ML17326B611
| ML17326B611 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 04/14/1989 |
| From: | ALEXICH M P INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | MURLEY T E NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| AEP:NRC:0537D, AEP:NRC:537D, NUDOCS 8904260177 | |
| Download: ML17326B611 (7) | |
Text
ACCELERATEDD1SIBUNIONDEMONSTRIONSYSTEM'REGULATORYINFORMATIONDISTRIBUTIONSYSTEM(RIDS)ACCESSIONNBR:8904260177DOC.DATE:89/04/14NOTARIZED:NODOCKETgFACIL:50-315DonaldC.CookNuclearPowerPlant,Unit1,Indiana&0500031550-316DonaldC.CookNuclearPowerPlant,Unit2,Indiana&05000316AUTH.NAMEAUTHORAFFILIATIONALEXICH,M.P..IndianaMichiganPowerCo.(formerlyIndiana&MichiganEleRECIP.NAMERECIPIENTAFFILIATIONMURLEY,T.E.DocumentControlBranch(DocumentControlDesk)R
SUBJECT:
RespondstostationblackoutruleforplantsusingACindependentstationblackoutresponsepower.DISTRIBUTIONCODE:A050DCOPIESRECEIVED:LTRENCLSIZE:TITLE:ORSubmittal:StationBlackout(USIA-44)10CFR50.63,MPAA-22NOTES:RECIPIENTIDCODE/NAMEPD3-1PDCOPIESLTTRENCL11RECIPIENTIDCODE/NAMESTANG,JCOPIESLTTRENCL11i'INTERNAL:NRRPDl-4PMTAMNRR/DEST/PSBNUDOCS-ABSTRACTEXTERNAL:LPDRNSIC1122111111NRR/DEST/ESBNRRDESTRSBRFILE0NRCPDR22111111RINarE'IOALLRICSRZCIPZZgZSPLEASEHELPUSK)REDUCEWASTE!CDNZACZ'XHEDOCUMENZCONTROLDESKSKXMPl-37(EXT.20079)KOELIMINATEKXJRMMEFKHDISTRIBUTIONLISTSH)RDOCtIMEÃISYOUDGNiTNEED!DDSTOTALNUMBEROFCOPIESREQUIRED:LTTR13ENCL13 19~t0~'1indianahlicbiganPowerCompanyP.O.Box16631Columbus,OH43216AEP:NRC:0537DDonaldC.CookNuclearPlantUnits1and2DocketNos.50-315and50-316LicenseNos.DPR-58andDPR-74GENERICRESPONSETOSTATIONBLACKOUTRULEFORPLANTSUSINGACINDEPENDENTSTATIONBLACKOUTRESPONSEPOWERU.S.NuclearRegulatoryCommissionAttn:DocumentControlDeskWashington,D.C.20555Attn:T.E.MurleyApril14,1989
DearDr.Murley:
'OnJuly21,1988,theNuclearRegulatoryCommission(NRC)amendeditsregulationsin10CFR,Part50.Anewsection,50.63,wasaddedwhichrequiresthateachlight-water-coolednuclearpowerplantbeabletowithstandandrecoverfromastationblackout(SBO)ofaspecifiedduration.Utilitiesareexpectedtohavethebaselineassumptions,analysesandrelatedinformationusedintheircopingevaluationavailableforNRCreview.Italsoidentifiesthefactorsthatmustbeconsideredinspecifyingthestationblackoutduration.Section50.63requiresthat,forthestationblackoutduration,theplantbecapableofmaintainingcorecoolingandappropriatecontainmentintegrity.Section50.63furtherrequiresthateachlicenseesubmitthefollowinginformation:1.AproposedstationblackoutdurationincludingajustificationfortheselectionbasedontheredundancyandreliabilityoftheonsiteemergencyACpowersources,theexpectedfrequencyoflossofoffsitepower,andtheprobabletimeneededtorestoreoffsitepower;2.Adescriptionoftheproceduresthatwillbeimplementedforstationblackouteventsfortheduration(asdeterminedin1above)andforrecoverytherefrom;and3.AlistandproposedscheduleforanyneededmodificationstoequipmentandassociatedproceduresnecessaryforthespecifiedSBOduration.8904260i778904i4rPDRADOCK05000315PPDCpo Dr.T.E.Murley-2-AEP:NRC:0537DTheNRChasissuedRegulatoryguide1.155"StationBlackout"whichdescribesameansacceptabletotheNRCStaffformeetingtherequirementsof10CFR50.63.RegulatoryGuide(RG)1.155statesthattheNRCStaffhasdeterminedthatNUMARC87-00"GuidelinesandTechnicalBasesforNUMARCInitiativesAddressingStationBlackoutAtLightWaterReactors"alsoprovidesguidancethatisinlargepartidenticaltotheRG1.155guidanceandisacceptabletotheNRCstaffformeetingtheserequirements.Table1toRG1.155providesacross-referencebetweenRG1.155andNUMARC87-00andnoteswheretheRGtakesprecedence.IndianaMichiganPowerhasevaluatedtheCookNuclearPlant,Units1and2,againsttherequirementsoftheSBOruleusingguidancefromNUMARC87-00exceptwhereRG1.155takesprecedence.Theresultsofthisevaluationaredetailedbelow.A.ProosedStationBlackoutDurationNUMARC87-00,Section3wasusedtodetermineaproposedSBOdurationoffourhours.Nomodificationswererequiredtoattainthisproposedcopingdurationcategory.Thefollowingplantfactorswereidentifiedindeterminingtheproposedstationblackoutduration:1.ACPowerDesignCharacteristicGroupisP2basedon:a.Expectedfrequencyofgrid-relatedloss-of-offsite-powerevents(LOOPs)-doesnotexceedonceper20years;b.EstimatedfrequencyofLOOPsduetoextremelysevereweather(ESW)placestheplantinESWGroup2;c.EstimatedfrequencyofLOOPsduetosevereweather(SW)placestheplantinSWGroup2;d.TheoffsitepowersystemisintheGroupIl/2.2.TheemergencyACpowerconfigurationgroupis"C"basedon:a.TherearetwoemergencyACpowersuppliesperunitnotcreditedasalternateACpowersources;b.OneemergencyACpowersupplyperunitisnecessarytooperatesafeshutdownequipmentfollowingalossofoffsitepower.
Dr.T.E.Murley-3-AEP:NRC:0537D3.Thetargetemergencydieselgenerator(EDG)reliabilityis0.975.AtargetEDGreliabilityof0.975wasselectedbasedonhavinganuclearunitaverageEDGreliabilityforthelast20demandsgreaterthan0'0consistentwithNUMARC87-00,Section3.2.4.B.ProcedureDescritionPlantprocedureshavebeenreviewedand,wherenecessary,willbemodifiedbyJuly31,1989,tomeettheguidelinesinNUMARC87-00,Section4inthefollowingareas:StationblackoutresponseperNUMARC87-00,Section4.2.1;ACpowerrestorationperNUMARC87-00,Section4.2.2;SevereweatherperNUMARC87-00,Section4.2.3;Proceduresreviewedand/orrevisedarelistedbelow:1,2-0HP4023.ECA-O.OLossofAllACPower;*1,2-0HP4023.001.020ResponsetoLossofOffsitePowertoBothUnitsandAnyOneDieselStarts;OHI-4011ConductofOperations(ShiftStaffing);1,2-0HP4021.056.002OperationofAuxiliaryFeedwaterSystemDuringStartupandShutdown;1,2-0HP4030.STP.017TTurbineDrivenAuxiliaryFeedwaterSystemTest;1,2-0HP4022.055.003LossofCondensatetoAuxiliaryFeedwaterPumps;1-OHP4030.STP.039SecurityDieselGeneratorOperabilityTest;1,2-0HP4023.001.001RemoteShutdownProcedures;OHI-5030PreventiveMaintenance;1,2-0HP4023.001.006LossofControlAir;1,2-0HP4023.ECA-0.1WithoutSIRequired;LossofAllACPowerRecovery1,2-0HP4023.ECA-0.2WithSIRequired;LossofAllACPowerRecovery Dr.T.E.Murley-4-AEP:NRC:0537DoPMP2080.EPP.111NaturalEmergencyGuidelines;oPMI4010PlantOperationsPolicy;*oLoadRestorationPlan,IndianaMichiganPowerCompanySystemOperationDepartment,August,1988.o1,2-0HP4030.STP.043SafetyRelatedManualValveCycling;*o1-THP6030.IMP.146(.246forUnit2)EmergencyPlantShutdownandCooldownIndicationLocalShutdownIndicationo1-THP6030.IMP.327(.427forUnit2)SteamGeneratorAtmosphereSteamReliefControlCalibration/Alignment*Proceduresrequiringmodification.C.ProosedModificationsandScheduleTheabilityofCookNuclearPlant,Units1and2,tocopewithastationblackoutforfourhoursinaccordancewithNUMARC87-00,Section3.2.5andasdeterminedinSection"A"above;wasassessedusingNUMARC87-00,Section7withthefollowingresults:CondensateInventorForDecaHeatRemovalSection~7.2.1IthasbeendeterminedfromSection7.2.1ofNUMARC87-00thatapproximately90,000gallonsofwaterperunitarerequiredfordecayheatremoval,aswellasforprimary/secondarysidepressurereduction,forthefourhourblackoutevent.Theminimumpermissiblecondensatestoragetanklevelpertechnicalspecificationsprovides175,000gallonsofwaterperunit,whichexceedstherequiredquantityforcopingwithafour-hourstationblackout.Class1EBatteriesCaacitSection7.2.2TheClass1Ebatteriesweredeterminedtobeinadequatetomeetstationblackoutloadsforfourhours.Thefollowingprocedurechangeisnecessarytoprovideafour-hourcapacity:variousloadsnotrequiredtomitigatethestationblackouteventwillbestripped.Theseloadswillbeidentifiedinplantprocedures'.ComressedAirSection7.2.3Procedurechangesarenecessarytoensurethatair-operatedvalvesrequiredfordecayheatremoval Dr.T.EDMurley-5-AEP:NRC:0537Dduringastationblackoutofafour-hourdurationhavesufficientbackupsourcesforoperationorwillbemanuallyoperated.Valvesrequiringmanualoperationorthatneedbackupsources(i.e.,steamgeneratorpower-operatedreliefvalves)foroperationwillbeidentifiedinplantprocedures.4.EffectsofLossofVentilationSection7.2.4Thecalculatedsteadystateambientairtemperatureforthesteamdrivenauxiliaryfeedwaterpumproom(thedominantareaofconcernforaPWR)duringastation0blackoutinducedlossofventilationis133.6F.TheassumptioninNUMARC87-00,Section2'.1thatthecontrolroomwillnotexceed120Fduringthestation0blackouthasbeenassessed.ThecontrolroomatCookNuclearPlant,Units1and2,doesnotexceed120Fduringastationblackout.0Therefore,thecontrolroomisnotadominantareaofconcern.Reasonableassuranceoftheoperabilityofstationblackoutresponseequipmentintheabovedominantarea(s)ofconcernhasbeenassessedusingAppendixFtoNUMARC87-00and/ortheNUMARC87-00TopicalReport.Nomodificationsorassociatedproceduresarerequiredtoprovidereasonableassuranceforequipmentoperability.ContainmentIsolationSection7.2.5Theplantlistofcontainmentisolationvalveshasbeenreviewedtoverifythatvalveswhichmustbecapableofbeingclosedorthatmustbeoperated(cycled)understationblackoutconditionscanbepositioned(withindication)independentofthepreferredandblacked-outunitsClass1Epowersupplies.Noplantmodificationsand/orassociatedprocedurechangesweredeterminedtoberequiredtoensurethatappropriatecontainmentintegritycanbeprovidedunderSBOconditions.6.ReactorCoolantInventorSection2.5Theabilitytomaintainadequatereactorcoolantsysteminventorytoensurethatthecoreiscooledhasbeenassessedforfourhours.Aplant-specificanalysiswasusedforthisassessment.TheexpectedratesofreactorcoolantinventorylossunderSBOconditionsdonotresultincoreuncoveryinaSBOoffourhours.Therefore,makeupsystemsinadditiontothosecurrently Dr.T.E.Murley-6-AEP'NRC:0537DavailableunderSBOconditionsarenotrequiredtomaintaincorecoolingundernaturalcirculation(includingrefluxboiling).TheprocedurechangesidentifiedinPartsA,BandCabovewillbecompletedbyJuly31,1989.TheframeworkforthisresponseletterwasgenericallypreparedbyNUMARCandwasconcurredwithbytheNRCstaff.PlantspecificparameterswereprovidedwhereneededandparagraphsselectedastheyappliedtoCookNuclearPlantfromthegenericresponse.format.NRCstaffconcurrencefortheframeworkwasprovidedinanOctober7,1988,letterfromMr.A.S.Thadani,AssistantDirectorforSystems,NuclearReactorRegulation,toMr.W.H.RasinofNUMARC.ThisdocumenthasbeenpreparedfollowingCorporateproceduresthatincorporateareasonablesetofcontrolstoensureitsaccuracyandcompletenesspriortosignaturebytheundersigned.Sincerely,P.AlichVicePresidentldpcc:D.H.Williams,Jr.W.G.Smith,Jr.-BridgmanR.C.CallenG.CharnoffA.B.DavisNRCResidentInspector-BridgmanG.Bruchmann