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

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.

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