ML17244A180

Application for Amend to License DPR-18,changing Tech Specs to Reflect Overpressure Protection Sys Requirements.Safety Evaluation & Justification for Continued Operation Encl

ML17244A180
Person / Time
Site:	Ginna
Issue date:	10/11/1978
From:	WHITE L D ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17244A179	List: ML17244A178 ML17244A180
References
TASK-05-03, TASK-5-3, TASK-RR NUDOCS 7810190069
Download: ML17244A180 (17)

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UNITEDSTATESOFAMERICANUCIEARREGULATORYCOMMISSIONIntheMatterofRochesterGasandElectricCorporation(R.E.GinnaNuclearPowerPlant.,UnitNo.l))))DocketNo.50-244))APPLICATIONFORAMENDMENTTOOPERATINGLICENSEPursuanttoSection50.90oftheregulationsoftheU.S.NuclearRegulatoryCommission(the"Commission"),RochesterGasandElectricCorporation("RG&E"),holderofProvisionalOperatingLicenseNo.DPR-18,herebyrequeststhattheTechnicalSpecifica-tionssetforthinAppendixAtothatlicensebeamendedtoincludereactoroverpressureprotectionsystemrequirements.Theproposedtechnicalspecificationchangeisset.forthinAttachmentAtothisApplication.AsafetyevaluationissetforthinAttachment,B.Thisevaluationalsodemonstratesthattheproposedchangedoesnotinvolveasignificantchangeinthetypesorasignificantincreaseintheamountsofeffluentsoranychangeintheauthorizedpowerlevelofthefacility.Justifi-cationforclassificationoftheamendmentpursuantto10C.F.R.Section170.22isincludedasAttachment,C.AcheckfortheappropriatefeeaccompaniesthisApplication.lS(o]qoo6q WHEREFORE,Applicantrespectfullyrequeststhat.AppendixAtoProvisionalOperatingLicenseNo.DPR-l8beamendedintheformattachedheretoasAttachmentA.RochesterGasandElectricCorporationByL.D.Whxe,Jr.VicePresident,ElectricandSteamProductionSubscribedandsworntobeforemeonthis///FLBayofOctober,1978.GARYL.REISSNOTARYPUBLIC,StatoofN.Y.MonroeCo.MyCommtssiooExpiresMarchpp,19,./yg AttachmentAFigure3.10-2isnotmet,theplantshallbetakentothehotshutdownconditionandtheoneloopshutdownmarginshallbemet.d.AtleastonereactorcoolantpumpshallbeinoperationforaplannedtransitionfromoneReactorOperatingModetoanotherinvolvinganincreaseintheboronconcentrationofthereactorcoolant.e.AreactorcoolantpumpshallnotbestartedwithoneormoreoftheRCScoldlegtemperatures<330'Funless1)thepressurizerwatervolume7slessthan324cubicfeet(38%level)or2)thesecondarywatertemperatureofeachsteamgeneratorislessthan50'FaboveeachoftheRCScoldlegtemperatures.3.1.1.2SteamGeneratora.Onesteamgeneratorshallbecapableofperformingitsheattransferfunctionwhenevertheaveragecoolanttemperatureisabove350'F.b.Thetemperaturedifferenceacrossthetubesheetshallnotexceed100'F.3.1.1.3SafetValvesa~Atleastonepressurizercodesafetyvalveshallbeoperablewheneverthereactorheadisonthevessel.b.Bothpressurizercodesafetyvalvesshallbeoperablewheneverthereactoriscritical.Basis:Whentheboronconcentrationofthereactorcoolantsystemistobereducedtheprocessmustbeuniformtopreventsuddenreactivitychangesinthereactor.Mixingofthereactorcoolantwillbesufficient3+12Proposed

Eachofthepressurizercodesafetyvalvesisdesignedtorelieve288,000lbs.perhr.ofsaturatedsteamatthevalvesetpoint.Below350'Fand350psiginthereactorcoolantsystem,theresidualheatremovalsystemcanremovedecayheatandtherebycontrolsystemtemperatureandpressure.Ifnoresidualheat.wereremovedbyanyofthemeansavailabletheamountofsteamwhichcouldbegeneratedatsafetyvalvereliefpressurewouldbelessthanhalfthevalves'apacity.Onevalvethereforeprovidesadequatedefenseagainstoverpressurization.ProhibitingreactorcoolantpumpstartswithoutalargevoidinthepressurizerorwithoutalimitedRCStemperaturedifferentialwillpreventRCSoverpressurizationduetoexpansionofcoolerRCSwaterasitentersawarmersteamgenerator.A38%levelinthepressurizerwillaccommodatetheswellresultingfromareactorcoolantpumpstartwithaRCStemperatureof140'Fandsteamgeneratorsecondarysidetemperatureof340'F,orthemaximumtemperaturewhichusuallyexistspriortocoolingthereactorwiththeRHRsystem.Thespecificationpermitsanorderlyreductioninpowerifareactorcoolant(gampislostduringoperationbetween130MWTand50%ofratedpower.Above50%power,anautomaticreactortripwilloccurifeitherpumpislost.Thepower-to-flowratiowillbemaintainedequaltoorlessthanonewhichensuresthattheminimumDNBratioincreasesatlowerflowsincethemaximumenthalpyrisedoesnotincrease.Temperaturerequirementsforthesteamgenerator'correspondwithmeasuredNDTfortheshellandallowablethermalstressesinthetubesheet.References(1)FSARSection14.1.6(2)FSARSection7.2.3Proposed c~Oneboricacidtankmaybeoutofserviceprovidedaminimumof2,000gallonsofa12%to13%byweightboricacidsolutionatatemperatureofatleast145'Fiscontainedintheoperabletankandprovidedthatthetankisrestoredtooperablestatuswithin24hours.d.Onechannelofheattracingmaybeoutofserviceprovideditisrestoredtooperablestatuswithin24hours.3.2.4Basis:Wheneverthereactorcoolantsystemis>200'FandisbeingcooledbytheRHRsystemandtheoverpressureprotectionsystemisnotoperable,atleastonechargingpumpshallbedemonstratedinoperableat,leastonceper12hoursbyverifyingthatthecontrolswitchisinthepull-stopposition.Thechemicalandvolumecontrolsystemprovidescontrolofthereactorcoolantsystemboroninventory.Thisisnormallyaccomplishedbyusingeitheroneofthethreechargingpumpsinserieswithoneofthetwoboricacidpumps.Analternatemethodofborationwillbetousethechargingpumpsdirectlyfromtherefuelingwaterstoragetank.Athirdmethodwillbetodepressurizeandusethesafetyinjectionpumps.Therearetwosourcesofboratedwateravailableforinjectionthroughthreedifferentpaths.(1)Theboricacidtransferpumpscandelivertheboricacidtankcontents(12%concentrationofboricacid)tothechargingpumps.(2)Thechargingpumpscantakesuctionfromtherefuelingwaterstoragetank.(2,000ppmboronsolution)(3)Thesafetyinjectionpumpscantaketheirsuctionsfromeithertheboricacidtanksortherefuelingwaterstoragetank.Thequantityofboricacidinstoragefromeithertheboricacidtanksortherefuelingwaterstoragetankissufficienttoborate.thereactorcoolant.inordertoreachcoldshutdownatanytimeduringcorelife.Approximately1800gallonsofthe12%to13%solutiqy)ofboricacidare.requiredtomeetcoldshutdowncondi-tions.'hus,aminimumof2000gallonsintheboricacidtanksisspecified.Anupperconcentrationlimitof13%boricacidinthetankisspecifiedtomaintainsolutionsolubilityatthespeci-fiedlowtemperaturelimitof145'F.Twochannelsofheattracingareinstalledonlinesnormallycontainingconcentratedboricacidsolutiontomaintainthespecifiedlowtemperaturelimit,.3~23Proposed Placingachargingpumpinpull-stopwheneverthereactorcoolantsystemtemperatureis>200'FandisbeingcooledbyRHRwithout,theoverpressureprotectionsystemoperablewillpreventinadvertayP)overpressurizationoftheRHRsystemshouldletdownbeterminated.

References:

(1)FSAR,Section9.2(2)FSAR,Page9.2-37(3)L.D.White,Jr.lettertoA.Schwencer,NRC,datedFebruary24,19773.2-4Proposed (ii)Thetworeactorcoolantdraintankpumpsshallbetestedandtheiroperabilitydemon-stratedpriortoinitiatingrepairsoftheinoperableresidualheatremovalpump.d.Oneresidualheatexchangermaybeoutofserviceforaperiodofnomorethan24hours.e.Anyvalverequiredforthefunctioningofthesafetyinjectionorresidualheatremovalsystemsmaybeinoperableprovidedrepairsarecompletedwithin12hours.Priortoinitiatingrepairs,allvalvesinthesystemsthatprovidetheduplicatefunctionshallbetestedtodemonstrateoperability.3.3.1.3f.Powermayberestoredtoanyvalvereferencedin3.3.1.1gforthepurposesofvalvetestingprovidingnomorethanonesuchvalvehaspowerrestoredandprovidedtestingiscompletedandpowerremovedwithin12hours.ExceptduringdieselgeneratorloadandsafeguardsequencetestingorwhenthevesselheadisremovedorthesteamgeneratormanwayisopenamaximumofonesafetyinjectionpumpshallbeoperablewheneverthetemperatureofoneormoreoftheRCScoldlegsis<330'F.3.3.1.3.13.3.23.3.2.1Wheneveramaximumofonesafetyinjectionpumpmaybeoperableby3.3.1.3atleasttwoofthesafetyinjectionpumpsshallbedemonstratedinoperableatleastoncepertwelvehoursbyverifyingthatthecontrolswitchesareinthepull-stopposition.ContainmentCoolinandIodineRemovalThereactorshallnotbemadecriticalexceptforlowtemperaturephysicstests,unlessthefollowingcondi-tionsaremet:a~b.c~Thesprayadditivetankcontainsnotlessthan4500gallonsofsolutionwithasodiumhydroxideconcentrationofnotlessthan30%byweight.Atleasttwocontainmentspraypumpsare'perable.Atleastthreefancoolerunitsareoperable.3.3-4Proposed

'untilrepairswereeffected.Thefacilityhasfourservicewaterpumps.Onlyoneisneededduringtheinjectionphase,andtwoarerequiredduringtherecirculationphaseofapostulatedloss-of-coolantaccident.(8)Thelimitsfortheaccumulatorpressureandvolumeassurethere-quiredamountofwaterinjectionduringanaccident,andarebasedonvaluesusedfortheaccidentanalyses.Theindicatedlevelof50%correspondsto1108cubicfeetofwaterintheaccumulatorandtheindicatedlevelof82%correspondsto1134cubicfeet.Thelimitationforamaximumofonesafetyinjectionpumptobeoperableandthesurveillancerequirementtoverifythattwosafetyinjectionpumpsareinoperablebelow330'FprovidesassurancethatamassadditionpressuretransientcanberelievedbytheoperationofasinglePORV.3~312Proposed 3.15OveressureProtectionSstem~lb1ApplieswheneverthetemperatureofoneormoreoftheRCScoldlegsis<330'F.Ob'ctiveTopreventoverpressurizationofthereactorcoolantsystem.Secification3.15.1Atleastoneofthefollowingoverpressureprotectionsystemsshallbeoperable:a.Twopressurizerpoweroperatedreliefvalves(PORVs)withaliftsettingof<435psig,orb.Areactorcoolantsystemventof>1.1squareinches.3.15.1.1WithonePORVinoperable,eitherrestoretheinoperablePORVtooperablestatuswithin7daysordepressurizeandventtheRCSthrougha1.1squareinchvent(s)withinthenext8hours;maintaintheRCSinaventedconditionuntilbothPORVshavebeenrestoredtooperablestatus.3.15.1.23.15.1.3WithbothPORVsinoperable,depressurizeandventtheRCSthrougha1.1squareinchvent(s)within8hours;maintaintheRCSinaventedconditionuntilbothPORVshavebeenrestoredtooperablestatus.UseoftheoverpressureprotectionsystemtomitigateaRCSpressuretransientshallbereportedinaccordancewith6.9.3.BasisTheoperabilityoftwopressurizerPORVsoranRCSventopeningofgreaterthan1.1squareinchesensuresthattheRCSwillbeprotectedfrompressuretransientswhichcouldexceedthelimitsofAppendixGto10CFRPart50whenoneormoreoftheRCScoldlegsare<330'F.EitherPORVhasadequaterelievingcapabilitytoprotecttheRCSfromoverpressurizationwhenthetransient,islimitedtoeither(1)thestartofanidleRCPwiththesecondarywatertemperatureofthesteamgenerator<50'FabovetheRCScoldlegtemperatureor(2)thestartof~1~afetyinjectionpumpanditsinjectionintoawatersolidRCS.

References:

(1)L.D.White,Jr.lettertoA.Schwencer,NRC,datedJuly29,19773.15-1Proposed OveressureProtectionSstemAlicabilit:Appliestothereactorcoolantsystemoverpressureprotectionsystem.Ob'ective:Toverifythattheoverpressureprotectionsystemwillfunctionproperlyifneeded.SecificationEachPORVshallbedemonstratedoperableby:a~PerformanceofachannelfunctionaltestonthePORVactuationchannel,butexcludingvalveopera-tion,within31dayspriortoenteringaconditioninwhichthePORVisrequiredoperableandatleastonceper31daysthereafterwhenthePORVisrequiredoperable.b.PerformanceofachannelcalibrationonthePORVactuationchannelat,leastonceper18months.c.VerifyingthePORVisolationvalveisopenatleastonceper72hourswhentheoverpressureprotectionsystemisrequiredtobeoperable.TheRCSvent(s)shallbeverifiedtobeopenatleastonceper12hourswhenthevent(s)isbeingusedforoverpressureprotectionexceptwhenthevent,pathwayisprovidedwithavalvewhichislocked,sealed,orotherwisesecuredintheopenposition.Thenverifythesevalvesopenatleastonceper31days.Proposed (2)Annually:Atabulationonanannualbasisofthenumberofstation,utilityandotherper-sonnel(includingcontractors)receivingex-posuresgreaterthan200mrem/yrandtheirassociatedmanremexposureaccordingtoworkandjobfunctions,e.g.,reactoroperationsandsurveillance,inserviceinspection,routinemaintenance,specialmaintenance(describemaintenance),wasteprocessing,andrefueling.Thedoseassignmenttovariousdutyfunctionsmaybeestimatesbasedonpocketdosimeter,TU),orfilmbadgemeasure-ments.Smallexposurestotallinglessthan20%oftheindividualtotaldoseneednotbeaccountedfor.Intheaggregate,atleast80%ofthetotalwholebodydosereceivedfromexternalsourcesshallbeassignedtospecificmajorworkfunctions.(NOTE:Thistabulationsupplementsthere-quirementsofSection20.407of10CFRPart20.)ReactorOverpressureProtectionSystemOperationIntheeventeitherthePORVsortheRCSvent(s)areusedtomitigateaRCSpressuretransient,aSpecialReportshallbepreparedandsubmittedtotheCommissionwithin30days.Thereportshalldescribethecircumstancesinitiatingthetransient,theeffectofthePORVsorvent(s)onthetransientandanyothercorrectiveactionnecessarytopreventrecurrence.6.9-10Proposed AttachmentBAreactorcoolantsystemoverpressureprotectionsystemhasbeeninstalledatR.E.GinnatomitigatepressuretransientsthatmightotherwiseexceedthoselimitswhicharebaseduponAppendixGto10CFRPart50.Thesystemisdesignedtomitigatetransientswhichmayresultfrompersonnelerror,equipmentmalfunctionorproceduraldeficiencies.AdescriptionofthissystemwasprovidedinlettersfromMr.L.D.White,Jr.,RochesterGasandElectricCorporation,toMr.A.Schwencer,U.S.NuclearRegulatoryCommission,datedFebruary24,1977,March31,1977,andJuly29,1977.Theoverpressureprotectionsystemwillpreventawatersolidreactorcoolantsystemfromexceedingapressureof535psigforasafetyinjectionpumpdischargingtothereactorcoolantsystem,areactorcoolantpumpstartwitha50'Ftemperaturedifferentialbetweentheprimaryandsecondarysystemorlessseveremassinputorheatinputtransients.Thespecificationprohibitingreactorcoolantpumpstartsunlessthefilledpressurizervolumeislessthan324ft(38%level)orunlessthetemperaturedifferentialbetweentheprimaryandsecondarysystemsislessthan50'Fwillproperlylimitheatinput,transients.Apressurizerlevelof38%willaccommodatetheswellresultingfromareactorcoolantpumpstartwithareactortemperatureof140'Fandsteamgeneratortemperatureof340'Fwithouttheneedforoperationoftheoverpressureprotec-tionsystem.Relieffromthepressurizerpoweroperatedreliefvalves(PORVs)would,however,increasethemarginbetweenthepeaktransientpressureandthelimitofTechnicalSpecification3.1.2.Withnogasorsteambubbleinthepressurizertheover-pressureprotectionsystemwillbyitselfpregytthepressurefromexceedingTechnicalSpecification3.1.2.Thespecificationtolimitthenumberofchargingpumpswhichmaybeoperablewhenthereactorcoolantsystemtemperatureisgreaterthan200'Fandtheoverpressureprotectionsystemisinoperablewillpreventapotentialoverpressurizationoftheresidualheatremovalsystem(RHR)shouldletdownbeisolated.AnalysishasshownthattheRHRsystemcanrelievetheinputfromthreechargingpumpswhenthereactorcoolantsystemtemperatureislessthan200'Fandcanrelievetheinputoftwocyygingpumpsattemperaturesgreaterthanorequalto200'F.Thecombinedcapacityof3chargingpumpsislessthanthat,ofonesafetyinjectionpumpandwillnotproducetransientpressuresgreaterthanthosewhichcanbemitigatedbytheoverpressureprotectionsystemwhenthatsystemisoperable.Proposedspecification3.3.1.3willprohibitmorethanonesafetyinjectionpumpfrombeingoperablewhenoneormoreoftheRCScoldlegtemperaturesislessthanorequalto330'Fexceptduringdieselgeneratorloadandsafeguardsequencetestingorwhenthevesselheadisremovedorthesteamgeneratormanwayisopen.Theshutoffheadofthesafetyinjectionpumpsislessthan1500psig,apressurewellbelowtheallowablepressurefor RCStemperaturesof330'Fandabove.Allsafetyinjectionpumpsmaybeoperablefortemperaturesabove330'F;onepumpmaybeoperablebelow330'F,whenthepotentialforoverpressuretransientsexists,becauseof~)emitigatingeffectoftheoverpressureprotectionsystem.Whenthereactorheadisremovedorwhenasteamgeneratormanwayisopenapotentialforoverpressurizationdoesnotexistandthereisnorestrictiononsafetyinjectionpumpoperation.Duringdieselgeneratorloadandsafeguardsequencetestingextraprecautionsaretakentopreventsafetyinjectionpumpdischargetothereactorcoolantsystem.Thepumpdischargevalvesareclosed,thevalvebreakersareopenedandtheDCcontrolfusesareremoved.Theseprecautionsreducethepotentialforoverpressurizationtoanacceptablelevelduringthetestperiod.Surveillanceofthepumpcontrolsoncepertwelvehourswhenonlyonepumpmaybeoperableisappropriatetopreventinadvertentpumpstarts.Proposedspecification3.15requiresthatanoverpressureprotectionsystembeoperablewhenoneormoreoftheRCScoldlegtemperaturesislessthanorequalto330'F.Fortemperaturesgreaterthan330'FtheallowableRCSpressureisgreaterthanthenormalreliefpressureofthetwopressurizerpoweroperatedreliefvalvessothatnootheroverpressureprotectionisrequired.Below330'FeachofthePORVs,usingalowpressuresetpointof435psig,willmitigatepressuretransientsinawater-solidRCSresultingfromthedischargeofasinglesafetyinjectionpumporthestartingofareactorcoolantpumpwitha50'Ftemyy~aturedifferentialbetweenthereactorandsteamgenerators.A1.1squareinchventistheorificeareaequivalenttothatofasinglePORV.BecauseeachofthePORVswillprovideoverpressureprotec-tion,7daysisanacceptabletimeduringwhichoneofthePORVsmaybeinoperable.Aftersevendays,orintheeventthatbothPORVsareinoperable,8hoursisanacceptableperiodoftimetoestablishaRCSventandisarelativelyshortperiodoftimetobewithoutadditionaloverpressureprotection.Proposedspecification4.16requiresappropriateactiontoassurethattheoverpressureprotectionsystemfunctionsproperly.Achannelfunctionaltestwillbeperformedpriortothetimethatthesystemisrequiredtobeoperableandatleastonceevery31daysthereafterwhenit,isoperable.Achannelcalibra-tionwillbeperformedatleastonceevery18months.Thesetestsandcalibrationsaresimilarinnatureandfrequencytothosewhichareperformedonplantprotectionsystemseventhoughthissystemdoesnotperformwhat,isconsideredtobeasafetyfunction.VerificationthatthePORVisolationvalveisopenatleastonceevery72hourswhentheoverpressureprotectionsystemisrequiredtobeoperablewillprovideappropriateassurancethattheoverpressureprotectionfunctionhasnotbeeninadvertentlydefeated.

(1)LetterfromL.D.White,Jr.,RochesterGas6ElectricCorporation,toA.Schwencer,NuclearRegulatoryCommission,July29,1977.(2)LetterfromL.D.White,Jr.,RochesterGas&ElectricCorporation,toA.Schwencer,NuclearRegulatoryCommission,February24,1977 AttachmentCTheproposedAmendment.totheProvisionalOperatingLicensehasbeenevaluatedanddeterminedtofallwithinthedefinitionofClassIIIof10C.F.R.Section170.22therebyreguiringafeeof94,000.Theproposedamendmentdealswithasinglesafetyissue,over-pressureprotectionofthereactorvessel.TheissuehasbeenclearlyidentifiedbyanNRCposition.

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