ML17244A742

Application for Amend to License DPR-18 Re Undervoltage Protection

ML17244A742
Person / Time
Site:	Ginna
Issue date:	07/31/1979
From:	WHITE L D ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17244A741	List: ML17244A740 ML17244A742
References
NUDOCS 7908080446
Download: ML17244A742 (18)

Text

BEFORETHEUNXTEDSTATESNUCLEARREGULATORYCOMMISSSXONIntheMatterofROCHESTERGASANDELECTRICCORPORATION(R.E.GinnaNuclearPowerStation,UnitNo.1)CERTIFICATEOFSERVICEDocketNo.52-244IherebycertifythatIhaveservedadocumententitled"ApplicationforAmendmenttoOperatingLicense"withthree(3)documents,AttachmentsA,B,andC,attachedthereto,bymailingcopiesthereoffirstclass,postagepre-paid,toeach,ofthefollowingpersonsthis3rddayofAugust,1979:Mr.MichaelL.Slade12TrailwoodCircleRochester,NewYork14618WarrenB.Rosenbaum,Esq.OneMainStreet707WilderBuildingRochester,NewYork14614EdwardG.Ketchen,Esp.OfficeoftheExecutiveLegalDirectorU.S.NuclearRegulatoryCommissionWashington,D.C.20555Mr.RobertN.PickneySupervisorTownofOntario107RidgeRoadWestOntario,NewYork14519V908080Q/(p'-

JeffreyL.Cohen,Esq.NewYorkStateEnergyOfficeSwanStreetBuildingCore1,SecondFloorEmpireStatePlazaAlbany,NewYorkl2223EdwardLuton,Esq.AtomicSafetyandLicensingBoardU.S.NuclearRegulatoryCommissionWashington,D.C.20555Dr.EmmethA.LuebkeAtomicSafetyandLicensingBoardU.S.NuclearRegulatoryCommissionWashington,D.C.20555Dr.DixonCallihanUnionCarbideCorporationP.O.BoxYOakRidge,Tennessee37830LxK.LarsonLeBoeuf,Lamb,Leiby6MacRaeAttorneysforRochesterGasandElectricCorporation II'if UNITEDSTATESOFAMERICANUCLEARREGULATORYCOMMISSIONIntheMatterofRochesterGasandElectricCorporation(R.E.GinnaNuclearPowerPlant,UnitNo.l),)))Docket.No.50-244))APPLICATIONFORAMENDMENTTOOPERATINGLICENSE<iPursuanttoSection50.90'oftheregulationsoftheU.S.NuclearRegulatoryCommission(the"Commission"),RochesterGasandElectricCorporation("RGB"),holderofProvisionalOperatingLicenseNo.DPR-18,herebyrequeststhattheTechnicalSpecifica-tionssetforthinAppendixAtothatlicensebeamendedtoaddrequirementsforundervoltageprotection.ThisrequestforachangeintheTechnicalSpecificationsrevisesandsupersedesourrequestofDecember22,1977,andissubmittedinresponsetoaletterfromA.Schwencer,Chief,OperatingReactorsBranch51,datedJune3,1977.TheproposedtechnicalspecificationchangeissetforthinAttachmentAtothisApplication.AsafetyevaluationissetforthinAttachmentB.Thisevaluationalsodemonstratesthattheproposedchangedoesnotinvolveasignificantchangeinthetypesorasignificantincreaseintheamountsofeffluentsoranychangeintheauthorizedpowerlevelofthefacility.AttachmentCdescribeswhynofeeunder10CFR170.22isrequired.

WHEREFORE,ApplicantrespectfullyrequeststhatAppendixAtoProvisionalOperatingLicenseNo.DPR-18beamendedintheformattachedheretoasAttachmentA.RochesterGasandElectricCorporationByL.D.White,Jr.VicePresident,ElectricandSteamProductionSubscribedandsworntobeforemeonthis3IdayofJuly1979.ROSEMARIEPERROHEIIQTftIIYPUBLIC,StateofII.Y.,MonroeCountyMyCommissionExpiresMarch30,Qg~

AttachmentA1.Removepages2.3-4,2.3-8,3.5-4,3.5-4a,and4.1-7.2.Inserttheenclosedrevisedpages2.3-4,2.3-8,2.3-9,3.5-4aand4.1-7.

f.Lowreactorcoolantflow->90%ofnormalindicatedflow~g.Lowreactorcoolantpumpfrequency->57.5Hz.2.3.1.3Otherreactortris2.3.2a.Highpressurizerwaterlevel-<92%ofspanb.Low-lowsteamgeneratorwaterlevel->5%ofnarrowrangeinstrumentspanProtectiveinstrumentationsettingsforreactortripinter-locksshallbeasfollows:2.3.2.1Removebypassof"atpower"reactortripsathighpower(lowpressurizerpressureandlowreactorcoolantflow)forbothloops:Powerrangenuclearflux-<8.'5%ofratedpower(1)(Note:Duringcoldroddroptests,thepressurizerhighleveltripmaybebypassed.)2.3.2.2Removebypassofsinglelossofflowtripat,highpower:2.3.3Powerrangenuclearflux-<50%ofratedpowerRelaysettingsfor480voltsafeguardsbusprotectionshallbeasfollows:2.3.3.1Lossofvoltagerelayoperatingtime<8.5secondsfor480voltsafeguardsbusvoltages<368volts2.3.3.2Acceptabledegradedvoltagerelayoperatingtimesandsetpoints,for480voltsafeguardsbusvoltages<414volts'and>368voltsaredefinedbythesafeguardequip-mentthermalcapabilitycurveshowninFigure2.3-1.Basis:TTTeEighfluxreactortrip(lowsetpoint)providesredundantpro-tectioninthepowerrangeforapowerexcursionbeginningfoplowpower.Thistripvaluewasusedinthesafetyanalysis.2.3-4PROPOSED e0theminimumDNBratioincreasesatlowerflowbecausethemaximumenthalpyrisedoesnotincrease.Forthisreasonthesinglepumplossofflowtripcanbebypassedbelow50%power.Thelossofvoltageanddegradedvoltagetripsensureopera-bilityofsafeguardsequipmentduringapostulateddesignbasis(9)(10)(11)eventconcurrentwithadegradedbusvoltagecondition.

References:

(1)FSAR14.1.1(2)FSAR,Page14-3(3)FSAR14.3.1(4)FSAR14.1.2(5)FSAR72I7~3(6)FSAR3.2.1(7)FSAR14.1.6(8)FSAR14.1.9(9)LetterfromL.D.White,Jr.toA.Schwencer,NRC,datedSeptember30,1977(10)LetterfromL.D.White,Jr.toA.Schwencer,NRC,datedSeptember301977(11)LetterfromL.D.White,Jr.toD.Ziemann,NRC,datedJuly24,19782.3-8PROPOSED o.016001400IISecondLevelI~I.'UnderVoltageProtectionLIFigure2.3-11200~ltdI88d001000800600-+-'I'I~I~I~~I"I~1400I+.AllowaI"blIlaOeReyperI'IlatingI200~iReion0SecondaryVolts(120Volts).PrimaryVolts(480Volts)t240PercentVolts(460VoltBase)5287080909232036870%80%103.5'1490%120=480104%ISafeguardsBusVoltage'.3-9PROPOSEDs~I Page3of312356NO.ofMIN.MIN.PERMISSIBLEOPERATORACTIONNO.ofCHANNELSOPERABLEDEGREEOFBYPASSIFCONDITIONSOFCHANNELSTOTRIPCHANNELSREDUNDANCYCONDITIONSCOLUMN3or5CANNOTBEMET17.CirculatingWaterFloodProtectiona.Screenhouse2b.Condenser18.LossofVoltage/DegradedVoltage480VoltSafe-guardsBus4/bus2/bus2/busNOTE1:Whenblockconditionexists,maintainnormaloperation.Poweroperationmaybecontinuedforaperiodofupto7dayswith1channelinoperableorforaperiodof24h~withtwochannelsin~operable.Poweroperationmaybecontinuedforaperiodofupto7dayswith1channelinoperableorforaperiodof24hrs.withtwochannelsinoperable.Maintainhotshut-downorplacebusondieselgenerator.F.P.***FullPowerNotApplicableIfbothrodmisalignmentmonitors(aandb)inoperablefor2hoursormore,thenuclearoverpowertripshallberesetto93%ofratedpowerinadditiontothein-creasedsurveillancenoted.Ifafunctionalunitisoperatingwiththeminimumoperablechannels,thenumberofchannelstotripthereactorwillbecolumn3lesscolumn4.Achannelisconsideredoperablewith1outof2logicor2outof3logic.

TABLE4.1-1(CONTINUED)ChannelCheckCalibrateTestRemarks25.ContainmentPressure26.SteamGeneratorPressureNarrowrangecontainmentpressure(-3.0,+3psigexcluded)27.TurbineFirstStagePressureS28.EmergencyPlanRadiationInstruments29.EnvironmentalMonitorsN.A.N.A.30.LossofVoltage/DegradedVoltage480VoltSafe-guardsBus.N.A.S-EachShiftD-DailyB/N-BiweeklyQ-QuarterlyM-MonthlyP-PriortoeachstartupifnotdonepreviousweekR.-EachRefuelingShutdownN.A.-Notapplicable AttachmentBByletterdatedJune3;1977,theNRCrequestedthatRG&Eassessthesusceptibilityofsafetyrelatedelectricalequipmentwithregardto(1)sustaineddegradedvoltageconditionsattheoffsitepowersourcesand(2)interactionbetweentheoffsiteandonsiteemergencypowersources.AnanalysisofundervoltageprotectionatGinnaStationwasperformedandsubmittedtotheNRCinaletterdatedJuly21,1977.ThisanalysisreviewedthecurrentundervoltageprotectionanddescribedthebasisforamodificationwhichwouldreducetheStation'ssusceptibilitytoasustaineddegradedvoltage.However,duetolackofspecificinformationregardingequipment,setpointsfortheadditionalundervoltageprotectionwerenotestablishedatthattime.Followingreceiptofadditionalinformation,RG&EsubmittedsetpointsinalettertotheNRCdatedSeptember30,1977.TheproposedspecificationsareidenticaltothosepresentedintheSeptember30letter.TheseSpecificationswillprovideprotectionforacompletelossof480volt.busvoltageaswellasfordegradedvoltageconditions.Bothrelayingsystemswillassurethatassumptionsofallsafetyanalysisaremet.Specifically,equipmentwillbeloadedontothedieselgeneratorswithinthetimeassumedinthesafetyanalyses.Theundervoltagerelayprotection,whichwasidentifiedas"second-levelprotection"intheJune3,1977NRCletterandinourtwosubsequentletters,willprotectequipment againstabusvoltagewhichisgreaterthanthelossofvoltagerelaysetpointbut.lessthanthevoltageguaranteedbyequipmentmanufacturersforcontinuousdutyforGinnasafeguardsequipment.Theproposedundervoltagesetpointswillprovidetherequiredprotectionwhilealsoassuringthat,spurioustripswillnotoccurwhileequipmentisbeingsequencedontothedieselgenerators.TheNRCStaffrequestedthattheproposedsystembemodifiedtoprovide"coincidentlogic"asdescribedinposition1,partboftheirJune3,1977letter.Provisionfor"coincident,logic"doesnot.effectthesetpointinformationcontainedintheDecember16,1977ApplicationforChangetoOperatingLicenseandre-submittedherewith.However,ithaschangedtherequirednumberofrelaysnecessarytotrip.ThecoincidentlogicschemeisdescribedinourJuly24,1978letter(ref.11totheTechnicalSpecificationBasis).Lossofvoltageanddegradedvoltageconditionssimulatedduringtherefuelingshutdownareperformedtoverifybothsystemperformanceandrelaycalibration.Thesafeguards480voltlossofvoltageanddegradedvoltageprotectionsystemsarenotpartofthereactorprotectionsystem.Itisnotpracticaltosimulatetheseconditionsduringplantoperationtosatisfyamonthlytestrequirement.BasedontheanalysesprovidedinourlettersofJuly21,1977,September30,1977,andJuly24,1978theproposedTechnicalSpecificationwillprovideprotectionagainst480voltbusunder-voltage.

AsstatedinourletterofJuly21,1977,weexpectthat,followingreceiptofapprovalofthemodificationdesignbytheNRC,detailedengineeringandprocurementofequipmentwillrequireapproximately9months.Installationmustbeperformedat.acoldorrefuelingshutdownandwouldrequireapproximatelytwoweeks..TheeffectivedataofaTechnicalSpecificationshouldbesetconsistentwiththisschedule.

AttachmentCTheTechnicalSpecificationchangeproposalrevisesaproposaloriginallysubmittedDecember22,1977whichwasfiledpriortotheeffectivedateof10CPR170.22.TherevisionisnecessarytoincorporateachangeindesignwhichwasrequestedbytheNRCStaff.ThedesignchangewasdescribedinoursubmittalofJuly24,1978.BecauseitisarevisionwhichtheStaffrequestedandisnowreviewing,andisnotanewrequest,nofeeisrequired.

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