ML17331B385

LER 94-004-00:on 940406,three Pressurizer Safety Valves Sent to Offsite Test Lab for Testing for Failure to Meet TS Acceptance Criteria.Cause Not Determined.Nozzle & Disc Seating Surfaces Lapped & polished.W/940510 Ltr

ML17331B385
Person / Time
Site:	Cook
Issue date:	05/10/1994
From:	BLIND A A, WEBER G A INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-94-004, LER-94-4, NUDOCS 9405190369
Download: ML17331B385 (6)

Text

ACCELERATEDITRIBUTIONDEMONS'ATIONSYSTEMREGULATORYINFORMATIONDISTRIBUTIONSYSTEM(RIDS)ACCESSIONNBR:9405190369DOC.DATE:94/05/10NOTARIZED:NODOCKETgFACIL:50-315DonaldC.CookNuclearPowerPlant,Unit1,IndianaM05000315AUTH.NAMEAUTHORAFFILIATIONWEBER,G.A.IndianaMichiganPowerCo.(formerlyIndiana&MichiganEleBLIND,A.A.IndianaMichiganPowerCo.(formerlyIndiana&MichiganEleRECIP.NAMERECIPIENTAFFILIATION

SUBJECT:

LER94-004-00:on940406,threepressurizersafetyvalves,senttotooffsitetestlabfortestingfailedtomeetTSacceptancecriteria.Causenotdetermined.Nozzle&discseatingsurfaceslapped&polished.W/940510ltr.DISTRIBUTIONCODE:IE22TCOPIESRECEIVED:LTR(ENCL0SIZE:TITLE:50.73/50.9LicenseeEventReport(LER),IncidentRpt,etc.NOTES:RECIPIENTIDCODE/NAMEPD3-1PDINTERNAL:AEOD/DOAAEOD/ROAB/DSPNRR/DE/EMEBNRR/DRCH/HHFBNRR/DRCH/HOLBNRR/DRSS/PRPBNRR/DSSA/SRXBRES/DSIR/EIBEXTERNAL:EG&GBRYCE,J.HNRCPDRNSICPOORE,W.COPIESLTTRENCL11112211111122111122'1111RECIPIENTIDCODE/NAMEHICKMAN,JAEOD/DSP/TPABNRR/DE/EELBNRR/DORS/OEABNRR/DRCH/HICBNRR/DRIL/RPEBNRRDSSA/SPLBGREG02FILE01LSTLOBBYWARDNSICMURPHY,G.ANUDOCSFULLTXTCOPIESLTTRENCL111111111111111111111111NOTETOALL"RIDS"RECIPIENTS:PLEASEHELPUSTOREDUCEiVASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMPl-37(EXT.20079)TOELIMINATEYOURNAMEFROiViDISTRIBUTIONLISTSFORDOCUMENTSYOUDON'TNEED!FULLTEXTCONVERSIONREQUIREDTOTALNUMBEROFCOPIESREQUIRED'TTR27ENCL27 IndianaMichigPowerCompanyCookNuclearPlantOneCookPlaceBridgrnan,Ml491066164655901INDlANANICHlGi4NPOWE'RMay10,1994UnitedStatesNuclearRegulatoryCommissionDocumentControlDeskRockville,Maryland20852OperatingLicensesDPR-58DocketNo.50-315DocumentControlManager:Inaccordancewiththecriteriaestablishedby10CFR50.73entitledLicenseeEventReortSstemthefollowingreportisbeingsubmitted:94-004-00A.A.BlindPlantManager/sbAttachmentc'.B.Martin,RegionIIIE.E.FitzpatrickP.A.BarrettR.F.KroegerM.A.Bailey-Ft.WayneNRCResidentInspectorJ.B.Hickman-NRCJ.R.PadgettG.Charnoff,Esq.D.HahnINPOS.J.Brewerqn.~,i~Ul,s<I'-v'7405190369940510PDRADOCK05000315SPDR NRCFORM366(592)U.S.NUCLEARREGULATORYCOMMISSIONAPPROVEDBYOMBNO.3150.0104EXPIRES5/31/95LICENSEEEVENTREPORT(LER)(Seereverseforrequirednumberofdigits/charactersforeachblock)ESTIMATEDBURDENPERRESPONSETOCOMPLYWITHTHISINFORMADONCOLLECTIONREQUEST:50.0HRS.FORWARDCOMMENTSREGARDUIGBURDENESDMATETOTHEINFQRMATICNANDRECORDSMANAGEMENTBRANCH(MNBBTrta),U.S.NUCLEARREGULATORYCOMMISSION>WASHINGTON,DC205550001,ANDTOTHEPAPERWORKREDUCTIONPROJECT(3150010a),OFFICEOFMANAGEMENTANDBUDGET,WASHINGTON,DC20503,FACILITYNAME(I)D.C.COOKNUCLEARPLANT-UNIT1DOCKETNUMBER(2)05000315PAGEP)10F3FAILUREOFTHREEPRESSURIZERSAFETYVALVESTO'MEETTECHNICALSPECIFICATIONRVEILLANCETESTCRITERIAEVENTDATE5LERNUMBER6REPORTNUMBER7OTHERFACILITIESINVOLVED6MONTH04DAY06YEAR94YEAR94SEQUENTIALNUMBER004REVISIONNUMBER0MONTHDAY051094FACIUTYNAMEFACILITYNAMEDOCKETNUMBER05000DOCKETNUMBcR05000OPERATINGMODE(9)20A02(b)20.405(c)50.73(a)(2)(iv)73.71(b)NTTOTHEREQUIREMENTSOF10CFRE:CheckoneormTHISREPORTISSUBMITTEDPURSUAore11POWERLEVEL(10)020.405(a)(1)(i)20.405(a)(1)(ii)20.405(a)(1)(iii)20.405(a)(1)(iv)2o.405(a)(1)(v)50.36(c)(1)50.36(c)(2)X50.73(a)(2)(i)50.73(a)(2)(ii)50.73(a)(2)(iii)LICENSEECONTACTFORTHISLER12M73(a)(2)(v)50.73(a)(2)(vii)50.73(a)(2)(viii)(A)50.73(a)(2)(viii)(B)50.73(a)(2)(x)73.71(c)OTHER(SpeotyinAtrctracttretowandinText,NRCForm366A)NAMEG.A.WEBER-PLANTENGINEERINGSUPERINTENDENTTELEPHONENUMBERFnctvdeAreacode)(616)465-5902COMPLETEONELINEFOREACHCOMPONENTFAILUREDESCRIBEDINTHISREPORT13CAUSESYSTEMCOMPONENTRVMANUFACTURERC710REPORTABLETONPRDS,D.;j.x',~CAUSESYSTEMCOMPONENTMANUFACTURERREPORTABLETONPRDSSUPPLEMENTALREPORTEXPECTED14YES0(yee,cornpteteExPEGTEDsUBMIssIQNDATE)NOABSTRACT(Limitto1400spaces,i.e.,approximately15single.spacedtypewrittenlines)(16)EXPFCTFDMONTHDAYYEARSUBMISSIONDATE(15)OnApri.l6,1994withUni.t1inMode5(ColdShutdown)itwasdeterminedthatallthreeofthepressurizersafetyvalves,whichweresenttoanoffsitetestlaboratoryfortesting,werefoundwithliftsettingsoutsideoftheTechnicalSpecificationacceptancecriteria.Acceptablesettingsarebetween,2461psigand2509psig.Valve1-SV-45Awasfoundtohavealiftsetpointof2536psig,valve1-SV-45Bhadaliftsetpointof2535psigand1-SV-45Chadaliftsetpointof2538psig.Therewasnosafety-signi.ficancesincetheworstcase(1-SV-45C-liftsetpointof2538psig)wouldresultinamaximumtransientpressureof2615psig(2538psigplus3percentaccumulationtoattainitsfullratedlift).ThisisbelowtheTechnicalSpecificationsafetylimitof2735psig.Allthreevalveswerepartiallydisassembled(retainingspringcompression)andinspected.Noproblemswerenoted.Thenozzleanddiscseatingsurfaceswerelappedandpolished.Thevalveswerereassembledandtestedsatisfactori.ly.ThesafetyvalveconditionsexperiencedattheD.C.CookPlantaresimilartocurrenti.ndustrytrends/concerns.-SinceaspecificRootCausecouldnotbedetermined,nopreventiveactioni.splannedatthistime.However,wewillbeevaluatingthetestmethodsandindustryactivitiespertainingtothepressurizersafetyvalves.NRCFORM366(5-92)

REQUIREDNUMBEROFDIGITS/CHARACTERSFOREACHBLOCKBLOCKNUMBERNUMBEROFDIGITS/CHARACTERSUPTO468TOTAL3INADDITIONTO05000VARIESTITLEFACILITYNAMEDOCKETNUMBERPAGENUMBER1012131415UPTO766TOTAL2PERBLOCK7TOTAL2FORYEAR3FORSEQUENTIALNUMBER2FORREVISIONNUMBER6TOTAL2PERBLOCKUPTO18*.FACILITYNAME8TOTAL-DOCKETNUMBER3INADDITIONTO050001CHECKBOXTHATAPPLIESUPTO50FORNAME14FORTELEPHONECAUSEVARIES2FORSYSTEM4FORCOMPONENT4FORMANUFACTURERNPRDSVARIES1CHECKBOXTHATAPPLIES6TOTAL2PERBLOCKTITLEEVENTDATELERNUMBERREPORTDATEOTHERFACILITIESINVOLVEDOPERATINGMODEPOWERLEVELREQUIREMENTSOF10CFRLICENSEECONTACTEACHCOMPONENTFAILURESUPPLEMENTALREPORTEXPECTEDEXPECTEDSUBMISSIONDATE NRCFORM366Ar(669)U.S.NUCLEARREGULATORYCOMMISSIONLICENSEEEVENTREPORT(LER)TEXTCONTINUATIONAPPROVEDOMBNO.31500104EXPIRES:4/30I92ESTIMATEDBURDENPERRESPONSETOCOMPLYWTHTHISINFORMATIONCOLLECTIONREOUESTI50.0HRS.FORWARDCOMMENTSREGARDINGBURDENESTIMATETOTHERECORDSANDREPORTSMANAGEMENTBRANCH(F630),U.S.NUCLEARREGULATORYCOMMISSION,WASHINGTON,OC20555,ANDTO1HEPAPERWORKREDUCTIONPRO)ECT(31500104),OFFICEOFMANAGEMENTANDBUDGET,WASHINGTON,DC20503.FACILITYNAME(1)DOCKE'TNUMBER(2)LERNUMBER(6)PAGE(3)YEARHr5SEOUENTIALNUMBERREVISIONNUMSFRD.C.COOKNUCLEARPLANT-UNIT1TEXT(ifmore4PeceJeeetrr9ed,Ireeeddttr'one)NRCForrrr3IJSA'et(12)o5ooo31594004-0002OF03ConditionsPriortoOccurrence:UnitOne-Mode5(ColdShutdown-followingrefueling).DescritionofEvent:OnApril6,1994,itwasdeterminedthatallthreesafetypressurizersafetyvalves,CrosbyValveModelHB-86-PB,(EZIS/AB-RV)hadliftsettingsoutsideTechnicalSpecification3.4.3acceptancecriteria.Thesafetyvalvesaretestedatatestlaboratoryusingsteamatnominaltemperatureandpressure,asrequiredbyTechnicalSpecification.Thevalvesarerequiredtoliftat2485psigplusorminus1percent,(i.e.between2461and2509psig).Valve1-SV-45Awasfoundtohavealiftsetpointof2536psig,valve1-SV-45Bhadaliftsetpointof2535psigand1-SV-45Chadaliftsetpointof2538psig.TechnicalSpecification4.4:3requiresthateachPressurizerCodeSafetyValvebedemonstratedoperableperSectionXIoftheASMEBoilerandPressureVesselCode,1974Edition.CauseofEvent:ThesafetyvalveconditionsexperiencedattheD.C.CookPlantaresimilartocurrentindustrytrends/concerns.ThephenomenonofsafetyvalvesetpointdriftoutsideofdesigntolerancesiscommonintheNuclearindustry.However,asyet,nocauseforthedrifthasbeendetermined.1-SV-45A,1-SV-45Band1-SV-45Cwerepartiallydisassembled(retainingspringcompression)andinspected.Noproblemswerenoted.Thenozzleanddiscseatingsurfaceswerelappedandpolished.Thevalveswerereassembledandtestedsatisfactorily.Thetestprogram(testfacilityandprocedure)forthePressurizerSafetyValveshasnotchangedfromprevioustesting.AnalsisofEvent:Thiseventhasbeendeterminedtobereportableundertheprovisionsof10CFR5073(a)(2)(i)(B)asanoperationprohibitedbyPlantTechnicalSpecification3.4.3,whichrequiresallofthepressurizersafetyvalvestobeoperablewithaliftsettingof2485psig+/-1percent.Theas-foundliftsetpointsofsafetyvalves1-SV-45A,1-SV-45Band1-SV-45CdidnothaveanyactualimpactontheReactorCoolantSystem(RCS)sincethesafetyvalveswerenotchallengedduringthelastfuelcycle.TherewasnopotentialimpactsincetheRCSwouldnothaveexceededthemaximumtransientlimitof2735psig,whichis110percentofdesignpressure(2485psig).Therewasnoimpactonthehealthorsafetyofthepublic.SafetyValve1-SV-45C(worstcase)hadaliftsetpointof2538psig.TheRCSpressurewouldhavetoreachapressureof2615psig(2538psigplus3percentaccumulation)forthisvalvetoattainitsfullratedlift.Valve1-SV-45Awouldhaveattaineditsratedliftat2612psig(2536psigplus3percent)and1-SV-45Bwouldhaveattaineditsratedliftat2612psig(2535plus3percent).NRCForm366A(669)

NRCFORM366A(64)9)U.S.NUCLEARREGULATORYCOMMISSIOLICENSEEEVENTREPORT(LER)TEXTCONTINUATIONAPPROVEDOMBNO.31504))04EXPIRES)4/30/92ESTIMATEDBURDENPERRESPONSETOCOMPLYWTHTHISINFORMATIONCOLLECTIONREGUESTI500HRS.FORWARDCOMMENTSREGARDINGBUADENESTIMATETOTHERECORDSANDREPORTSMANAGEMENTBRANCHIP430),U.S.NUCLEARAEGULATOAYCOMMISSION,WASHINGTON,OC20555,ANDTOTHEPAPERWORKREDUCTIONPAOJECT(31500104),OFFICEOFMANAGFMENTANDBUDGET,WASHINGTON,OC20503.FACILITYNAME(1)DOCKETNUMBER(21LFRNUMBER(6)PAGE(3)YEAR)'.yi(SSOVSNTIALNVMSSRREVISIONNVM54D.C.COOKNUCLEARPLANT-UNIT1TEXT///mttttptctBnqvnd.IItttddldoIM//Y/ICFdmt3/)BA'4/(I2)050003I5940040003oF0AnalsisofEventcontinued!ThereactorvesselandpressurizerweredesignedtoASMEBGPVSectionIIIwhichpermitsamaximumtransient.pressureof2735psig,110percentofdesignpressure(2485psig).TheRCSpiping,valvesandfittingsaredesignedtoANSIB31.1,1967Edition,whichpermitsamaximumtransientpressureof2985psig,120percentofdesignpressure(2485psig).Inaddition,theentireRCSwashydrotestedto3107psig,125percentofdesign(2485psig),todemonstratesystemintegritypriortoinitialoperation.Inconclusion,thiseventdidnothaveanysafetysignificanceanddidnotrepresentahazardtothepublichealthandsafety.Thesafetylimitof2735psigwouldnothavebeenexceededsincethemaximumRCSpressurewouldnothaveexceed2615psig(1-SV-45Csetpointof2538psigplus3percent).InadditiontothisSafetyAnalysis,anadditionalSafetyEvaluationisbeingperformedtoreviewthecombinedeffectofrecentMainSteamSafetyValveliftsetpoints(reportedinLER50-315/94-001and94-003)inconjunctionwiththeas-foundliftsetpointsofthePressurizerSafetyValves.ThisevaluationisscheduledtobecompletedbyJune30,1994.Wedonotanticipateanyadverseconditionstobeidentifiedduringthisevaluation,however,anupdatedLERwillbesubmittedifdeemednecessary.CorrectiveAction:Thenozzleanddiscseatingsurfaceswerelappedandpolishedforallthreesafetyvalves.Retestsweresatisfactorilycompletedforsteamsetpressureandseatleakage.Thespringpressureon1-SV-45Awasadjustedby1/3flattobringthesetpressurebackintotolerance.SinceaspecificRootCausecouldnotbedetermined,nopreventiveactionisplannedatthistime.However,wewillcontinuetofollowindustryactivitiespertainingtosafetyvalvesetpointdrift.FailedComonentIdentification:PressurizerSafetyValvePlantDesignation:1-SV-45A,1-SV-45Band1-SV-45CManufacturer:CrosbyValveCompanyModel:HB-86-BPEIISCode:AB-RVPreviousSimilarEvents:LERS50-315/90-16,92-09LER:50-316/89-04,92-06NRCForm366A(669)