ML17319B287

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Tech Specs for Redundant Decay Heat Removal Capability, Donald C Cook Nuclear Plant,Units 1 & 2, Technical Evaluation Rept
ML17319B287
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 02/28/1982
From: STEVERSON J A
EG&G, INC.
To: DONOHEW J N
Office of Nuclear Reactor Regulation
References
CON-FIN-A-6429 EEG-EA-5746, EGG-EA-5746, NUDOCS 8204140631
Download: ML17319B287 (20)


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EGG"EA-5746FEBRUARY1982TECHNICALSPECIFICATIONSFORREDUNDANTDECAYHEATREMOVALCAPABILITY,DONALDC.COOKNUCLEARPLANT,UNITNOS.1AND2J.A.SteversonU.S.DepartmentofEnergyIdahoOperationsOffice~IdahoNationalEngineeringLaboratory~Iii14I~A~%8WThisIsaninformalreportIntendedforuseasapreliminaryorworkingdocumentPreparedfortheU.S.Nuc1earRegulatoryCommissionUnderDOEContractNo.DE-AC07-76ID01570.FINNo.A6429~+E&Z&Idah0o~n~

+QG&g&Idaho.Inc.FOAME04G-508[Rsv.114'I)INTERIMREPORTAccessionNo.ReportNoEGG-EA"5746ContractProgramorProjectTitle:SelectedOperatingReactorsIssuesProgramtIII)SubjectofthisDocument:TechnicalSpecificationsforRedundantDecayHeatRemovalCapability,DonaldC.CookNuclearPlant,UnitNos.1and2TypeofDocument:TechnicalEvaluationReportAuthor(s):J.A.SteversonDateofDocument:February1982ResponsibleNRCIDQEIndividualandNRCIDOEOfficeorDivision:J.N.DonohevI,DivisionofLicensing,NRCThisdocumentwaspreparedprimarilyforpreliminaryorinternaluse.Ithasnotreceivedfullreviewandapproval.Sincetheremaybesubstantivechanges,thisdocumentshouldnotbeconsideredfinal.EGBGIdaho,inc.IdahoFalls,Idaho83415PreparedfortheU.S.NuclearRegulatoryCommissionWashington,D.C.UnderDOEContractNo.DE-AC07-76ID04670.~4649INTERIMREPORT 0030'ECHNICALEVAIUATIONREPORTTECHNICALSPECIFICATIONSFORREDUNDANTDECAYHEATREMOVALCAPABILITYDONALDC.COOKNUCLEARPLANT,UNITNOS.1AND2DocketNos.50-315and50-316February1982J.A.SteversonReliabilityandStatisticsBranchEngineeringAnalysisDivisionEGKIdaho,Inc.TACNo".42093and42094 ABSTRACTThisreportreviewstheDonaldC.CookNuclearPlant,UnitNos.1and2,proposedtechnicalspecificationsforredundancyindecayheatremovalcapabilityinallmodesofoperation.FOREWORDThisreportissuppliedaspartofthe"SelectedOperatingReactorIssuesProgram(III)"beingconductedfortheU.S.NuclearRegulatoryCommission,OfficeofNuclearReactorRegulation,DivisionofLicensing,byEGKIdaho,Inc.,ReliabilityandStatisticsBranch.TheU.S.NuclearRegulatoryCommissionfundedtheworkundertheauthorization,B&R20190206,FINNo.A6429.

TECHNICALEVALUATIONREPORTTECHNICAISPECIFICATIONSFORREDUNDANTDECAYHEATREMOVALCAPABILITY'.0INTRODUCTION'numberofeventshaveoccurredatoperatingPWRfacilitieswheredecayheatremovalcapabilityhasbeenseriouslydegradedduetoinadequateadministrativecontrolsduringshutdownmodesofoperation.Oneoftheseevents,describedinIEInformationNotice80-20,occurredattgeDavis-Besse,UnitNo.1plantonApril19,1980.InIEBulletin80-12~datedMay9,1980,licenseeswererequestedtoimmediatelyimplementadministra-tivecontrolswhich'wouldensurethatpropermeansareavailabletoprovideredundantmethodsofdecayheatremoval.Whilethefunctionofthebul-letinwastoeffectimmediateactionwithregardtothisproblem,theNRCconsidereditnecessarythatanamendmentofeachlicensebemadetopro-videforpermanentlong-termassurancethatredundancyindecayheatremovalcapabilitywillbemaintained.'yletterdatedJunell,1980,~allPWRlicenseeswererequestedto:1)proposetechnicalspecification(TS)changesthatprovideforredundancyindecayheatremovalcapabilityinallmodesofoperation,2)usetheNRCmodelTSwhichprovideanacceptablesolutionoftheconcernandincludeappropriatesafetyanalysesasbases,and3)submittheproposedTSwiththebasesbyOctoberll,1980.Indiana5MichiganElectricCompany,NewYork,NewYork,submittedpro-posedrevisionsfordecayheatremovaltotheirtechgicalspecificationsforDonaldC.CookNuclearPlant,UnitNos.1and2,onAugust14,1981.ThefollowingdiscussionevaluatestheproposedTSandnotesanydifferencesexistingbetweenthemandthemodelTSprovidedbytheNRC(AppendixA).Therequirementsarecompared'orequivalentmodesofoperation.2.0DISCUSSIOND.C.Cook,Units1and2arefour-loopWestinghousePWRplants.SpecificsectionsoftheWestinghouseStandardTechnicalSpecifications5thatapplytothistaskare:3/4.43/4.413/4.93/4.9.8REACTORCOOLANTSYSTEMREACTORCOOLANTLOOPSANDCOOLANTCIRCULATIONREFUELINGOPERATIONSRESIDUALMEATRBSVALANDCOOLANTCIRCULATIONTheproposed0.C.CooktechnicalspecificationsareinverycloseagreementwiththemodelTSgoaded'ytheNRC.SurveillanceRequire-ment4.9.8.1,however,statesthatatleastoneresidualheatremovalloopmustbeverifiedtobeinoperationand,circulatingreactorcoolantataflowrateofgreaterthanorequalto2800gpmatleastonceper4hours.TheproposedTSrequiretheflowrateofatleast3000gpmtobeverifiedatleastonceevery24hours.Alothe~ltMingConditionsandSurveil-lanceRequirementsinte.C~ookproposedTSareincompleteagreementwiththoseintheNRCmodelTS.1 j'.0REFERENCES1.'RCIEInformationNotice80-20,May8,1980.2.NRCIEBulletin80-12,May9,1980.3.NRCletter,0G.Eisenhut,ToAllOperatingPressurizedWaterReac-tors(PWR's),datedJunell,1980.4.Indiana5MichiganElectricCo.letter,G.P.MaloneytoH.R.Denton,datedAugust14,1981.5.StandardTechnicalSpecificationsforWestinghousePressurizedWaterReactors,NUREG-0452-Rev.3,Fall1980.2 APPENDIXAMODELTECHNICALSPECIFICATIONSFORREDUNDANTDECAYHEATREMOVALFORWESTINGHOUSEPRESSURIZEDWATERREACTORS(PWR's)~I3

~~I/:,]>),"'/lgo/y11 3/4.4REACTORCOOLANTSYSTEM3/4.4.1REACTORCOOLANTLOOPSANDCOOLANTCIRCULATIONSTARTUPANDPOMEROPERATIONLIMITINGCONDITIONFOROPERATION3.4.1.1Allreactorcoolantloopsshallbeinoperation.APPLICABILITY:MODES1and2.*ACT!ON:Mithlessthantheaboverequiredreactorcoolantloopsinoperation,beinatleastHOTSTANDBYwithin1hour.SURVEILLANCEREQUIREMENT4.4.1.1Theaboverequiredreactorcoolantloopsshallbeverifiedtobeinoperationandcirculatingreactorcoolantatleastonceper12hours.*SeeSpecialTestException3.10.4:5

RECTORCOOLANTSYSTEM.HOTSTANDBYLIMITINGCONDITIONFOROPERATION3.4.1.2a.AtleasttwoofthereactorcoolantloopslistedbelowshallbeOPERABLE:1.ReactorCoolantLoop(A)anditsassociatedsteamgeneratorandreacto'rcoolantpump,'2.ReactorCoolantLoop(B)anditsassociatedsteamgeneratorandreactorcoolantpump,3.ReactorCoolantLoop(C)anditsassociatedsteamgeneratorandreactorcoolantpump,4.ReactorCoolantLoop(0)anditsassociatedsteamgeneratorandreactorcoolantpump.b.Atleastoneoftheabovecoolantloopsshallbeinoperation.*APPLICABILITY:MODE3ACTION:a.WithlessthantheaboverequiredreactorcoolantloopsOPERABLE,restoretherequiredloopstoOPERABLEstatuswithin?2hoursorbeinHOTSHUTDOWNwithinthenext12hours.*Allreactorcoolantpumpsmaybede-energizedforupto1hourprovided(1)nooperationsarepermittedthatwouldcausedilutionofthereactorcoolantsystemboronconcentration,and(2)coreoutlettemperatureismaintainedatleast10oFbelowsaturationtemperature.

REACTORCOOLANTSYSTEMb.Withnoreactorcoolantloopinoperation,suspendalloperationsinvolvingareductioninboronconcentrationoftheReactorCoolantSystemandimmediatelyinitiat'ecorrectiveactionto.returntherequiredcoolantloopto"operation.SURVEILLANCEREQUIREMENT4.4.1.2.1Atleasttheaboverequiredreactorcoolantpumps,ifnotinoperation,shallbedeterminedtobeOPERABLEonceper7daysbyverifyingcorrectbreakeralignmentsandindicatedpoweravailability.4.4.1.2.2Atleastonecoolingloopshallbeverifiedtobeinoperationandcirculatingreactorcoolantatleastonceper12hours.7 REACTORCOOLANTSYSTEMSHUTDOWNLIMITINGCONDITIONFOROPERATION3.4.1.3a.AtleasttwoofthecoolantloopslistedbelowshallbeOPERABLE';ReactorCoolantLoop(A)anditsassociatedsteamgen-eratorandreactorcoolantpump,*2.ReactorCoolantLoop(B)anditsassociatedsteamgen-eratorandreactorcoolantpump,*3.ReactorCoolantLoop(C)anditsassociatedsteamgen-eratorandreactorcoolantpump,*4.ReactorCoolantLoop(0)anditsassociatedsteamgen-eratorandreactorcoolantpump,*l5.ResidualHeatRemovalLoop(A),~6.ResidualHeatRemovalLoop(B).~b.Atleastoneoftheabovecoolantloopsshallbeinoperation.*~*Areactorcoolantpumpshallnot.bestartedwithoneormoreoftheRCScoldlegtemperatureslessthanorequalto.(275)Funless1)thepressurizerwatervolumeislessthancubicfeetor2)thesecondarywatertemperatureofeachsteamgeneratorislessthanFaboveeachoftheRCScoldlegtemperatures.ThenormaloremergencypowersourcemaybeinoperableinMODE5.*"+Allreactorcoolantpumpsanddecayheatremovalpumpsmaybede-ynergizedforupto1hourprovided1)nooperationsarepermittedthat-~ouldcausedilutionofthereactorcoolantsystemboronconcentration,and2)coreoutlettemperatureismaintainedatleast10oFbelowsaturationtemperature.8 REACTORCOOLANTSYSTEMAPPLICABILITY:MODES4and5.ACTION:a.WithlessthantheaboverequiredloopsOPERABLE,immediatelyinitiatecorrectiveactiontoreturntherequiredloopstoOPERABLEstatusassoonaspossible;beinCOLDSHUTDOWNwithin20hours.b.Withnocoolant,loopinoperation,suspendalloperationsinvolvingareductioninboronconcentrationoftheReactorCoolantSystemandimmediatelyinitiatecorrectiveactiontoreturntherequiredcoolantlooptooperation.SURVEILLANCEREQUIREMENT4.4.1.3.1Therequiredresidualheatremovalloop(s)shallbedeterminedOPERABLEperSpecification4.0.5.4.4.1.3.2Therequiredreactorcoolantpump(s),ifnotinoperation,shallbedeterminedtobeOPERABLEonce'per7daysbyverifyingcorrectbreakeralignmentsandindicatedpoweravailability.4.4.1.3.3Therequiredsteamgenerator(s)shallbedeterminedOPERABLEbyverifyingsecondarysideleveltobegreaterthanorequalto()Xatleastonceper12hours.4.4.1.3.4Atleastonecoolantloopshallbeverifiedtobeinoperationandcirculatingreactorcoolantatleastonceper12hours.

SREFUELINGOPERATIONS3/4.9.8RESIDUALHEATREMOVALANDCOOLANTCIRCULATIONALLWATERLEVELSLIMITINGCONDITIONFOROPERATION3.9.8.1Atleastoneresidualheatremoval(RHR)loopshallbeinoperation.APPLICABILITY:MODE6ACTION:a.Withlessthanone.residualheatremovalloopinoperation,exceptasprovidedinb.below,suspendalloperationsinvolvinganincreaseinthereactordecayheatloadorareductionin-boronconcentrationoftheReactorCoolantSystem.Closeallcontainmentpenetrationsprovidingdirectaccessfromthecon-tainmentatmospheretotheoutsideatmospherewithin4hours.b.Theresidualheatremovalloopmayberemovedfromoperationforupto1hourper8hourperiodduringtheperformanceofCOREALTERATIONSinthevicinityofthereactorpressure.vessel(hot)legs..c.TheprovisionsofSpecification3.0.3arenotapplicable.NSURVEILLANCEREQUIREMENT4.9.8.1Atleastoneresidualheatremovalloopshallbeverifiedtobeinoperationandcirculatingreactorcoolantataflowrateofgreaterthanorequalto(7800)gpmatleastonceper4hours.10 REFUELINGOPERATIONSLOWWATERLEVELLIMITINGCONDITIONFOROPERATION3.9.8.2TwoindependentResidualHeatRemoval(RHR)loopsshallbeOPERABLE.*APPLICABILITY:MODE6whenthewaterlevelabovethetopoftheirradiatedfuelassembliesseatedwithinthereactorpressurevesselislessthan23feet.ACTION:a.WithlessthantherequiredRHRloopsOPERABLE,immediatelyinitiatecorrectiveactiontoreturntherequiredRHRloopstoOPERABLEstatusassoonaspossible.b.TheprovisionsofSpecification3.0.3arenotapplicable.SURVEILLANCEREQUIREMENT4.9.8.2TherequiredResidualHeatRemovalloopsshallbedeterminedOPERABLEperSpecification4.0.5.*Thenormaloremergencypowersourcemay.beinoperableforeachRHRloop.

BASES3/4.4.1REACTORCOOLANTLOOPSANDCOOLANTCIRCULATIONTheplantisdesignedtooperatewithallreactorcoolantloopsinoperation,andmaintainDNBRabove1.30duringallnormaloperationsandanticipatedtransients.InMODES1and2withonereactorcoolantloopnotinoperationthisspecificationrequiresthattheplantbeinatleastHOTSTANDBYwithin1hour.InMODE3,asinglereactorcoolantloopprovidessufficientheatremovalcapabilityforremovingdecayheat;however,singlefailurecon-siderationsrequirethattwoloopsbeOPERABLE.InMODES4and5,asinglereactorcoolantlooporRHRloopprovidessufficientheatremovalcapabilityforremovingdecayheat;butsinglefailureconsiderationsrequirethatatleasttwoloopsbeOPERABLE.Thus,ifthereactorcoolantloopsarenotOPERABLE,thisspecification'requirestwoRHRloopstobeOPERABLE.TheoperationofoneReactorCoolantPumporoneRHRpumpprovidesadequateflowtoensuremixing,preventstratificationandproducegradualreactivitychangesduringboronconcentrationreductionsintheReactorCoolantSystem.Thereactivitychangerateassociatedw'thboronreductionwill,therefore,bewithinthecapabilityofoperatorrecognitionandcontrol.TherestrictionsonstartingaReactorCoolantPumpwithoneormoreRCScoldlegslessthanorequalto(275)oFareprovidedtopreventRCSpressuretransients,causedbyenergyadditionsfromthesecondarysystem,whichcouldexceedthelimitsofAppendixGto10'CFRPart50.TheRCSwillbeprotectedagainstoverpressuretransientsandwillnotexceedthelimitsofAppendixGbyeither(1)restrictingthewatervolumeinthe'ressurizerandtherebyprovidingavolumefortheprimarycoolanttoexpandinto,or(2)byrestrictingstartingoftheRCPstowhenthesecon-darywatertemperatureofeachsteamgeneratorislessthan()FaboveeachoftheRCScoldlegtemperatures.12

.*sREFUELINGOPERATIONSBASES3/4.9.8RESIDUALHEATREMOVAIANDCOOLANTCIRCULATIONTherequirementthatatleastoneresidualheatremoval(RHR)loopbeinoperationensuresthat(1)sufficientcoolingcapacityisavailabletoremovedecayheatandmaintainthewaterinthereactorpressurevesselbelow140FasrequiredduringtheREFUELINGMODE,and(2)sufficientcool-antcirculationismaintainedthroughthereactorcoretominimizetheeffectofaborondilutionincidentandpreventboronstratification.TherequirementtohavetwoRHRloopsOPERABLEwhenthereislessthan23feetofwaterabovethecoreensuresthatasinglefailureoftheoper-atingRHRloopwillnotresultinacompletelossofresidualheatremovalcapability.Withthereactorvesselheadremovedand23feetofwaterabovethecore,alargeheatsinkisavailableforcorecooling.Thus,intheeventofafailureoftheoperatingRHRloop,adequatetimeisprovidedto~nitiateemergencyprocedurestocoolthecore.13 I4=