ML17329A670
| ML17329A670 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 11/11/1992 |
| From: | FITZPATRICK E E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | MURLEY T E NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML17329A671 | List: |
| References | |
| AEP:NRC:1169, NUDOCS 9211170207 | |
| Download: ML17329A670 (14) | |
Text
SUBJECT:
ApplicationforamendstoLicensesDPR-58&DPR-74,requestingTechSpecsTables4.7-1S3.7-4associatedw/TechSpecs3.7.1.1remainsteamsafetyvalvetolerance.DISTRIBUTIONCODE:AOOZDCOPIESRECEIVEDILTRgENCL/SIZE:Ã+ITITLE:ORSubmittal:GeneralDistributionNOTES:-/J.RECIPIENTCOPIESCOPIESIDCODE/NAMELTTRENCLLTTRENCLPD3-1LA1111STANGFJ22RECIPIENTIDCODE/NAMEPD3-1PDACCELERATEDDISFRIBUTIONDEMONSTR<TION'YSTEMREGULATINFORMATIONDZSTRIBUTIOSTEM(RIDE)ACCESSIONNBR:9211170207DOC.DATE:92/ll/llNOTARIZED:YESiDOCKETFACIL:50-315DonaldC.CookNuclearPowerPlant,Unit1,IndianaM0500031550-316DonaldC.CookNuclearPowerPlant,Unit2,IndianaM05000316AUTH.NAMEAUTHORAFFILIATIONFITZPATRICK,E.EIndianaMichiganPowerCo.(formerlyIndiana6MichiganEleRECIP.NAMERECIPIENTAFFILIATIONMURLEY,T.E.DocumentControlBranch(DocumentControlDesk)DINTERNAL:NRR/DET/ESGBNRR/DST/SELB7ENRR/DST/SRXB8EOC/LFMB-EGFI01NRR/DOEA/OTSB11NRR/DST/SICB8H7NUDOCS-ABSTRACTOGC/HDS2RES/DSIR/EIB1111111011.,11D1111S1011EXTERNAL:NRCPDR11NSIC11DNOTETOALL"RIDS"RECIPIENTS:PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK.ROOMPl-37(EXT.504-2065)TOELIMINATEYOURNAMEFROMiDISTRIBUTIONLISTSFORDOCUMENTSYOUDON'TNEED!rDDTOTALNUMBEROFCOPIESREQUIRED:LTTR16ENCL14 indianaMichiganPowerCompanyP.O.Box16631Coiumbus,OH43216AEP:NRC:1169.DonaldC.CookNuclearPlantUnits1and2DocketNos.50-315and50-316LicenseNos.DPR-58andDPR-74TECHNICALSPECIFICATIONSCHANGETOINCREASETHEALLOWABLETOLERANCEFORMAINSTEAMSAFETYVALVESU.S.NuclearRegulatoryCommissionDocumentControlDeskWashington,D.C.20555Attn:T.E.MurleyNovemberll,1992
DearDr.Murley:
ThisletteranditsattachmentsconstituteanapplicationforamendmenttotheTechnicalSpecifications(T/Ss)forDonaldC.CookNuclearPlantUnits1and2.Specifically,werequestthatT/SsTables4.7-1(Unit1)and3.7-4(Unit2)associatedwithT/S3.7.1.1beamendedtoreflectanincreasedmainsteamsafetyvalvetoleranceof+3%.Inaddition,werequestthatUnit2T/S3.5.2beamendedtoreflectathermalpowerlimitationresultingfromthesmallbreakLOCAanalysiswhenasafetyinjectioncross-tievalveisclosed.Theliftsetpointsofthemainsteamsafetyvalvesfrequentlydriftoutsideoftheoriginallyintended+1$allowanceoverafuelcycle.Inattemptingtominimizethesetpointdriftproblemanddeterminetherootcause,severalvalveshavebeeninspectedandrefurbished.Theseactionshavebeenunsuccessfulinkeepingthesetpointswithinspecificationoverthefuelcycle.Themanufacturerofthesevalveshasrecommendedanincreaseintheallowabletoleranceto+3S.ThistoleranceisconsistentwithrecentASMEcoderequirements.Consequently,wearemakingthissubmittaltoimplementthechangesintheT/Ssidentifiedabove.In1986,aNoticeofViolationwasissuedduetoconcernsnotedinInspectionReportNumbers50-315/86030and50-316/86030(referenceAEP:NRC:1013)regardingthedriftinthesetpointforthesubjectvalves.Althoughthiswasnotfoundtobeasignificantsafetyconcern,wecommittedtosubmitalicenseeeventreport(LER)whenanyofthevalveswerefoundoutsideofthe+1%range.InadditiontorequestingyourapprovalofthisproposedT/Sschange,itisalsorequestedthatthiscommitmentbecancelled.Thisrequestisbasedontheoperatingcharacteristicsofthesevalves,thatthevalvesoperateasabank,notindividually,andareanalyzedassuch.Inthefuture,therefore,itisconsideredmoreappropriatetosubmit92111-70207,921111PDR'ADGCK05000815PDR
~O Dr.T.E.Murley2AEP:NRC:1169anLERonlyifthe"as-found"conditionofthisbankofvalvesdoesnotsupporttheChapter14safetyanalysisofrecord.Althoughitispossible,basedonhistoricaltrends,thatsomevalvesmayexceedthe3%driftlimit,sufficientcapacityfromtheremainingvalvesinthebankwouldtypicallybeavailabletoensurethattheplantwouldhaverespondedwithintheanalyzedlimits.ThisT/SchangeisbeingrequestedforimplementationbeforethenextregularlyscheduledUnit2refuelingoutageandassociatedvalvetesting.Tosupporttheschedule,werequestthattheamendmentbeapprovedforbothunitsbytheendofthethirdquarterof1993.WewillkeepNRCprojectmanagementinformedofanyschedulechangethroughroutineprojectreviewmeetings.AdetaileddescriptionoftheproposedchangesandouranalysesconcerningsignificanthazardsconsiderationsareincludedinAttachment1tothisletter.Attachment2containstheproposedrevisedT/Sspages.Attachment3containsmarked-upcopiesoftheexistingT/Ss.WestinghouseReportSECL-91-429,"DonaldC.CookUnits1and2,MainSteamSafetyValveLiftSetpointToleranceRelaxation,"isfoundinAttachment4.Webelievethattheproposedchangeswillnotresultin(1)asignificantchangeinthetypesofeffluentsorasignificantincreaseintheamountofanyeffluentthatmaybereleasedoffsite,or(2)asignificantincreaseinindividualorcumulativeoccupationalradiationexposure.TheseproposedchangeshavebeenreviewedbythePlantNuclearSafetyReviewCommitteeandbytheNuclearSafetyandDesignReviewCommittee.Incompliancewiththerequirementsof10CFR50.91(b)(1),copiesofthisletteranditsattachmentshavebeentransmittedtotheMichiganPublicServiceCommissionandtheNFEMSectionChief.Thisletterissubmittedpursuantto10CFR50.54(f)and,assuch,anoathstatementisenclosed.Sincerely,VicePresidenttjwAttachments Dr.T.E.Murley3AEP:NRC:1169cc:D.H.Williams,Jr.A.A.Blind-BridgmanJ.R.PadgettG.CharnoffA.B.Davis-RegionIIINRCResidentInspector-BridgmanNFEMSectionChief Dr.T.E.Murley4AEP'NRC:1169bc:S.J.BrewerD.H.Malin/K.J.TothM.L.Horvath-BridgmanJ.B.KingseedD.F.PowellJ.B.ShinnockW.G.Smith,Jr.W.M.Dean,NRC-Washington,D.C.AEP:NRC:1169DC-N-6015.1 COUNTYOFFRANKLINE.E.Fitzpatrick,beingdulysworn,deposesandsaysthatheistheVicePresidentoflicenseeIndianaMichiganPowerCompany,thathehasreadtheforegoingTechnicalSpecificationsChangetoIncreasetheAllowableToleranceforMainSteamSafetyValves,andknowsthecontentsthereof;andthatsaidcontentsaretruetothebestofhisknowledgeandbelief.Subscribedandsworntobeforemethisdayof19~mNOTARYPUBLICRITADHILLNOTAIIYPUBLIC.STAlEOFOHI)
ATTACHMENT1toAEP:NRC:1169NOSIGNIFICANTHAZARDSCONSIDERATIONEVALUATIONINSUPPORTOFTHEINCREASEDALLOWABLETOLERANCEONMAINSTEAMSAFETYVALVES Attachment1toAEP:NRC:1169Page1I.INTRODUCTIONThereareatotaloftwentyDressermainsteamsafetyvalves(MSSV)installedonfourmainsteamheaders(fivevalvesperheader)ineachunitatCookNuclearPlant.ThesevalvesarerequiredtobesetpointtestedperSectionXIoftheASMEBoilerandPressureVesselCode,1974Edition.Thesetpoints(liftsettings)mustbewithinthe+1%tolerancespecifiedintheTechnicalSpecifications.Typically,one-thirdofthevalvesaretestedeachrefuelingoutage.Onefailuretomeetthe+1%T/Scriteriacausesadditionalvalvestobetested.AtCookNuclearPlant,wehavehadtotestalltwentyvalvesduringeveryrecentrefuelingoutage.Sincethe1987"TreviTest,"animprovedtestingdevicehasbeenemployedtotesttheMSSVs.Evenwiththeimprovedtestmethods,thetestresultsdonotshowadefinitivetrendofvalvedegradation.Themanufacturer(Dresser)believesthat,ifthevalveswerecycledmorefrequentlythanthe18-monthtest,the+1%tolerancecouldbeachieved.Cyclingthevalvesmoreoftenthanevery18months,,however,isnotfeasibleduetoplantoperationalconstraints.Dresserrecommendsanincreaseinthetolerancerangefrom+1%to+3%forMSSVsatCookNuclearPlant.HistoricaltestresultsofMSSVsatCookNuclearPlantrevealthat90%ofthesetpointdrifthasbeenwithinthe+3%band.The+3%bandisconsistentwithANSI/ASMEOM-1,1981Edition(StandardforReliefDevices),whichspecifiesa+38testingtoleranceforallISIsafetyandreliefvalves.Thetestingrequirementsofthi,sstandardareapplicablevia1986andlatereditionsofASMESectionXI.II.DESCRIPTIONOFPROPOSEDTECHNICALSPECIFICATIONCHANGESA.Unit11.Table4.7-1Table4.7-1isbeingchangedtoreflectthe+3%toleranceratherthanthe+1%toleranceontheMSSVs.2~Basespage3/47-1TheBasesarebeingchangedtoreflecttheallowabletoleranceandtherequirementtoresetthevalvestotheirnominalsetting.ThedescriptionofthevalvefunctioninthefirstparagraphwasclarifiedtobeconsistentwiththeequivalentdescriptionintheUnit2Bases.
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Attachment1toAEP:NRC:1169B.Unit2Page21.T/S3.5.2TechnicalSpecification3.5.2isbeingchangedtolimittheTHERMALPOWERto3250MW~whenasafetyinjectioncross-tievalve(s)isclosed.InanalyzingasmallbreakLOCA,theMSSVtoleranceincreaseresultsinanincreaseinsteamgenerator,andconsequentlyprimarysystem,pressure.Thisresultsinalowersafetyinjectionflow.Theadditionalloweringofthesafetyinjectionflowforthecross-tievalveclosedconfigurationiscompensatedforbyalowerthermalpowertoobtainacceptablesmallbreakLOCAresults.2.Table3.7-4Table3.7-4isbeingchangedtoreflectthe+3%toleranceratherthanthe+1%toleranceontheMSSVs.3.Basespage5-1TheBasesarebeingchangedtoreflecttherequirementtoreducepowerwhenasafetyinjectioncrosstievalveisclosed.4.Basespage3/47-1TheBasesarebeingchangedtoreflecttheallowabletoleranceandtherequirementtoresetthevalvestotheirnominalsetting.III.JUSTIFICATIONFORCHANGEWestinghouseReportSECL-91-429,"DonaldC.CookUnits1and2,MainSteamSafetyValveLiftSetpointToleranceRelaxation,"foundinAttachment4,summarizestheaccidentanalysesaffectedbyarelaxationintheallowableMSSVtoleranceto+38.ThisWestinghousereportprovidesajustificationfortheT/Sschange.IV.NOSIGNIFICANTHAZARDSANALYSISWehaveevaluatedtheproposedT/Sschangesandhavedeterminedthattheydonotrepresentasignificanthazardsconsiderationbasedonthecriteriaestablishedin10CFR50.92(c).OperationofCookNuclearPlantinaccordancewiththeproposedamendmentwillnot:1)InvolveasinificantincreaseintherobabilitorconseuencesofanaccidentreviouslevaluatedBasedontheanalysespresentedinAttachment4,alloftheapplicableLOCAandnon-LOCAdesignbasisacceptancecriteriaaresatisfied.Althoughincreasingthevalvesetpointmay 0o Attachment1toAEP:NRC:1169Page3resultinanincreaseinthesteamreleasefromtherupturedsteamgeneratorintheeventofasteamgeneratortuberuptureabovethecurrentUFSARvaluefoundinChapter14.2.4forbothunitsbyapproximately0.2%,theanalysisindicatesthatthecalculateddosesarewithinasmallfractionofthe10CFR100doseguidelines.Theevaluationalsoconcludesthattheexistingmassreleasesusedintheoffsitedosecalculationsfortheremainingtransients(i.e.,steamlinebreak,rodejection)arestillapplicable.Therearenohardwaremodificationstothevalvesand,therefore,thereisnoincreaseintheprobabilityofaspuriousopeningofaMSSV.Sufficientmarginexistsbetweenthenormalsteamsystemoperatingpressureandthevalvesetpointswiththeincreasedtolerancetoprecludeanincreaseintheprobabilityofactuatingthevalves.Basedontheabove,thereisnosignificantincreaseintheprobabilityofanaccidentpreviouslyevaluatedintheUFSARorinthedoseconsequences.2)CreatetheossibilitofanewordifferentkindofaccidentfromanreviouslanalzedIncreasingtheliftsetpointtoleranceontheMSSVsdoesnotintroduceanewaccidentinitiatormechanism.Nonewfailuremodeshavebeendefinedforanysystemorcomponentimportanttosafetynorhasanynewlimitingsinglefailurebeenidentified.NoaccidentwillbecreatedthatwillincreasethechallengetotheMSSVsandresultinincreasedactuationofthevalves.Therefore,thepossibilityofanewordifferentkindofaccidentthananyalreadyevaluatedintheUFSARisnotcreated.3)InvolveasinificantreductioninamarinofsafetAsdiscussedinthesafetyevaluation(Attachment4),theproposedincreaseintheMSSVliftsetpointtolerancewillinvalidateneithertheLOCAnorthenon-LOCAconclusionspresentedintheUFSARaccidentanalysesofrecord.Thenewlossofload/turbinetripanalysisconcludedthatallapplicableacceptancecriteriaarestillsatisfied.ForalltheUFSARnon-LOCAtransients,theDNBdesignbasis,primaryandsecondarypressurelimits,anddoselimitscontinuetobemet.Peakcladdingtemperaturesremainbelowthelimitsspecifiedin10CFR50.46fornormaloperationandwhenthethermalpowerisreducedtocompensateforclosureofthesafetyinjectioncrosstievalvesasrequiredbytheproposedTechnicalSpecifications.Thecalculateddosesresultingfromasteamgeneratortuberuptureeventremainwithinasmallfractionofthe10CFR100permissiblereleases.Thus,thereisnoreductioninthemargintosafety.
TABLE4-1STEAMLINESAFETYVALVESPERLOOPVALVENUMBERa.SV-1b.SV-1c.SV-2d.SV-2e.SV-3LIFTSETTING*3X*1065psig1065psig1075psig1075psig1085psigORIFICESIZE-16in.216in.216in.216in.216in.2*Theliftsettingpressureshallcorrespondtoambientconditionsofthevalveatnominaloperatingtemperatureandpressure.COOKNUCLEARPLANT-UNIT13/47-4AMENDMENTNO.