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{{#Wiki_filter: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'-
{{#Wiki_filter:BEFORETHEUNXTEDSTATESNUCLEARREGULATORY COMMISSSXON IntheMatterofROCHESTER GASANDELECTRICCORPORATION (R.E.GinnaNuclearPowerStation,UnitNo.1)CERTIFICATE OFSERVICEDocketNo.52-244IherebycertifythatIhaveservedadocumententitled"Application forAmendment toOperating License"withthree(3)documents, Attachments A,B,andC,attachedthereto,bymailingcopiesthereoffirstclass,postagepre-paid,toeach,ofthefollowing personsthis3rddayofAugust,1979:Mr.MichaelL.Slade12Trailwood CircleRochester, NewYork14618WarrenB.Rosenbaum, Esq.OneMainStreet707WilderBuildingRochester, NewYork14614EdwardG.Ketchen,Esp.OfficeoftheExecutive LegalDirectorU.S.NuclearRegulatory Commission Washington, D.C.20555Mr.RobertN.PickneySupervisor TownofOntario107RidgeRoadWestOntario,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.  
JeffreyL.Cohen,Esq.NewYorkStateEnergyOfficeSwanStreetBuildingCore1,SecondFloorEmpireStatePlazaAlbany,NewYorkl2223EdwardLuton,Esq.AtomicSafetyandLicensing BoardU.S.NuclearRegulatory CommissionWashington, D.C.20555Dr.EmmethA.LuebkeAtomicSafetyandLicensing BoardU.S.NuclearRegulatory CommissionWashington, D.C.20555Dr.DixonCallihanUnionCarbideCorporation P.O.BoxYOakRidge,Tennessee 37830LxK.LarsonLeBoeuf,Lamb,Leiby6MacRaeAttorneys forRochester GasandElectricCorporation II'if UNITEDSTATESOFAMERICANUCLEARREGULATORY COMMISSION IntheMatterofRochester GasandElectricCorporation (R.E.GinnaNuclearPowerPlant,UnitNo.l),)))Docket.No.50-244))APPLICATION FORAMENDMENT TOOPERATING LICENSE<iPursuanttoSection50.90'oftheregulations oftheU.S.NuclearRegulatory Commission (the"Commission"
),Rochester GasandElectricCorporation
("RGB"),holderofProvisional Operating LicenseNo.DPR-18,herebyrequeststhattheTechnical Specifica-tionssetforthinAppendixAtothatlicensebeamendedtoaddrequirements forundervoltage protection.
ThisrequestforachangeintheTechnical Specifications revisesandsupersedes ourrequestofDecember22,1977,andissubmitted inresponsetoaletterfromA.Schwencer, Chief,Operating ReactorsBranch51,datedJune3,1977.Theproposedtechnical specification changeissetforthinAttachment AtothisApplication.
Asafetyevaluation issetforthinAttachment B.Thisevaluation alsodemonstrates thattheproposedchangedoesnotinvolveasignificant changeinthetypesorasignificant increaseintheamountsofeffluents oranychangeintheauthorized powerlevelofthefacility.
Attachment Cdescribes whynofeeunder10CFR170.22isrequired.  


WHEREFORE,ApplicantrespectfullyrequeststhatAppendixAtoProvisionalOperatingLicenseNo.DPR-18beamendedintheformattachedheretoasAttachmentA.RochesterGasandElectricCorporationByL.D.White,Jr.VicePresident,ElectricandSteamProductionSubscribedandsworntobeforemeonthis3IdayofJuly1979.ROSEMARIEPERROHEIIQTftIIYPUBLIC,StateofII.Y.,MonroeCountyMyCommissionExpiresMarch30,Qg~
WHEREFORE, Applicant respectfully requeststhatAppendixAtoProvisional Operating LicenseNo.DPR-18beamendedintheformattachedheretoasAttachment A.Rochester GasandElectricCorporation ByL.D.White,Jr.VicePresident, ElectricandSteamProduction Subscribed andsworntobeforemeonthis3IdayofJuly1979.ROSEMARIEPERROHEIIQTftIIY PUBLIC,StateofII.Y.,MonroeCountyMyCommission ExpiresMarch30,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.
Attachment A1.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.
f.Lowreactorcoolantflow->90%ofnormalindicated flow~g.Lowreactorcoolantpumpfrequency
->57.5Hz.2.3.1.3Otherreactortris2.3.2a.Highpressurizer waterlevel-<92%ofspanb.Low-lowsteamgenerator waterlevel->5%ofnarrowrangeinstrument spanProtective instrumentation settingsforreactortripinter-locksshallbeasfollows:2.3.2.1Removebypassof"atpower"reactortripsathighpower(lowpressurizer pressureandlowreactorcoolantflow)forbothloops:Powerrangenuclearflux-<8.'5%ofratedpower(1)(Note:Duringcoldroddroptests,thepressurizer highleveltripmaybebypassed.)
2.3.2.2Removebypassofsinglelossofflowtripat,highpower:2.3.3Powerrangenuclearflux-<50%ofratedpowerRelaysettingsfor480voltsafeguards busprotection shallbeasfollows:2.3.3.1Lossofvoltagerelayoperating time<8.5secondsfor480voltsafeguards busvoltages<368volts2.3.3.2Acceptable degradedvoltagerelayoperating timesandsetpoints, for480voltsafeguards busvoltages<414volts'and
>368voltsaredefinedbythesafeguard equip-mentthermalcapability curveshowninFigure2.3-1.Basis:TTTeEighfluxreactortrip(lowsetpoint)providesredundant pro-tectioninthepowerrangeforapowerexcursion beginning foplowpower.Thistripvaluewasusedinthesafetyanalysis.
2.3-4PROPOSED e0theminimumDNBratioincreases atlowerflowbecausethemaximumenthalpyrisedoesnotincrease.
Forthisreasonthesinglepumplossofflowtripcanbebypassedbelow50%power.Thelossofvoltageanddegradedvoltagetripsensureopera-bilityofsafeguards equipment duringapostulated designbasis(9)(10)(11) eventconcurrent withadegradedbusvoltagecondition.


==References:==
==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.
(1)FSAR14.1.1(2)FSAR,Page14-3(3)FSAR14.3.1(4)FSAR14.1.2(5)FSAR72I 7~3(6)FSAR3.2.1(7)FSAR14.1.6(8)FSAR14.1.9(9)LetterfromL.D.White,Jr.toA.Schwencer, NRC,datedSeptember 30,1977(10)LetterfromL.D.White,Jr.toA.Schwencer, NRC,datedSeptember 301977(11)LetterfromL.D.White,Jr.toD.Ziemann,NRC,datedJuly24,19782.3-8PROPOSED o.016001400IISecondLevelI~I.'UnderVoltageProtection LIFigure2.3-11200~ltdI88d001000800600-+-'I'I~I~I~~I"I~1400I+.AllowaI"blIlaOeReyperI'IlatingI200~iReion0Secondary Volts(120Volts).PrimaryVolts(480Volts)t240PercentVolts(460VoltBase)5287080909232036870%80%103.5'1490%120=480104%ISafeguards BusVoltage'.3-9 PROPOSEDs~I Page3of312356NO.ofMIN.MIN.PERMISSIBLE OPERATORACTIONNO.ofCHANNELSOPERABLEDEGREEOFBYPASSIFCONDITIONS OFCHANNELSTOTRIPCHANNELSREDUNDANCY CONDITIONS COLUMN3or5CANNOTBEMET17.Circulating WaterFloodProtection a.Screenhouse 2b.Condenser 18.LossofVoltage/DegradedVoltage480VoltSafe-guardsBus4/bus2/bus2/busNOTE1:Whenblockcondition exists,maintainnormaloperation.
AttachmentCTheTechnicalSpecificationchangeproposalrevisesaproposaloriginallysubmittedDecember22,1977whichwasfiledpriortotheeffectivedateof10CPR170.22.TherevisionisnecessarytoincorporateachangeindesignwhichwasrequestedbytheNRCStaff.ThedesignchangewasdescribedinoursubmittalofJuly24,1978.BecauseitisarevisionwhichtheStaffrequestedandisnowreviewing,andisnotanewrequest,nofeeisrequired.
Poweroperation maybecontinued foraperiodofupto7dayswith1channelinoperable orforaperiodof24h~withtwochannelsin~operable.
Poweroperation maybecontinued foraperiodofupto7dayswith1channelinoperable orforaperiodof24hrs.withtwochannelsinoperable.
Maintainhotshut-downorplacebusondieselgenerator.
F.P.***FullPowerNotApplicable Ifbothrodmisalignment monitors(aandb)inoperable for2hoursormore,thenuclearoverpower tripshallberesetto93%ofratedpowerinadditiontothein-creasedsurveillance noted.Ifafunctional unitisoperating withtheminimumoperablechannels, thenumberofchannelstotripthereactorwillbecolumn3lesscolumn4.Achannelisconsidered operablewith1outof2logicor2outof3logic.
TABLE4.1-1(CONTINUED)
ChannelCheckCalibrate TestRemarks25.Containment Pressure26.SteamGenerator PressureNarrowrangecontainment pressure(-3.0,+3psigexcluded) 27.TurbineFirstStagePressureS28.Emergency PlanRadiation Instruments 29.Environmental MonitorsN.A.N.A.30.LossofVoltage/Degraded Voltage480VoltSafe-guardsBus.N.A.S-EachShiftD-DailyB/N-BiweeklyQ-Quarterly M-MonthlyP-PriortoeachstartupifnotdonepreviousweekR.-EachRefueling ShutdownN.A.-Notapplicable Attachment BByletterdatedJune3;1977,theNRCrequested thatRG&Eassessthesusceptibility ofsafetyrelatedelectrical equipment withregardto(1)sustained degradedvoltageconditions attheoffsitepowersourcesand(2)interaction betweentheoffsiteandonsiteemergency powersources.Ananalysisofundervoltage protection atGinnaStationwasperformed andsubmitted totheNRCinaletterdatedJuly21,1977.Thisanalysisreviewedthecurrentundervoltage protection anddescribed thebasisforamodification whichwouldreducetheStation's susceptibility toasustained degradedvoltage.However,duetolackofspecificinformation regarding equipment, setpoints fortheadditional undervoltage protection werenotestablished atthattime.Following receiptofadditional information, RG&Esubmitted setpoints inalettertotheNRCdatedSeptember 30,1977.Theproposedspecifications areidentical tothosepresented intheSeptember 30letter.TheseSpecifications willprovideprotection foracompletelossof480volt.busvoltageaswellasfordegradedvoltageconditions.
Bothrelayingsystemswillassurethatassumptions ofallsafetyanalysisaremet.Specifically, equipment willbeloadedontothedieselgenerators withinthetimeassumedinthesafetyanalyses.
Theundervoltage relayprotection, whichwasidentified as"second-level protection" intheJune3,1977NRCletterandinourtwosubsequent letters,willprotectequipment againstabusvoltagewhichisgreaterthanthelossofvoltagerelaysetpointbut.lessthanthevoltageguaranteed byequipment manufacturers forcontinuous dutyforGinnasafeguards equipment.
Theproposedundervoltage setpoints willprovidetherequiredprotection whilealsoassuringthat,spurioustripswillnotoccurwhileequipment isbeingsequenced ontothedieselgenerators.
TheNRCStaffrequested thattheproposedsystembemodifiedtoprovide"coincident logic"asdescribed inposition1,partboftheirJune3,1977letter.Provision for"coincident, logic"doesnot.effectthesetpointinformation contained intheDecember16,1977Application forChangetoOperating Licenseandre-submitted herewith.
However,ithaschangedtherequirednumberofrelaysnecessary totrip.Thecoincident logicschemeisdescribed inourJuly24,1978letter(ref.11totheTechnical Specification Basis).Lossofvoltageanddegradedvoltageconditions simulated duringtherefueling shutdownareperformed toverifybothsystemperformance andrelaycalibration.
Thesafeguards 480voltlossofvoltageanddegradedvoltageprotection systemsarenotpartofthereactorprotection system.Itisnotpractical tosimulatetheseconditions duringplantoperation tosatisfyamonthlytestrequirement.
BasedontheanalysesprovidedinourlettersofJuly21,1977,September 30,1977,andJuly24,1978theproposedTechnical Specification willprovideprotection against480voltbusunder-voltage.
 
AsstatedinourletterofJuly21,1977,weexpectthat,following receiptofapprovalofthemodification designbytheNRC,detailedengineering andprocurement ofequipment willrequireapproximately 9months.Installation mustbeperformed at.acoldorrefueling shutdownandwouldrequireapproximately twoweeks..Theeffective dataofaTechnical Specification shouldbesetconsistent withthisschedule.
Attachment CTheTechnical Specification changeproposalrevisesaproposaloriginally submitted December22,1977whichwasfiledpriortotheeffective dateof10CPR170.22.Therevisionisnecessary toincorporate achangeindesignwhichwasrequested bytheNRCStaff.Thedesignchangewasdescribed inoursubmittal ofJuly24,1978.BecauseitisarevisionwhichtheStaffrequested andisnowreviewing, andisnotanewrequest,nofeeisrequired.
I}}
I}}

Revision as of 15:01, 29 June 2018

Application for Amend to License DPR-18 Re Undervoltage Protection
ML17244A742
Person / Time
Site: Ginna Constellation icon.png
Issue date: 07/31/1979
From: WHITE L D
ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17244A741 List:
References
NUDOCS 7908080446
Download: ML17244A742 (18)
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Text

BEFORETHEUNXTEDSTATESNUCLEARREGULATORY COMMISSSXON IntheMatterofROCHESTER GASANDELECTRICCORPORATION (R.E.GinnaNuclearPowerStation,UnitNo.1)CERTIFICATE OFSERVICEDocketNo.52-244IherebycertifythatIhaveservedadocumententitled"Application forAmendment toOperating License"withthree(3)documents, Attachments A,B,andC,attachedthereto,bymailingcopiesthereoffirstclass,postagepre-paid,toeach,ofthefollowing personsthis3rddayofAugust,1979:Mr.MichaelL.Slade12Trailwood CircleRochester, NewYork14618WarrenB.Rosenbaum, Esq.OneMainStreet707WilderBuildingRochester, NewYork14614EdwardG.Ketchen,Esp.OfficeoftheExecutive LegalDirectorU.S.NuclearRegulatory Commission Washington, D.C.20555Mr.RobertN.PickneySupervisor TownofOntario107RidgeRoadWestOntario,NewYork14519V908080Q/(p'-

JeffreyL.Cohen,Esq.NewYorkStateEnergyOfficeSwanStreetBuildingCore1,SecondFloorEmpireStatePlazaAlbany,NewYorkl2223EdwardLuton,Esq.AtomicSafetyandLicensing BoardU.S.NuclearRegulatory CommissionWashington, D.C.20555Dr.EmmethA.LuebkeAtomicSafetyandLicensing BoardU.S.NuclearRegulatory CommissionWashington, D.C.20555Dr.DixonCallihanUnionCarbideCorporation P.O.BoxYOakRidge,Tennessee 37830LxK.LarsonLeBoeuf,Lamb,Leiby6MacRaeAttorneys forRochester GasandElectricCorporation II'if UNITEDSTATESOFAMERICANUCLEARREGULATORY COMMISSION IntheMatterofRochester GasandElectricCorporation (R.E.GinnaNuclearPowerPlant,UnitNo.l),)))Docket.No.50-244))APPLICATION FORAMENDMENT TOOPERATING LICENSE<iPursuanttoSection50.90'oftheregulations oftheU.S.NuclearRegulatory Commission (the"Commission"

),Rochester GasandElectricCorporation

("RGB"),holderofProvisional Operating LicenseNo.DPR-18,herebyrequeststhattheTechnical Specifica-tionssetforthinAppendixAtothatlicensebeamendedtoaddrequirements forundervoltage protection.

ThisrequestforachangeintheTechnical Specifications revisesandsupersedes ourrequestofDecember22,1977,andissubmitted inresponsetoaletterfromA.Schwencer, Chief,Operating ReactorsBranch51,datedJune3,1977.Theproposedtechnical specification changeissetforthinAttachment AtothisApplication.

Asafetyevaluation issetforthinAttachment B.Thisevaluation alsodemonstrates thattheproposedchangedoesnotinvolveasignificant changeinthetypesorasignificant increaseintheamountsofeffluents oranychangeintheauthorized powerlevelofthefacility.

Attachment Cdescribes whynofeeunder10CFR170.22isrequired.

WHEREFORE, Applicant respectfully requeststhatAppendixAtoProvisional Operating LicenseNo.DPR-18beamendedintheformattachedheretoasAttachment A.Rochester GasandElectricCorporation ByL.D.White,Jr.VicePresident, ElectricandSteamProduction Subscribed andsworntobeforemeonthis3IdayofJuly1979.ROSEMARIEPERROHEIIQTftIIY PUBLIC,StateofII.Y.,MonroeCountyMyCommission ExpiresMarch30,Qg~

Attachment A1.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%ofnormalindicated flow~g.Lowreactorcoolantpumpfrequency

->57.5Hz.2.3.1.3Otherreactortris2.3.2a.Highpressurizer waterlevel-<92%ofspanb.Low-lowsteamgenerator waterlevel->5%ofnarrowrangeinstrument spanProtective instrumentation settingsforreactortripinter-locksshallbeasfollows:2.3.2.1Removebypassof"atpower"reactortripsathighpower(lowpressurizer pressureandlowreactorcoolantflow)forbothloops:Powerrangenuclearflux-<8.'5%ofratedpower(1)(Note:Duringcoldroddroptests,thepressurizer highleveltripmaybebypassed.)

2.3.2.2Removebypassofsinglelossofflowtripat,highpower:2.3.3Powerrangenuclearflux-<50%ofratedpowerRelaysettingsfor480voltsafeguards busprotection shallbeasfollows:2.3.3.1Lossofvoltagerelayoperating time<8.5secondsfor480voltsafeguards busvoltages<368volts2.3.3.2Acceptable degradedvoltagerelayoperating timesandsetpoints, for480voltsafeguards busvoltages<414volts'and

>368voltsaredefinedbythesafeguard equip-mentthermalcapability curveshowninFigure2.3-1.Basis:TTTeEighfluxreactortrip(lowsetpoint)providesredundant pro-tectioninthepowerrangeforapowerexcursion beginning foplowpower.Thistripvaluewasusedinthesafetyanalysis.

2.3-4PROPOSED e0theminimumDNBratioincreases atlowerflowbecausethemaximumenthalpyrisedoesnotincrease.

Forthisreasonthesinglepumplossofflowtripcanbebypassedbelow50%power.Thelossofvoltageanddegradedvoltagetripsensureopera-bilityofsafeguards equipment duringapostulated designbasis(9)(10)(11) eventconcurrent withadegradedbusvoltagecondition.

References:

(1)FSAR14.1.1(2)FSAR,Page14-3(3)FSAR14.3.1(4)FSAR14.1.2(5)FSAR72I 7~3(6)FSAR3.2.1(7)FSAR14.1.6(8)FSAR14.1.9(9)LetterfromL.D.White,Jr.toA.Schwencer, NRC,datedSeptember 30,1977(10)LetterfromL.D.White,Jr.toA.Schwencer, NRC,datedSeptember 301977(11)LetterfromL.D.White,Jr.toD.Ziemann,NRC,datedJuly24,19782.3-8PROPOSED o.016001400IISecondLevelI~I.'UnderVoltageProtection LIFigure2.3-11200~ltdI88d001000800600-+-'I'I~I~I~~I"I~1400I+.AllowaI"blIlaOeReyperI'IlatingI200~iReion0Secondary Volts(120Volts).PrimaryVolts(480Volts)t240PercentVolts(460VoltBase)5287080909232036870%80%103.5'1490%120=480104%ISafeguards BusVoltage'.3-9 PROPOSEDs~I Page3of312356NO.ofMIN.MIN.PERMISSIBLE OPERATORACTIONNO.ofCHANNELSOPERABLEDEGREEOFBYPASSIFCONDITIONS OFCHANNELSTOTRIPCHANNELSREDUNDANCY CONDITIONS COLUMN3or5CANNOTBEMET17.Circulating WaterFloodProtection a.Screenhouse 2b.Condenser 18.LossofVoltage/DegradedVoltage480VoltSafe-guardsBus4/bus2/bus2/busNOTE1:Whenblockcondition exists,maintainnormaloperation.

Poweroperation maybecontinued foraperiodofupto7dayswith1channelinoperable orforaperiodof24h~withtwochannelsin~operable.

Poweroperation maybecontinued foraperiodofupto7dayswith1channelinoperable orforaperiodof24hrs.withtwochannelsinoperable.

Maintainhotshut-downorplacebusondieselgenerator.

F.P.***FullPowerNotApplicable Ifbothrodmisalignment monitors(aandb)inoperable for2hoursormore,thenuclearoverpower tripshallberesetto93%ofratedpowerinadditiontothein-creasedsurveillance noted.Ifafunctional unitisoperating withtheminimumoperablechannels, thenumberofchannelstotripthereactorwillbecolumn3lesscolumn4.Achannelisconsidered operablewith1outof2logicor2outof3logic.

TABLE4.1-1(CONTINUED)

ChannelCheckCalibrate TestRemarks25.Containment Pressure26.SteamGenerator PressureNarrowrangecontainment pressure(-3.0,+3psigexcluded) 27.TurbineFirstStagePressureS28.Emergency PlanRadiation Instruments 29.Environmental MonitorsN.A.N.A.30.LossofVoltage/Degraded Voltage480VoltSafe-guardsBus.N.A.S-EachShiftD-DailyB/N-BiweeklyQ-Quarterly M-MonthlyP-PriortoeachstartupifnotdonepreviousweekR.-EachRefueling ShutdownN.A.-Notapplicable Attachment BByletterdatedJune3;1977,theNRCrequested thatRG&Eassessthesusceptibility ofsafetyrelatedelectrical equipment withregardto(1)sustained degradedvoltageconditions attheoffsitepowersourcesand(2)interaction betweentheoffsiteandonsiteemergency powersources.Ananalysisofundervoltage protection atGinnaStationwasperformed andsubmitted totheNRCinaletterdatedJuly21,1977.Thisanalysisreviewedthecurrentundervoltage protection anddescribed thebasisforamodification whichwouldreducetheStation's susceptibility toasustained degradedvoltage.However,duetolackofspecificinformation regarding equipment, setpoints fortheadditional undervoltage protection werenotestablished atthattime.Following receiptofadditional information, RG&Esubmitted setpoints inalettertotheNRCdatedSeptember 30,1977.Theproposedspecifications areidentical tothosepresented intheSeptember 30letter.TheseSpecifications willprovideprotection foracompletelossof480volt.busvoltageaswellasfordegradedvoltageconditions.

Bothrelayingsystemswillassurethatassumptions ofallsafetyanalysisaremet.Specifically, equipment willbeloadedontothedieselgenerators withinthetimeassumedinthesafetyanalyses.

Theundervoltage relayprotection, whichwasidentified as"second-level protection" intheJune3,1977NRCletterandinourtwosubsequent letters,willprotectequipment againstabusvoltagewhichisgreaterthanthelossofvoltagerelaysetpointbut.lessthanthevoltageguaranteed byequipment manufacturers forcontinuous dutyforGinnasafeguards equipment.

Theproposedundervoltage setpoints willprovidetherequiredprotection whilealsoassuringthat,spurioustripswillnotoccurwhileequipment isbeingsequenced ontothedieselgenerators.

TheNRCStaffrequested thattheproposedsystembemodifiedtoprovide"coincident logic"asdescribed inposition1,partboftheirJune3,1977letter.Provision for"coincident, logic"doesnot.effectthesetpointinformation contained intheDecember16,1977Application forChangetoOperating Licenseandre-submitted herewith.

However,ithaschangedtherequirednumberofrelaysnecessary totrip.Thecoincident logicschemeisdescribed inourJuly24,1978letter(ref.11totheTechnical Specification Basis).Lossofvoltageanddegradedvoltageconditions simulated duringtherefueling shutdownareperformed toverifybothsystemperformance andrelaycalibration.

Thesafeguards 480voltlossofvoltageanddegradedvoltageprotection systemsarenotpartofthereactorprotection system.Itisnotpractical tosimulatetheseconditions duringplantoperation tosatisfyamonthlytestrequirement.

BasedontheanalysesprovidedinourlettersofJuly21,1977,September 30,1977,andJuly24,1978theproposedTechnical Specification willprovideprotection against480voltbusunder-voltage.

AsstatedinourletterofJuly21,1977,weexpectthat,following receiptofapprovalofthemodification designbytheNRC,detailedengineering andprocurement ofequipment willrequireapproximately 9months.Installation mustbeperformed at.acoldorrefueling shutdownandwouldrequireapproximately twoweeks..Theeffective dataofaTechnical Specification shouldbesetconsistent withthisschedule.

Attachment CTheTechnical Specification changeproposalrevisesaproposaloriginally submitted December22,1977whichwasfiledpriortotheeffective dateof10CPR170.22.Therevisionisnecessary toincorporate achangeindesignwhichwasrequested bytheNRCStaff.Thedesignchangewasdescribed inoursubmittal ofJuly24,1978.BecauseitisarevisionwhichtheStaffrequested andisnowreviewing, andisnotanewrequest,nofeeisrequired.

I

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