit1&2THAN5%REACTORPOWERTO30%Rev.0055REACTORPOWERPage5of104

2.0 REFERENCES

2.1 Performance References A.0-PI-NUC-092-002.0,IncoreExcore DetectorSinglePoint Alignment B.0-PI-NUC-092-081.0, PrestartupNISCalibrationFollowingCore Load C.0-PI-NUC-092-082.0, Poststartup NIS CalibrationFollowingCoreLoad D.0-PI-OPS-047-760.1,MainTurbine Actual Overspeed (Annual and 18 Month Tests)E.0-PI-SXX-000-022.0, Calorimetric Calculations F.0-RT-NUC-000-001.0, RestartTestProgram G. Generator HydrogenCoolingSystem H.0-SO-35-2, StatorCoolingWaterSystemI.0-SO-35-4, Monitoring Generator ParametersJ.0-SO-35-6, GeneratorCoreCondition MonitorK.0-SO-35-7, Hydrogen Dryer OperationL.0-SO-27-1, Condenser CirculatingWaterSystem M.0-SI-NUC-092-079.0, Power Range Monitor Channel Calibration By Incore-Excore Axial Imbalance Comparison N.0-SI-OPS-092-078.0, Power Range NuclearFluxChannelCalibrationbyHeat Balance ComparisonO.1 -002.0, Cycling of Unit PCBsPriortoPlacingPCBinServiceP.1 ,2-S0-5-1, Feedwater Heaters and Moisture Separator Reheaters Q.1,2-S0-5-2, NO.3 HeaterDrainTankandPumps R.1,2-S0-5-3, NO.7 HeaterDrainTankandPumpsS.0-SO-1-2,SteamDumpSystem T.0-SI-NUC-000-038.0, Shutdown Margin U.1-PI-OPS-000-020.1,OATCMCR DutyStationShift Relief and System Status ChecklistsModes1-4 ((SQN POWER ASCENSIONFROMLESS 0-GO-4 Unit1&2 THAN 5%REACTOR POWER TO30%Rev.0055 REACTOR POWERPage6of104 2.1 Performance References (continued) V.1-PI-OPS-057-001.0, Functional Testing ofLowVoltageBusCoolingPumps W.2-PI-OPS-0-00-022.1,OATCMCR DutyStationShift ReliefandSystemStatus ChecklistsModes1-4 X.0-'GO-5, Normal Power Operation Y.0-SO-24-1,RawCoolingWaterSystem Z.1,2-S0-47-2, Electro-HydraulicControlSystem AA.0-SO-85-1,ControlRodDriveSystem BB.SSP-6.24, Maintenance Management System Configuration Control CC.Switchyard Letter14,Visual Confirmation of Motor Operated Disconnects and Power Circuit Breaker Operation DO.Switchyard Letter 32, Delle-Alsthom Airblast Circuit BreakersEE.TI-28,CurveBookFF.TI-40, Determination of Reconditioned Reactor Power GG.0-PI-OPS-000-666.0, RiverTemperatureLimits SpecifiedbyNPDES permitHH.SI-53, SpecificIodineIsotopic Activity Concentration and/or DEI-131 Determination II.SI-407.2, RadioactiveGaseousWaste Effluent ParticulateandIodine Dose Rates from Shield and Auxiliary Building Exhausts (Weekly/Special) and CondenserVacuumExhausts(Special) JJ.0-SI-CEM-030-415.0, Gaseous Effluent Requirements (GrossAlpha,Noble Gas and Tritium KK.0-SO-57-1,MainBank Transformer Cooling LL.0-SO-58-1, Main GeneratorBusDuctCoolingSystem (saNPOWERASCENSIONFROMLESS0-GO-4 Unit 1&2THAN5%REACTORPOWERTO30%Rev.0055REACTORPOWERPage7 of 104 2.2 Developmental References A.FSARSection13.5B.0-GO-2-3,PlantStartupFromLessThan5%ReactorPowerTo30% Reactor Power c.WletterGP89-155,RIMSS57 891026972D.Wletter86-02/B44861112002E.WFAR 5-S0-3771-075 Response ((SQN POWER ASCENSIONFROMLESS 0-GO-4 Unit 1&2 THAN 5%REACTOR POWERTO30%Rev.0055 REACTOR POWERPage8 of 104 3.0 PRECAUTIONS AND LIMITATIONS 3.1 Precautions NOTE Adherence to Precautions and Limitations is referenced in SPP-2.2.A.Reactor Engineeringshouldbe contacted for guidanceoncore operating recommendationsduringunusualpower maneuverssuchasstartupduringendofcorelife. [C.11]B.TRM 3.3.3.15requiresLEFMcorethermalpower (U2118)tobeusedto perform 0-SI-OPS-092-078.0above15%reactorpower.LEFM indication is availableifthe following conditionsaremet:*LEFM status NORMALonICS CalorimetricDatascreen*LEFMcore thermalpower(ICSpoint U2118)showsgood (green)data.*LEFM MFW headertemp(ICSpoint T8502MA)greaterthan250°F.IfLEFM indicationisNOT availableabove15%reactorpower,thenTR 3.3.3.15 action mustbeentered.C.Duringstartup,NISpowerrange indicationmaybereading significantly higher than true power until calibration adjustmentsaremade.Thefollowingshouldbeusedto determine the most accurate indication for comparisonwithNIS:*When reactor powerislessthanorequalto15%,use average loopT (U0485).*When reactor power is greaterthan15%,useLEFMcore thermal power indication (U2118).IfLEFMisNOTavailable,thencontinueusing average loopTupto 40%.(U1118willbeusedabove40%withLEFM unavailable).D.Theboron concentrationinthe pressurizershouldbemaintainedwithin50ppmoftheRCSbyuseof pressurizerheatersandspray. E.Pressurizer enclosure temperatureshouldbe maintainedlessthan150°F. Rapid changes in pressurizer enclosure temperaturemayresultin pressurizer safety valve simmer. (SON POWER ASCENSIONFROMLESS0-GO-4Unit1&2THAN5%REACTORPOWERTO30%Rev.0055 REACTOR POWERPage9of104 3.1 Precautions (continued) F.The low pressure turbine steam inlet temperature should be limited to 400°F when unitloadislessthan10%.When reducingload,the reheater control valvesshouldbe adjusted to limit reheater outlet temperaturetoa maximum of 400°F within approximately 15 minutes after reaching10%load.G.00 NOTpasssteam through the turbinewiththerotoratrest. The turbine shouldbeon turning gear anytimethemain steamlinesare pressurizedupto turbinestopvalves. H.Changeinloadshouldbe controlled in accordancewithload changing curves of TI-28, Figures A.15andA.16.I.The turbineshouldbe operatedin'IMPOUT"control during normal unit operation."IMPIN" operation results in system swings and shouldonlybeused during the performance of valvetests.(W letter GP 89-155,RIMSS57 901-26 972)J.The Predictive Maintenance Engineer (POM)should be contacted following a unittripso thathemay determineiflocal vibration monitoringofthe Turbine-Generator,bythePOM staff should be performed whentheunitis restarted. Normally, monitoring is necessary following a refueling outage, a major maintenance outageonthe turbine-generator, or after a plant trip which wasduetoa turbine initiatedtripora generator electrical initiated trip.Two hoursleadtime priortotheinitial turbinerollis necessary to ensure thatthePOM staff is onsite to monitor the start-up.The Maintenance Shift Supervisor (MSS)hasthe telephone numbers and pager numbersforthe Predictive Maintenance Engineerandthe SupervisorforthePOMstaff. ((SQN POWERASCENSIONFROMLESS 0-GO-4Unit1&2THAN5% REACTOR POWER TO 30%Rev.0055 REACTOR POWERPage10of104 3.1 Precautions (continued)K.Anyoff frequencyturbineoperationistobereportedtothe Component EngineeringGroupVibration Engineerforrecordkeeping.Thereportwill includedurationandmagnitudeof off-frequency operation. L.Operation at off-frequenciesistobeavoidedinordertopreventtheprobable occurrenceofturbinebladeresonance.Prolongedperiodsofoperationatcertainoff-designfrequenciescouldcauseexcessive vibratory stresseswhichcould eventuallygeneratefatiguecrackingintheblades. Off-frequency operationispermittedtothedegreeandtimelimitspecifiedonthechart"Off-Frequency TurbineOperation",FigureA.26ofTI-28.M.Thevalvepositionlimitershouldbe periodically positioned approximately 10%above governor control indications(keepsgovernorvalvesoffofthelimiter)as turbineloadisincreased.Thisprevents inadvertent load increasesbylimiting governorvalveopeningandallowsafasterresponseoftherunback feature which ensures main feedwatersystemwillsupplytherequired amountofflow.N.Thepositionofcontrolrodbank 0 should normally be215stepswhenpowerlevelis steadystateatorabove85%RTP.Atsteadystatepowerlevelsbelow85%,controlbank 0 should normally be165steps.Ifrodpositionismorethan2stepsbelowthisguidanceforlongterm,thenanimpacttosafety analysis assumptionsmayoccur.Longtermwillbe defined/determined by Reactor EngineeringandtheFuelVendor.O.Atlow powerlevels,theLPHeatersmaybeunbalancedinextractionsteam supplyuseandheatpickupacrossthe condensatesideoftheheaterstring.Thisconditionshouldcorrectitselfastheunit approaches 45-50%TurbinePower.(REF.PER 99-003789-000) P.Operationofmain generator without automaticvoltagecontrolcould impact grid voltage requirements.TheSouthEastAreaLoad Dispatcher (SELD)shouldbe notified immediately if generatorisinservice without automatic voltage regulator.Also,refertoSectionEofGOI6forMVARlimits. Q.Main Generator operation without AutomaticVoltagecontrolrequiresthat NarrativeLogentriesbemade(time,date,reason &duration)andthat notificationbemadeto Operations Duty Specialist(ODS)within twenty four(24)hours.R.Main GeneratoroperationoutsideoftheVoltageScheduleinGOI-6requires that NarrativeLogentriesbemade(time,date,reason &duration)andthat notificationbemadetoSouthEastAreaLoad Dispatcher(SELD)withinone(1)hour. (("'SQN POWER ASCENSIONFROMLESS 0-GO-4 Unit1&2THAN5%REACTOR POWERTO30%Rev.0055 REACTOR POWER Page 11 of104 3.1 Precautions (continued) S.0-PI-OPS-035-001.0shouldbeperformedpriortoturbinerestart when recommended by engineering, following maintenanceorplantactivitiesinwhichthe generator was depressurizedduringaforcedoutage,or after arefuelingoutage. 0-PI-OPS-035-001.0 provides verification and adjustment oftheSealOilSystemnormalandbackupregulators.(REF PER-04-24237-000) 3.2 Limitations A.Afterrefuelingoperations,theNIS indications may be inaccurate until calibrationathigherpowerlevels.TheNIScalibration procedureswilladjustthePRMtripsetpointsto ensurethattheexcore detectorsdonot contribute to an overpowercondition.Priortostartup,thePRMhighrangefluxtrip setpointwillbeadjustedfrom109to60%,withtherodstop(C-2)remainingat103%. [C.2]B.PreconditionedPowerLevelsandMaximum AllowableRatesofPower IncreasearespecifiedinTI-40, Determination of Preconditioned Reactor Power.C.Duringinitialstartups,basedon Westinghouse recommendations,alower powerrampratelimithasbeen implemented for powerlevelsabovethe intermediatepowerthreshold.The IntermediatePowerThresholdis unit/cycle dependentandis determinedbytheVendor.RefertoTI-40.D.ICSwill automatically monitor pre-conditionedpowerlevelasfollows:1.PointU1127isreactorpowerin percentofRTPbasedon either secondary calorimetricorRCS 8 T dependingonpowerlevel.2.PointU0103isa20minuterolling averageofreactorpower rate-of-changefittedovera20minuteperiod. U0103isaleading indicator of%/hourpowerramprateandcanbeusedindecidingtospeeduporslowdowntheramprate.3.PointU0104isa1hourrollingaverageofreactorpower rate-of-changefittedovera1hourperiod. U0104isusedin demonstrating compliance With fuel pre-conditioningpowerrampratelimits.4.PointK0058isthe currentlyqualified(or pre-conditioned)powerlevel. 5.ThesepointscanallbemonitoredwiththeICSgroupdisplay"TI40". AppendixAmaybeusediftheICSis unavailable.E.AnyTI-40power increase limitthatisexceededin anyonehourisevaluatedin accordancewithSPP-3.1. ((SON POWER ASCENSIONFROMLESS0-GO-4Unit1&2THAN5%REACTORPOWERTO30%Rev.0055REACTORPOWERPage12of104 3.2 Limitations (continued)F.Intheeventofachangeintheratedthermalpowerlevel exceeding15%inonehour,notify Chemistrytoinitiatethe conditionalportionsof SI-407.2 0-SI-CEM-000-050.0 and 0-SI-CEM-030-415.0duetothe thermal power change.G.Themain turbineshallbeonturninggearatleastonehourpriortorollingwith steam.H.Westinghouse shouldbecontactedifthe turbineisoperated outsideofits operating limits.I.To prevent high vibratory stresses and fatigue damagetothelaststage turbineblading,do NOT operatetheturbineforevenbriefperiods outsideoflimits listed below:[WLtrGP86-02(B44861112002)]1.Atloadslessthanorequalto30%(350MW),themaximum permissible backpressureis1.72psia.(3.5"Hg).TheICS Computeralarmpoint UP5007whichwill identify.theconditionof condenser pressure>1.72psia in conjunctionwithMWbeing <350.2.Atloads greaterthan30%,themaximumpermissible backpressure is2.7psia(5.5"Hg)witha5minute limitation beforetrippingthe turbine.J.Generator voltage shall NOTexceed24.8kV.K.Themain generatorfieldshall NOT be energizedatlessthan90%ratedspeed.L.Do NOT allow the generatortobecome under-excited. SQN POWER ASCENSIONFROMLESS 0-GO-4 Unit1&2 THAN 5%REACTOR POWERTO30%Rev.0055 REACTOR POWERPage13 of 104 4.0 STARTUPPREREQUISITES Unit J NOTE Throughout this Instruction where an IFITHEN statementexists,thestepshouldbe N/A'd if the condition does NOT exist.[1]ENSURE Instructiontobeusedisacopyof effective version.[2]ENSURE Precautions &Limitationof Section3.0havebeen reviewed.[3]ENSURE Reactor Power is between1and 4%withfourmain feedwater bypassregvalvesin AUTO.(N/A if manual bypassregvalve operation is allowedbyPlant Manager)([4]ENSURE each performer documents their nameandinitials:PrintName Initials SQN POWER ASCENSIONFROMLESS 0-GO-4 Unit1&2THAN5%REACTOR POWERTO30%Rev.0055 REACTOR POWERPage14of104 5.0 STARTUPINSTRUCTIONS Unitl 5.1 ActionsToBe Performed Prior To Increasing Reactor Power[1]ENSURE Prerequisites complete.NOTE Steps5.1[2]through5.1[12]canbe performedoutofsequence. ([2][3]IF O-GO-4, Appendix A, Mode 2toMode 1 Review And Approval is NOT currentforthisstartup, THEN INITIATE Appendix A, while continuingwiththis instruction. IFtheMode3toMode2toMode1 surveillance checklists are NOT currentforthisstartupforMode1entry, THEN REQUEST Periodic Test CoordinatortoissuetheMode3toMode2toMode1 surveillance checkliststothe applicable departments. I Initials Time Date[4]ENSURE Reactor Power is between1and4%withfourmain feedwater bypassregvalvesin AUTO.(N/Aifmanual bypassregvalve operationisallowedbyPlant Manager)NOTE Duringstartupafteracold shutdown the Condensate 01 normallywillbealignedforfull flow polishinguntiltheMSRsareinservice. [5]ENSURE Condensate 01 polishing operation in accordancewithRCL recommendations. (SQN POWER ASCENSION FROM LESS 0-GO-4 Unit1&2THAN5%REACTOR POWERTO30%Rev.0055 REACTOR POWERPage15of104 1 Unit 0.....-_STARTUP5.1 ActionsToBe PerformedPriorTo Increasing Reactor Power (continued) CAUTION After refueling operation, NIS indicationsmaybe inaccurate until calibration at higher power levelshasbeen performed.RTPshallNOTbe allowed to exceed 4%priortothe verificationofthe proper (or conservative) IR andPR setpoints. [6]IFstartupisfollowingarefueling, THEN[6.1]MAINTAINreactorpowerbetween3to4%. [6.2]VERIFYtripand permissive setpointsarewithinlimitsin accordance with 0-PI-NUC-092-082.0. [C.2]ENSURE P-10 actuation setpointislessthantheIRtrippowerlevelsetpoint. [C.2]([6.3]Rx EngineeringDateTime Rx EngineeringDateTime[6.4]ENSURE all applicableportionsof 0-RT-NUC-000-001.0arecomplete. Rx EngineeringDateime NOTE The relationshipbetweenT AVG and reactorpowerwithSteamDumpsinPressureMode while maintainingSteamPressureis0.52deg.F/%. [7]MAINTAIN T AVGstablewiththesteamdumpsinthepressuremodeorwiththeSG atmosphericreliefvalvessetat84%or1005psig. [8]ENSURE 0-SI-NUC-000-038.0 shutdownmargincalculationis complete (N/A if NOT required). / SQN POWER ASCENSIONFROMLESS 0-GO-4 Unit1&2THAN5%REACTOR POWER TO30%Rev.0055 REACTOR POWERPage16of104 STARTUPUnit----l-'_ (5.1 ActionsToBe Performed Prior To Increasing Reactor Power (continued) [9]ENSURE containment air temperaturesarewithinlimitsin accordance with 1,2-SI-OPS-000-003.D,App.B.(TS 3.6.1.5)[10]INITIATE AppendixE, PreparationsforTurbineRoll. [11]INITIATE Appendix F, Preparations for Generator Synch.[12]REVIEWTI-40to determine applicable Preconditioned PowerLevelsand Maximum AllowableRatesofPowerIncrease. [13]VERIFY all applicable actionstepsinSection5.1are completeorinitiated. [14]ENSURE Appendix A, Mode 2toMode 1 Review and Approval completedtoverifyallrestraintstoMode1entry havebeenresolvedand approvalsformodechangegranted. SM SignatureENDOF TEXTDate vV'-Time SQN POWER ASCENSIONFROMLESS 0-GO-4 Unit1&2THANS%REACTOR POWERTO30%Rev.OOSS REACTOR POWERPage17of104 STARTUP vv"-UnitL DateS.2 Reactor Power Ascension To Between13%And1S%RTP NOTEThesteam generator level operatorisincontrolofunitstartupuntilthemain feedwater regvalvesarein AUTO.[C.S][1]REVIEWplantparametersandindications, AND VERIFYstabilitypriortoreactorpowerescalation. (NOTES 1)AdjustingblowdownflowwillprovideanadditionalmethodofcontrollingSGwater inventory.(Closeblowdownisolationvalvesonlyiflevelcannotbe maintained)2)Priorto increasingreactorpowerabove5%,SGblowdownshouldbeinservice. 3)Maximumblowdownrateislessthanorequalto270gpm.Eachsteam generatorflow,upto60gpmisindicatedonpanelL-357locatedintheA.B.SupplyFanRm.Minimumblowdownrateequals5gpmforeachsteamgenerator.Finalblowdownrateshouldbe determinedbychemicalanalysis. 4)Computerpointsrequireaprefix0,1,or2beplacedinfrontofthepointnumber;for example,1F2261A. [2]IFSGblowdownisinservice, THEN ADJUSTFIC-15-43asdesired.(plant computerpt.F2261A) SQN POWER ASCENSIONFROMLESS 0-GO-4Unit1&2THANS%REACTOR POWERTO30%Rev.OOSS REACTOR POWERPage18of104 STARTUP_Unit__Date_5.2 Reactor Power Ascension To Between13%And1S%RTP (continued) NOTES 1)Actions effecting reactivity are directedinthe following step.0-SO-62-7 requirementsshallbe adheredtofor reactivity changes (i.e.reactivity balance, amountsofboricacidorwater).All appropriate verifications and peerchecksshallbeutilized during performance. 2)Recommendeddilutionrateis50to75gallon batchesevery12to15 minutesfora steady power increase.Rod movementshouldbelimitedto1/2step increments approximatelyevery11/2minutes.Dilutionandrod movementratesmaybe adjusted dependingonSGlevelcontrol stability.3)ControlRod withdrawaland/or dilution requirementsmaybe significantly impacted bythechangeincore reactivitydueto changing Xenon concentration. ([3][4][5]INITIATE a methodical and deliberate reactor power increasebymanual adjustmentofthecontrolbanksorbydilutingthe RCS.MODE1 WHEN reactor power is above 5%, THEN LOG Mode1entryintheUnit Narrative Log.MAINTAINtheSGlevelsonprogramby periodically adjusting thefeedwaterbypassreg controller level setpoints using Appendix Band C.D D D[6]IF Turbinerollinparallelwithpower increaseisdesired, THEN PERFORMSection5.3inparallelwiththe remainderofthis section. SON POWER ASCENSIONFROMLESS0-GO-4 Unit 1&2THAN5%REACTORPOWERTO30%Rev.0055 REACTOR POWERPage19 of 104 STARTUP_Unit__Date---5.2 Reactor Power Ascension To Between 13%And15%RTP (continued)[7]IFthe intermediaterangerodstop setpointisreachedbeforeP-10energizes,THEN[7.1]STOPthepowerescalation. o[7.2]CONTACTReactorEngineeringtoevaluatepowerrangecalibration.[C.3] Initials[8]WHENreactorpowerisgreaterthanorequalto10%onatleast2outof4PRMs,THEN[C.1][C.3][8.1]VERIFY annunciatorXA-55-4A,window 0-5: Time Date (P-10 NUCLEAR ATPOWER PERMISSIVEisLIT.o[8.2]VERIFY annunciatorXA-55-4A,windowB-5:P-7LOWPOWERTRIP BLOCKisDARK.o[8.3]COMPAREthehighestreadingPRMwiththehighestreadingloop L\Tindicationtobewithin5%ofeachother.[C.1][C.3] o[8.4]IFtheaboveconditionalresponseisNOTattained, THEN A.STOPthepowerincrease.B.NOTIFYtheSRO. Initials Time o Date SQN POWER ASCENSION FROM LESS 0-GO-4 Unit 1&2 THAN 5%REACTOR POWERTO30%Rev.0055 REACTOR POWER Page 20 of 104 STARTUP_Unit--Date_5.2 Reactor Power Ascension To Between 13%And15%RTP (continued) NOTE The followingstepwillblockbothIR (25%)andPR (25%)low power reactor trips.[9]BLOCKtheIRHIFLUX reactortripandPRLORangeHI FLUX reactortripby performing the following:[9.1]PLACEIRMTRIP BLOCKP-10[HS-92-50031 AND[HS-92-50041to BLOCK.o[9.2]VERIFY annunciator XA-55-4A, window C-2: INTERMED RANGE TRAINS A&BTRIP BLOCKEDisLIT.o[9.3][9.4]RELEASE[HS-92-50031 AND[HS-92-50041. PLACEPRMLOW POWER TRIP BLOCK P-10[HS-92-50051 AND[HS-92-50061to BLOCK.D o[9.5]VERIFY annunciator XA-55-4A, window 0-1: POWER RANGE LOW SETPOINT TRAINS A&BTRIPisLIT. BLOCKED[9.6]RELEASE[HS-92-50051 AND[HS-92-50061. D D SQN POWER ASCENSION FROM LESS 0-GO-4 Unit 1&2 THAN 5%REACTORPOWERTO30%Rev.0055 REACTOR POWER Page 21 of 104 STARTUP_Unit__Date_(5.2 Reactor Power Ascension To Between 13%And15%RTP (continued)[10]WHEN reactor powerisbetween13and15%, THEN[10.1]STOP power increase.[10.2]STABILIZEtheplant.[11]IFrollingofsecondMFWPonrecirc withoutpumpingforward for testing or maintenanceisdesired, THEN PLACEsecondMFPTinserviceby performing the following: [11.1]RECORDwhichMFPTistobetested. ____MFPT[11.2]PLACEsecondMFPTinservicein accordancewithSO-2/3-1Sect.8.12or 2-S0-2/3-1 ,Sect.8.4.3. [12]IF unit shutdownisrequired, THENGOTO0-GO-6, PowerReductionFrom30% Reactor PowerToHotStandby. [13]ENSUREsteps5.2[1]through5.2[11]ofthissection complete.(applicable steps)o o o NOTE If Section5.3has already been initiated, then performance should continueatthestepineffect.[14]IFrollingtheturbine, THENGOTOSection5.3.ENDOF TEXT (SQN POWER ASCENSIONFROMLESS 0-GO-4 Unit1&2THAN5%REACTOR POWER TO 30%Rev.0055 REACTOR POWERPage81of104 Appendix B(Page1of1) FIGURE 1 STEAM GENERATOR LEVEL SETPOINT VS REACTOR POWER NOTE This figure does NOT represent the automaticS/Glevelprogram.The operating band provides a guide for Operators during Unit start-upandisintendedto enhanceS/Glevel control during transitionfromAFWlevelcontrolto BypassRegvalvecontroltoMainReg Valve control. ..\\....,..\\\-t-\\\....\--\\'.1\\.......\I.,.........t\,.l-\.I*I'<I..N"', r',-., , T\, I.\"" I, T I ,\-r"'\1\'""""\\I.-+-"\\-r\..L\\i:\o'irle:\ct\\I\.......,\,\"\\\..."..., I.I....,..l\ -,--------\'I\T..\\, ( SQN POWER ASCENSIONFROMLESS 0-GO-4 Unit 1&2 THAN 5%REACTOR POWERTO30%Rev.0055 REACTOR POWERPage82 of 104 Appendix C (Page 1 of 5)MAIN FEEDWATERREGANDREG BYPASS VALVE INSTRUCTIONS1.0REG BYPASS CONTROLLER LEVEL SETPOINT ADJUSTMENTS CAUTION It is VERY important that adjustments to reg valves are made SLOWLY with the operator observing indicators to verify the desired results.This point cannot be over stressed as it is a key point to a successful startup.NOTES1)TheSGreg bypass controllershouldbeadjustedononlyONESGatatime.[C.5]2)Thereg bypass controllershouldbein MANUALpriorto adjusting setpointvalueto prevent controllergaininputchange. ([1]WHENregbypass controller level setpoint requires adjustment, THEN PERFORM the followingstepsononeregbypassvalveata time:[C.5](N/AvalvesNOT adjusted)[1.1]REFER TO Appendix B for allowable setpoint.SG-1SG-2SG-3SG-4 000 0[1.2]PLACEregbypass controller in MANUAL.SG-1SG-2SG-3 SG-4 0 000 NOTE Allow sufficienttimeforthereg bypasstorespond. [1.3]STABILIZESGlevelatadesiredlevel. SG-1 SG-2 SG-3 SG-4 0 0 0 0[1.4]ADJUST controller setpointinsmall increments while I monitoringSGlevel.\SG-1 SG-2 SG-3 SG-4 0 0 0 0 SONPOWERASCENSIONFROMLESS0-GO-4 Unit 1&2THAN5%REACTORPOWERTO30%Rev.0055REACTORPOWER Page 83 of 104 Appendix C(Page2 of 5)STARTUP Unit Date---1.0REG BYPASS CONTROLLER LEVEL SETPOINT ADJUSTMENTS (continued) [1.5]PLACEregbypasscontrollerinAUTO.SG-1SG-2 o 0 SG-3 o SG-4 o 2.0[1.6]ALLOWtheplanttostabilizebeforeadjustinganothervalvesetpoint.SG-1SG-2 o 0 DAMPENINGSGLEVEL OSCILLATIONS WITH FEEDWATER REG BYPASS VALVESINSERVICE SG-3 o SG-4 o (1)NOTESPerformadjustmentstooneSGatatime.AllowPlantParameterstoStabilizebetweenvalveadjustments.[C.5]2)Thewiderangelevelrecordersmayrespondtoachangeinlevelbeforethenarrowrangeindicators.[C.5]3)IndicatedflowrateonthefeedflowindicatorsmayNOTreflectanaccuratevalueofflow.Theflowindicationistobeusedasareferencevalueonly.[C.5]4)ThefollowingstepmaybeperformedanytimeSGleveloscillatesoutsidetheSGlevel setpointoperatingbandof+/-5percent.[1]IFrequiredtodampenSGleveloscillationsatanytimeduringSGlevelcontrolwiththeregbypasscontrollersinAUTO, THENPERFORMthefollowing:[C.5][1.1][1.2][1.3]PLACEtheregbypasscontroller in MANUAL.CHANGEvalvedemandpositionLESSTHAN10percentintheoppositedirectionofvalvetravel.PLACEtheregbypasscontrollerinAUTO. o o o SQN POWER ASCENSIONFROMLESS0-GO-4 Unit1&2THAN5%REACTORPOWERTO30%Rev.0055 REACTOR POWERPage84 of 104 Appendix C(Page3 of 5)STARTUP UnitDate_3.0 POSITIONING MAIN FEEDWATERMAINREG VALVES OFF SEATDURINGUNIT STARTUP NOTES 1)AfteramainregisadjustedDONOTincrease reactorpoweroropenmainreg furtheruntilplant stabilizesandSGlevelreturnstoprogram. ALLOWING PLANT PARAMETERS TO STABILIZEBETWEENREGVALVE ADJUSTMENTSISTHEKEYTO SMOOTH POWER ASCENSION. 2)Anticipatelevelshrinkwhenthemainregcomesoffitsseat.[C.5]3)Usemain feedwaterflowindicationtodeterminewhenmainregvalvescomeoffseat. [1]PERFORMthefollowingstepstopositionmainregvalvesoff seat: ([1.1]REVIEW plant parameters and indicationspriortoinitial opening.SG-1SG-2SG-3SG-40000[1.2]OPENthemain feedwaterregvalveinsmall increments while maintainingtheregbypassvalvebetween25and60percentopen. SG-1SG-2SG*3 SG-4 0 000[1.3]ENSUREregbypassvalvestartsclosingwhenmainregvalveisopened. SG-1SG-2SG*3 SG-40000[1.4]ENSURESGlevelreturnstoregbypass controller setpointwhenmainregvalveis adjusted.SG-1 SG-2SG-3SG*4 0 0 0 0[1.5]ENSURESGlevelandMFWsystem stabilizes before performing subsequent valve adjustments. SG-1 SG-2 SG-3 SG-4 0 0 0 0 SQN POWER ASCENSIONFROMLESS 0-GO-4 Unit1&2 THAN 5%REACTOR POWERTO30%Rev.0055 REACTOR POWERPage85 of 104 Appendix C (Page 4 of 5)4.0 STARTUP Unit--PLACING FEEDWATERMAINREG VALVES IN AUTOMATIC Date---CAUTIONS1)DONOT place a main reg valve in AUTO without sufficient flow being indicated on the controlling steam/feed flow indicators. 2)BothMFWreg and reg bypass controllers shouldNOTbe left in AUTO simultaneously for an extended period.[C.5].[1]WHENdesiredtoplacemain feedwaterregvalvesin AUTO, THEN PERFORM the following: ([1.1]ADJUST SGlevelto SGprogramlevelsetpoint, and ADJUSTthemainregvalvetoobtainnearzero deviation (between-5 percentand+5 percent)while matchingsteamandfeedflows.SG-1SG-2 o 0 SG-3 o SG-4 o[1.2]WHEN controller deviationisnearzero, THEN PLACEthemainregvalvein AUTO.SG-1SG-2 o 0 SG-3 o SG-4 o[1.3]VERIFYthemainregvalveis controlling SG level.SG-1SG-2 o 0 SG-3 o SG-4 o SQN POWER ASCENSION FROM LESS 0-GO-4 Unit1&2 THAN 5%REACTOR POWER TO30%Rev.0055 REACTOR POWER Page 86of104 Appendix C (Page5of5)4.0 STARTUP Unit--PLACING FEEDWATER MAIN REG VALVES IN AUTOMATIC (continued) Date---[1.4]PLACE the associated reg bypass valve in MANUAL.SG-1SG-2SG-3 o00 SG-4 o[1.5]CLOSEthereg bypassvalveinsmall increments, AND ENSUREthemainregvalve respondstocontrolSG level.SG-1SG-2 o 0 SG-3 o SG-4 o ([1.6]WHENmainregvalveis controllingSGlevel, THEN PROCEED TO anotherSGloop.SG-1SG-2 o 0 SG-3 o SG-4 o I Appendix D Scenario OutlineFormES-D-1 I ((Facility: SequoyahScenarioNo.: 4OpTestNo.: NRC Examiners: Operators: Initial Conditions: -41%PowerBOLReadytoIncreasePowerandRoll2nd Main Feedwater Pump.TurbineDriven Auxiliary FeedwaterPumpOOSfor maintenance Turnover:Continueplantstartup. CurrentlyatO-GO-5Section5.1,Step23. TargetCTs:Insert NegativereactivityusingrodsorborationpriortocompletionofFR-S.1Step4.CloseMSIVsand Stop/IsolateAFWflowtoFaultedS/GpriortotransitionoutofE-2butpriortoorangepathFR-P.1beingreached. EventMalf.No.Event Event No.Type*Description1N/AR-ATC-41%ContinuePowerincreasetoRoll2nd MFP N-SRO/BOP2RX06ATS-SROControllingPressurizerlevel transmitterfailslowLT68-339. I-SRO/ATCResultsinletdownisolationwhichrequiresrestoration.TechSpec Evaluation.3RX16D TS-SRO Steam Generator#4narrowrangelevel transmitterfailslow.I-SROTechSpecEvaluation.4RX24 I-SRO/BOP Feed WaterHeaderPressure TransmitterPT-3-1FailsLow.MFPSpeedwillincreaserequiringmanualcontrol.5MS06C C-SROSmallSteamLeakOutside ContainmentUpstreamOfMSIVOnLoop3.(Non-Isolable)6MS06C M-AIISteamleakincreasestolargebreakrequiringReactorTripandSafetyInjection. 7 RP01C C-AIIBothReactortripBreakersfailtotrip automaticallyormanuallyresultinginATWS. 8 RD09 C-SRO/ATCRodsFailtomoveinautobutwillmove manually5secondsafterturbinetrip. 9 FW04C C-SRO/BOPMotorDrivenAFWLevelControlValveToLoop3S/G(Faulted)FailsFullOpen.RequiresStoppingAFWPumpOrLocalIsolationToStopFeedwaterToFaultedS/G.

• (N)ormal, (R)eactivity, (I)nstrument,(C)omponent, (M)ajor Appendix D NUREG1021Revision9 I Appendix D Scenario Outline Scenario 4 SummaryFormES-D-1 I (Crewwill assumeshiftat approximately at-41%reactor powerwithdirectionto continue plantstartup.Crewwill continue power increaseandrollsecondMain FeedwaterPump(MFP).WhentheMain feedwaterpumphasbeenrolled,and adequate powerchangehasbeen performed to demonstrate proficiency, the controlling pressurizer level channelwillfaillow.Thiswillresultin letdown isolation,channeldefeat,and restorationofletdownas directedbytheAOP.SROwill evaluate and enter applicable Technical Specifications.

Following restorationofletdown,aSteam Generator#4 narrowrangelevel transmitterwillfaillow.Noplant transientwillresultduetothemedian selectorcircuit.SROwill directAOPand evaluate and enter applicable Technical Specifications. Feedwater header pressure transmitterPT-3-1willfaillowresultinginMFPspeed increasing to attempt to restore steam header to feedwater differential pressuretoprogram.Thiswillrequire manual controlofMFPspeed.AOPwillbe performed;however,MFPspeedwillhavetoremaininmanual.Whenplantis stableasmall unisolablesteamleakwill occuronloop3Steam generator outside containment upstreamoftheMainSteamIsolationValve.Crewwillperform actionsoftheAOPto stabilizetheplantand monitor key parameters for Reactor trip.Whenthesmallsteamleakhasbeen addressed,thesteamleakwillbe increasedtoa significant break requiring ReactorTripand Safetyinjection.When manual reactortripis actuated, both reactor trip breakerswillfailtoopen automatically and manuallyresultinginan ATWS and entry into contingency procedure FR-S.1.During responsetotheATWS,controlrodswill initiallyinsertin automaticbutstop after-5 seconds requiring manual rod insertion.Whenthe Reactor is shutdown and Safety injection has occurred, the auxiliary feedwater supplyvalvetothe faultedS/Gwillfailfullopenrequiringthatthe associated AFWpumpbe stoppedtostopfeedflowtothefaultedS/G.Local isolationofthe failed AFWvalvemayalsoinitiated. The scenario may be terminatedwhencrew transitionsoutof emergency procedure E-2.Appendix D NUREG1021Revision9 Page1of2 NRC08DRev0 CONSOLE OPERATOR INSTRUCTIONS Sim.Setup Reset IC---1H-Performswitchcheck.Allowthe simulatortorunforatleast3minutesbeforeloadingSCENfileorstartingtheexercise.ThiswillinitializeICS. Load SCENS: NRC08DPlacesimulator momentarilyinRUN,PlaceOOS equipmentinrequiredpositionwithtags,ClearalarmsandReturntoFREEZE. These remoteIMFFW07C f:1.functionsareactivelOR ZLOHS151A_GREEN f:OwhentheSCENSfilelOR ZLOHS117A_GREEN f:Oisloaded.lOR ZLOHS118A_GREEN f:O lOR ZLOHS3136AA_GREEN1 f:O lOR ZLOHS3136AA_GREEN2 f:O lOR ZLOHS3136AA_RED1 f:O lOR ZLOHS3136AA_RED2 f:O (lOR ZDIHS3136AA f:O lOR ZLOHS3179AA_GREEN1 f:O lOR ZLOHS3179AA_GREEN2 f:O lOR ZLOHS3179AA_RED1 f:O lOR ZLOHS3179AA_RED2 f:O lOR ZDIHS3179AA f:O Event#1: IncreaseUseRemoteFunctionsFWR10AandPoweras determined FWR10Btoadjustfeedpumpspeed.byNRC Examiner.FWR10A=3360 over 30 sec period and FWR10B=3300. OR adjust as necessary as requestedbycrew.Event#2:WhenIMFRX06Af:1k:1 Power Increase complete as determinedbyNRCExaminer,Insertthis Malfuinction using Key 1 Event#3: WhenIMFRX15D f:O k:2 DeterminedbyNRCExaminer,insertthis Malfunction using Key 2.(\, Initialize simulatorat-41%%RTPBOL. Place Mode_1_placard on panels.Place-A-Train Week sign on the simulator. Set Ranges on Tave/Tref Recorder on 1-M-6 to+/-3 degrees for current conditions(SystemMenu/StripChartAssign...Tabthroughto fix)TDAFWPUMPIS INOPERABLE. Close FCV-1-17&18&place Hold Noticeon 1-17&18 and FCV-1-51.Also place Hold order on TDAFW Pump ERCW supply valves.Place Protected EquipmentTagsonMD AFW Pumps.-41%POWER,READYTOINCREASEPOWERANDSTART2ND MAIN FEEDWATER PUMP,CONTINUEPLANTSTARTUP. CONTROLLINGPZRLEVEL TRANSMITTER FAILSLOWCHNLLT68-339WhenIMs or MSS contacted to trip bistables, inform the crew thattheIMs will reporttotheMCRin-45 minutes.STMGENLEVEL TRANSMITTERFAIL,CNTRLCHNLSSG#4LT3-106.WhenIMs or MSS contacted to trip bistables, inform the crew thattheIMs will reporttotheMCRin-45 minutes. CONSOLE OPERATOR INSTRUCTIONS Page 2 of 2 NRC08D Rev 0 (Event#4: WhenIMFRX24f:1k:3 FEED WATER HEADER PRESSURE DeterminedbyNRC TRANSMITTERFAILSLOW;PT-3-1.Examiner,insertthis Malfunction using If dispatched to check instrument locally, wait-5 Key 3.min and report no obvious problem locally.Event#5: WhenIMFMS06Cf:25k:4MAINSTEAMLINELEAK OUTSIDE DeterminedbyNRC CONTAINMENT-LP3 UPSTREAMOFMSIV.Examiner,insertthis Malfunction using If Dispatched to look for steam or feedwater leaks Key 4.wait-amtn and report steam coming from the East Valve vault room.Event#6: WhenMMFMS06Cf:75r:300INCREASESTEAMLEAKTORUPTUREOVER5 DeterminedbyNRCMINREQUIRINGRXTRIPAND SAFETY Examiner, Modify this INJECTION. Malfunction. If Dispatched to look for steam or feedwater leaksNote:IfCrewElects wait-3m in and report steam coming from the to manuallytripfor East Valve vault room.smallsteamleak,modifywhenmanual If dispatched previously, report leak much worse rip attempted. when asked.Event#7: TheseIMFRP01Cf:1BOTHREACTORTRIP BREAKERSFAILTOOPEN Malfunctions areONMANUALORAUTOTRIPSIGNALS.ATWSactivewhenthe CONDITION ESTABLISHED.SCENSfileisloaded. When dispatched toIRFRPR05Af:1d:180k:5OPENSBOTHREACTORTRIP BREAKEROpenRxTripIRFRPR05Bf:1d:183k:5 LOCALLY3SECAPART AFTER3MINDELAY. Breakers locally inserttheseremote functions immediately using KeyS Event#8:EventIMFRD09f:1e:7d:10RODSFAILTOMOVEINAUTO10 SECONDS Trigger 10 seconds AFTERTURBINETRIP. after Turbine Trip.Event#9: EventIMFFW04Cf:1e:2MDAFWTO#3S/GLCV-3-148FAILSFULLOPEN.trigger,insertedattimeofSI.Whendispatchedtocheckvalvelocally,wait -3to5 minutes, and inform crew that the valve is full open but not sure what the problem is.If RequestedtocloseIRFFWR05f:Ok:6POSITIONMDAFWISOLATIONVLV-3-826LP3 nanisolvlvforloop3(IsolatesMainandBypass valves)I MDAFW LeV use Key 6 When Dispatched wait-5 min and report closed. I Appendix D Required Operator ActionsFormES-D-2 IOpTestNo.:EventDescription:NRCScenario

1. 4Event#Powerincreaseand2ndMFPTRollPage1of35.....;...----

Time II Position II Console Operator:Noactionrequiredforevent1 Indications Available: None ApplicableApplicant'sActionsorBehavior (Direct load increase from-41%power in accordancewith0-GO-5, SRO Normal Power Operation,beginninginSection5.1,atStep23. NOTEWithverbal approvalfromthe Operations Superintendent,placingthesecondmainfeedpumpin service may be deferred until power is approximately55%(Unit1)or65%(Unit2).Logic prevents opening the standby MFPT condenser isolationvalvesifthepumpis NOTresetpriorto exceeding9millionIbs/hrflowontherunningpump. WHEN approximately40to45%turbineload, THEN SRO PLACEsecondMFPTinserviceby performing the followinq: IF the Operations Superintendent has approved one MFP operation duri,ng, tile power ascension, THEN A.1.RECORO which MFPT is in service.SRO MFPT B.MONITOR loading of the rvlFP in service as load is increased.(StepisN/ASecondMFPTistobeplacedin Service)SRO/BO P WHEN second MFPT is to be placed iin service, THEN PLACE second MFPT in service in accordance with 1..2-50-2/3-1 .(Evaluator Note: The followingstepsarefrom 1-S0-2/3-1Section5.16.4 beginning atstep15.The preceding stepsoftheSOwere previously performedandsnappedinto the Scenario Initial Conditions. I Appendix D Required Operator ActionsFormES-D-2 I (OpTestNo.: Event

Description:

NRCScenario

1. 4Event#Powerincreaseand2ndMFPTRollPage2of35--'--------II Time Position II BOP Applicant'sActionsorBehavior OPEN GovernorValvebyPERFORMINGoneofthefollowing:*IFMCRoperationof Governor Valve Positioner is available, THEN*PLACEtheapplicableGovernorValve PositionertotheRAISEpositiontoopenthesteamchestvalvesand acceleratetheMFPT: MFPT B HAN DSWITCHGVPositioner 1-HS-46-40A POSITION OPEN CAUTIONDONOT increasesecondMFPTspeedfasterthanthemasterspeedcontrolcanmaintainprogram dip.NOTEAsthesecondMFPTisloaded,thefirstMFPTshouldbackdowninload.

(BOP BOP BOP SLOWLYLOADthesecondMFPTtoraiseMFPTspeeduntildemandonMFPTspeedcontrollermatchesthedemandoutputofthefirstMFPT.ENSUREMFPInjectionWaterIntermediate Leakoff PressureforBOTHMFPsisatleast250psig.*[1-PI-54-2],1AMFP AND*[1-PI-54-6],1BMFPENSUREMFPInjectionWaterDifferentialPressureforpumpstartedisequaltoor greaterthan25psid.*[1-PDI-54-1],1AMFP OR*[1-PDI-54-5],1BMFPWHENtheoutputmeterfortheSICforthesecondMFPTmatchestheoutputmeterontheMasterController,THENPLACEthesecondMFPTSICinAUTO. I Appendix D Required Operator ActionsFormES-D-2 IOpTestNo.:EventDescription:NRCScenario

1. 4Event#Powerincreaseand2ndMFPTRoll.....;..Page3of....;3;.;;.5---11 Time II Position IIApplicant'sActionsorBehaviorCLOSEthesecondMFPTdrainvalves1BDrainValves1-HS-BOP46-41CLOSED CAUTION1MFPRecircvalves controllersshouldNOTbeoperatedin AUTOMATICduetothe potentialforisolatingallthree intermediate heaterstringsandresultingMFP damage.CAUTION2 OperationofMFPRECIRCvalveshouldbeperformed slowlyduetoaffectonMFPDP program.ENSURE[1-FCV-3-70]or

[1-FCV-3-84]MFPRecircvalveis BOP CLOSEDandinMANUAL. CAUTIONFailureto readjust the minimumspeedonthesecondMFWPcouldresultinthesecond MFWPbeingunableto supply adequatefeedflowintheeventthefirstMFWPtrips. NOTE The followingstepmaybeperformedinparallelwithpowerincreasebutshouldbe completed prior to exceeding55%power.WHENMFWPspeedcontrollers [1-SIC-46-20A] and[1-SIC-46-20B]areinAUTO,THENPERFORMthefollowingto adjusttheminimumspeedonthesecondMFWP:

• VERIFYbothMFWPspeed controllerbiassettingsat50%.
• NOTIFYMIGtoslowly adjustthehandspeed changer onthesecondMFWPsothattheMFWPspeedsareequal.

Continuedirectingpowerincreasein accordancewith0-GO-5. SROUsingDilution,RodWIDand TurbineloadincreasetomaintainTavgonprogramandAFD. Evaluator Note:ThefollowingStepsarefrom 0-SO-62-7 Boron Concentration Control,Section6.2, DiluteCAUTION1:WhenmakinganRCSdilutionof 2..3000gallons,itshouldbedonein batcheswithanRCSboron concentrationverificationatthe halfwaypoint(e.g.,1500 gallons).Allowatleast15 minutesbetweenbatches. I Appendix D Required Operator Actions Form ES-D-2 IOpTestNo.:EventDescription:NRCScenario

1. 4Event#Powerincreaseand2ndMFPTRollPage4of35-----

Time II Position IIApplicant'sActionsorBehavior CAUTION 2;Returning the Boric Acid Blender to service afterunplugging,cleaning, or maintenanceonthe Boric Acid System could introduce debris, sludge,airor chunks of solidifiedboronintotheCCP suction resulting in pump damage.Extreme care must be exercised to properlyflushthe Boric Acid Blender system following an outage.NOTE1:Ifan excessive amount of dilution is required (plant startup), the pressurizer heaters should be energizedtocause pressurizer spray operation for equalizing boron concentrationinRCSand pressurizer. NOTE2:Dilute modewillbeused anytime a long-term positive reactivity addition is desired.The operator shouldusethe normal dilute mode whenever conditions permit.RO ENSUREunitis NOTina Tech SpecorTRM action that prohibits positive reactivity additions. NOTE: HUT level increaseof1%isequalto1380 gallons (TI-28 fig.C.21)ENSURE sufficient capacfty avai:lable in the HUT selected to receive expected amounts of cvcs ietoown: (NfA jf not used)RO HUT LEVEL INITriALS A%B%RO ENSURE makeup system is aligned for AUTO operation in accordance with Section 5.1.RECORD the quantity of dilution water required to achieve RO desired boron concentration using Appendix D.(N/A for minor power changes)NOTEDueto eyeball interpolation the verified calculation may slightly differfromthe initial calculation. The following signoff indicates that any differencesinthetwo results have been discussedandare close enoughtobe considered validated. PERFORM Appendix I Independent Verification of Calculation SRO for AmountofBoricAcidor Primary Water.(N/AifApp.Dwas performedbySROto verifydatafromRx Engineering)(Step not required provided in shift turnover package)RO PLACE[HS-62-140A], Boric Acid Supply to Blender Flow Control Switchtothe STOP position. I Appendix 0 Required Operator Actions Form ES-D-2 IOpTestNo.:EventDescription:NRCScenario

1. 4Event#Powerincreaseand2ndMFPTRollPage5of35-----""";";'--11 Time II Position IIApplicant'sActionsorBehavior (RO PLACE[HS-62-140B], CVCS Makeup Selector Switchtothe DILUTE position.RO ENSURE[HS-62-140D],BoricAcidValvetothe Blender is CLOSED(GreenlightisLIT).

RO SET[FQ-62-142], Batch Integratorforthe desired quantity.NOTE: Primary Water Flow Controller [FC-62-142] receives its referencesignal(70 gpm)from setpoint potentiometer (dial indicator)locatedonpanelM-6.A setpoint of 35%correspondstoa70gpm primary waterflowrate.RO ADJUST[FC-62-142], Primary Makeup Water Flow Controllerforthe desiredflowrate.RO PLACE[HS-62-140A],BoricAcid Supply to Blender Flow ControlSwitchtothe START position.NOTE: Flow oscillations and/or erratic controller responsemayrequire manual operation of Primary Water Flow Controller [FC-62-142]untilstable conditions exist.VERIFY the following; RO[a)Inlet to top of VCT[FC'J-62-128) is OPEN.[b]Primary Water flow by (FUi2-142A] OR (FO-'62-142l NOTE: Alternate dilutioninsmall amounts is acceptableona regular basis, provided no significant changesinseal water temperatureorseal leakoff are indicated. Batchesof5to10 gallons maybeadded through FCV-62-144ona frequencynotto exceedonceper 30 minutes.ICSpointsforNo. 1 seal leakoffsandseal water temperaturesontheRCPs should be monitored durinq and after dilution.U: primary water addition to tne bottom of the VeT n::cv-62-144]is desired, THEN[a]CLOSE[FOJ-62-128] with[HS-62-1231 RO OPEN with[HS-62-1441. [b][el VER1FY Primary Water flow by (FI.",62-'142A] OR (FO-62-142]. NOTE:Itmaytake approximately 15 minutesbeforeany changes to reactivity are indicated on nuclear instrumentationorRCS temperature indication. RO MONITOR nuclear instrumentation and reactor coolant temperature to ensure the proper response from dilution. I Appendix D Required Operator ActionsFormES-D-2 IOpTestNo.:NRCScenario

1. 4 Event#.-;...Page6 of 35 Event

Description:

Powerincreaseand 2ndMFPTRollTimePosition Applicant'sActionsor Behavior ((IF[L1-62-129] , VolumeControlTank Level, increases to 63 RO percent, THEN ENSURE[LCV-62-118], Volume Control TankDivertValve OPENS to divert excess watertothe Holdup Tanks.WHEN dilldion is complete, THEN (a]PLACE[HSc62-140A), Boric Acid to Blender Flow Control Switch to the STOP posnioo.[b]IF[FCV-62-144) was previously OPENED, THEN RO Cl.OSE (FeV-62-144]with[HS-62-144). [e]VER.IFY no primary water flow on either (FI-62-142AJ OR (FQ-62-142]. Ed]ENSURE[FCV-6.2-128] is CLOSED.Lead Examiner may direct initiationofthe next event at his discretion. Steps on thenexttwo pages are associated with performance of repetitive dilutions or maynotbe performeduntilall dilutions are complete.RO[17]IF power increase in progress and additional dilutions will be required,THEN use this table to re-perform steps[4]through[18]. I Appendix D Required Operator Actions Form ES-D-2 I Op TestNo.:NRC Scenario#4 Event#-.;..Page 7 of 35 Event

Description:

Power increase and 2nd MFPT Roll Position A licant's Actions or Behavior (STEP[4]RECORD the quantit]'of dilution water required to achieve desired boron concentration using Appu,mdix D.[5]PERfORM Appendix l, IV of Calculation for amount of SA or PV![0]PLACE fHS-6:l-140Al Boric Acid Supp'ly to Blender Flow Control Switch to the STOP position.'[1]PLACE eves Makeup Selector Switch to the DILUTE positiofL[3]ENSURE fHS-62-140Dj Boric Acid Valve to Blender is CLOSED (Green light lIT}.[9]SET fFQ-62-1421, Batch integrator for the desired quantity.[10]ADJUST[fC-62-142], Primary Makeuptater flow Controller for the desired flow rate.[11]PLACE[HS-62-140A), 5A Suppl'y to mender flow Control Switch to START.[12]VERIFY the foHowing:[a]InIet to top of VCT[FCV-62-128] is OPEN.[b]Primary V'later flmv by[fI-6Z-142A] or[FQ-62-1421 [13]IF PV'V'addition to top afVCT[FCV-62-128J. is not warranted, but PW addition to the bottom of the\lCT[FCV-62-1441is desired, THEN[a)CLOSE[FC\}-62-128]with [HS-62-128] [b)OPEN[FCV-62-144] with[HS-62-144]. [e]VERIFY Primary l/<iater now by[FI-62-142A J or[FQ-62-1i421 [14]MONnOR nuclear instrumentation and reactor coolant temperature to ensure the proper response from dilution,[15]IF ILI-6l-US], VCTleveI, increases to 63 percent, THEN ENSURE VCT Divert Valve, OPENS[.0 divert excess water to the HUTs.'[16]WHEN dilution is complete, THEN[a]PLACE fHS-62-140Al. Boric Acid to Stender flow Control S'N/teh ta STOP[b)IF[FCV c62-144]was previously OPENED, THEN CLOSE[FO/-62-144] 'tlith[HS-62-144]. [e]VERIFY no primary vilater flow on either IF/c62-14M]or[FQ c02-142].[d)ENSURE ifCV-62-128] is CLOSED.1'" 2"Y J'"00000 D f J!CVCV fa.C¥f J!7cv 7*-;:;re;-f!!rMc't't---cv00 D00 D DOD DOD DOD DOD DOD DOD DOD DOD[18]IF step[17]wilf: be repeated, THEN P:ERfORM the foHmvil1g: [a]PLACE[HS-62-140Bl, eves Makeup Selector SWitch to lheAUTO posmon.[13]PLACE[HS-62-140Al, SA to Blender Flow Control Switch to START position.[el.ENSURE dilution is logged in Hnit Narrative Log.REALIGN the blender controls for AUTO makeuptothe RO eves in accordancewithSection5.1 RO ENSURE dilution(s) is ioqcedinUnit Narrative Log. I Appendix 0 Required Operator ActionsFormES-D-2 IPowerincreaseand2ndMFPTRoll (OpTestNo.:EventDescription:NRCScenario#4 Event#-.;..Page8 of 35 Time II Position II Applicant'sActionsorBehavior ((NOTE Sample maybeobtainedatnormalRCSsampleintervalsprovidedtheunitisat powerandtheunitresponsefollowingthedilutionisas expected.IFRCSboronsampleisrequired, THEN NOTIFYChemLabtoobtainRCSboronsample. I Appendix D Required Operator Actions Form ES-D-2 IOpTestNo.:NRCScenario

1. 4Event#2EventDescription:ControllingPressurizerLevelChannelFailsLow Time II Position II Applicant'sActionsorBehavior (Booth Instructor:

When directed, initiate event 2 Indications available: 1-AR-M5-A, C3, PRESSURIZER LEVEL HIGH-LOW 1-AR-M5-A, E3, PRZRLVLLOW HEATEROFF&LETDOWN SECURED 0-AR-M27B-B, A5, LETDOWN HX OUTLET FLOWITEMP ABNORMAL Crew Refertoalarm response procedures Direct entrytoAOP-1.04, Pressurizer Instrument Malfunction, US section 2.2 NOTE: Appendixes"I"isa layoutofPZRlevelcontrolprovidedfor operator reference. CHECK L1-68-339 indicates NORMAL.(NO)PERFORM the following: RO*ENSURE LEVEL CONTROL CHANNEL SELECTOR switch XS-68-339EinL T-68-335&320.*ENSURE LEVEL REC CHANNEL SELECTOR switch XS-68-339B in LT-68-320 or LT-68-335. CHECK letdown IN SERVICE.(NO)RO*RESTOREletdownUSING EA-62-5, Establishing Normal ChargingandLetdown. EvaluatorNote:The following stepsarefrom EA-62-5 performedbytheROto reestablish Letdown.SRO may continue in AOP-I04withTech Spec Evaluationetc..NOTE EA-62-3, Establishing ExcessLetdown,maybeutilizedifNormal Letdown cannot be established. I Appendix D Required Operator ActionsFormES-D-2 IOpTestNo.:NRCScenario

1. 4Event#2EventDescription:ControllingPressurizerLevelChannelFailsLow Time II Position IIApplicant'sActionsorBehavior (IFchargingflowNOTestablished,THEN ROPERFORMSection4.2.(Chargingflowis established)

VERIFY pressurizer level greaterthan17%.ROENSUREletdownorificeisolationvalvesCLOSED:

• FCV-62-72 RO*FCV-62-73*FCV-62-74OPENletdownisolationvalves:
• FCV-62-69 RO*FCV-62-70*FCV-62-77 NOTEPlacingcooling waterontheLetdownHeat Exchangerpriortorestoringletdownflow should prevent TIS-62-79B/Afromactuatingandfullyopening TCV-70-192.

PLACE[HIC-62-78]inMANUAL,ANDOPEN [TCV-70-192] to RO-50%.PLACEletdownpressure controller [PCV-62-81] in MANUAL RO and ADJUSToutputbetween40and50%, (50%-60%open).ADJUSTchargingflowas necessarytopreventflashinginthe ROletdownline.OPENletdownorificeisolationvalvesasneeded:

• FCV-62-72 RO*FCV-62-73*FCV-62-74 I Appendix D Required Operator ActionsFormES-D-2 IOpTestNo.:NRCScenario

1. 4 Event#2 of 35 Event

Description:

Controlling PressurizerLevelChannelFailsLow Time II Position II Applicant'sActionsor Behavior NOTENormalletdownpressureis325psigatnormaloperating temperature. ADJUSTletdownpressure controller [PCV-62-81] output ROtoobtaindesiredpressure. ADJUSTletdownpressure controller [PCV-62-81] setpoint ROtomatchexistingpressure. ROPLACEletdownpressure controller [PCV-62-81]inAUTO.NOTENormalletdown temperature is-100°F.ADJUST[HIC-62-78A]toobtaindesiredletdown temperature, ROasindicatedon [T1-62-78]. RO PLACE[HIC-62-78A]inAUTO.NOTE Letdown temperaturemayswingduetorepeated actuation of TIS-62-79B/A, whichcausesletdown temperaturecontrolvalve TCV-70-192tofullyopen. IF necessarytostabilizeletdown temperature, THEN PERFORMthefollowing:

• PLACE[HIC-62-78A]

in MANUAL and ADJUST RO controlleroutputinOPEN direction.

• WHENletdownheat exchanger outlet temperature isstabilizedat approximately100°F,THENPLACE[HIC-62-78A]inAUTO.ENSUREhigh temperature divert valve[HS-62-79A]inDEMIN RO position.ADJUSTchargingandletdownas necessarytomaintainRCP ROsealinjectionflowand pressurizer level.

I Appendix DRequiredOperatorActionsFormES-D-2 I OpTestNo.:NRCScenario

1. 4Event#2 of 35 Event

Description:

Controlling PressurizerLevelChannelFailsLowTimePosition Applicant'sActionsorBehavior (EVALUATEthefollowingTechSpecsforapplicability:

• 3.3.1.1(3.3.1), Reactor Trip System Instrumentation.

Enters action 6.*3.3.3.5RemoteShutdownInstrumentation US*3.3.3.7 Accident Monitoring Instrumentation. Enters action 2.*3.4.4 Pressurizer. For Heaters, momentary entry for action (a)due to cutoff.ROENSUREpressurizerheatersrestoredtoservice. CAUTION:RCSpressurechangesandchangesinRCSboronconcentration(dueto differencesbetweenpzrandRCSboron)mayimpactcorereactivity.MONITORreactorpower:a.CHECKreactorinMode1or2. ROb.MONITORcorethermalpowerforunexpectedchanges. NOTE:IfperformingAOPinconjunctionwith AOP-1.11foranEagleLCPfailure,thenactionstohardtripbistablesshouldbedelayeduntilEaglesystemresetisattempted.Actionstohardtripbistablesmustbecompletedwithin6hoursUNLESSaffectedloopisrestoredtooperablestatusbyresettingEaglerack. NOTIFY 1MtoremovefailedpressurizerlevelchannelfromserviceUSINGappropriateAppendix:

• L-68-339AppendixI When Letdown is restored and Technical Specifications are addressed, the Lead Examiner may cue the next event IAppendixDRequiredOperatorActionsFormES-D-2 IOpTestNo.:NRCScenario

1. 4Event#3of35EventDescription:SteamGenerator#3NRLevel TransmitterfailslowTime"Position IIConsoleOperator:Whendirected,initiateevent3 Applicant'sActionsorBehavior Indications available:

S/G Level instrumentLT-3-106indicates downscaleAlarm:XA-55-6B, 0-4"LS-3-106B STEAM GENERATORLOOP4LOWLOWWATERLEVEL" Alarm: XA-55-3C, 0-2"EAMITTOSGLOOP4LOLOLEVEL" CREW SROReferto AnnunciatorResponse.Diagnosefailure.(Evaluator Note:NoPlant transientoccursduetomedianselectioncircuit).Enteranddirectactionsof AOP-1.06,Section2.2. EVALUATEthefollowingTechSpecsforapplicability:*3.3.1.1(3.3.1),ReactorTripSystem Instrumentation*Action9Appliesfor S/G WaterLevelLowLowTrip)*3.3.2.1(3.3.2),Engineered SafetyFeatureActuation System Instrumentation*Action17AppliesforTurbineTripandFWIsolation from S/GwaterLevelHighHigh. SRO*Action36appliesfor S/G waterlevellowlowAFW start*Action22cappliesforP-14Interlock,noadditionalactionsrequired.*3.3.3.5,RemoteShutdown Instrumentation -N/A*3.3.3.7,AccidentMonitoring Instrumentation-NA IAppendix0RequiredOperatorActionsFormES-D-2 I Op TestNo.:NRC Scenario#4 Event#3 Page 14 of 35 Event

Description:

Steam Generator#3NR Level Transmitter fails low Time II Position II Applicant's Actions or Behavior NOTE: IfperformingAOPinconjunctionwith AOP-1.11foranEagleLCPfailure,thenactionstohardtripbistablesshouldbedelayeduntilEaglesystemresetisattempted.Actionstohardtripbistablesmustbecompletedwithin 6 hoursUNLESSaffectedloopisrestoredtooperablestatusbyresettingEaglerack. NOTIFY 1MtoremovefailedS/Glevel instrumentfromservice USING appropriate Appendix: L-3-106-AppendixVWhenTechnical Specificationsareaddressed,theLead Examinermaycuethenextevent Appendix 0RequiredOperatorActionsFormES-D-2OpTestNo.: NRC Scenario#4 Event#4 Page15of 35--Event

Description:

FWHdrPress TransmitterFailslow (PT-3-1)Time II Position II Applicant'sActionsor Behavior Console Operator: When directed, initiate Event 4 Indications available: MFW Pump speed increases increasing FW flow to all SIG Hotwell level decreases due to increased FW demand Alarm: XA-55-3C, C-1"PS-3-4NO1FWHTRPRESSURE HI" Rods may step out due to this failure.Evaluator Note:Forthisevent,crewmayrespondperthe Annunciator ResponseProcedureorAOP-S.01Section2.2.Botharenotrequired.TheARPisoutlinedfirstthentheAOP. (BOP Crew BOPTakeManualControlofMFPMasterSpeedcontrolandreduceFeedwaterpressureandFlow.RefertoannunciatorResponseprocedure. [1J DISPATCH operator to#1 feedwater heaters to verify the following valves open: a.1-PSY-3-4 1:1'-1-PSY-3-14 c.1-PSV-3-24[2]REDUCE feedwater pressure to 00 psrc9.[3J WHEN pressure reduces to-1100 psig, THEN VERIFY the above mentioned PS\t's dosed.[4]IF alarm still illuminated or by SRO decision, THEN GO TO AOP-SJ)1 , Loss of Normal Feedwater. SROImplementAOP-S.01Section2.2.(Optional) Appendix 0NUREG1021Revision9 Appendix D Required Operator Actions Form ES-D-2OpTestNo.:NRCScenario

1. 4 Event#4Page16of35

--EventDescription:FWHdrPress TransmitterFailslow(PT-3-1) Time II Position IIApplicant'sActionsorBehavior NOTE: Step 1 is an IMMEDIATE AGTION_(BOP RESTORE feedwater pressure: a.PLACE affected MFP speed controller(s} ill MANUAl:*MfPT 1A{2A)&1B(28)Speed Control OR*MfPT 1A(2A)Speed Controller OR*MFPT 18(2B)Speed Controller b.ADJUST speed on affected MFP(s)to restore feedwater pressure to normal (-1040 psig at pov,fer).DETERMINE if MfP trip IS needed: Appendix D a.CHECK BOTH MFWPs in service.b.IF..1FW pump trip is needed due to loss of speed control, BOP THEN PERFORM the following: 1)TRIP affectedMFP. 2}GO TO applkabJe section: (Step ShouldbeN/A)Feed flow transients may impact core thermall power.NUREG 1021 Revision 9 Appendix 0 Required Operator ActionsFormES-D-2OpTestNo.: NRC Scenario#4 Event#4Page17of35----EventDescription:FWHdrPress TransmitterFailslow(PT-3-1) Time I Position II Applicant'sActionsorBehavior BOP MAINTAIN steam ,generator leveI(s)on proqsam.NOTE: Appendix C may be used to determine program feedwater DIP for current power.MAINTAIN MFP dIscharge pressure BOP on program USING res or ava;llable control board indicaticns. CREW INITIATE repairs on failed equipment When Plant is stable with MFP speed control in manual, Lead Examiner may cue the next eventathis discretion. Appendix 0 NUREG 1021 Revision 9 Appendix D Required Operator ActionsFormES-D-2 Op TestNo.:NRC Scenario#4Event#5 Page 18of35--Event

Description:

SmallSteamLeakOutside containmentonloop3 I Time II Position I Applicant's Actions or Behavior Booth Instructor: When directed,initiateEvent5 Indications available:NISPower Increasing CondenserHotwellleveldecrease Appendix D Crew SRO SRO Diagnose Secondaryleakoutside containmentbasedonNISpowerincrease, containment conditions normal, Hotweillevel decreasinq EnteranddirectactionsofAOP-S.05,SteamLineor Feedwater Line BreaK/Leak. MONITOR actions necessary to protect personnel:

• IF immediate isolation of steamlfeedwater lines is needed to protect personnel, THEN PERFORM the following:

a)TRIP the reactor.b)WHEN reactor is tripped, THEN CLOSE MSIVs and FEED REG VALVES.e)GO TO E-{l, Reactor Trip or Safpfu IntpctiorLNUREG1021Revision9 (Appendix D Required Operator ActionsFormES-D-2 Op TestNo.:NRC Scenario#4Event#5 Page 19of35--Event

Description:

SmallSteamLeak Outside containmentonloop3 I Time II Position I Applicant's Actions or Behavior MONITOR reactor power STABLE or CONTROLLED.(RNaMayBeperformedlaterwhenleakincreasestobreak)PERfORM the following: RO a.TRIP'the reactor.D.WHEN readoris tripped, THEN CLOSE MSiVs.c.GO TO E-O, ReadorTrip or Safety RO MONITORreactorpowerlessthan100% BOP MONITOR steam generator levels STABLE on program.RO MONITORT-avg/T-refdeviationlessthan5°F. EVALUATE EPIP-1 , Emergency Plan Initiating Conditions SRO Matrix.(Notify Shift ManaqertoEvaluate REP)MONITOR nomel'l level STABLE BOP*VERIfY LCV-2-9 maintaining hotwell level In AUTO.(RNa Maybe required)Appendix DNUREG1021Revision9 (Appendix DRequiredOperatorActionsFormES-D-2OpTestNo.:NRC Scenario#4 Event#5 Page 20of35--Event

Description:

SmallSteamLeakOutside containmentonloop3 I Time II Position II Applicant's ActionsorBehavior INITIATE makeup to homel:1 att 00%[M-2l a.PLACE UC-2-9, Auto Makeup, in MANUAL D.OPEN lCV-2-9 USING UC-2-9, Auto Makeup, to fm notwell.c.If loss of nomeii level IS imminent, THEN PERfORM the following: 1 TRIP the reactor.2.WHEN reactor IS tripped, THEN CLOSE fv1SIVs.3.GO TO E-O, Reactor Trip or Safety Injection. NOTE Tech Spec lCO 3J'i 1.4 action is applicable if containment pressure exceeds 0.3 pSlig.RO MONITOR containmentpressureSTABLE. CHECK the fonowing containment parameters NORMAL: BOP/RO*Contaiinment temperature

• Containment humidity Lead Examiner may initiatenexteventto increaseleaktoalargebreakator before this point whencrewhas determinedthereisa secondary leak outside containment.

Appendix DNUREG1021Revision9 ((Appendix D Required Operator ActionsFormES-D-2OpTestNo.:NRC Scenario#4 Event#6,7,8,&9 Page 21of35--Event

Description:

Steamleakincreasestolargebreak,ATWSoccurs,Rodsfailtomoveinauto(5secdelay)andMDAFWpumpLviControlVlvtofaultedS/Gfailsopen. Time II Position II Applicant'sActionsor Behavior Booth Instructor: When directed,initiateEvent6 Indications available:SteamLeak IncreasestoLargeBreak:

• NIS Power Increasing
• HotwellLevel decreasing
• ATWS:*Reactor Trip breakersstillclosedafter attemptingtoopenwithbothRxTrip switches.*RodsFailtoMoveinauto:
• Rodsstopmoving5seconds followingturbinetrip.

Motor Driven AFWPumpLevelcontrolvalvetoLoop3failsopen:

• Red position indicatinglightremainsonwhen attempting to manually close*ContinuedFlowtoFaulted S/G when attempting to manually isolate.DirectmanualRxTripandMSIVclosurebasedon AOP-S.05 SROcriteria.(RxPowernotstableorLossofHotwellLevel Imminent)RO Identify ATWS afterattemptingbothRxtripSwitches.

USDirectentrytoFR-S.1,NuclearPower Generation/ATWS CAUTION:RCPsshouldNOTbetrippedwithreactor power greater than 5%.NOTE:Steps1and2are immediateactionsteps. Appendix DNUREG1021Revision9 Appendix D Required Operator ActionsFormES-D-2OpTestNo.:NRCScenario

1. 4 Event#6,7,8,&9 Page 22of35 Event

Description:

Steamleak increasestolargebreak,ATWSoccurs,Rodsfailtomoveinauto(5secdelay)andMDAFWpumpLviControlVlvtofaultedS/Gfailsopen. I Time II Position II Applicant's ActionsorBehavior I Evaluator Note:CrewmaycloseMSIV'sand attempttoisolateAFWtofaulted S/.G WHEN REACTOR IS TRIPPED during performanceofFR-S.1.When attempting to isolateAFW,levelcontrolvalvewillnotcloseandcrewmayelecttostop1BAFWPumpatthattime. (CRITICAL TASK RO VERIFYreactorTRIPPED:

• ReactortripbreakersOPEN
• ReactortripbypassbreakersOPENor DISCONNECTED*Neutronflux DROPPING*RodbottomlightsLIT*Rodposition indicatorslessthanorequalto12steps.(RNOrequired)

TRIP reactor.IF reactortripbreakerswillNOTopen, THEN MAINTAINautoormanualrodinsertionatmax achievablerateUNTILrodsareatbottom (Should identify rodfailingto insert automatically 10 sec afterturbineTripinitiates rod insertion and begin manually inserting rods)CriticalTask"Priortocompletion ofFR-S.1step 4" VERIFYturbineTRIPPED: Appendix DBOP*ALLturbinestopvalves CLOSEDNUREG1021Revision9 ((Appendix D Required Operator ActionsFormES-D-2OpTestNo.:NRCScenario

1. 4Event#6,7,8,&9Page23of35 Event

Description:

Steamleak increasestolargebreak,A lWSoccurs,Rodsfailtomoveinauto(5secdelay)andMDAFWpumpLviControlVlvtofaulted S/Gfailsopen. Time II Position II Applicant'sActionsor Behavior CHECKAFWSystemoperation:MDAFWpumpsRUNNINGTDAFWpumpRUNNINGasnecessary.(Not Running TaggedOOSin initial conditions) BOPMDAFWLCVsinAUTO.TDAFWLCVsOPEN.MDAFWpumprecirculationvalves FCV-3-400andFCV-3-401 CLOSED.CRITICAL EMERGENCY BORATERCSby performing the following: TASKENSUREatleastoneCCPRUNNING. a.b.INITIATE EmergencyBorationUSINGEA-68-4.

• PLACEboricacid transferpumpsinfastspeed.
• ADJUST emergencyboratevalve

[FCV-62-138] toobtainboricacidflowbetween35gpmand150gpmon [FI-62-137 A].*MONITOR emergencyborationflow: a.CHECK emergencyborationflow establishedon[FI-BOP 62-137A].b.IFboricacidflowlessthan35gpm,THEN(N/A)c.VERIFYchargingflowpath established:

• FCV-62-90OPEN
• FCV-62-91OPEN
• FCV-62-86orFCV-62-85OPEN.

d.CHECK pressurizerpressurelessthan2335psig. CriticalTask"Priorto completion ofFR-S.1step 4" Appendix DNUREG1021Revision9 (Appendix D Required Operator ActionsFormES-D-2OpTestNo.: NRC Scenario#4 Event#6,7,8,&9 Page 24 of 35 Event

Description:

Steamleak increasestolargebreak,ATWSoccurs,Rodsfailtomoveinauto(5secdelay)andMDAFWpumpLviControlVlvtofaultedS/Gfailsopen. Time II Position II Applicant'sActionsor Behavior VERIFY ContainmentPurgeisolated: (Crew Crew Crew VERIFY containmentpurgeandvent dampers (System 30)CLOSED.[Panel6Kand6L] MONITORSINOT actuated:*S.1.ACTUATED permissiveDARK[M-4A,D4].(RNarequiredIfSIoccursduring performanceofFR-S.1)IFSI actuated, THEN PERFORM the following WHILE continuing with this procedure:

a. Reactor Trip or Safety Injection, Steps 1 through 4.Reactor TRIPPED.(RNa)PERFORMthefollowing:

• DISPATCH personnel to locally open reactor trip breakersandMGset output breakers[MGSetRoom,AuxBldgel.759].
• DISPATCH personnel to locally open breakerstoMGsets[480VUnitBoardsAandB].(EvaluatorNote:Crew will likely have dispatched personnel priortoreachingthisstep)

Turbine TRIPPED: Appendix DBOP*ALL turbinestopvalves CLOSED.NUREG1021Revision9 (Appendix D Required Operator ActionsFormES-D-2OpTestNo.:NRCScenario

1. 4 Event#6,7,8,&9Page25of35 Event

Description:

Steamleakincreasestolargebreak,ATWSoccurs,Rodsfailtomoveinauto(5secdelay)andMDAFWpumpLviControlVlvtofaultedS/Gfailsopen. Time I Position II Applicant'sActionsor Behavior IMONITORreactorsubcritical: RO*Powerrangechannelslessthan5%.

• IntermediaterangeSURNEGATIVE.SROGOTOStep19.

SRO19.ENSUREstatustreemonitoringinitiated.MONITORborationterminationcriteria:

• NOTIFYChernLabtosampleRCSboron concentration.

RO*CHECKforallofthefollowing: 0allcontrolrodsFULLYINSERTED 0 RCS temperature greaterthan540°F 0noRCSdilutionhasoccurred. WHEN emergencyborationisnolongerneeded,THENSTOP RO/US emergencyborationUSINGEA-68-4, Emergency Boration.SRORETURNTOprocedureandstepineffect. SRODirectstransitionto E-O, ReactorTriporSafetyInjection VERIFYreactorTRIPPED:

• ReactortripbreakersOPEN
• Reactortripbypassbreakers DISCONNECTED or OPEN RONeutronfluxDROPPING
  • RodbottomlightsLIT
• Rodpositionindicatorslessthanorequalto12steps.

Appendix DNUREG1021Revision9 ((Appendix DRequiredOperatorActionsFormES-D-2OpTestNo.:NRCScenario

1. 4 Event#6,7,8,&9 Page 26 of 35 Event

Description:

Steamleak increasestolargebreak,ATWSoccurs,Rodsfailtomoveinauto(5secdelay)andMDAFWpumpLviControlVlvtofaultedS/Gfailsopen. Time II Position II Applicant'sActionsorBehaviorVERIFYturbineTRIPPED: BOP*TurbinestopvalvesCLOSED.VERIFYatleastonetrainofshutdownboardsENERGIZED. BOPDETERMINEifSIactuated:

• ECCSpumpsRUNNING.

RO*AnySIalarmLIT[M-4D](May manually actuate 51 if not already actuated.Auto 51 will likely occur when MSIV's are closed after Rx Trip in FR-S.1 and faulted S/G continues to depressurize)PERFORMES-0.5,EquipmentVerificationsWHILEcontinuing BOPinthisprocedure.(Atend of scenario)DETERMINEifsecondaryheatsinkavailable: a.CHECKtotalAFWflowgreaterthan440gpm. b.CHECKnarrowrangelevel greaterthan10%[25ADV] ROinatleastoneS/G. c.CONTROLfeedflowtomaintainnarrowrangelevelbetween10%[25%ADV]and50%inallS/Gs. Appendix DNUREG1021Revision9 Appendix DRequiredOperatorActionsFormES-D-2OpTestNo.: NRC Scenario#4Event#6,7,8,&9 Page 27of35--Event

Description:

Steamleakincreasestolargebreak,ATWSoccurs,Rodsfailtomoveinauto(5secdelay)andMDAFWpumpLviControlVlvtofaultedS/Gfailsopen. I Time II Position II Applicant'sActionsorBehavior ICHECKifmainsteamlinesshouldbeisolated:a.CHECKifanyofthefollowingconditionshave occurred:*AnyS/Gpressurelessthan600psigANDSTEAMLINEPRESSISOLSIBLOCKRATEISOLENABLEpermissiveDARK[M-4A,A4] OR*AnyS/Gpressuredropping UNCONTROLLED. OR (RO*PhaseBactuationb.ENSUREMSIVsandMSIVbypassvalvesCLOSED.(May have already closed MSIVs)c.ENSURE applicabJe Foldout Page actions COMPLETED.(Includes AFWisolationto faultedS/Gifnot previously performed)NOTE:LossofsealinjectionflowcouldadverselyaffectRCPseals. (Appendix D ROCHECKRCPtripcriteria:a.CHECKthefollowing:*RCSpressurelessthan1250psig.(NO) AND*AtleastoneCCPORSIpumpRUNNINGNUREG1021Revision9 Appendix DRequiredOperatorActionsFormES-D-2OpTestNo.:NRCScenario# 4Event#6,7,8,&9 Page 28of35 Event

Description:

Steamleakincreasestolargebreak,ATWSoccurs,Rodsfailtomoveinauto(5secdelay)andMDAFWpumpLviControlVlvtofaulted S/Gfailsopen. Time II Position II Applicant'sActionsor Behavior b.IF eooldown continues, THEN CONTROL toml feed flow USING Manual Control of AFW FIOVII,MONITORRCStemperatures:*IFanyRCPrunning, THENCHECKT-avgstableatortrendingbetween547degreesFROand552degreesF.(RNO)IF temperature less than 547°1='and dropping, THEN PERFORM the following: 3, ENSURE steam dumps and atmospheric raners CLOSED.BOP (ROCHECKpressurizerPORV's,safeties,andsprayvalves:a.PressurizerPORV'sCLOSED.b.PressurizersafetyvalvesCLOSED.c.NormalsprayvalvesCLOSED.d.PowertoatleastoneblockvalveAVAILABLE.e.AtleastoneblockvalveOPEN. Appendix DNUREG1021Revision9 ((Appendix D Required Operator ActionsFormES-D-2OpTestNo.:NRCScenario#4 Event#6,7,8,&9 Page 29 of 35 Event

Description:

Steamleakincreasestolargebreak,ATWSoccurs,Rodsfailtomoveinauto(5secdelay)andMDAFWpumpLviControlVlvtofaultedS/Gfailsopen. Time II Position II Applicant'sActionsor Behavior CHECK S/G secondary pressure boundaries INTACT:*All S/G pressures CONTROLLEDorRISING(NO)

• All S/G pressures greater than140psig.(RNO)RO/SRO PERFORM the foliOViiing:

a..M ONITORstalus trees.b.GO TO E m2.Faulted Steam Generator Isolation.EnsureStatusTreesmonitoringandDirectentrytoE-2, SROFaultedSGIsolation.(Status Tree monitoring should already be implemented due to previous transition to FR-S.1)CAUTION UnisoiaUng a faulted SlG or secondary break should NOT be considered UNLESS needed for ReS cooldown.CHECKMSIVsandMSIVbypassvalvesCLOSED. RO/BOP (MSIV's should already be closed shortly after Rx Trip in FR-S.1 or in E-O per foldout page)CHECK ANY S/G secondary pressure boundary INTACT: RO/BOP*Any S/Gpressurecontrolledor rising.Appendix DNUREG1021Revision9 Appendix DRequiredOperator ActionsFormES-D-2OpTestNo.: NRC Scenario#4 Event#6,7,8,&9Page30of35 --Event

Description:

Steamleak increasestolargebreak,ATWSoccurs,Rodsfailtomoveinauto(5secdelay)andMDAFWpumpLviControlVlvtofaulted SfGfailsopen. Time II Position II Applicant's Actions or Behavior IDENTIFY Faulted S/G(s): CHECK S/G pressures:*Any S/G pressure DROPPINGBOPinanuncontrolledmanner. OR*Any S/G pressurelessthan140psig. Caution: Secondaryheatsinkrequiresatleastone S/G available. Caution:IsolatingbothsteamsuppliestotheTDAFWpumpwhenitistheonly sourceoffeedflowwillresultinlossof secondaryheatsink.Evaluator Note:AFWmayhave previouslybeenisolatedper E-O fold-outpage.Ifnot previously performed,1BAFWpumpwillbestoppeduntillocalisolationofloop3AFWLCVis performedsinceitfailedopen) CRITICAL TASK Appendix D ROIBOP ISOLATE Faulted S/G(s):*ISOLATE MFW.Evaluator information Loop 3 Valves: Main FeedRegValve3-90 Main Feed Reg BypassValve3-90 FW Isolation Valve 3-87 A*ISOLATE AFW.Evaluator information Loop 3 Valves: MD AFWMain3-148 MD AFW Bypass 3-148a TDAFW3-172 (RNO)*CLOSE valves manuallyoflocally*CLOSETDAFWpumpsteamsupplyfromfaulted S/G o FCV-1-15 (S/G1)or FCV-1-16(S/G4).*VERIFY S/GblowdownvalvesCLOSED.

• VERIFY atmosphericreliefCLOSED.

CriticalTask"priortotransitionout of E-2"NUREG1021Revision9 (Appendix DRequiredOperatorActionsFormES-D-2OpTestNo.:NRCScenario

1. 4 Event#6,7,8,&9Page31of35 Event

Description:

Steamleakincreasestolargebreak,ATWSoccurs,Rodsfailtomoveinauto(5secdelay)andMDAFWpumpLviControlVlvtofaultedS/Gfailsopen. Time II Position II Applicant'sActionsorBehavior (ROIBOP BOP Crew CHECKCSTlevel greaterthan5%.VERIFY secondary radiation NORMAL: a.CHECK secondary radiation NORMAL USING Appendix A, Secondary Rad Monitors. A also contained In ES-O.5)O.NOTIFY Ohern lab to take SlG adivity samples.CHECK SI termination criteria: a.RCS suocoo.ling based all.core exit T!Cs 9reater than 40'"'F.b.Secondary heat sink:*Narrow range level in at feast one intact S!G greater than 1 0% ADV]OR*Total feed flow to Intact SIGs greater than 440 gpm.c.ReS pressure stable or rising.d.Pressurizer level greater than 1 0%, ADVj.*.GO TO ES-1.1, Sf Termination. Scenariomaybe terminated when crew transitionstoES-1.1, 51 Termination Appendix DNUREG1021Revision9 (Appendix 0 Required Operator ActionsFormES-D-2OpTestNo.:NRC Scenario#4 Event#ES-O.5Page32of35--Event

Description:

Equipment Verifications Time II Position II Applicant'sActionsor Behavior ES-O.5 Actions CHECKERCWsystemoperation: BOP*VERIFYatleastfourERCWpumpsRUNNING.

• VERIFY DIGERCWsupplyvalvesOPEN.

VERIFYCCSpumpsRUNNING:

• Pump1A-A (2A-A)BOP*Pump1B-B(2B-B)
• PumpC-S.VERIFYEGTSfansRUNNING.

BOP VERIFY generator breakers OPEN.BOP VERIFYAFWpumpsRUNNING: BOP*MDAFWpumps

• TOAFWpump.

Appendix 0NUREG1021Revision9 ((Appendix 0RequiredOperatorActionsFormES-D-2OpTestNo.:NRCScenario

1. 4 Event#ES-O.5 Page33of35--Event

Description:

Equipment Verifications Time II Position II Applicant'sActionsor Behavior NOTEAFWlevelcontrolvalvesshouldNOTberepositionedifmanualactionhasbeentakentocontrolS/Glevels,toestablishflowduetofailure,ortoisolateafaultedS/G. CHECKAFWvalvealignment: a.VERIFYMDAFWLCVsinAUTO. BOP b.VERIFYTOAFWLCVsOPEN. c.VERIFYMDAFWpumprecirculationvalvesFCV-3-400andFCV-3-401CLOSED. VERIFYMFWIsolation:

• MFWpumpsTRIPPED
• MFWregulatingvalvesCLOSED BOP*MFWregulatingbypassvalve controlleroutputsZERO
• MFWisolationvalvesCLOSED
• MFWflowZERO.

MONITORECCSoperation: VERIFYECCSpumpsRUNNING: BOP*CCPs*RHRpumps*SIpumps Appendix 0NUREG1021Revision9 ((Appendix 0 Required Operator ActionsFormES-D-2OpTestNo.:NRCScenario

1. 4Event#ES-O.5 Page34of35--Event

Description:

Equipment Verifications Time II Position II Applicant'sActionsorBehavior VERIFYCCPflowthroughCCPIT.

• CHECKRCSpressurelessthan1500psig.

BOP*VERIFYSIpumpflow.

• CHECKRCSpressurelessthan300psig.
• VERIFYRHRpumpflow.

VERIFYESFsystemsALIGNED:

• PhaseA ACTUATED: 0 CONTAINMENT ISOLATIONPHASEATRAINAalarmLIT[M-6C,B5].

0 CONTAINMENT ISOLATIONPHASEATRAINBalarmLIT[M-6C,B6].

• ContainmentVentilationIsolation ACTUATED: 0 CONTAINMENT VENTILATION ISOLATIONTRAINAalarmLIT[M-6C,C5].

0 CONTAINMENT VENTILATION ISOLATIONTRAINBalarmLIT[M-6C,C6]. BOP*Status monitor panels: 06CDARK 0 60 DARK 06ELIT OUTSIDEoutlinedarea 06HDARK 06JLIT.*TrainAstatuspanel6K: 0 CNTMTVENTGREEN 0PHASEAGREEN

• TrainBstatuspanel6L:

0 CNTMTVENTGREEN 0PHASEAGREEN MONITOR containmentsprayNOTrequired:

• PhaseBNOT ACTUATED BOP AND*Containmentpressurelessthan2.81psig
• Ensure ContainmentSprayisactuated Appendix 0NUREG1021Revision9 (Appendix D Required Operator Actions Form ES-D-2 Op TestNo.:NRC Scenario#4 Event#ES-O.5 Page35of35----Event

Description:

Equipment Verifications I Time II Position II Applicant's Actions or Behavior I VERIFYpocketsumppumps STOPPED:[M-15, upper left corner]*HS-77-410,RxBldgAuxFloorand Equipment Drain BOPSumppumpA*HS-77-411,RxBldgAuxFloorand Equipment DrainSumppumpB. DISPATCH personneltoperformEA-0-1, Equipment Checks BOPFollowingESF Actuation. Appendix D NUREG1021Revision9 SHIFT TURNOVER CHECKLISTPage1of3 Today r8J SM r8J US/MCR Unit 1 r8J UO Unit 1Off-going-Name 0 AUOStationSON r8JSTA(STA Function)AUOCampActionsOn-coming-Name Part1-Completed by Off-going Shift/Reviewed by On-coming Shift: Abnormal Eauioment Lineuo/Conditions: """ tMfJl'IIJ TrainA Week All equipment normal*TDAFW pump was tagged 2 hours ago for repairtotheT&T valve.The packing was blowing excessively. Expected Return to service is 8 hours.uWO 07-080025-000 Total: 0.04 gpm;Identified: 0.02 gpm;Unidentified: 0.02 gpm (today) SHIFT TURNOVER CHECKLISTPage2of3 Today SIITest in Progress/Planned: (Including Need for New Brief)As Needed for Startup.Major Activities/Procedures in Progress/Planned: Plant Startupheldat-41%awaiting availabilityofMFPBforpast72hrs. Currently in 0-GO-5 Section5.1,Step 23.Continue plant startupperRx Engineering Spreadsheet. Spreadsheethasbeenverifiedbythe SRO/ST A.1-S0-62-7 AppendixDandEhavebeen completed. Pre-conditioned Powerlevelis100%. 1-S0-2/3-1 Section5.16.4Startup of Second MFPTisin progress and completethroughstep14.AUO,MIG,andPDM, support are presentattheB MFPT as needed.Radiological Changes in Plant During Shift: Reactor power increase will increase doseratesinside containmentandvarious locationsintheAux.Bldg.See applicableRadCon RWPs fordetailsand entry requirements. TSLCO3.7.1.2.a: TDAFW pump was tagged 2 hours ago for repair to theT&Tvalve.The packing was blowing excessively. Expected Return to service is 8 hours.TS3.3.3.7.18b action 1;Accident Monitoring Instrumentation, ERCW to AFW Valve Position, Turbine Driven Pump.(:lart2-Performed by on-coming shift oReviewofOperatingLogSinceLastShiftHeldor 3Days,WhicheverisLess(N/AforAUO's) oReviewofRounds Sheets/Abnormal Readings(AUO'sonly)ReviewtheFollowingProgramsforChangesSinceLastShift Turnover: oStandingOrders 0 LCO(s)inActions(N/AforAUOs) oImmediateRequired Reading 0TACF(N/AforAUO's)Part3-Performed by both off-going and on-coming shift oWalkdownofMCRControlBoards(N/AforAUO's)ReliefTime:ReliefDate: todayTVA40741[03-2001]OPDP-1-1[03-14-2001 SHIFT TURNOVER CHECKLISTPage3of3 Disabled Annunciators Today PANEL WINDOW ANNUNCIATOR Equipment Off-Normal (Pink Tags)WO I PER Number (UNID And Noun Name ID And Noun Name Panel Panel Problem Description MCRWO List Problem Description WO I PER Number WOlPER Number UNITONE REACTIVITY BRIEFDate:TodayTime:NowRCSBoron: 1346 ppm Today IBAControllerSetpoint: 34%*IRCSB-10Depletion:2ppmOperableBAT: A IBATABoron:6850ppm IBATCBoron:6850ppm IRWSTBoron: 2601 ppmNominalGallonsperrodstepfrom180: 17gallonsofacid, 75gallonsofwater

• Verifyboricacidflow controllerissetatAdjustedBAControllerSettingiaw0-SO-62-7section5.1Gallonsofacid:

22Gallonsofwater: 94RodSteps: 1 (Power reduction amountEstimatedFinalRodPositionEstimatedboron addition 10%168StepsonbankD 91 gallons 30%139StepsonbankD 294 gallons 50%n/a n/a**Thesevaluesare approximationsandnotintendednorexpectedtobeexact.Thevaluesmaybesupercededby Rx Engineering or SO-62-7calculatedvalues.Thesevaluesarecalculatedassuming100%steadystatepower operation only.Engineeringdatalastupdatedoneweekago.DataValiduntilthreeweeksfromnow.Numberofdilutions:0Numberofborations:Rodstepsin:Gallonsperdilution:0Gallonsperboration:Rodstepsout: Total amountdiluted:0Totalamountborated:Netchange: IN/Out Numberofdilutions:

• • • Numberofborations:Rodstepsin:Gallonsperdilution:0Gallonsperboration:Rodstepsout:Totalexpecteddilution:
    • Totalexpectedboration:Netchange:In/Out Remarks:RxPower-41%MWD/MTU-1000Xenon

&SamariumatEquilibrium

• • • AsRequiredbyReactor Engineering startup spreadsheet.NextUnit1FluxMapis scheduled-UnitSupervisor:

Name/Date N/A Operations Chemistry Information SamplePointUnitsBoronDate/TimeGoalLimitU1RCS ppm 1346 Today/Now Variable VariableU2RCS ppm 816 Today/Now Variable Variable U1 RWST ppm 2601 Today/Now 2550-2650 2500-2700 U2 RWST ppm 2569 Today/Now2550-26502500-2700BATA ppm 6850 Today/NowVariableVariableBATB ppm 6850 Today/Now Variable Variable BATC ppm 6850 Today/NowVariableVariable U1 CLA#1 ppm 2556 Today/Now 2470-2630 2400-2700U1CLA#2 ppm 2575 Today/Now 2470-2630 2400-2700U1CLA#3 ppm 2591 Today/Now 2470-2630 2400-2700U1CLA#4 ppm 2589 Today/Now 2470-2630 2400-2700 U2 CLA#1 ppm 2531 Today/Now 2470-2630 2400-2700 U2 CLA#2 ppm 2650 Today/Now 2470-2630 2400-2700 U2 CLA#3 ppm 2522 Today/Now2470-26302400-2700 U2 CLA#4 ppm 2526 Today/Now 2470-2630 2400-2700 (SpentFuelPoolppm 2547 Today/Now 2.18-2.48 2.33 IndicatorUnitsU1Date/TimeU2 Date/TimeSI50S/G Leakage?Yes/No No Today/Now No Today/Now SI 137.5 CVE Leakrate gpd<0.1 Today/Now<0.1 Today/Now5gpdleak equivalent cpm 229 Today/Now 68 Today/Now15gpd(30min increase)cpm567 Today/Now 83 Today/Now30gpd leak equivalent cpm 1174 Today/Now 206 Today/Now75gpdleak equivalent cpm 2875 Today/Now 455 Today/Now150gpdleak equivalent cpm 5710 Today/Now 870 Today/Now CVE Air Inleakage cfm 10 Today/Now 12.5 Today/NowBkgdon 99/119 cfm 40 Today/Now 40 Today/Now ...-..,,, Unit 1 DELTA REACTOR POWER ASSUMED INSERTED EXPECTED DELTA RHO BORON DELTA RECOMMEND RECOMMEND IODINE TIME POWER DEFECT ROD HT WORTH XENON BORON CONC PPM DILUTION BORATION CONC (hrs)(%)(pcm)(steps)(pcm)(pcm)(pcm)(ppm)(ppm)(gal)(gal) (%eq)0.0 41.0 698.8 180.0-290.1-2020.0 1346.0 41.4 1.0 50.0 836.5 190.0-206.3-1998.9 32.8 1340.9-5.1 247 0 41.8 2.0 60.0 990.0 200.0-127.4-1957.5 33.2 1335.7-5.2 251 0 43.1 3.0 70.0 1144.5 210.0-60.0-1904.6 34.1 1330.3-5.3 259 0 45.3 4.0 80.0 1301.6 216.0-27.9-1849.0 69.4 1319.5-10.9 530 0 48.2 5.0 90.0 1464.2 216.0-26.2-1797.5 109.5 1302.3-17.1 847 0 51.8 6.0 100.0 1634.0 216.0-24.5-1755.1 125.6 1282.7-19.7 987 0 56.1 7.0 100.0 1643.0 216.0-24.5-1736.3-9.8 1284.2 1.5 0 17 60.4 8.0 100.0 1642.3 216.0-24.5-1746.2 9.2 1282.8-1.4 72 0 64.3 9.0 100.0 1642.9 216.0-24.5-1775.7 30.1 1278.1-4.7 238 0 67.8 10.0 100.0 1645.1 216.0-24.5-1818.0 44.5 1271.1-7.0 353 0 71.0 11.0 100.0 1648.3 216.0-24.5-1868.2 53.4 1262.8-8.3 426 0 73.8 12.0 100.0 1652.1 216.0-24.5-1922.7 58.3 1253.6-9.1 469 0 76.4 13.0 100.0 1656.3 216.0-24.5-1978.9 60.3 1244.2-9.4 489 0 78.7 14.0 100.0 1660.6 216.0-24.5-2034.9 60.4 1234.8-9.4 492 0 80.8 15.0 100.0 1664.9 216.0-24.5-2089.6 59.0 1225.6-9.2 485 0 82.7 16.0 100.0 1669.1 216.0-24.5-2142.0 56.7 1216.7-8.8 469 0 84.4 17.0 100.0 1673.2 216.0-24.5-2191.7 53.8 1208.3-8.4 448 0 85.9 18.0 100.0 1677.0 216.0-24.5-2238.4 50.5 1200.4-7.9 423 0 87.3 19.0 100.0 1680.6 216.0-24.5-2281.9 47.1 1193.1-7.4 3'97 0 88.6 20.0 100.0 1684.1 216.0-24.5-2322.2 43.8 1186.3-6.8 371 0 89.7 21.0 100.0 1687.4 216.0-24.5-2359.4 40.5 1179.9-6.3 345 0 90.7 22.0 100.0 1690.4 216.0-24.5-2393.6 37.2 1174.1-5.8 318 0 91.6 23.0 100.0 1693.2 216.0-24.5-2424.9 34.1 1168.8-5.3 293 0 92.4 24.0 100.0 1695.8 216.0-24.5-2453.5 31.1 1164.0-4.9 269 0 93.2 25.0 100.0 1698.1 216.0-24.5-2479.5 28.4 1159.5-4.4 246 0 93.9 26.0 100.0 1700.2 216.0-24.5-2503.3 25.8 1155.5-4.0 225 0 94.5 27.0 100.0 1702.1 216.0-24.5-2524.8 23.5 1151.9-3.7 205 0 95.0 28.0 100.0 1703.9 216.0-24.5-2544.4 21.3 1148.5-3.3 186 0 95.5 29.0 100.0 1705.5 216.0-24.5-2562.1 19.3 1145.5-3.0 169 0 95.9 30.0 100.0 1706.9 216.0-24.5-2578.2 17.5 1142.8-2.7 154 0 96.3 31.0 100.0 1708.2 216.0-24.5-2592.7 15.9 1140.3-2.5 140 0 96.7 32.0 100.0 1709.4 216.0-24.5-2605.9 14.3 1138.1-2.2 127 0 97.0 33.0 100.0 1710.5 216.0-24.5-2617.8 13.0 1136.1-2.0 115 0 97.3 ,..,..-"., Unit 1 34.0 100.0 1 711.4 216.0-24.5-2628.5 11.7 1134.2-1.8 104 0 97.6 35.0 00.0 1712.3 216.0-24.5-2638.2 10.6 1132.6-1.7 94 0 97.8 36.0 100.0 1713.1 16.0-24.5-2647.0 9.6 1131.1-1.5 85 0 98.0 37.0 100.0 1713.8 216.0-24.5-2654.9 8.6 1129.8-1.3 77 0 98.2 38.0 100.0 1714.4 216.0-24.5-2662.1 7.8 1128.5-1.2 69 0 98.4 39.0 100.0 1715.0 216.0-24.5-2668.6 7.0 1127.4-1.1 63 0 98.6 40.0 100.0 1715.5 216.0-24.5-2674.4 6.4 1126.5-1.0 57 0 98.7 41.0 100.0 1716.0 216.0-24.5-2679.6 5.7 1125.6-0.9 51 0 98.8 42.0 100.0 1716.4 216.0-24.5-2684.4 5.2 1124.8-0.8 46 0 98.9 43.0 100.0 1716.8 216.0-24.5-2688.7 4.7 1124.0-0.7 42 0 99.0 44.0 100.0 1717.2 216.0-24.5-2692.5 4.2 1123.4-0.7 38 0 99.1 45.0 100.0 1717.5 216.0-24.5-2696.0 3.8 1122.8-0.6 34 0 99.2 46.0 100.0 1717.8 216.0-24.5-2699.2 3.4 1122.3-0.5 31 0 99.3 47.0 100.0 1718.0 216.0-24.5-2702.0 3.1 1121.8-0.5 28 0 99.4 48.0 100.0 1718.3 216.0-24.5-2704.5 2.8 1121.3-0.4 25 0 99.4 49.0 100.0 1718.5 216.0-24.5-2706.9 2.5 1120.9-0.4 22 0 99.5 50.0 100.0 1718.7 216.0-24.5-2708.9 2.3 1120.6-0.4 20 0 99.5 51.0 100.0 1718.8 216.0-24.5-2710.8 2.0 1120.3-0.3 18 0 99.6 52.0 100.0 1719.0 216.0-24.5-2712.5 1.8 1120.0-0.3 17 0 99.6 53.0 100.0 1719.1 216.0-24.5-2714.0 1.7 1119.7-0.3 15 0 99.7 54 0 100.0 1719.2 16.0-24.5-2715.4 1.5 1119.5-0.2 13 0 99.7 55.0 100.0 1719.3 216.0-24.5-2716.6 1.4 1119.3-0.2 12 0 99.7 56.0 100.0 1719.4 216.0-24.5-2717.8 1.2 1119.1-0.2 11 0 99.8 57.0 100.0 1719.5 216.0-24.5-2718.8 1.1 1118.9-0.2 10 0 99.8 58.0 100.0 1719.6 216.0-24.5-2719.7 1.0 1118.8-0.2 9 0 99.8 59.0 100.0 1719.7 216.0-24.5-2720.5 0.9 1118.6-0.1 8 0 99.8 60.0 100.0 1719.8 216.0-24.5-2721.2 0.8 1118.5-0.1 7 0 99.8 Total 12046 17 Hold Tavg=Tref+/-1.SF Small hourly boration/dilution 6820 BAT ppm volumes may be accumulated for larger single additions Reason for Power Increase Plant Startup DateRxENGName Beeper 70808 Comments SON 0-SO-62-7 1,2 BORON CONCENTRATION CONTROLRev.46 Page161of 199APPENDIX0 Page1of1 CALCULATIONFORAMOUNTOFBORICACIDOR PRIMARY WATER (TI-44)NOTE 1 NOTE 2 One calculation is required for each major change.BoricacidamountstoachieverequiredRCSboronconcentrationmaybesignificantlyhigherthancalculatedamountsifCVCSdeminresinsareremovingboron.Amountofboronremovalbymixedbedresinswi!!dependonRCSboron,resinage,whetherdeminbedwaspreviouslyborated,andletdowntemperature.Chemistryshouldbeconsultedifrequiredtoevaluateresinbedremoval. [1]IF REACTF notused, THEN CALCULATE amount of primary water or boric acid required using TI-44.(RCSBORON/34 b ppm Current PPM CHANGE-II AMOUNT PRIMARYWATERORBORICACID5Z t./f);I v3-e.TOTAL GAL(s)NOTE REACTF data sheetsaretobe signed by the preparer and reviewer.NOTE[2]IF REACTF used attach printout to procedure. IV is not required if appendix is performedbyan SRO to verify data providedbyRx.Eng.[3]ENSURE independently verifiedbyan SRO in accordance with Appendix I.ENDOF TEXT Initials (v NRC08D Dilute.txt 0[REACTF-VERS SQ2.1]BORATION/DILUTION CALCULATION SEQUOYAH UNIT 1 CYCLE 15 RCS AVG TEMP 560.0 DEG F RCS PRESSURE 2235.0 PSIG PZR LEVEL 39.4%MAKEUP WTR CONC.0 PPM BORIC ACID CONC 6850.0 PPM INITIAL CONC FINAL BORIC ACID MAKEUP WTR BORON CONC CHANGE BORON CONC ADDITION ADDITION (PPM)(PPM)(PPM)(GAL)(GAL)----------

---

---

---

1346.0-11.0 1335.0.0 524.1 0 page 1 NOTE1NOTE2 SQN BORON CONCENTRATION CONTROL 0-SO-62-7 1,2Rev.46Page162 of 199 APPENDIX EPage1of18 REACTIVITY BALANCE CALCULATION One calculation is requiredforeach major change.Calculationisan approximation of required Boron change.Eyeball interpolation of graphs is expected.Dilution or Boration value for power change from P1%to P 2%powerintimeperiodTwith rods movingfromstep position R 1toR 2.(Subscript convention: 1=currentpoint,2=target point)[1]ENTER the following data: DATA REQUIRED DATAWhereToGet CurrentRCSBoron/3'LI b ppmChemLabor Estimate using Appendix 0CoreBurnup /0 0 0 MWO/MTUICSU0981 Current Reactor power L;/%NISorICS Final Reactor power b'D%As required for plant conditions Total Reactor Power change/1Currentandfinal Reactor powerRateof Reactor power change/.5:%/hr As requiredforplant conditions Numberofhoursto change power Z hr(s)Asrequiredfor plant conditionsICSorMCRBoard Current Rod Position/80 steps Estimate numberofrod steps required toFinalRod Position 2 0 0 steps controlandrod withdrawal requirements for power change. SQN BORON CONCENTRATION CONTROL 0-80-62-7 1,2Rev.46Page163of199APPENDIXEPage2of 18 CAUTION Follow sign conventions explicitly.(See Example Rower Increase and Power decrease.) [2]CALCULATE changeinboron concentration by performing the following: Parameter WhereToGet Calculation ValueAttachedPowerDefectCurves: 680 pem PD 1-97V pem PD 2=-27D (negative[a]f1pPOWERDEFECTUnit1: Figure1,2,or3 pemforpower (current)tl.pPOWERDEFECT increase)Unit2: Figure8,9,or10.Xenon-, From ICS*or REACTF(eithercurrent NOTE: Xenon reactivity must be negative (negativeconditionsorprojectiontoinitialcondition).forrisein[b]f1p XENON Xenon-,FromICS*or REACTF pem XE z-(-ZOZo)pem XE 1=70 pem Xenon(projectionovertimeperiodT).-J ctsDconc)*(ICSXenonvaluesmustaddnegativesign).(current)tl.p XENON[C]f1p RODSAttachedRodWorthCurves: _/30 pem Rods,-(-Z8n)pem Rods,=IS-a (negativeUnit1: Figure4,5,or6 pemforrod (current)tl.p RODS insertion)Unit2: Figure11,12,or13. [d]f1pPOWERDEFECT +XENON+RODS (CHANGE IN REACTIVYDUETO POWER DEFECT, XENON, AND RODS)-7°pem raj pem tl.pPOWERDEFECT +[bJ pcm L\p XENON+[cJ pcm L\p RODS=[e]f1p BORON (CHANGE IN BORON REACTIVITY) 70 pem ([dJ pem f1pPOWERDEFECT +XENON+RODS)X (-1)=tl.p BORON[f]Apprn BORON (CHANGE IN BORON CONCENTRATION)(negative pcm tl.p BORON)-:-(fordilution, ([eJ-6.3 pcm/ppm Boron Worth)=-tl ppmpositiveforfromFig.7(U-1) orFig.14(U-2)boration)[3]ENSURE independently verified by 8RO in accordance with Appendix J.(N/Aif performedbyan 8ROtoverifydataprovidedbyRx.Eng) ".(SQN 1-S0-2/3-1 1 CONDENSATE AND FEEDWATER SYSTEMRev47Page118of268 Date5.16.4 Startup of Second MFPT NOTE Throughoutthissection,N/AthenonselectedMFPT handswitchesandvalves. [1]RECORDMFPTselectedtobestartedsecond.ANDRECORDMFPTtobestartedspeed. B LIG[2]ENSUREapplicablePreparationforStartuphasbeencompleted: MFPT PREPARATION FOR STARTUP INITIALS 1ASection5.16.1ofthisinstruction /v j;t-1BSection5.16.2ofthisinstruction ,./VI----[3]ENSUREapplicableMFPToutletvalveOPEN: (DESCRIPTION VALVENO.POSITION INITIALSFWP1AOutletFlow fi//f}ControlValve 1-FCV-3-67 OPENFWP1BOutletFlowControl Valve1-FCV-3-81OPENFPTNOTstarted) SPEED SWITCH..J DEMAND..J A.MFPT CONTROLLER POSITION SETPOINT ,./A 1-SIC-46-20A MAN ZERO./B 1-SIC-46-20B MAN[9/ZERO Y[4]ENSUREMFPTSpeed ControllerfortheMFPTtobestartedin MANUAL AND ADJUST Demand SetpointtoZERO.(N/Afor M[5]DISPATCHpersonnelto determineifelectricspeed changeroutletpressureon 1-PI-46-5100forAMFPTor 1-PI-46-5105forB MFPTindicatingbetween18-22psig. SQN 1-S0-2/3-1 1 CONDENSATEANDFEEDWATERSYSTEMRev47 Page119of268Date_5.16.4 Startup of SecondMFPT(Continued)[6]IFelectricspeedchangeroutletpressureisnotcorrect,THENNOTIFYIMstoevaluateEHspeedchangesignal.[7]ENSUREMFPTsH-PandL-PsteamisolationvalvesfortheMFPbeingstartedareOPEN.[C.5] VALVEDESCRIPTIONPOSITION ./1-611MFPTAHPISOLOPEN

Jt1r1-603MFPT ALPISOLOPEN JJl$r1-612MFPTBHPISOLOPEN

[iY'1-604MFPTBLPISOLOPEN vr[9]RESETtheStandbyMFPT.TheMFP suction pressure should be monitored when operating the recirc valve on the idle pump.[8]PERFORMthefollowing:[a]ENUSRE[1-HCV-3-70] CLOSED.[b]ENUSRE[1-HCV-3-84] CLOSED.[c]IFstartingAMFP,THEN THROTTLE[1-FCV-3-70]MFPRecircvalvebetween30%-50%OPENUSING[1-FIC-3-701 [d]IFstartingBMFP,THEN THROTTLE[1-FCV-3-84]MFPRecircvalvebetween30%-50%OPENUSING[1-FIC-3-841CAUTION ([10]ENSUREthefollowing: MFPT A B DESCRIPTIONCondenserInletIsolvalveCondenserOutletIsolvalveCondenserInletIsolvalveCondenserOutletIsolvalve VALVE FCV-2-205A FCV-2-210A FCV-2-211A FCV-2-216A POSITION OPEN OPEN OPEN OPEN SQN 1-S0-2/3-1 CONDENSATE AND FEEDWATER SYSTEMRev47 1Page120of268 5.16.4 Date vv:-:: Startup of Second MFPT (Continued) NOTEEitherstopvalvehandswitchwillopenbothhighpressureandlowpressurestopvalvesfortheapplicableMFPT. ([11]OPENtheStopValvesfortheMFPTtobestartedbyplacingeithertheHIP orLIPhandswitchtotheRAISEposition:MFPTDESCRIPTION HANDSWITCH VALVE INITIALS POSITION 1AHIPStopValve 1-HS-46-15A OPEN JlJk:-LIPStopValve 1-HS-46-16A OPEN AJ/rr-18HIPStopValve 1-HS-46-43A OPENLIPStopValve 1-HS-46-44A OPEN[12]VERIFYtheMFPturninggearmotorhasSTOPPED. CAUTION NOTE Observe MFP speed, flow, discharge pressure duringtheMPFT startup to prevent an inadvertent FW swing ifthe MFPT minimum speed setpoint is excessively high.The feedwaterpumpspeed controllerwilltakecontrolattheminimumspeedsettingandrunthe governor valve positionerouttoits upperlimit.Minimumspeedonhighpressuresteamis3100to3,300rpmand3650to3850rpmonlowpressuresteam.Thisvaluemayvarybasedonprevioushandspeedchangeradjustment. [13]NOTIFYMIGtoadjusttheMFPThandchangerforthe properrpmasthesecondMFPTisaccelerated. SQN 1-S0-2/3-1 1 CONDENSATE AND FEEDWATER SYSTEMRev47Page121of268 5.16.4 Startup of SecondMFPT(Continued)NOTE1NOTE2NOTE3 Vibrationandthrustbearingwearshould bemonitoredonlocalBentlyNevadapanelandICS(SecondaryMimics,MFPBearingData).Max allowablevibration(dangerlimit)is5milsabovebaseline;alertvalueis3milsabovebaseline.Thrustbearingweartrip setpointis10milsabovebaseline(7milsalertabovebaseline).1AMFWPcondenservacuummaybemonitoredusing1-PI-2-331A(TBel.685),ICScomputerpoint1U2082,orbymonitoring condenser drain temperature(ICSpoint1T2360A).1BMFWP condenservacuummaybemonitoredusing,1-PI-2-331B(TBel.685),ICS computer point1U2084,orbymonitoring condenser drain temperature(ICSpoint1T2361A).Draintemps160°Findicatesvacuumofatleast20"Hg.MFWPtrip setpointof12.2psia corresponds to-5"Hgvacuumordraintempof -200°F.Maxallowablebearing temperatureis225°F.([14]MONITORthefollowingparametersduringMFWPstartup:

• Vibrationandthrustbearingwear(atlocalpanel)
• MFWP Condenser vacuum/drain temperature.*Oilsystemandbearing temperatures.[15]OPEN GovernorValvebyPERFORMINGoneofthefollowing:[a]IFMCRoperationof Governor Valve Positionerisavailable, THEN PLACEtheapplicable Governor Valve PositionertotheRAISEpositiontoopenthesteamchestvalvesand accelerate the MFPT" MFPT DESCRIPTION HANDSWITCH POSITION INITIALS AGVPositioner 1-HS-46-13A OPEN B GV Positioner 1-HS-46-40A OPEN SQN 1-S0-2/3-1 CONDENSATE AND FEEDWATER SYSTEMRev47 1Page122of268 5.16.4Date_Startup of Second MFPT (Continued)

[b]IFMCRoperationof GovernorValvePositionerisunavailable, THEN 1.ESTABLISHdirectcommunicationsbetweenthepersonneloperatingthe U1MFPspeedcontrollocallyand the U1MainControlRoom. 02.DIRECTMIGtoslowlyadjust U1MFPSpeedControlusinglocalmanualcontroloftheMFPGovernorValvePositionertothrottlesteamchestvalesandcontrolMFPT speed.0 (CAUTION NOTEDONOT increase second MFPT speed faster than the master speed control can maintain program dIp.AsthesecondMFPTisloaded,thefirstMFPTshouldbackdowninload. [16]SLOWLYLOADthesecondMFPTtoraiseMFPTspeeduntildemandonMFPTspeedcontrollermatchesthedemandoutputofthefirstMFPT.[17]ENSUREMFPInjectionWaterIntermediateLeakoffPressureforBOTHMFPsisatleast250psig. [a][1-PI-54-2],1AMFP AND[b][1-PI-54-611BMFP[18]ENSUREMFPInjectionWaterDifferentialPressureforpumpstartedisequaltoorgreaterthan25psid. [a][1-PDI-54-111AMFP OR[b][1-PDI-54-51 1BMFP[19]WHENtheoutputmeterfortheSICforthesecondMFPTmatchestheoutput meterontheMasterController,THEN PLACEthesecondMFPTSICinAUTO. o '.SQN 1-S0-2/3-1 1 CONDENSATEANDFEEDWATERSYSTEMRev47Page123of268 5.16.4 Startup of SecondMFPT(Continued)[20]CLOSEthesecondMFPTdrainvalves(N/Avalvesnotclosed):Date_(MFPTDESCRIPTIONHANDSWITCHPOSITIONINITIALS1ADrainValves1-HS-46-14CLOSED 18DrainValves1-HS-46-41CLOSEDCAUTION1MFP Recirc valves controllers shouldNOTbe operated inAUTOMATICduetothe potential for isolating all three intermediate heater strings and resulting MFP damage.(

Reference:

PER00-002540-000).CAUTION2 Operation ofMFPRECIRC valve should be performed slowly due to affectonMFPDP program.[21]ENSURE[1-FCV-3-70]or[1-FCV-3-84]MFPRecircvalveisCLOSEDandinMANUAL. CAUTION NOTE Failure to readjust the minimum speedonthe second MFWP could resultinthe second MFWP being unable to supply adequate feed flow in the event the first MFWP trips.Thefollowingstepmaybeperformedinparallelwithpowerincreasebutshouldbecompletedpriortoexceeding55%power.[22]WHENMFWPspeedcontrollers [1-SIC-46-20A] and[1-SIC-46-20B]areinAUTO,THENPERFORMthefollowingtoadjusttheminimumspeedonthesecondMFWP:[a]VERIFYbothMFWPspeedcontrollerbiassettingsat50%.[b]NOTIFYMIGtoslowlyadjustthehandspeedchangeronthesecondMFWPsothattheMFWPspeedsareequal. o o

• " SQN 1-80-2/3-1 CONDENSATE AND FEEDWATER SYSTEMRev47 1Page124of268Date_5.16.4 Startup of SecondMFPT(continued)

CAUTION1A bias adjustment in the upward direction (>50%)shouldNOTbe used unless evaluated by Systems Engineering since this could impact a MFPT's maximum speed and the ability to fully load in the event the other MFPT trips.CAUTION 2 TransferringaMFPT Controller from Manual to Auto with the bias not set to 50%will resultinan instantaneous speed change of the MFPT.Transferring the Master MFPT Controller from Manual to Auto with bias not set to 50%will resultinan instantaneous speed change of the MFPT.NOTE1ThefollowingstepmaybeperformedatanytimewhenbothMFPTsare inserviceandinAUTO, (NOTE2WithbothMFPTsinAUTOitmaybecome necessarytoadjusttheMFPTspeedcontrolbiasononeofthe operatingMFPTsto preventMFPTsfromfightingeachother (oscillating). [23]IFan adjustmentoftheflowbalancebetweentheMFPTsis desired, THEN SLOWLY ADJUSToneMFPTspeedcontrolbiasin downward direction(0%to50%)untildesiredflowbalanceis achieved.End of Section 5.16.4 o (Sequoyah Nuclear Plant Unit 1&2 General Operating Instructions O-GO-5 NORMAL POWER OPERATION Revision 0052 Quality Related Level of Use: Continuous UseEffectiveDate:10-27-2007 ResponsibleOrganization:OPS,OperationsPreparedBy:Judy R.VarnerApprovedBy:W.T.Leary Current Revision DescriptionRevisedtoremovereferencestoDCN22190whichwasnotimplementedU1C15. PERFORMANCEOFTHISPROCEDURECOULDIMPACTREACTIVITY. SQN NORMALPOWEROPERATION 0-GO-5 Unit 1&2Rev.0052Page2 of 93 Table of Contents

1.0 INTRODUCTION

31.1Purpose 31.2Scope 3

2.0 REFERENCES

4 2.1 Performance References 4 2.2 Developmental References 5 3.0 PRECAUTIONS AND LIMITATIONS 6 3.1 Precautions 63.2Limitations 11 4.0 PREREQUiSiTES 14 5.0 INSTRUCTIONS 165.1PowerAscensionFrom30%to100% 175.2AtPowerConditions 585.3PowerReductionFrom100%to30% 645.4PowerCoastdownatEndofLife 775.5LOADFOLLOWOPERATIONS 826.0RECORDS 86 AppendixA:DELETED 87 Appendix B: TURBINE RUNBACK RESTORATION 88 Appendix C: ISOLATIONOFMSRSTARTUPVENTS 90 Appendix D: RECOMMENDED POWER VALUES BASED ON CONDENSATED PRESSURE 91 Source Notes 92 ATTACHMENTS Attachment1:NORMALPOWEROPERATION ((SQNNORMALPOWEROPERATION0-GO-5Unit1&2Rev.0052Page3of93

1.0 INTRODUCTION

1.1Purpose This General Operating(GO)Instructionprovides guidanceforpower ascension from approximately30to100%power,atpowerconditions,power reduction from100to30%power,Power CoastdownatEndofLife operations,andLoad Follow operations. This instruction provides additional guidanceforturbinecontrol restoration following a turbine runback.1.2ScopeThisGO contains the following sections: 5.1 Power AscensionFrom30%Powerto100%5.2At Power Conditions 5.3 PowerReductionFrom100%to30% 5.4 Power CoastdownatEndofLife5.5Load Follow Operations SQN NORMAL POWER OPERATION 0-GO-5 Unit1&2Rev.0052Page4of93

2.0 REFERENCES

2.1 Performance References A.1,2-80-5-1, FeedwaterHeatersandMoisture Separator Reheaters B.1,2-80-5-2, No.3 HeaterDrainTankandPumps C.1,2-80-5-3, No.7 HeaterDrainTankandPumps D.1,2-80-2/3-1, Condensate and Feedwater System E.1,2-80-2-9, CondenserVacuumandTurbineSteamSealSystemsOperation 0-80-68-3, Pressurizer Spray and HeaterPressureControlSystem 1,2-80-62-9, CVCS Purification System 0-81-NUC-000-038.0,ShutdownMargin 0-80-62-7, Boron Concentration Control F.0-80-12-1, Auxiliary Boiler System G.0-80-35-4, Monitoring Generator Parameters 0-80-58-1. Main GeneratorBusDuctCoolingSystem H.I.(J.K.L.M.0-80-85-1,ControlRodDriveSystem N.0-PI-OP8-000-666.0, RiverTemperatureLimits SpecifiedbyNPDES permit O.0-81-0P8-092-078.0, PowerRangeNeutronFluxChannelCalibrationByHeat Balance ComparisonP.0-81-CEM-000-050.0, 72-Hour Chemistry Requirements Q.0-81-CEM-030-407.2, Radioactive GaseousWasteEffluent Particulate andIodineDoseRatesfromShieldand AuxiliaryBuildingExhausts (Weekly/Special) and Condenser Vacuum Exhausts (Special)R.0-81-CEM-030-415.0,GaseousEffluent Requirements(GrossAlpha,Noble Gas and Tritium 8.0-81-0P8-000-001.0, Initial 8tartup 8ystemParameterLogT.TI-40, Determination of Preconditioned Reactor Power (SON NORMAL POWER OPERATION 0-GO-5 Unit1&2Rev.0052Page5of93 2.2 Developmental References A.Memorandum from System Engineering concerning MSR operation-RIMSS57 880322999 B.Memo from Reactor Engineering-RIMSS57 941219 934C.S57-880322-999andS57-880808-851D.W Letter GP89-076 (RIMSNo.S53 890427 984)E.W Letter GP 89-155 (RIMS S57 891026 972)F.W Letter GP 86-02(B44 861112 002)G.SSP-2:3, Administration of Site Procedures H.TVA-NQA-PLN89-A I.GOI-10, ReactivityControlatEnd ofCycleLife (Trojan Nuclear Plant)J.FSAR, Section 13.5 K.Memo from Reactor Engineering -August6,1996(GBair) (SQN NORMAL POWER OPERATION 0-GO-5 Unit 1&2Rev.0052Page6 of 93 3.0 PRECAUTIONS AND LIMITATIONS 3.1 PrecautionsA.To ensurethatNIS ReactorPowerlevel indicationsremainwithin2%oftrue powerduringpowerlevelchanges,acheckshouldbe performed about every 20%powerlevelchange,when greaterthan15%power,by comparing calorimetricpowertoeachNIS PowerRangedrawer.The20%powerlevel checkdoesnotprecludethe operatingcrewsfrommaking necessary changes in responsetochangingplant conditions. B.TRM 3.3.3.15requiresLEFMcorethermalpower (U2118)tobeusedto perform 0-SI-OPS-092-078.0 above15%reactorpower.LEFM indication is availableifthefollowing conditionsaremet:*LEFMstatus NORMALonICS CalorimetricDatascreen.*LEFMcorethermalpower(ICSpoint U2118)showsgood (green)data.*LEFMMFW headertemp(ICSpoint T8502MA)greaterthanorequalto250°F.IfLEFM indicationisNOT availableabove15%reactorpower,thenTR 3.3.3.15 action mustbeentered.C.The followingshouldbeusedto determinethemost accurate reactor power indication for comparisonwithNIS:*When reactorpoweris greaterthan15%,useLEFM calorimetric power indication (U2118).*IfLEFMisNOTavailable,thenuse average loop (U0485orM-5 indicators)upto40%.Above40%,use computerpointU1118.D.Theturbineshouldbe operatedin"IMPOUT"controlduringnormalunit operation."IMPIN" operationresultsinsystemswingsandshouldonlybeused during the performanceofvalvetests.(WLtrGP89-155;RIMSS57891026972) E.Pressurizerheatersandspraysmaybe operatedasrequiredto maintain pressurizerandRCSboron concentrationwithin50ppm.Ifloopboron concentrationischangedby20ppmorgreater,usethe pressurizer backup heaterstoinitiate automatic spray. (SQN NORMAL POWER OPERATION O-GO-5Unit1&2Rev.0052Page7of93 3.1 Precautions (continued) F.Condensate 01 polishing operations during power ascension are controlled by staying within system parametersandby recommendationsfromthe Chemistry Section.G.The valve position limitershouldbe periodically positioned approximately 10%above the current governor control indications (keeps governorvalvesoffofthe limiter)as turbine load is changed.This prevents inadvertent load increases by limiting governor valve opening and allows a faster responseoftherun back feature which ensures main feedwatersystemwill supply the required amountofflow.H.Any off-frequency turbine operation istobereportedto Engineeringforrecord keeping.The report will include duration and magnitude of off-frequency operation. I.Operation at off-frequencies istobeavoidedin order to prevent the probable occurrence of turbine blade resonance. Prolonged periods of operation at certain off-design frequenciescouldcause excessive vibratory stresses which could eventually generate fatigue crackingintheblades. Off-frequency operation is permitted to the degreeandtimelimit specifiedonthechart"Off-Frequency Turbine Operation",FigureA.26ofTI-28. J.The potentialexistsfor condensation formation in steam extractionlineswhen feedwater heatersareisolated.K.Initial Startup After Refueling-After refueling operations,theNIS indicationsmaybe inaccurate until calibration at higher powerlevels.TheNIS calibration procedures will adjustthePRMtrip setpoints to ensurethatthe excore detectorsdonot contributetoan overpower conditionatthe followingRTPhold points.Reactor Engineering and/or Systems Engineering will determine procedure performance. [C.3]1.At<50%RTPafluxmapand single point alignment,ahotchannel factor determination,anaxial imbalance comparison,andaPRNIS calibrationwillbe performed.ThePRhighrangetrip setpoint willthenbe increased to its normalvalueof109%.2.At<75%RTP, calorimetric calculationsandRCSflow verificationmaybe performed, EAGLE-21 updatedpriorto increasingpower,afluxmap,ahot channel factor determination,anaxial imbalance comparisonmaybe requiredifnot performed at<50%,a detector calibration (ifAFO?3%),andaPRNIS calibrationmaybe performed. (SQN NORMAL POWER OPERATION 0-GO-5Unit1&2Rev.0052Page8of93 3.1 Precautions (continued)3.Ifnotperformedat75%holdpoint,anaxialimbalancecomparisonandadetectorcalibration(ifAFD3%)shouldbeperformedat -100%RTP.EngineeringwilldetermineifPRNIScalibrationmustbeperformed. Calorimetriccalculations,RCSflowverification,ahotchannelfactordetermination,andareactivitybalancewillbeperformedandEAGLE-21updated.ReactorEngineeringwillnotifyOperationsthatnormalfullpoweroperationsmayproceed.4.PreconditionedPowerLevelsandMaximumAllowableRatesofPowerIncreasearespecifiedinTI-40, Determination of Preconditioned Reactor Power.5.Duringinitialstartups,basedonWestinghouserecommendations,alowerpowerrampratelimithasbeenimplementedforpowerlevelsabovetheintermediatepowerthreshold.TheIntermediatePowerThresholdisunit/cycledependentandisdeterminedbytheVendor.RefertoTI-40.6.\CSwillautomaticallymonitorpre-conditionedpowerlevelasfollows:a.PointU1127isreactorpowerinpercentofRTPbasedoneithersecondarycalorimetricor ReSTdependingonpowerlevel.b.PointU0103isa20minuterollingaverageofreactorpowerrate-of-changefittedovera20minuteperiod. U0103isaleadingindicatorof%/hourpowerramprateandcanbeusedindecidingtospeeduporslowdowntheramprate.c.PointU0104isa1hourrollingaverageofreactorpowerrate-of-changefittedovera1hourperiod. U0104 is used in demonstrating compliancewithfuel pre-conditioning powerramprate limits.d.PointK0058isthecurrentlyqualified(or pre-conditioned)powerlevel.e.ThesepointscanallbemonitoredwiththeICSgroupdisplay"TI40".AppendixAmaybeusediftheICSisunavailable.L.TI-40powerincreaselimitsthatareexceeded,in anyonehour,areevaluatedin accordancewithSPP-3.1. SQN NORMAL POWER OPERA liON O-GO-5Unit1&2Rev.0052Page9of93 3.1 Precautions (continued)M.Power CoastdownAtEndOfLife: 1.Reactorpowerchangesshouldbelimitedtolessthanorequalto1%perhourtoavoidcausingxenonpeakingwhichcouldforceaplant shutdown.2.Donotperform unnecessaryunitpower maneuversortesting(e.g., turbinevalvetesting).Suchtestingcouldresultinan uncontrollable Xenon oscillation. 3.Nonessentialworkonsystemswhichcouldcauseaplantupsetshouldbe deferred.4.SecondaryPlantrunbackssuchasMainFeedPump Turbinetripor#3HeaterDrainTankrunbackwillrequireaunitshutdownif Reactor powerisnot promptlyreturnedto pre-transientlevelduetotheresultingsevereXenontransient.Ifasystempoweralertisineffect,andelectrical generationiscritical,unitloadshouldbereducedas necessary keeping T AVGonprogram.Contact Reactor Engineeringforanevaluationand guidance concerningunitshutdownorreductionofload. 5.Managementshouldbeconsultedtoevaluatethe feasibilityofaunitrestartifareactortripoccurswithRCSequilibriumboron concentrationlessthan50ppm.Ifthereactoristoberestarted,thepowerlevelshallbelimitedtonominalpre-trippowerlevel.N.AxialFlux Difference Management:Whenthereactoris operatingatasteadypowerorduringnormalloadchanges, maintainwithintheoperatinglimitsoftheCore OperatingLimitsReport (COLR).Itis recommendedthatthecoreaxialflux difference (AFD)be maintained within+/-5%ofthetargetbandatalltimes, excluding the performance of 0-PI-NUC-092-036.0,"Incore-Excore Calibration,"andEndoflifepowercoastdowns.Operatingtime outsidetheband,whichisgivenin TI-28 Attachments1and2,shouldbeminimized. Reactor Engineering shouldbecontactediftime outof the+/-5%targetbandexceeds approximately30minutes.O.ThepositionofcontrolbankDshould normally be215stepswhenpowerlevelis steadystateatorabove85%RTP.At steadystatepowerlevelsbelow85%,controlbankDshouldnormallybe165steps.Ifrodpositionismorethan2stepsbelowthisguidanceforlongterm,then impactmayoccurtosafety analysis assumptions.P.Duringheatupandcooldowntransients,RCS densitychangeswillcausechangesinNISindicatedpower.At constantreactorpower,a1°Fchangein TAVGmaycauseasmuchasa1%(ormore)changeinindicatedNISpower. (SQN NORMAL POWER OPERATION 0-GO-5 Unit1&2Rev.0052Page10of93 3.1 Precautions (continued) Q.Operationofmain generator without automaticvoltagecontrolcould impact grid voltage requirements.TheSouth EastAreaLoad Dispatcher (SELD)shouldbe notified immediately if generatorisin service without automatic voltage regulator.Also,refertoSectionEofGOI6forMVARlimits. R.Main Generator operation without Automatic Voltagecontrolrequiresthat NarrativeLogentriesbe made(time,date,reason &duration)andthat notificationbemadeto Operations Duty Specialist (ODS)within twenty four (24)hours.S.Main Generator operation outsideofthe Voltage ScheduleinGOI-6requires that NarrativeLogentriesbe made(time,date,reason &duration)andthat notificationbemadetoSouthEastAreaLoad Dispatcher (SELD)withinone (1)hour.1.The following limitations are applicabletoUnitTwoONLY.1.In wintermonths#7 HDTP capacityisnot adequatetopump#6 Heaterdrainswhenall Condensate Demineralizerpumpsareinservice. Current practiceistoruntwoCond 01Pumpsand/or throttle the condensatesystemtoreduce backpressure.Thepreferredmethodisto throttle condensate pressure insteadofrunningonlytwo Condensate Demineralizer boosterpumpsatfullpowerduetopump runout concerns.2.Siemens-Westinghouse analysis has determined that the maximum unitpowerwithoneMFP operationis65%under worst case conditions. Theplantcould operate higherifplant conditions permit.3.MFPflowfromtheleadMFPshouldnotexceed53.7%ofthetotalflow.FlowratesabovethiswouldresultinHPsteamflowtotheleadMFPT. Computerpoints1 (2)U0504 and U0505canbeusedto monitor. (SQNNORMALPOWER OPERATION 0-GO-5Unit1&2Rev.0052Page11of93 3.2 Limitations A.Whentheaxialflux difference monitoralarmis inoperable, the AFD must be loggedeveryhourby performing 0-SI-NUC-000-044.0.(SR 4.2.1.1.a.2 &4.2.1.1.b) B.Whenboththeplant computerandNIS QPTR alarm systems are inoperable, the QPTRmustbe calculatedevery12hoursby performing 0-SI-NUC-000-133.0.(SR 4.2.4.1.b)C.Donotexceedaload changerateofplusorminus5%perminuteorastep changeof10%.D.River water temperaturesshallbe maintainedwithinthe limitationsofthe NPDESpermitas specified in 0-PI-OPS-000-666.0. NOTE Westinghouse should be contactediftheturbineis operated outsideofits operating limitsasstated below.E.To prevent high vibratory stresses and fatigue damagetothe last stage turbine blading,donot operate the turbine outsideoflimitslistedbelow:[WLtrGP86-02(B44 861112 002)]1.Atloadslessthanorequalto30%(350MW),the maximum permissible backpressureis1.72psia.(3.5"Hg)2.Atloads greaterthan30%,the maximum permissible backpressure is2.7psia(5.5"Hg)witha5minute limitation beforetrippingthe turbine.F.Donot allow the generator to become underexcited.G.Inthe eventofa changeintherated thermal power level exceeding15%inonehour,notify Chemistrytoinitiatethe conditional portions of 0-SI-CEM-000-050.0, 0-SI-CEM-030-407.2 and 0-SI-CEM-000-415.0duetothe thermal power change. ((SQN NORMAL POWER OPERATION 0-GO-5 Unit 1&2Rev.0052Paae12 of 93 3.2 Limitations (continued)H.The following Main Turbine vibration limitationsandactionsshouldbeadhered to: 1.Vibrationlevelswhichexceed7mils(alarmsetpoint)shouldbeverifiedby Predictive Maintenance Group.2.Vibrationlevelsgreaterthan7milsandlessthan14milsshouldbe continuouslymonitoredby Predictive Maintenance Group.3.IF vibrationlevelis greaterthanorequalto14mils,THENTRIPthe turbine.I.Westinghouse recommendsthatifanythrottlevalveisheldclosedformorethan10minutes,thenitshouldbere-tested immediatelyuponreopeningin accordance with 1,2-PI-OPS-047-002.0.J.The generatormaybeoperated withoutabusductcoolerupto approximately729MWturbineload.K.To ensure sufficientvoltageforasafeshutdownafterlossofbothunits,voltageandreactivepowershouldbemaintainedwithinthelimitsofGOI-6. L.WithLEFM calorimetricpowerindicationavailable,fullpower operation isdefinedas approximately3455MW rnottoexceed3455.0MW raveragedover a 8-hourperiod.[C.1]IfLEFMisavailable,powershallbemonitoredusing plant computerpointU2118 InstantaneousValue.DONOTallowaverage thermalpowertoexceed3455MWthermalfortwo consecutive hours.M.The followingrestrictionsapplyifLEFM calorimetricpowerindication (U2118)is unavailable: 1.ApplicableactionofTRM3.3.3.15mustbeentered.2.AFDlimitsinCOLRandTI-28mustbemademore restrictiveby1%.3.Rod insertionlimitsinCOLRmustberaisedby3steps.4.If reactorpoweris greaterthan40%,powershouldbemonitoredusingU1118.IfU1118isalso unavailable,usethe highestreadingNISchannel.5.Ifreactorpowerislessthan40%,usetheRCS average bTasthe preferredmethodfor determiningpowerlevel.N.IF equilibrium conditionsareachieved,afterexceedingby10%ormoreofratedthermalpowerthethermalpoweratwhichtheheatfluxhotchannelfactorwas last determined,THENconditional performance of 0-SI-NUC-000-126.0, Hot Channel Factor Determinationisrequired. ((SQN NORMAL POWER OPERATION 0-GO-5 Unit 1&2Rev.0052Page13 of 93 3.2 Limitations (continued)O.Atlow powerlevels,theLPHeatersmaybe unbalanced in extraction steam supplyuseandheatpickup across the condensatesideofthe heater string.This condition should correct itselfastheunit approaches 45-50%TurbinePower.(Ref:PER 99-003789-000)P.WithoneLP heaterstringoutof service (isolated), powerislimitedto86%(Unit1)or90%(Unit2).ThisisbasedonLPturbine blading limitations.(Ref: DeN E21203A). SQN NORMAL POWER OPERATION 0-GO-5 Unit1&2Rev.0052Page14of93 4.0 STARTUP No.PREREQUISITES Unit\DateVV---NOTES 1)Throughout this Instruction where an IFITHEN statementexists,thestepshouldbe N/A'difthe condition doesnotexist.2)Prerequisites may be completedinanyorder. ([1][2][3][4][5][6][7]ENSURE Instructiontobeusedisa copy of effective version.T AVGisbeing maintained within1.5°FofT REF.SGlevel controlsarebeing maintained in AUTO (N/Aifauto control NOT available). Controlrodsarebeing maintained within the operatingbandof Core Operating Limits Report (COLR)(N/A if shutting downdueto dropped or misaligned rod).Steam dump control systemisintheT AVG mode (N/A if Tavg Mode NOT available). The EHC systemshouldbein OPER AUTO (pushbutton lit).Generator pressurized with hydrogen according to capability curve.(TI-28, Fig.A.14)NOTE During start up afteracold shutdown the Condensate 01 normally will be alignedforfull flow polishinguntilthe MSRsarein service.[8]ENSURE Condensate 01 polishing operation in accordancewithRCL recommendations. SQN NORMAL POWER OPERATION 0-GO-5 Unit1&2Rev.0052Page15of93 4.0 STARTUP No.PREREQUISITES (continued) Unit-:...I_ (([9]ENSURE each performer documentstheirnameandinitials: Print Name InitialsV'----v-....r--V\,./'-"""'-- (SQN NORMAL POWER OPERATION 0-GO-5 Unit 1&2Rev.0052Page16of93 5.0 INSTRUCTIONS CAUTION Stepsofthis proceduremustbe performed sequentially, unless specifically stated otherwise. NOTES1)RADCONshouldbenotifiedduringnormalplantoperationsifpowerlevelincreasesordecreasesareeitherstoppedorstarted.2)GuidanceonrestorationofEHCControlsafteraBOPrunbackiscontainedin Appendix B, Turbine Runback Restoration. [C.4] SQN NORMALPOWEROPERATION 0-GO-5 Unit1&2Rev.0052Page17 of 93 STARTUP No.5.1 Power AscensionFrom30%to 100%Unit--L-NOTES1)Main Generator operation without Automatic Voltagecontrolrequiresthat NarrativeLogentriesbemade(time,date,reason &duration)andthat notificationbemadeto Operations Duty Specialist(ODS)withintwentyfour(24)hours.2)Main GeneratoroperationoutsideoftheVoltageScheduleinGOI-6requiresthat NarrativeLogentriesbemade(time,date, reason&duration)andthat notification be madetoSouthEastAreaLoad Dispatcher(SELD)withinone(1)hour. 3)Operationofmain generator without automaticvoltagecontrolcould impact grid voltage requirements.TheSouthEastAreaLoad Dispatcher (SELD)shouldbe notified immediately if generatorisinservice without automatic voltage regulator.Also,refertoSectionEof Gal6forMVARlimits. 4)Confirmation from Chemistry Section SHALLbeobtainedpriorto exceeding 30%reactor power.(([1][2][3]ENSURESection4.0, Prerequisites complete.VERIFY from ChemistrySectionthatSG and feedwater secondary chemistryiswithin acceptable limits.Chemistrypersonnelcontacted IFthisisastartupfollowingrefueling, THEN ENSURE applicableportionsof 0-RT-NUC-000-001.0 are COMPLETE for operation above 35%power.RxEngr. SQN NORMAL POWER OPERATION 0-GO-5 Unit1&2Rev.0052Page18of93 \Unit__STARTUPNo.../V-5.1 Power AscensionFrom30%to100%(continued) NOTES1)Thisstepmaybeperformedoutofsequenceasnecessarytomeetpowerlevel. 2)O-SI-OPS-092-078.0maybeperformedatthediscretionoftheOperatorifoneormore PRMs is indicatingclosetothe +/-2%tolerance. [4]PERFORMthefollowingat approximately35%reactorpower: [4.1]IFLEFMindicationisavailable, THEN CALCULATE Calorimetric power: Calorimetricpower=U2118= 34.55[4.2]IFLEFMindicationisNOTavailable, THEN CALCULATEreactorpower: AveragevalueofRCS L1T (U0485)=v}}V%[4.3]VERIFYallNISPowerRangechanneldrawersare within+/-2%ofthecalculatedreactorpower: N-41 (XI-92-5005B) YESNOD N-42 (XI-92-5006B) YESNOD N-43 (XI-92-5007B) YES D N-44 (XI-92-5008B) YES it'NOD[4.4]IFanyoftheabovestepsarecheckedNO, THEN PERFORM O-SI-OPS-092-078.0. SQN NORMAL POWER OPERATION 0-GO-5Unit1&2Rev.0052Page19of93 STARTUP No.Unit_\!....-_ 5.1 Power Ascension From 30%to100%(continued) NOTES1)Withreactorengineeringconcurrence,powerincreasepersteps5.1[6]through5.1[9]maybeperformedinparallelwiththisstep.2)Ifstartupisfollowingrefuelingoperationsand secondarysidechemistryis acceptableforpowerincrease,thenN/AStep 5.1[5].(StartupReactivityCalibrationsand Testswillbeperformedat <<45%ReactorPowerifnotperformedat >>30%Power). [5]IFstartupisfollowingrefuelingactivitiesandsecondary chemistryholdisprecludingpowerascension, THEN ENSUREthefollowinghavebeenperformedpriortoexceeding50%ratedthermalpower:(Maybeperformedinanyorder)([5.1]0-SI-NUC-000-126.0,HotChannelFactorDetermination.RxEng ate[5.2]0-SI-NUC-092-079.0,Incore-ExcoreAxialImbalance Comparison.RxEng[5.3]0-PI-NUC-092-002.0,DetectorSinglePointAlignment.RxEng ate SON NORMAL POWER OPERATION 0-GO-5 Unit 1&2Rev.0052Page20 of 93 5.1 STARTUP No.unitL Power Ascension From 30%to 100%(continued) DateRxEng[5.5]PRHighFluxTripresetto109%.[C.3]. [5.6]Applicable portions of 0-RT-NUC-000-001.0 COMPLETEforoperationabove50%power. MIG MIG 0-PI-IXX-092-N45.0,PRNISCalibration. [5.4]([6]DETERMINEthefollowingfromTI-40ANDRECORDin narrativelogANDbelow:[6.1]Reactorpreconditionedpowerlevel. 10 ()[6.2]Rampraterestrictions.NOTE N/A Substep5.1[6.3]and 5.1[6.4]ifnotinitialstartupafterrefuelingoutage. [7][6.3]Intermediate power[6.4]RampRateabovethe intermediatepowerthreshold. MONITORTI-40limits(usingICStrendfeaturesifavailable). (SON NORMAL POWER OPERATION 0-GO-5Unit1&2Rev.0052Page21of93 5.1 STARTUP No. Power Ascension From 30%to 100%(continued) NOTE DateRaisingloadontheMain Generatorwillcause VARstotrendinthe negative direction (toward incoming).Thiswillrequireraising generator voltage.Refer to GOI-6SectionEfor MVAR limits for generatorstability.Referto precautionsQ,R,andS.[8]PERFORM the followingasrequired:[8.1]IF Automatic VoltageControlisinservice, THEN ADJUST Main Generator VARs USING[HS-57-221 Exciter Voltage Auto Adjuster as necessary during power escalation. ([8.2]IF Automatic VoltageControlisNOTinservice, THEN ADJUST Main Generator VARs USING[HS-57-231 Exciter Voltage Base Adjuster as necessary during power escalation. NOTES 1)Steps5.1[9]through5.1[15]maybe performed concurrentlyoroutof sequence.2)Valve position limit and governor control meter are displayedonEHC Displaypanel1 ,2-XX-047-2000 (M-2).3)Actions effecting reactivityaredirectedinthe following step.0-SO-62-7 requirementsshallbe adheredtofor reactivity changes (i.e.reactivity balance, amountsofboricacid or water).All appropriate verificationsandpeer checksshallbeutilized during performance. [9]INITIATE power increase to between45and49%and (MAINTAINvalvepositionlimit approximately 10%above current governor control indication as turbineloadis changed. SQN NORMAL POWER OPERATION 0-GO-5 Unit 1&2Rev.0052Paae22 of 93 5.1 STARTUP No.unitL Power Ascension From 30%to 100%(continued) NOTE DateControlrodsmaybeusedalongwithdilutionduringreactorpowerincreasetomaintainAFDwithinthetargetcontrolband.[10]IFdilutingtheRCStoincreaseT AVG, THENCONTINUEdilutionandincreaseturbineloadtomaintainT REFwithTAV G.(0-SO-62-7)[11]PERFORMthefollowingduringpowerincrease: NOTE (T AVGwillbeprogrammedfrom547°Fatnoloadto578.2°Fat100%loadatarateof0.312°Fper%power.[11.1]MONITORT AVGfollowingTREFonprogram.[11.2]MONITOR pressurizerlevelonprogram(25to60%asafunctionofT AVG).NOTEIfLEFMisavailable,computerpointU2118shouldbeusedastruereactorpower.IfLEFMisNOTavailable,useU1118whengreaterthanorequalto40%andtheaveragevalueof RCS L1Twhenlessthan40%.[11.3]MONITORallRPls,groupstepcountersforrodinsertionlimitsandinoperablerodsorrodmisalignment,Loop L1T,andNISforcorrectpowerdistributionandquadrantpowertilts. NOTE GeneratorMVARsmaybereducediftheGeneratorStatorGroundFaultRelayindication approachesthealarmvalueof50%.RefertoGOI-6SectionEforMVARlimitsfor generator stability.[11.4]MONITOR generatorconditionsinaccordancewith 0-50-35-4,MonitoringGeneratorParameters. [C.6] SQN NORMAL POWER OPERATION 0-GO-5 Unit 1&2Rev.0052Page23 of 93 STARTUP No.Jv----.Unit\ 5.1 Power Ascension From 30%to 100%(continued) NOTETheturbineloadincreaseshouldbestoppeduntilthemainfeedwaterregvalvesareoperatinginthe acceptable band.[11.5]ENSUREmainfeedwaterregvalvesareoperatingproperlyinauto(within +/-5%fromzerodeviationisacceptable).[11.6]IFmainfeedwaterreg.valvesareNOTmaintainingwithinthe5%band,THENNOTIFYInstrumentMaintenance. CAUTION (The potential exists for condensation formation in steam extraction lines when feedwater heaters are isolated.NOTE Instrument Maintenancesupportmayberequiredifcontrolleradjustmentsareneeded. [11.7]ENSUREFeedwaterHeaters5and6,MSRDrainTank,and#7HeaterDrainTanklevelcontrollersareadjustedtomaintainlevelswithinnormalranges. SON NORMAL POWER OPERATION 0-GO-5 Unit1&2Rev.0052Page24 of 93 5.1 STARTUP No.\.IV'-Unit L Power Ascension From 30%to 100%(continued)[12]WHENreactorpoweris approximately35%,THEN VERIFY annunciator XA-55-4A, window C-5: DateP-8LOW POWER LOW FLOW TRIP BLOCKisDARK.([13]IFunitisreturningtoserviceafterapowerreductionandtheMSRswereremovedfromservice,THEN PLACEMSRHPsteamwarmingvalvestoOPENposition: MSR HANDSWITCH WARMING VALVE INITIALSA1HS-1-142 FCV-1-1421st I I CV81HS-1-144 FCV-1-1441st CV C1 HS-1-146 FCV-1-146 1st CVA2HS-1-136 FCV-1-136 1st CV 82 HS-1-138 FCV-1-1381stCV C2 HS-1-140 FCV-1-1401st v CV ([14]ENSURE#3and#7 heaterdraintanksonrecircin accordance with 1,2-S0-5-2 and 1,2-S0-5-3. [15]ENSURE the remaining availablepumpsarealignedandreadyforservicein accordance with 1,2-S0-2/3-1: [15.1]Condensate booster pumps.[15.2]Hotwellpump. SQNNORMALPOWER OPERATION 0-GO-5Unit1&2Rev.0052Page25of93 5.1 unitL Power AscensionFrom30%to100%(continued) NOTES 1)When placing additional condensate pumps inservice, or HOT pumps in service, ensure thatthemainregvalvesrespond correctlyandthen stabilizeinthe acceptable band.2)The followingstepmaybe performedoutof sequenceandmaybemarkedN/Aifit was previously performed in O-GOA.[16]WHEN the condensate boosterpumpreaches approximately140amps, THEN START the following pumps in accordancewith1 ,2-S0-2/3-1: ([16.1]ThirdHWpump(if available).[16.2]SecondCBP. SQN NORMAL POWER OPERATION 0-GO-5Unit1&2 Rev.0052Page26of93 5.1 STARTUP No.Unit+Power AscensionFrom30%to100%(continued) (CAUTION Valves 106A and 1068shallbeverifiedtobe controlling properly aftereach#3HOTpumpstart. NOTES1)Whenplacingadditional condensatepumpsorHOTpumpsinservice,ensurethatthemainregvalvesrespondcorrectlyandthen stabilizeinthe acceptable band.2)Withverbal approvalfromthe Operations Superintendent,pumpingforwardofthe#3and#7 HeaterDrainSystemmaybedeferreduntilturbineloadis approximately 60%,ifsystem conditions warrant.3)Steps5.1[17]through5.1[22]maybeperformedoutof sequence.[17]DETERMINEif#3and#7heaterdraintankpumpscanbealignedtopumpforward: [17;1]WHEN confirmationobtainedfrom ChemistrySectionthat#3heaterdraintank chemistryiswithin limits, THEN (STARTpumpingforwardusingtwo(2)#3 heater draintankpumpsusing 1,2-S0-5-2. .[17.2]WHEN confirmationobtainedfrom ChemistrySectionthat#7heaterdraintank chemistryisinlimits, THEN STARTpumpingforwardusingthe#7 heaterdraintankpumpsusing 1,2-S0-5-3. [18]IF turbine load increase continues withoutthe#3heaterdraintankpumpspumpingforward, THEN[18.1]MAINTAIN Condensate BoosterPumpsuctionpressure greaterthanorequalto75psig (PI-2-77). [18.2]MAINTAIN Main FeedwaterPumpsuctionpressure greaterthan330psig (PI-2-129). SQN NORMAL POWER OPERATION 0-GO-5 Unit1&2 Rev.0052Page27of93 5.1 STARTUP No.\f'J\...<UnitPower AscensionFrom30%to100%(continued) CAUTIONS (1)MSR heatup limits are restrictedto100°Fperhouror25°Fina 15-minute period (automatic mode)or50°Fina 30-minute period (manual mode).(SECO limits, contract 85P62-836839)2)OntheLP turbineinlet,doNOT exceed an instantaneous changeof50°Forarateof change of 125°F/Hr for turbine expansion considerations.3)Foracold start,theHP bundle warming valvesshouldbeopenedat least 15 minutes before bringingtheMSRinservice. NOTE Placing MSRs in service before 35%turbineloadcancause turbinerotorlong condition. [19]WHEN:::: 35%turbine load, THEN[19.1]IF cold start (LP turbineinletmetal temperaturelessthan 300°F), THEN DEPRESS the RESET pushbuttononthe moisture separator reheatercontrolpanel. [19.2]CLOSE the following steam inlet leakoff isolation valves: MSRVALVEPOSITIONINITIALS 1-679 CLOSEDA-1 1-714 CLOSED1-680CLOSED --,B-11-715CLOSED1-681CLOSEDC-1.........-'\... 1-716 CLOSED 1-682 CLOSEDA-21-717CLOSED1-683 CLOSED---v-B-2 1-718 CLOSED..../\,., 1-684 CLOSEDC-21-719 CLOSED SQNNORMALPOWER OPERATION 0-GO-5Unit1&2Rev.0052Page28of93 STARTUP No.\.../"-- (5.1Power AscensionFrom30%to100%(continued) NOTEDuetorequired interlocksonMSRvalvesthefollowingvalveslistedinthetableshouldbe performed in sequentialorder.Forexample:OpenFCV-1-241andwhenfullopen,then open FCV-1-141. [19.3]ENSUREMSRHPsteam suppliesALIGNEDasfollows: MSR EQUIPMENT HANDSWITCH POSITION-..j/MSRBYPASSISOL HS-1-241A OPENA1MSRMAINISOL OPENMSRBYPASSISOL HS-1-243A OPEN mI;B1 cg/MSRMAINISOL HS-1-143A OPENMSRBYPASSISOL HS-1-245A OPEN cY C1 rn/MSRMAINISOL HS-1-145A OPENMSRBYPASSISOL HS-1-235A OPEN w: A2 t:('MSRMAINISOL HS-1-135A OPENMSRBYPASSISOL HS-1-237A OPEN 4V B2 u:vMSRMAINISOL HS-1-137A OPEN MSRBYPASSISOL HS-1-239A OPEN Q./C2 ,0/MSRMAINISOL HS-1-139A OPEN NOTES1)Controlvalvesrampopenfor120minutesfor turbinecoldstart.2)MSRControlvalvesrampopenfromthe400°Fpositiontofullopeninonehourwhen Hot Start buttonwaspreviouslydepressedduring performanceof0-GO-4or0-GO-11. [19.4]DEPRESStheRAMP pushbuttononthemoisture separator reheatercontrolpaneltoinitiatesteamflowtothereheater.(stepcontinuedonnextpage) (SQN NORMAL POWER OPERATION 0-GO-5 Unit1&2Rev.0052Page29of93 5.1 STARTUP No.Unit-L Power AscensionFrom30%to 100%(continued) [19.5]IFMSRcontrolswillNOTfunctioninRAMPmode, THEN PERFORM the following: A.DEPRESS MANUAL pushbuttononMSRcontrol panel.B.ADJUST manual potentiometer to gradually openMSRTCVsoverapprox.120minutes WHILE continuinginthis procedure. [19.6]OPEN all MSR OPERATING vents(6-3thru6-93)onpanelXS-6-3. [19.7]CLOSEallMSR STARTUP vents(6-1thru6-91)onpanelXS-6-1. [19.8]PERFORM AppendixCto locallyisolateMSR startup vents. ([19.9]ENSUREMSRHPsteam warmingvalvesare CLOSED: MSR EQUIPMENT HANDSWITCH POSITIONA1 MSR WARMING LINE HS-1-142 CLOSED B'"B1MSR WARMING LINE HS-1-144 CLOSEDC1MSR WARMING LINE HS-1-146 CLOSEDA2MSR WARMING LINE HS-1-136 CLOSEDB2MSR WARMING LINE HS-1-138 CLOSED c¥/C2MSR WARMING LINE HS-1-140 CLOSED SQN NORMAL POWER OPERATION 0-GO-5Unit1&2Rev.0052Page30of93 STARTUP No.Unit , (5.1 Power AscensionFrom30%to100%(continued) [19.10]IFthispowerascensionisduringthemonthsofOctober1throughMarch31, THEN REFER to 0-PI-OPS-000-006.0andconsultSystem EngineerforpositionofMSR doghouses'ventdampers. [19.11]IFthispowerascensionisduringthemonthsofApril1 through September 30, THEN OPEN MSR doghouses'ventdampers. [20]IFpumpingforwardwith#3HOT, THEN ENSURE1,2-LCV-6-106Aand Bare maintaining#3heaterdraintanklevel. NOTE Benchboard instrumentsPI-5-87Afor#7heaterand PI-5-84A for#6 heatermaybeusedto determineheatershellsidepressure. [21]IF#7heaterdraintank(HOT)pressureisindicatingan overpressure condition, THEN PERFORM 1,2-S0-5-3,Section8.0, InfrequentOperationto prevent#7HOT overpressurization. SQN NORMAL POWER OPERATION 0-GO-5 Unit1&2Rev.0052Page31of93 5.1 STARTUP No.\.../".A.-- unitl PowerAscensionFrom30%to 100%(continued) [22]WHEN approximately40%turbineload: [22.1]VERIFY annunciator XA-55-4A, window E-7: C-20 AMSAC ARMED is LIT.[22.2]CLOSEthedrainsonthe operating main feedwater pump turbine (N/A other pump). (MFPT DESCRIPTION HANDSWITCH POSITION A DRAIN VALVES HS-46-14 CLOSED V B DRAIN VALVES HS-46-41 CLOSED SQN NORMAL POWER OPERATION 0-GO-5 Unit1&2Rev.0052Page32of93 STARTUPNo._Unit--Date_5.1 Power Ascension From30%to 100%(continued) NOTEWithverbal approvalfromthe Operations Superintendent,placingthesecondmainfeed pump in servicemaybedeferreduntilpoweris approximately55%(Unit1)or65%(Unit 2).Logic prevents opening the standby MFPT condenserisolationvalvesifthepumpis NOT resetpriorto exceeding 9millionIbs/hrflowontherunningpump. [23]WHEN approximately 40 to 45%turbine load, THEN PLACEsecondMFPTin service by performing the following: [23.1]IF the Operations Superintendenthasapprovedone MFP operationduringthe power ascension, THEN A.1.RECORDwhichMFPTisinservice. (___MFPT B.MONITORloadingoftheMFPinserviceasloadis increased. 0[23.2]WHEN second MFPTistobe placed in service, THEN (PLACEsecondMFPTin service in accordance with 1,2-S0-2/3-1. o SON NORMAL POWER OPERATION 0-GO-5 Unit 1&2Rev.0052Page33 of 93 STARTUPNo._Unit--Date---5.1 Power Ascension From 30%to 100%(continued) NOTEThisstepandindividualsubstepsmaybeperformedoutofsequence.[24]PERFORMthefollowingassystemparameterspermit:[24.1]VERIFYthree(3)Hotwellpumpsrunning(ifavailable). D[24.2]VERIFYtwo(2)Condensateboosterpumpsrunning. D[24.3]VERIFYMFW pump(s)inservice(only1requiredifapprovedbyOperationsSuperintendent). D[24.4]VERIFYtwo(2)#3heaterdraintankpumpsrunning. D ([24.5]VERIFYone(1)#7HeaterDrainTankpumpinservice. D[24.6]ENSUREoneglandsteamexhausterrunningandone stopped inAUTOposition: EXHAUSTER HANDSWITCHA HS-47-209A AUTODSTARTD B HS-47-209B AUTODSTARTD[24.7]IF gland seal water is being supplied from opposite unit, THENRESTOREnormalglandsealwateralignment(suppliedfromthisunit)inaccordancewith1 ,2-S0-37-1, GlandSealWaterSystem. D SQN NORMAL POWER OPERATION 0-GO-5 Unit 1&2Rev.0052Paae34 of 93 STARTUPNo._Unit__Date_(5.1 Power Ascension From30%to100%(continued) NOTESteps5.1[25]through 5.1[30]maybeperformedoutofsequence.[25]IFthesecond#7heaterdraintankpumphasnotbeenstarted, THEN STARTthesecond#7heaterdraintankpumpinaccordance with 1,2-S0-5-3. NOTEHydrogenpressureshouldbemaintainedgreaterthanorequalto66psig.[26]ENSURE generatorhydrogenpressureissufficientforanticipatedloadinaccordancewithTI-28,FigureA.14, GeneratorCapabilityCurve.[27]VERIFYriverwatertemperaturewithinthelimitationsoftheNPDESpermitasspecifiedin 0-PI-OPS-000-666.0. CAUTION D (After refueling operations,theNIS indications may be inaccurate until calibration at higher power levels.DONOT increase power greater than 50%until Reactor Engineering has ensured that applicable portions of0-RT-NUC-000-001.0are complete.[28]IFapplicableportionsof 0-RT-NUC-000-001.0arecompleteforpowerincreaseabove50%ofratedthermalpower,THEN N/AthefollowingStep 5.1[29].(ReactorEngineering) SQNNORMALPOWEROPERATION0-GO-5Unit1&2Rev.0052Page35 of 93 STARTUPNo._Unit--Date_5.1 Power AscensionFrom30%to100%(continued) [29]IFstartupisfollowingrefuelingactivities, THEN ENSUREthefollowinghavebeenperformedpriorto exceeding50%ratedthermalpower: (maybeperformedinanyorder)A.0-SI-NUC-000-126.0,HotChannelFactor Determination.RxEng Date B.0-SI-NUC-092-079.0, Incore-Excore Axial Imbalance Comparison.RxEng Date (C.0-PI-NUC-092-002.0, Detector Single Point Alignment.RxEng Date D.0-PI-IXX-092-N45.0,PRNIS Calibration ..MIG Date E.PRHighFluxTripresetto109%. [C.3].MIG Date F.Applicableportionsof 0-RT-NUC-"000-001.0 COMPLETEforoperationabove50%power.RxEng Date[30]WHENreactorpoweris approximately 49%.THEN PERFORMthefollowing:(inanyorder). ([30.1]ENSUREindicatedAxialFlux Differenceiswithinthe ,limitsspecifiedintheCOLR (T8 3.2.1.1). SQN NORMAL POWER OPERATION 0-GO-5Unit1&2Rev.0052Page36of93 STARTUPNo._Unit--Date_(5.1 Power AscensionFrom30%to100%(continued) [30.2]PERFORMaconditional 0-SI-NUC-000-044.0, Axial Flux Difference. NOTE QPTR alarmspertaintotheplant computer and annunciatorpanelAR-M4-B, windows B-3,C-3,and 0-4.Alarmsmay sporadicallyoccurat1.5%whenthe setpointis2%.[30.3]PERFORMaconditional 0-SI-NUC-000-133.0, Quadrant PowerTiltRatio. [30.4]IF QPTR exceeds 1.015, THEN CONTACT Reactor Engineering for evaluation. NOTERamploadrate increasesshallbewithinthelimitsstatedinTI-40. [31]RECORD the following fromTI-40: ([31.1]Power ascensionrampratefromTI-40._ NOTE N/A substep5.1[31.2]and5.1[31.3]if NOTinitialstartupafterrefuelingoutage. [31.2]Intermediate powerthresholdsetpoint. _[31.3]RampRateabovethe intermediate power threshold. o o o SQNNORMALPOWER OPERATION 0-GO-5Unit1&2Rev.0052Page37of93 STARTUPNo,_Unit__Date_5.1 Power AscensionFrom30%to100%(continued) [32]CONTINUEreactorpower ascensionto74%.NOTE o (Controlrodsmaybeusedalongwithdilutionduringreactorpower increasetomaintainAFDwithinthe targetcontrolband. [33]IF dilutingtheRCSto increase TAVG, THEN CONTINUEdilutionand increase turbineloadtomaintainT REF withTAVG.(0-SO-62-7) 0 NOTE Valvepositionlimitand governor control meter are displayedonEHC Displaypanel1 ,2-XX-047-2000 (M-2).[34]MONITORtheturbineload increasing and MAINTAINvalvepositionlimit approximately 10%above current governor control indication as turbineloadischanged. 0 NOTE Steps5.1[35]through5.1[37]maybe performedoutofsequence. [35]WHEN greaterthanorequalto50%reactorpower, THEN[35.1]VERIFY annunciator XA-55-4A, window E-4:P-9LOW POWERTURB TRIP-REACTRIPBLOCK is DARK.o SQN NORMAL POWER OPERATION 0-GO-5 Unit 1&2Rev.0052Page38 of 93 STARTUPNo._Unit--Date_5.1 Power Ascension From 30%to 100%(continued) [35.2]VERIFY annunciator XA-55-4B, window B-3: NIS POWER RANGE UPPER DETECTOR HI FLUXDEVNOR AUTO DEFEAT is DARK.o[35.3]VERIFY annunciator XA-55-4B, window C-3: NIS POWER RANGE LOWER DETECTOR HI FLUXDEVNORAUTODEFEAT is DARK.o ([35.4]VERIFY annunciator XA-55-4B, window 0-4: COMPUTER ALARMRODDEV&SEQNISPWR RANGE TILTS is DARK.o{[36]ENSURE MFPTCvacuumnormal (greaterthan20inchesHG vacuum)using PI-2-331Aand PI-2-331BonPanelL-69. 0 NOTE During power operationabove50%, condenser air inleakageshouldbe maintained lessthan6CFM.[37]IF condenser air inleakage exceeds15CFM,THEN INITIATEactionsto identify the source of inleakage and NOTIFY Engineeringandthe Operations Superintendent orPlantManager. SQN NORMAL POWER OPERATION 0-GO-5 Unit1&2Rev.0052Page39of93 STARTUPNo._Unit--Date---5.1 Power Ascension From 30%to 100%(continued) NOTES 1)Steps5.1[38]through5.1[41]maybe performedoutof sequence.2)O-SI-OPS-092-078.0maybe performedatthe discretionofthe Operatorifoneormore PRMs is indicatingclosetothe +/-2%tolerance. [38]PERFORM the following at approximately 55%reactor power:[38.1]IF LEFM indication is available, THEN CALCULATE Calorimetric power: Calorimetricpower=U2118 34.55=%---o[38.2]IF LEFM indicationisNOT available, THEN CALCULATE reactor power: Calorimetric power=U1118 34.11=%---D[38.3][38.4]VERIFYthatall operable NIS Power Range channel drawersarewithin+/-2%ofthe calculated calorimetric power.N-41 (XI-92-5005B) YESD NOD N-42 (XI-92-5006B) YESD NOD N-43 (XI-92-5007B)YESD NOD N-44 (XI-92-5008B)YESD NOD IFanyofthe abovestepsare checked NO, THEN PERFORM O-SI-OPS-092-078.0. SON NORMAL POWER OPERATION 0-GO-5 Unit1&2Rev.0052Page40 of 93 STARTUPNo._Unit__Date----5.1 Power Ascension From 30%to 100%(continued) NOTES1)MorerestrictiveturbineloadlimitforUnit1isbasedonensuringadequateMFPsuctionpressuretoallowpumpingagainsthigherS/GpressuresfollowingS/Greplacement.(Ref:DCNE21203A).2)Siemens WestinghouseanalysishasdeterminedthatthemaximumUnitTwounitpowerwith1MFPoperationis65%underworstcaseconditions.Operationathigherpowerlevelsaredependentoncurrentconditions.ThiswouldrequireSystemEngineeringevaluation.(Ref:DCND21732A). ([39][40]ENSUREsecondMFPTisinservicePRIORTOincreasingturbineloadabove55%(Unit1)or65%(Unit2). ENSUREatleastonebusductcoolerisinservice USING 0-80-58-1PRIORTOincreasingloadabove729MWe. CAUTION#3 and#7 heater drains must be pumping forward prior to exceeding 60%turbine load.This load limit assumes that both MFW pumpsarein service.If only oneMFWPis running, turbine load must be further limited to maintain adequate MFWP suction pressure.[41]ENSUREboth#3and#7heaterdraintanksystemsarepumpingforwardPRIORTOincreasingturbineloadabove 60%. SQNNORMALPOWEROPERATION0-GO-5Unit1&2Rev.0052Page41of93STARTUPNo._ Unit--Oate_(5.1PowerAscensionFrom30%to100%(continued) CAUTIONS1)Valves106Aand 1068shallbeverifiedtobeoperatingproperlyaftereach#3HOTpumpstart.2)At approximately79%turbineloadwithLCV-6-105Aor8openandonlytwo#3HOTpumpsareinservice,therequiredNPSHfortheMFPwillbeinsufficient. NOTES1)WhenplacingHOTpumpsinservice,ensuremainfeedwaterpumpsandmainregvalvesrespondcorrectlyandthenstabilizeinanacceptableband. 2)LCV-6-105Awillcomeopenatabout70%turbineloadif condensate dischargepressureishigh.Minimizedurationatthisloadtoreducewearonthevalve.Asloadisincreasedto100%condensatepressurewillgradually decreaseallowingthe#3HOTpumpstopumpforwardandthecondenserbypassvalve(s)toclose.3)Steps 5.1[42]through5.1[45]maybeperformedinanyorder. [42]WHEN approximately70%turbineload, THEN[42.1]PLACEthethird#3heaterdrainpumpinserviceinaccordancewith 1,2-S0-5-2. [C.2][42.2]ENSUREvalvesLCV-6-106AandLCV-6-106Barecontrolling#3heaterdraintanklevelproperly. SQN NORMAL POWER OPERATION 0-GO-5 Unit1&2Rev.0052Page42of93 STARTUP No.,_Unit__Oate_(5.1 Power AscensionFrom30%to100%(continued) CAUTION Evaluate starting and stopping of Condensate Oemineralizer pumps using condensate pressure, MFP inlet pressure, condensate booster pump inlet pressure,and#3and#7HOTpumpand bypass valve operation. The US/SRO may startorstop Condensate Oemineralizer pumpsathis discretion,butifanyofthe following occurs the pumps mustbestarted: 1)Condensate Booster Pump suction pressureislessthan125 psig,as indicatedon[PI-2-771. 2)Main Feedwater Pump suction pressurelessthan420psig,as indicated on[PI-2-1291. 3)Injection Water Pump discharge pressureislessthan265psig,as indicated by an alarm on XA-55-3B window E-1.NOTES1)Should#7heaterdraintank pump(s)ampsswingorifsystempressureneedstobe increased by approximately40psig,thenCond 01 Boosterpumpscanbe started;however,twoofthethreepumpsmustbestartedatthesametime. 2)When placing condensatepumpsinservice, ensuremainregvalvesrespondcorrectlyandthen stabilizeinan acceptable band.[43]EVALUATEstartingtwo condensate demineralizer boosterpumpsin accordance with 1,2-S0-2/3-1(ThisstepcanbeN/A'dor signed-offattimewhenpumpsarestarted). NOTE If starting up following refueling operations and reactivity calculationsandtestswere completed at>>30%reactorpower,thenreactivity calculationsandtestsmustbe performed again at<<75%RTP.([44]IF all applicableportionsof 0-RT-NUC-000-001.0arecompleteforpower increase above75%ofratedthermalpower, THEN N/AthefollowingStep5.1[45].(Reactor Engineering) SQN NORMAL POWER OPERATION 0-GO-5Unit1&2Rev.0052Page43of93 STARTUPNo._Unit__Date_(5.1 Power AscensionFrom30%to100%(continued) CAUTION After refueling, NIS indicationsmaybe inaccurate until calibration at higher power levels.DO NOT increase power above75%until applicable portions of O-RT-NUC-000-001.0 are complete.[45]IF startup is following refueling, THEN PERFORM the followingpriorto operation above75%power: (may be performedinanyorder) [45.1]ENSUREthefollowinghavebeen performed (may beN/A'dby ReactorEng.and InstrumentMaint.ifNOT required): A.O-SI-NUC-OOO-126.0, Hot Channel Factor Determination.RxEng B.O-SI.,.NUC-092-079.0, Incore-Excore Axial Imbalance Comparison.RxEng Date Date SQN NORMAL POWER OPERATION 0-GO-5 Unit1&2Rev.0052Page44of93 STARTUPNo._Unit--Date_5.1 Power Ascension From 30%to100%(continued)C.O-PI-NUC-092-036.0, Incore/Excore Detector Calibration (N/A if NOTrequiredorif MFD<3%).RxEngD.O-PI-NUC-092-002.0,DetectorSinglePoint Alignment. RxEngE.O-PI-IXX-092-N45.0,PRNISCalibration.RxEng Date ([45.2]NOTIFYSystemsEngtoperform O-PI-SXX-OOO-022.2 tocheckRCSLoopZeros.[C.7] [45.3]ENSURE applicableportionsof O-RT-NUC-OOO-001.0arecompleteforoperationabove75%RTP. oRxEngr. SQN NORMAL POWER OPERATION 0-GO-5Unit1&2Rev.0052Page45of93 STARTUP No.Unit__Date_5.1 Power AscensionFrom30%to100%(continued) NOTES 1)O-SI-OPS-092-078.0maybeperformedatthediscretionofthe OperatorifoneormorePRMsis indicatingclosetothe +/-2%tolerance.2)Steps5.1[46]and5.1[47]maybeperformedoutofsequence. [46]PERFORMthefollowingat approximately75%reactorpower:[46.1]IFLEFMindicationisavailable, THEN CALCULATE Calorimetric power: Calorimetricpower=U2118 34.55=%---D ([46.2]IFLEFMindicationisNOTavailable, THEN CALCULATEreactorpower: Calorimetricpower=U1118 34.11=%---D[46.3]VERIFYthatallNISPowerRangeAchanneldrawersarewithin+/-2%ofthecalculated calorimetric power.N-41 (XI-92-5005B) YESD NOD N-42 (XI-92-5006B) YESD NOD N-43 (XI-92-5007B) YESD NOD N-44 (XI-'92-5008B)YESD NOD[46.4]IFanyofthe abovestepsarecheckedNO, THEN PERFORM O-SI-OPS-092-078.0. SQN NORMAL POWER OPERATION 0-GO-5 Unit1&2Rev.0052Page46 of 93 STARTUP No.Unit__Date_(5.1 Power Ascension From 30%to 100%(continued) CAUTIONS 1)LCV-6-105A and/or 1058 may be throttling open due to condensate system pressure being higher than#3HDT pump discharge pressure.2)Turbine run back will occur if#3HDT pump flow to the condensate system drops below 5500 gpm (for greater than 10 seconds), condensate bypass valve LCV-6-105A or 1058 opens, and turbine load is above 81%(Unit 1)or 82%(Unit 2).[47]PRIORtoincreasing turbineloadabove77%: ENSUREthefollowing:[47.1]LCV-6-106Aand -1068arecontrollingproperly. [47.2]LCV-6-105A and-1058 are CLOSED.NOTERamploadrate increasesshallbewithinthelimitsofTI-40. [48]RECORD power ascensionrampratefromTI-40._ NOTES o 1)Operation above75%LoadwithonlytwoHotwellPumpsinservicerequiresfurther evaluation. 2)Steps5.1[49]through5.1[52]maybeperformedoutof sequence.([49]CONTINUE the powerascensionto90%reactorpower. o SON NORMAL POWER OPERATION 0-GO-5 Unit 1&2Rev.0052Page47 of 93 STARTUPNo._Unit__Date_(5.1 Power Ascension From 30%to 100%(continued) NOTEControlrodsmaybeusedalongwithdilutionduringreactorpowerincreasetomaintainAFOwithinthetargetcontrolband.[50]IFdilutingtheRCStoincreaseT AVG, THENCONTINUEdilutionandincreaseturbineloadtomaintainT REF with TAVG.(0-SO-62-7) D NOTE GuidanceonrestorationofEHCControlsafteraBOPrunbackviathevalvepositionlimiteriscontainedinAppendixB, Turbine Runback Restoration. [C.4][51]MONITORtheturbineloadincreasingand MAINTAINvalvepositionlimit approximately 10%abovethecurrentgovernorcontrolindicationasturbineloadis changed.D NOTEWhentheturbineimpulsepressurerelaynumberisilluminatedonPanelL-262,therelayisclosedandRunbackcircuitisarmed.[52]WHENgreaterthan77%TurbineLoad,THEN VERIFY[PIS-47-13RLY1] light[fJ,'TurbineRunbackFromLossof1MFP'isilluminatedonPanelL-262.[53]WHENgreaterthan82%TurbineLoad,THENVERIFYthefollowingrelaylightsareilluminatedonPanel L-262:[53.1][PIS-47-13RLY2]J.TurbineRunbackFrom#3HOT.[2] [53.2][PIS-47-13RLY 3]J.NPSHProtectionVLV-6-106Bcloseson#3HOTpumptrip. [1J D o (SQN NORMAL POWER OPERATION 0-GO-5Unit1&2Rev.0052 Paue48of 93 STARTUPNo._Unit__Date_(5.1 Power Ascension From 30%to 100%(continued) NOTES 1)Reactor powercanbeincreased greaterthan90%aslongas adequateMFPsuction is maintained. 2)Steps5.1[54]through5.1[58]maybe performedoutof sequence.[54]WHEN approximately85to90%reactor power OR when determinedbyUnitSRO(if powerraisedabove 90%), THEN ENSURE third condensate boosterpumpin service in accordance with 1,2-S0-2/3-1. [C.2]NOTE A nominal CBP suction pressure of approximately180psig,as indicated on[PI-2-77], will alleviate bypassingtothe condenseratfullpower. [55]IF condensate pressureishigh resultingin#3or#7 heaterdraintank bypassingtothecondenser, ORthenormallevelcontrolvalvesarenearfullopen, THEN[55.1]THROTTLE[14-550]toattaindesired condensate pressure.[55.2]IF unabletothrottle [14-550], THEN REFER to 1,2-S0-5-2, Section8.0to adjust condensate pressure.OR[55.3]EVALUATEremovalofthe condensate demineralizer booster pumps (N/AifNOTin service).o SQN NORMAL POWER*OPERATION 0-GO-5 Unit1&2Rev.0052 Page49of93 STARTUP No.._Unit__Date_(5.1 Power Ascension From 30%to 100%(continued) NOTETwoCond 01 Boosterpumpsmustbestartedatthesametime. [56]EVALUATE starting available condensate demineralizer boosterpump(s)toraisesystem pressure-40psig.Pump StartedYES0 NO 0[57]WHENreactorpoweris approximately 90%, THEN PERFORM the following: [57.1]ADJUST Power Range instrumentation in accordance with 0-SI-OPS-092-078.0. [57.2]INITIATE performance of 1-PI-OPS-000-020.1 or 2-PI-OPS-000-022.1, Appendix B.CAUTION The potential exists for condensation formation in steam extraction lines when feedwater heaters are isolated.[57.3]ENSURE the following level controllers are maintaininglevelswithinnormalranges: A.Secondaryplantheaters.B.MSRdraintanks. CAUTION DO NOT exceed an average of 3455.0 MWT during an a-hour period.rC.1][58]MONITOR NIS, L\Tand calorimetriesonplant computer (pt.U2118)while increasingreactorpower. o o o SQN NORMAL POWER OPERATION 0-GO-5 Unit 1&2Rev.0052Page50 of 93 STARTUP No.-.--_Unit__Date_5.1 Power Ascension From 30%to 100%(continued) NOTES 1)FeedwaterventuriunfoulingmayimpactU1118indication.LEFM calorimetric power (U2118)isnotaffectedbyventuriunfouling.2)IfU1118isbeingusedtomonitorreactorpowerduetoLEFMunavailable,then CalorimetricCalculationshouldbeperformedpriortoexceeding97%reactorpower.3)Steps5.1[59]through 5.1[63]maybeperformedoutofsequence.[59]IFUnitisreturningtofullpowerafteraturbineloadreductiontolessthan50% AND U1118isbeingusedtomonitorpower, THEN (PERFORMthe followingpriortoexceeding97%power:[59.1]NOTIFYSystemsEngineeringtoperform0-PI-SXX-000-022.2,CalorimetricCalculation,Section8.1,ifnecessary.[59.2]PERFORMapplicablesectionsof 0-PI-SXX-000-022.2toadjustFeedwaterFlowConstant.(N/AifNOT required)oBOPEng SQN NORMALPOWEROPERATION 0-GO-5 Unit 1&2Rev.0052Page51 of 93 STARTUPNo,_Unit__Date_(5.1 Power Ascension From 30%to 100%(continued) NOTERamploadrateincreasesshallbewithinthelimitsofTI-40.[60]RECORDthefollowingfromTI-40: [60.1]PowerascensionrampratefromTI-40._ NOTEN/Asubstep5.1[60.2]and5.1[60.3]ifnotinitialstartupafterrefuelingoutage.[60.2]Intermediatepowerthresholdsetpoint_[60.3]RampRateabovetheintermediatepowerthreshold._[61]CONTINUEpowerascensionto100%RTP. NOTE o o o oControlrodsmaybeusedalongwithdilutionduringreactorpowerincreasetomaintainAFDwithinthetargetcontrolband.[62]IFdilutingtheRC8toincrease TAVG.THENCONTINUEdilutionandincreaseturbineloadtomaintainT REF with TAVG.(0-80-62-7) 0 NOTEValvepositionlimitandgovernorcontrolmeteraredisplayedonEHCDisplaypanel1,2-XX-047-2000(M-2).[63]MONITORtheturbineloadincreasingAND MAINTAINvalvepositionlimitapproximately10%abovethecurrentgovernorcontrolindicationasturbineloadischanged.0 SQN NORMAL POWER OPERATION 0-GO-5Unit1&2Rev.0052 Paqe52of93 STARTUPNo._Unit__Date----5.1 Power AscensionFrom30%to100%(continued) NOTE Steps5.1[64]through5.1[66]maybeperformedoutofsequence. [64]WHEN reactor power approaches 100%, THEN ADJUST governorvalveposition limiter-2%above governor valve position.0 CAUTION Governor valve position limit metermayNOT match the governor valve position meter;therefore, monitor the megawatt meterandvalve position limit light continuously during the following step.NOTES (1)Operationwiththe VALVEPOSLIMITlightLITis acceptable if unsatisfactory load swings are experienced. 2)Actions effecting reactivityaredirectedinthe followingstep.All appropriate verificationsandpeerchecksshallbeutilizedduring performance. [65]IF unsatisfactoryloadswingsare experiencedastheunit approachesfullpower, THEN[65.1]WITH turbineloadsetfor maximumof100%power, SLOWLY and CAUTIOUSLY PULSE the governor VALVE POSITIONLIMITin LOWERdirectionwhile monitoring megawattsfora decreaseandVALVEPOS LIMITlightto ILLUMINATE. 0[65.2]WHEN the limiter just reaches the governor valve position, THEN STOP limiter adjustment. o (SQN NORMAL POWER OPERATION 0-GO-5 Unit1&2Rev.0052Page53of93 STARTUPNo._Unit__Date----5.1 Power AscensionFrom30%to100%(continued) CAUTIONDonotraisethe limiter position unless the turbinecontrolis positively controlling the turbine (limit lightNOTLIT).NOTE Actions effecting reactivityaredirectedinthefollowingstep.All appropriate verificationsandpeerchecksshallbeutilizedduring performance. [66]PERFORMthefollowingifthe limiterpreventsreactor operation at approximately 100%:[66.1]ADJUST SETTER/REFERENCEcontrolstoreduceturbineloadinguntiltheVALVEPOSLIMITlightisNOT LIT.0 ([66.2]INCREASEVALVEPOSITIONLIMITtoallowaload increaseusingthe SETTER/REFERENCE controls,NOTtoexceed3455.00MWT. o SQNNORMALPOWEROPERATION0-GO-5Unit1&2Rev.0052 Page54of93 STARTUP No.._Unit__Date_5.1 Power AscensionFrom30%to100%(continued) NOTES1)Full power operationisdefinedas100%power operation at approximately 3455 MW T instantaneousvalue,U2118nottoexceed 3455.00 MW T average thermalpowerinan 8-hour period.[C.1]2)Donot intentionally operatethereactorat greaterthan100%power(e.g.,if reactor powerislessthan100%foranytimeperiodthen operation at slightly greaterthan100%to"makeup"for"lost"powerisnot permissible). [C.1]3)Computer pointU2118shouldbetrendedonatrend recorderintheunit horseshoe and monitored for increasing reactorpowertrends above 3455 MW T.Prompt actionshallbetakento decreasereactorpower whenever an increasing powertrendis observed.[C.1]4)Donotexceedan 8-hour average value (U2126)of 3455.00 MWT.Donot allow U2125 (one houravg)toexceed 3455.00 MW T (100%)formorethanonehour. [C.1]5)Portionsofstep5.1[68]maybe performedinparallelwithstep5.1[67]ifrequired. [67]WHENtheunit stabilizesat100%reactor power, THEN PERFORM the following:(maybe performedinanyorder) [67.1]ADJUST GovernorValveposition,rodheight, and/orRCSboron concentration as necessary to establish core thermal poweratdesired value and Auctioneered Hi T-avg approximatelyequalto Tvref.0[67.2]NOTIFY load coordinatorthatthe power increase is complete.0[67.3]NOTIFY RADCONthatpowerhas stabilizedat100%.0(stepcontinuedonnextpage) SQN NORMAL POWER OPERATION 0-GO-5 Unit 1&2Rev.0052Pace55 of 93 STARTUPNo,_Unit__Date_5.1 Power Ascension From30%to100%(continued) NOTEUseofsealsteamspilloverbypass FCV-47-191shouldbeminimizedtoreducetheeffectofunittriponsealsteampressure.[67.4]IFSealSteamspilloverbypass[FCV-47-1911isINSERVICE,THEN THROTTLESealSteamspilloverbypasstocontrol[FCV-47-1911asrequiredtocontrolsealsteam pressure.[67.5]IFrivertemperatureislessthan45°F,THEN o CONSULTEngineeringtodetermineifthirdCCWpumpshouldberemovedfromservice. 0 ([67.6]CONTACTvibrationengineerin Predictive MaintenanceGrouptomonitorMFWPvibration. CAUTION A bias adjustment in the upward direction (>50%)shouldNOTbe used unless evaluated by Systems Engineering since this could impact a MFPT's maximum speed and the ability to fully loadinthe event the other MFPT trips.o[67.7]IFfeedpumpvibrationisabovedesiredlevels, THEN CONSULTwithvibrationengineerandsystemengineertodeterminewhichfeedpumptobiastoreduce vibration. 0[67.8]IFMFPTmastercontrolleroutputisNOTindicating45%to55%THEN CONSULTwithMFPTcontrolssystemengineertoevaluateifadjustmentisrequiredper 1,2-S0-2/3-1. 0 SQN NORMAL POWER OPERATION 0-GO-5 Unit1&2Rev.0052Page56of93 STARTUP No.._Unit__Date_5.1 Power AscensionFrom30%to 100%(continued) [68]IFstartupisfollowingrefuelingactivities, THEN ENSUREthefollowingareperformedatapproximately100%RatedThermalPower:(maybeperformedinanyorder)[68.1]0-PI-SXX-000-022.2,CalorimetricCalculation.[68.2]0-PI-SXX-000-022.1,DeltaTandTavgUpdate.[C.?][68.3]0-SI-NUC-000-126.0,HotChannelFactorDetermination.SystemsEng.SystemsEng.. SQN NORMAL POWER OPERATION 0-GO-5 Unit 1&2Rev.0052Page57 of 93 STARTUPNo._Unit--Date_5.1 Power AscensionFrom30%to 100%(continued) NOTEThisstepmaybe performedoutof sequenceifrequired. [69]IF Steam GeneratorWRlevel recorderswerere-scaledto80%-90%in0-GO-2, THEN NOTIFYMIGtore-scale LR-3-43AandLR-3-98A,Steam GeneratorWideRangeLevel Recorders,to0%-100%. [70]IFunitshutdownto minimum load, THENGOTOSection5.3. [71]IFunitistobe maintainedatnormalpower, THENGOTOSection5.2.ENDOFTEXT}}