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{{#Wiki_filter:ACCELERATEDDISTRIBUTIONDEMONSTRATIONSYSTEMREGULATORYINFORMATIONDISTRIBUTION-SYSTEM(RIDS)ACCESSIONNBR:9406030044DOC.DATE:94/05/27NOTARIZED:NOFACIL:50-244RobertEmmetGinnaNuclearPlant,Unit1,RochesterGAUTH.NAMEAUTHORAFFILIATIONST.MARTIN,J.T.RochesterGas&ElectricCorp.MECREDY,R.C.RochesterGas&ElectricCorp.RECIP.NAMERECIPIENTAFFILIATIONI
{{#Wiki_filter:ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEMREGULATORY INFORMATION DISTRIBUTION-SYSTEM(RIDS)ACCESSION NBR:9406030044 DOC.DATE:
94/05/27NOTARIZED:
NOFACIL:50-244 RobertEmmetGinnaNuclearPlant,Unit1,Rochester GAUTH.NAMEAUTHORAFFILIATION ST.MARTIN,J.T.
Rochester Gas&ElectricCorp.MECREDY,R.C.
Rochester Gas&ElectricCorp.RECIP.NAME RECIPIENT AFFILIATION I


==SUBJECT:==
==SUBJECT:==
LER94-007-00:on940427,feedwatertransientoccurredduetolossofabilitytocontrolfeedwaterregulatinqvalve,causingloloSGlevelreactortrip.Causedbyimproperlysecuredstrokeadjustsetscrew.W/940527ltr.DISTRIBUTIONCODE:IE22TCOPIESRECEIVED:LTRjENCL/SIZE:TITLE:50.73/50.9LicenseeEventReport(LER),IncidentRpt,etc.DOCKETg05000244.RD8NOTES:LicenseExpdateinaccordancewith10CFR2,2.109(9/19/72).05000244ARECIPIENTIDCODE/NAMEPD1-3PDINTERNAL:AEOD/DOAAEOD/ROAB/DSPNRR/DE/EMEBNRR/DRCH/HHFBNRR/DRCH/HOLBNRR/DRSS/PRPBNRR/DSSA/SRXBRES/DSIR/EIBIEXTERNAL:EG&GBRYCE,J.HNRCPDRNSICPOOREiW~COPIESLTTRENCL111122111111221111221111RECIPIENTIDCODE/NAMEJOHNSON,AAEOD/DSP/TPABNRR/DE/EELBNRR/DORS/OEABNRR/DRCH/HICBNRR/DRIL/RPEBNRR/~SSA/SPLBREGFFL~02G1FILE01LSTLOBBYWARDNSICMURPHY,G.ANUDOCSFULLTXTCOPIESLTTRENCL11111111111111111.11,11'11DDDNOTETOALL"RIDS"RECIPIENTS:ADDPLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMPl-37(EXT.20079)TOELIMINATEYOURNAMEFROMDISTRIBUTIONLISTSFORDOCUMENTSYOUDON'TNEED!FULLTEXTCONVERSIONREQUIREDTOTALNUMBEROFCOPIESREQUIRED:LTTR27ENCL27 AsrROCHESTERGASANDELECTRICCORPORATIONROBERTC.MECREOYVicePreridrnrCinnaCrurlesrProducuonrrC~~~~vr4'rroerrScare89EASTAVENUE,ROCHESTERN.Y.14649-0001TELEPHONEAicEAcoDE716546'2700May27,1994U.S.NuclearRegulatoryCommissionAttn:AllenR.JohnsonPWRProjectDirectorateI-3DocumentControlDeskWashington,DC20555
LER94-007-00:on 940427,feedwater transient occurredduetolossofabilitytocontrolfeedwater regulatinq valve,causingloloSGlevelreactortrip.Causedbyimproperly securedstrokeadjustsetscrew.W/940527 ltr.DISTRIBUTION CODE:IE22TCOPIESRECEIVED:LTR jENCL/SIZE:TITLE:50.73/50.9 LicenseeEventReport(LER),IncidentRpt,etc.DOCKETg05000244.RD8NOTES:License Expdateinaccordance with10CFR2,2.109(9/19/72).
05000244ARECIPIENT IDCODE/NAME PD1-3PDINTERNAL:
AEOD/DOAAEOD/ROAB/DSP NRR/DE/EMEB NRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DRSS/PRPB NRR/DSSA/SRXB RES/DSIR/EIB IEXTERNAL:
EG&GBRYCE,J.H NRCPDRNSICPOOREiW~COPIESLTTRENCL111122111111221111221111RECIPIENT IDCODE/NAME JOHNSON,A AEOD/DSP/TPAB NRR/DE/EELB NRR/DORS/OEAB NRR/DRCH/HICB NRR/DRIL/RPEB NRR/~SSA/S PLBREGFFL~02G1FILE01LSTLOBBYWARDNSICMURPHY,G.A NUDOCSFULLTXTCOPIESLTTRENCL11111111111111111.11,11'11DDDNOTETOALL"RIDS"RECIPIENTS:
ADDPLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMPl-37(EXT.20079)TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEED!FULLTEXTCONVERSION REQUIREDTOTALNUMBEROFCOPIESREQUIRED:
LTTR27ENCL27 AsrROCHESTER GASANDELECTRICCORPORATION ROBERTC.MECREOYVicePreridrnrCinnaCrurlesrProducuon rrC~~~~vr4'rroerrScare89EASTAVENUE,ROCHESTER N.Y.14649-0001 TELEPHONE AicEAcoDE716546'2700May27,1994U.S.NuclearRegulatory Commission Attn:AllenR.JohnsonPWRProjectDirectorate I-3DocumentControlDeskWashington, DC20555


==Subject:==
==Subject:==
LER94-007,FeedwaterTransient,DuetoLossofAbilitytoControlFeedwaterRegulatingValve,CausesaLoLoSteamGeneratorLevelReactorTllpR.E.GinnaNuclearPowerPlantDocketNo.50-244Inaccordancewith10CFR50.73,LicenseeEventReportSystem,item(a)(2)(iv),whichrequiresareportof,"anyeventorconditionthatresultedinamanualorautomaticactuationofanyengineeredsafetyfeature(ESF),includingthereactorprotectionsystem(RPS)",theattachedLicenseeEventReportLER94-007isherebysubmitted.Thiseventhasinnowayaffectedthepublic'shealthandsafety.Verytrulyyours,g.P~g'~/rX.C~RobertC.Mecredyxc:U.S.NuclearRegulatoryCommissionRegionI475AllendaleRoadKingofPrussia,PA19406GinnaUSNRCSeniorResidentInspector9406030044'ss40527PDRADOCK05000244C~PDR NRCFORH366(5-92)U.S.NUCLEARREGULATORYC(NHISSIOHPROVEDBYMSNO.3150-0104EXPIRES5/31/95LICENSEEEVENTREPORT(LER)(Seereverseforrequirednunberofdigits/charactersforeachblock)ESTIHATEDBURDENPERRESPONSETOCOMPLYWITHTHISINFORMATIONCOLLECTIONREQUEST:50.0HRS.FORWARDCOMMENTSREGARDINGBURDENESTIMA'IETOTHEINFORMATIONANDRECORDSMANAGEMENTBRANCH(HNBB7714),U.S.NUCLEARREGULATORYCOMMISSION,WASHINGTON,DC20555-000'IANDTOTHEPAPERWORKREDUCTIONPROJECT(31400104),OFFICEOFMANAGEHENTANDBUDGETWASHINGTONDC20503.FAGILITYNAME(1)R.E~GinnaNuclearPowerPlantDOCKETHNNIER(2)05000244PAGE(3)10F9TITLE(4)FeedwaterTransient,DuetoLossofAbilitytoControlFeedwaterRegulatingValve,CausesaLoLoSteamGeneratorLevelReactorTripHONTHDAYYEAREVENTDATE5YEARLERNINBER6SEQUENTIALNUMBERREVISIONNUMBERMONTHDAYYEARREPORTDATE7OTHERFACILITIESINVOLVED8DOCKETNUMBERFACILITYNAME04279494--007--000527FACILITYHAHEDOCKETNUMBEROPERATINGMODE(9)POWERLEVEL(10)N045THISREPORTISSUBMITTEDPURSUANT20.402(b)20.405(a)(1)(i)20.405(a)(1)(ii)20.405(a)(1)(iii)20.405(a)(1)(iv)20.405(a)(1)(v)20.405(c)50.36(c)(1)50.36(c)(2)50.73(a)(2)(i)50.73(a)(2)(ii)50.73(a)(2)(iii)X50.73(a)(2)(iv)50.73(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(b)73~71(c)OTHER(SpecifyinAbstractbelo~andinText,NRCForm366ATOTHEREQUIREMENTSOF10CFR:(Checkoneormore11LICENSEECONTACTFORTHISLER12NAMEJohnT.St.Martin-Director,OperatingExperienceTELEPHONENUMBER(IncludeAreaCode)(315)524.4446C(NPLETEONELINEFOREACHCOHPOHENTFAILUREDESCRIBEDINTHISREPORT13CAUSESYSTEHBJBLCVB042COMPONENTMANUFACTURERREPORTABLETONPRDSPj's)kj~';.CAUSESYSTEMCOMPONENTMANUFACTURERREPORTABLETONPRDSSUPPLEMENTALREPORTEXPECTED14YES(Ifyes,coapleteEXPECTEDSUBMISSIONDATE).XNOEXPECTEDSUBHISSIONDATE(15)MONTHDAYYEARABSTRACT(Limitto1400spaces,i.e.,approximately15single-spacedtypewrittenlines)(16)OnApril27,1994,atapproximately1407EDST,withthereactoratapproximately454reactorpower,theabilitytocontrolthe"A"mainfeedwaterregulatingvalvewaslost.At1410EDST,thereactortrippedonLoLolevel((/=17%)inthe"A"SteamGenerator.TheControlRoomoperatorsperformedtheactionsofproceduresE-0andES-0.1.Theunderlyingcausewasdeterminedtobeanimproperlysecuredstrokeadjustsetscrewforthevalvepositionersignaldiaphragmassemblyforthe"A"mainfeedwaterregulatingvalve.ThiseventisNUREG-1022CauseCode(B),"Design,Manufacturing,Construction/Installation."Immediatecorrectiveactionwastoinstallanewvalvepositionerofapreviousdesign.CorrectiveactiontoprecluderepetitionisoutlinedinSectionV(B).NRCFORM366(5-92)
LER94-007,Feedwater Transient, DuetoLossofAbilitytoControlFeedwater Regulating Valve,CausesaLoLoSteamGenerator LevelReactorTllpR.E.GinnaNuclearPowerPlantDocketNo.50-244Inaccordance with10CFR50.73,LicenseeEventReportSystem,item(a)(2)(iv),whichrequiresareportof,"anyeventorcondition thatresultedinamanualorautomatic actuation ofanyengineered safetyfeature(ESF),including thereactorprotection system(RPS)",theattachedLicenseeEventReportLER94-007isherebysubmitted.
NRCFORM366A(5.92)U.S.NUCLEARREGULATORYCOMMISSIOHLICENSEEEVENTREPORT(LER)TEXTCONTINUATIONPROVEDBYQHINO.3150-0104EXPIRES5/31/95ESTIMATEDBURDENPERRESPONSETOCOMPLYMITHTHISINFORMATIONCOLLECTIONREQUEST:50.0HRS.FORNARDCOMMENTSREGARDIHGBURDENESTIMATETOTHEINFORMATIONAHDRECORDSMANAGEHENTBRANCH(MHBB7714),U.S.NUCLEARREGULATORYCOMMISSION,NASHINGTON,DC20555-0001ANDTOTHEPAPERHORKREDUCTIONPROJECT(3140.0104),OFFICEOFMANAGEMENTAHDBUDGETllASHINGTONDC20503.FACILITYNAME1R.E.GinnaNuclearPowerPlantDOCKETNMBER205000244YEAR94LERNUMBER6SEQUENTIAL--007--REVISION00PAGE32OF9TEXT(Ifmorespaceisrequired,useadditionalcopiesofHRCForm366A)(17)PRE-EVENTPLANTCONDITIONSTheplantachievedfullpoweroperationonApril23,1994,aftercompletionofthe1994annualrefuelingandmaintenanceoutage.OnApril26,1994,theplantwasmanuallyshutdowntorepairasmallsteamleakonaninstrumentfittingonthehighpressure(HP)turbine.Duetostabilityproblemswithcontrol,offeedwaterflowtothe"A"SteamGenerator(S/G)atsteadystateconditions,thevalvepositionerforthe"A"mainfeedwaterregulatingvalve(MFRV)wasreplacedduringthisbriefshutdown.OnApril27,1994,aloadincreasewasinprogress,controlledbyPlantOperatingProcedure0-1.2,"Plant-StartupfromHotShutdowntoFullLoad".Theplantwasatapproximately45%reactorpower.Preparationswerebeingmadetostartasecondmainfeedwaterpump,perSystemOperatingProcedureT-4.F,"Restoring1BFeedwaterPumptoServiceAfterMaintenanceorPowerReduction".II.DESCRIPTIONOFEVENTA.DATESANDAPPROXIMATETIMESOFMAJOROCCURRENCES:oApril27,1994,1410EDST:Eventdateandtime.oApril27,1994,1410EDST:Discoverydateandtime.oApril27,1994,1410EDST:ControlRoomoperatorsverifybothreactortripbreakersopen,andallcontrolandshutdownrodsinserted.oApril27,1994,1412EDST:ControlRoomoperatorsmanuallystoptheoperatingmainfeedwaterpumptolimitareactorcoolantsystemcooldown.oApril27,1994,1416EDST:ControlRoomoperatorsmanuallyclosebothmainsteamisolationvalvestolimitareactorcoolantsystemcooldown.oApril27,1994,1440EDST:Plantstabilizedathotshutdowncondition.NRCFORM366A(5-92)
Thiseventhasinnowayaffectedthepublic'shealthandsafety.Verytrulyyours,g.P~g'~/r X.C~RobertC.Mecredyxc:U.S.NuclearRegulatory Commission RegionI475Allendale RoadKingofPrussia,PA19406GinnaUSNRCSeniorResidentInspector 9406030044
NRCFORM366A(5-92)U.S.NUCLEARREGULATORYCQOIISSIONLICENSEEEVENTREPORT(LER)TEXTCONTINUATIONAPPROVEDBYQ(BHO.3150-0104EXPIRES5/31/95ESTIMATEDBURDENPERRESPONSETOCOMPLYWITHTHISIHFORMATIONCOLLECTIOHREQUEST:50.0HRS.FORWARDCOMMENTSREGARDINGBURDENESTIMATETOTHEINFORMATIONANDRECORDSMANAGEMENTBRANCH(MNBB7714),U.S.NUCLEARREGULATORYCOMMISSION,WASHINGTON,DC20555-0001ANDTOTHEPAPERWORKREDUCTIONPROJECT(31/0-0104),OFFICEOFMANAGEMENTANDBUDGETWASHINGTONDC20503.FACILITYNAME1R.E.GinnaNuclearPowerPlantDOCKETHQIBER2YEAR0500024494LERNUMBER6SEOUENTIALM--007--REVISION00PAGE33OF9TEXT(Ifmorespaceisrequired,useadditionalcopiesofHRCForm366A)(17)B.EVENT:OnApril27,1994,aloadincreasewasinprogress,followingthebriefplantshutdownonApril26,1994.PlantOperatingProcedure0-1.2wasbeingfollowedtocontroltheloadincrease.Onlyonemainfeedwaterpumpwasinoperation,andpreparationswerebeingmadetostartthesecondmainfeedwaterpumpandtocontinuewiththeloadincrease.OnApril27,1994,atapproximately1407EDST,theControlRoomoperatorsnoticedaslightdecreaseinfeedwaterflowtothe"A"S/G.Theyattemptedtomanuallyincreasefeedwaterflow,butthe"A"MFRVdidnotrespondtothedemandsignaltoopenthevalvefromtheMainControlBoard.Atapproximately1408EDST,MainControlBoardannunciatorG-22,"ADFCSSystemTrouble"alarmed,duetoadeviationbetweenthedemandsignalandactualpositionofthe"A"MFRV.Levelcontinuedtodecreaseinthe"A"S/G.TheShiftSupervisororderedarapidloadreduction,inanattempttodecreasetheneedforfeedwaterflow.Withintwominutes,powerhadbeendecreasedbyapproximately15%,andactualfeedwaterflowbeingdeliveredtothe"A"S/Gexceededsteamflow.However,levelinthe"A"S/Gdecrea'sedto(17oIresultinginareactortriponS/GLoLolevel,at1410EDST.TheControlRoomoperatorsperformedtheimmediateactionsofEmergencyOperatingProcedureE-O,"ReactorTriporSafetyInjection",andtransitionedtoEmergencyOperatingProcedureES-0.1',"ReactorTripResponse",whenitwasverifiedthatbothreactortripbreakerswereopen,allcontrolandshutdownrodswereinserted,andsafetyinjectionwasnotactuatedorrequired.DuringperformanceofES-0.1,theControlRoomoperatorsnotedthatananticipatedreactorcoolantsystem(RCS)cooldownwasoccurring,andmanuallystoppedtheoperatingmainfeedwaterpump.Inaddition,bothmainsteamisolationvalves(MSIVs)weremanuallyclosedbytheControlRoomoperators.TheseactionsmitigatedtheRCScooldown.Duringthisevent,pressurizer(PRZR)leveldecreasedbelowthesetpointforletdownisolation,closingtheletdownisolationvalvesanddeenergizingthePRZRheaters.AfterPRZRlevelwasrestoredabovethesetpoint,theControlRoomForemandirectedthatletdownandPRZRheatersberestoredtoservice.Theplantwassubsequentlystabilizedinhotshutdown(atapproximately1440EDST)usingPlantOperatingProcedures0-3,"HotShutdownwithXenonPresent",and0-2,"PlantShutdown".HRCFORM366A(5-92)
'ss40527PDRADOCK05000244C~PDR NRCFORH366(5-92)U.S.NUCLEARREGULATORY C(NHISSIOHPROVEDBYMSNO.3150-0104 EXPIRES5/31/95LICENSEEEVENTREPORT(LER)(Seereverseforrequirednunberofdigits/characters foreachblock)ESTIHATED BURDENPERRESPONSETOCOMPLYWITHTHISINFORMATION COLLECTION REQUEST:50.0HRS.FORWARDCOMMENTSREGARDING BURDENESTIMA'IE TOTHEINFORMATION ANDRECORDSMANAGEMENT BRANCH(HNBB7714),U.S.NUCLEARREGULATORY COMMISSION, WASHINGTON, DC20555-000'I ANDTOTHEPAPERWORK REDUCTION PROJECT(31400104),OFFICEOFMANAGEHENT ANDBUDGETWASHINGTON DC20503.FAGILITYNAME(1)R.E~GinnaNuclearPowerPlantDOCKETHNNIER(2)05000244PAGE(3)10F9TITLE(4)Feedwater Transient, DuetoLossofAbilitytoControlFeedwater Regulating Valve,CausesaLoLoSteamGenerator LevelReactorTripHONTHDAYYEAREVENTDATE5YEARLERNINBER6SEQUENTIAL NUMBERREVISIONNUMBERMONTHDAYYEARREPORTDATE7OTHERFACILITIES INVOLVED8DOCKETNUMBERFACILITYNAME04279494--007--000527FACILITYHAHEDOCKETNUMBEROPERATING MODE(9)POWERLEVEL(10)N045THISREPORTISSUBMITTED PURSUANT20.402(b) 20.405(a)(1)(i)20.405(a)(1)(ii) 20.405(a)(1)(iii) 20.405(a)(1)(iv) 20.405(a)(1)(v) 20.405(c) 50.36(c)(1) 50.36(c)(2) 50.73(a)(2)(i) 50.73(a)(2)(ii) 50.73(a)(2)(iii)
HRCFORM366A(5-92).S.NUCLEARREGUULTORYCOMMISSIONLICENSEEEVENTREPORT(LER)TEXTCONTINUATIONPROVEDBYOIBNO.3150-0104EXPIRES5/31/95ESTIMATEDBURDENPERRESPONSETOCOMPLYWITHTHISINFORMATIONCOLLECTIOHREQUEST:50.0HRS.FORWARDCOMMENTSREGARDINGBURDENESTIMATETOTHEINFORMATIOHAHDRECORDSMANAGEMENTBRANCH(MNBB7714),U.S.NUCLEARREGULATORYCOMMISSION,WASHINGTON,DC20555-0001ANDTOTHEPAPERWORKREDUCTIONPROJECT(3140-0104),OFFICEOFMANAGEMENTANDBUDGETWASHINGTONDC20503.FACILITYNAME1R.E.GinnaNuclearPowerPlantDOCKETNMBER205000244iLERNMBER6YEARSEQUEH'TIAL94--007REVISION00PAGE34OF9TEXT(Ifmorespaceisrequired,useadditionalcopiesofNRCForm366A)(17)C~INOPERABLESTRUCTURESICOMPONENTSIORSYSTEMSTHATCONTRIBUTEDTOTHEEVENT:NoneD.OTHER'YSTEMSORSECONDARYFUNCTIONSAFFECTED:NoneE.METHODOFDISCOVERY:ThiseventwasapparentduetoMainControlBoardindicationsofthelossofabilitytocontrolfeedwaterflowtothe"A"S/G.ThereactortripwasimmediatelyapparentduetoalarmsandindicationsintheControlRoom.F.OPERATORACTION:Afterthereactortrip,theControlRoomoperatorsperformedtheactionsofEmergencyOperatingProceduresE-O,"ReactorTriporSafetyInjection"andES-0.1,"ReactorTripResponse".Theoperatingmainfeedwaterpumpwasmanuallystopped,andtheMSIVsweremanuallyclosedtolimitfurtherRCScooldown.Theplantwasstabilizedathotshutdown.Subsequently,theControlRoomoperatorsnotifiedhighersupervisionandtheNuclearRegulatoryCommissionper10CFR50.72,Non-Emergency,4HourNotification.G.SAFETYSYSTEMRESPONSES:NoneIII.CAUSEOFEVENTA.IMMEDIATECAUSE:Thereactortripwasdueto"A"S/GLoLolevel((/=17%),causedbydecreasedfeedwaterflowtothe"A"S/G.B.INTERMEDIATECAUSE:Thedecreasedfeedwaterflowtothe"A"S/Gwasduetolossofabilitytocontrolthe"A"MFRV,causedbythevalvepositionerforthe"A"MFRVnotrespondingtothedemandopensignal.HRCFORM366A(5-92)
X50.73(a)(2)(iv) 50.73(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(b)73~71(c)OTHER(SpecifyinAbstractbelo~andinText,NRCForm366ATOTHEREQUIREMENTS OF10CFR:(Checkoneormore11LICENSEECONTACTFORTHISLER12NAMEJohnT.St.Martin-Director, Operating Experience TELEPHONE NUMBER(IncludeAreaCode)(315)524.4446C(NPLETEONELINEFOREACHCOHPOHENT FAILUREDESCRIBED INTHISREPORT13CAUSESYSTEHBJBLCVB042COMPONENT MANUFACTURER REPORTABLE TONPRDSPj's)kj~';.CAUSESYSTEMCOMPONENT MANUFACTURER REPORTABLE TONPRDSSUPPLEMENTAL REPORTEXPECTED14YES(Ifyes,coapleteEXPECTEDSUBMISSION DATE).XNOEXPECTEDSUBHISSIONDATE(15)MONTHDAYYEARABSTRACT(Limitto1400spaces,i.e.,approximately 15single-spaced typewritten lines)(16)OnApril27,1994,atapproximately 1407EDST,withthereactoratapproximately 454reactorpower,theabilitytocontrolthe"A"mainfeedwater regulating valvewaslost.At1410EDST,thereactortrippedonLoLolevel((/=17%)inthe"A"SteamGenerator.
HRCFORM366A(5-92)U.S.NUCLEARREGULATORYCOMMISSIONLICENSEE.EVENTREPORT(LER)TEXTCONTINUATIONPROVEDBYOMBNO.3150-0104EXPIRES5/31/95ESTIMATEDBURDENPERRESPONSETOCOMPLYWITHTHISINFORMATIONCOLLECTIONREQUEST:50.0HRS.'ORWARDCOMMENTSREGARDINGBURDENESTIMATETOTHEINFORMATIONANDRECORDSMANAGEMENTBRANCH(MNBB7714),U.S.NUCLEARREGULATORYCOMMISSIOH,WASHINGTON,DC20555-0001,ANDTOTHEPAPERWORKREDUCTIONPROJECT(31500104),OFFICEOFMANAGEMENTANDBUDGETWASHINGTONDC20503.FACILITYNAME1'R.E.GinnaNuclearPowerPlantDOCKETNWBER205000244LERNI&#xc3;BER6)YEARSEQUENTIAL94--007--REVISION,00PACE35OF9TEXT(lfmorespaceisrequired,useadditionalcopiesofHRCForm366A)(17)C.ROOTCAUSE:Theunderlyingcauseofthevalvepositionerforthe"A"MFRVnotproperlyrespondingtoachangeininput,demandsignalfromthecontrollerontheMainControlBoardwasanimproperlysecuredstrokeadjustsetscrew.Thesetscrewwasfoundinabackedoutconditioninthevalvepositionsignaldiaphragmassemblyforthe"A"MFRV.Itispostulatedthatthisstrokeadjustallenheadsetscrewdidnothaveadequatethreadsealanttopreventitfrombackingoutofthesignaldiaphragmassemblycoverwhensubjected-tovibration.Withthesetscrewbackedout,thesignaldiaphragmwasrestrictedfromrespondingtoaninputdemandsignaltoopentheMFRV.Notethatthesetscrewisafactory-setadjustment.Thisparticularsetscrewbackedoutwhensubjectedtolessthantwelvehoursofoperation,andthisfailuremodehasnotoccurredinothervalvepositionersthathave'accumulatedthousandsofhoursofoperation.ThiseventisNUREG-1022CauseCode(B),"Design,Manufacturing,Construction/Installation."IV.ANALYSISOFEVENTThiseventisreportableinaccordancewith10CFR50.73,LicenseeEventReportSystem,item(a)(2)(iv),whichrequiresareportof,"anyeventorconditionthatresultedinmanualorautomaticactuationofanyengineeredsafetyfeature(ESF)includingthereactorprotectionsystem(RPS)".The"A"S/GLoLolevelreactortripwasanautomaticactuationoftheRPS.Anassessmentwasperformedconsideringboththesafetyconsequen-cesandimplicationsofthiseventwiththefollowingresultsandconclusions:oTherewerenosafetyconsequencesorimplicationsattributedtothereactortripbecause:*Thetworeactortripbreakersopenedasrequired.*Allcontrolandshutdownrodsinsertedasdesigned.*Theplantwasstabilizedathotshutdown.HRCFORM366A(5-92)
TheControlRoomoperators performed theactionsofprocedures E-0andES-0.1.Theunderlying causewasdetermined tobeanimproperly securedstrokeadjustsetscrewforthevalvepositioner signaldiaphragm assemblyforthe"A"mainfeedwater regulating valve.ThiseventisNUREG-1022 CauseCode(B),"Design,Manufacturing, Construction/Installation."
NRCFORH366A(5-92)U.SNUCLEARREGULATORYCOMMISSIONLICENSEEEVENTREPORT(LER)TEXTCONTINUATIONAPPROVEDBY(HGINO.3150-0104EXPIRES5/31/95ESTIMATEDBURDENPERRESPONSETOCOMPLYWITHTHISINFORMATIONCOLLEC'IIOHREQUEST:50.0HRS~FORNARDCOMMENTSREGARDINGBURDENESTIMATETOtHEINFORMATIONANDRECORDSMANAGEMENTBRANCH(MNBB7714),U.S.NUCLEARREGULATORYCOMMISSION,MASHIHGTON,DC20555-0001,ANDTOTHEPAPERNORKREDUCTIONPROJECT(3150-0104),OFFICEOFMANAGEMENTANDBUDGETMASHINGTONDC20503.FACILITYNAME1R.E.GinnaNuclearPowerPlantDOCKETHINSER2I05000244YEAR94--00700LERNIMBER6SEQUENTIALREVISIONPAGE36OF9TEXT(Ifmorespaceisrequired,useadditionalcopiesofNRCForm366A)(17)oTheGinnaUpdatedFinalSafetyAnalysisReport(UFSAR)transient,asdescribedinChapter15.2.6,"LossofNormalFeedwater",describesaconditionwherethereactortripsonLoLoS/Glevel.ThisUFSARtransientwasreviewedandcomparedtotheplantresponseforthisevent.TheUFSARtransientisacompletelossofMainFeedwater(MFW)atfullpower,withonlyoneauxiliaryfeedwater(AFW)pumpavailableone(1)minuteafterthelossofMFW,andsecondarysteamrelief(i.e.,decayheatremoval)throughthesafetyvalvesonly.TheprotectionagainstalossofMFWincludesthereactortriponLoLoS/GlevelandthestartoftheAFWpumps.Theseprotectionfeaturesoperatedasdesigned.Basedontheaboveevaluation,theplanttransientofApril27,1994,isboundedbytheUFSARSafetyAnalysisassumptions.oTechnicalSpecifications(TS)werereviewedwithrespecttotheposttripreviewdata.'hefollowingaretheresultsofthatreview:*Followingthereactortrip,PRZRwaterleveldecreased'oapproximately12.5%duetoamoderateRCScooldown.Thiscooldownoccurredduringtheposttriprecoveryperiod.Thiscooldownwasboundedbytheplantaccidentanalysis,anddidnotexceedtheTSlimitof100degreesFperhour.AdditionalmitigationwasprovidedbyclosingtheMSIVsandstopping-themainfeedwaterpump.TS3.1.1.5states,inpart,thatwhentheRCStemperatureisatorabove350degreesF,atleast100KWofPRZRheaterswillbeoperable.TS3.1.1.5alsostates,inpart,thatifthePRZR,isinoperableduetoheaters,restorethePRZR'tooperablestatuswithinsix(6)hours.PRZRwaterlevelwasrestoredabovethesetpointforletdownisolationwithintwo(2)minutes,restoringthePRZRheaterstooperablestatus,wellbeforethesix'(6)houractionstatement.NRCFORM366A(5-92)
Immediate corrective actionwastoinstallanewvalvepositioner ofapreviousdesign.Corrective actiontoprecluderepetition isoutlinedinSectionV(B).NRCFORM366(5-92)
NRCFORH366A(5.92)U.S.NUCLEARREGULATORYCOMHISSIONLICENSEEEVENTREPORT(LER)TEXTCONTINUATIONAPPROVEDBYQGINO.3150-0104EXPIRES5/31/95ESTIHATEDBURDENPERRESPONSETOCOMPLYWITHTHISINFORMATIONCOLLECTIONREOUEST:50.0HRS.FORWARDCOMMENTSREGARDINGBURDENESTIMATETOTHEINFORMATIONANDRECORDSMANAGEHENTBRANCH(MNBB7714),U.STNUCLEARREGULATORYCOMMISSION,WASHINGTON,DC20555-0001ANDTOTHEPAPERWORKREDUCTIONPROJECT(31400104),OFFICEOFHANAGEMENTANDBUDGETWASHINGTONDC20503.FACILITYNAHE1R.E.GinnaNuclearPowerPlantDOCKETNINBER205000244LERNUMBER6YEARSEOUENTIAL94--007--REVISION00PAGE37OF9TEXT(Ifmorespaceisrequired,useadditionalcopiesofNRCForm366A)(17)*BothS/Glevelsdecreasedfollowingthereactortrip."A"S/Gleveldecreasedto<04,and"B"S/Gleveldecreasedto<14'.Thisisanexpectedtransient.TS4.3.5.5statesthatinordertodemonstratethatareactorcoolantloopisoperable,theS/Gwaterlevelshallbe>/=169.Thus,bothcoolantloopswere.inoperable,eventhoughbothloopswerestillinoperationandperformingtheirintendedfunctionofdecayheatremoval.BothS/Gswereavailableasaheatsink,andsufficientAFWflowwasmaintainedforadequatesteamreleasefrombothS/Gs.TS3.1.1.1(c)states,inpart,thatexceptforspecialtests,whentheRCStemperatureisatorabove350degreesFwiththereactorpowerlessthanorequalto130MWT(8.5%),atleastonereactorcoolantloopanditsassociatedS/Gandreactorcoolantpumpshallbeinoperation.Bothreactorcoolantloopswereinoperation,buttheS/Gswereinoperableduetolevelindication.BothloopswererestoredtooperablestatuswhenS/Glevelswererestoredto>/=164("B"S/Glevelinlessthanfour(4)minutes,and"A"S/Glevelinapproximatelyten(10)minutes).Basedontheaboveandareviewofposttripdataandpastplanttransients,itcanbeconcludedthattheplantoperatedasdesigned,thattherewerenounreviewedsafetyquestions,andthatthepublic'shealthandsafetywasassuredatalltimes.NRCFORM366A(5-92)
NRCFORM366A(5.92)U.S.NUCLEARREGULATORY COMMISSIOH LICENSEEEVENTREPORT(LER)TEXTCONTINUATION PROVEDBYQHINO.3150-0104 EXPIRES5/31/95ESTIMATED BURDENPERRESPONSETOCOMPLYMITHTHISINFORMATION COLLECTION REQUEST:50.0HRS.FORNARDCOMMENTSREGARDIHG BURDENESTIMATETOTHEINFORMATION AHDRECORDSMANAGEHENT BRANCH(MHBB7714),U.S.NUCLEARREGULATORY COMMISSION, NASHINGTON, DC20555-0001 ANDTOTHEPAPERHORK REDUCTION PROJECT(3140.0104),
NRCFORH366A(5-92)U.S.NUCLEARREGULATORYC(SOIISSIOHLICENSEEEVENTREPORT(LER)TEXTCONTINUATIONAPPROVEDBYMBNO.3150-0104EXPIRES5/31/95ESTIMATEDBURDENPERRESPONSETOCOMPLYWITHTHISINFORMATIONCOLLECTIONREQUEST:50.0HRS.FORWARDCOMMENTSREGARDIHGBURDEN'STIMATETOTHEINFORMATIONANDRECORDSMANAGEMENTBRANCH(MHBB7714),U.S.NUCLEARREGULATORYCOMMISSION,WASHINGTON,DC20555-0001ANDTOTHEPAPERWORKREDUCTIONPROJECT(3140-0104),OFFICEOFMANAGEMENTANDBUDGET'WASHINGTONDC20503.FACILITYNAME1R.E.GinnaNuclearPowerPlantDOCKETNQIBER205000244YEAR94--007--00LERHINBER6SEQUENTIALREVISIONMPAGE38OF9TEXT(Ifmorespaceisrequired,useadditionalcopiesofNRCForm366A)(17)V.CORRECTIVEACTIONA.ACTIONTAKENTORETURNAFFECTEDSYSTEMSTOPRE-EVENTNORMALSTATUS:oThevalvepositionerforthe"A"MFRV(BaileyModelAV112100Ior"TypeAV1")hadbeenreplacedonApril26,1994,withanotherTypeAV1positioner.Thisspecificpositionerfailedinlessthantwelvehoursofuseandwasreplacedafterthisevent(onApril28,1994)withaBaileyModel5321030A10(or"5321030")valvepositioner.TheBaileyModel5321030istheoriginalmodelofvalvepositionerfortheMFRVapplicationandhadoperatedsuccessfullysinceplantstartupin1969.Thispositionermodelwaschangedoutin1991aspartofEWR4773,whichinstalledtheAdvancedDigitalFeedwaterControlSystem(ADFCS).TheTypeAV1positionershavehadahistoryofreliabilityandstabilityconcernsinthisMFRVapplication.oThevalvepositionerforthe"B"MFRVwasalsoreplacedonApril28,1994,forthereasonsdiscussedabove.oValve.rampandstepchangediagnostictestingwasperformedforbothMFRVstoverifypropervalvepositioningandresponse.B.ACTIONTAKENORPLANNEDTOPREVENTRECURRENCE:oThepositionersforbothMFRVswerereplacedwithModel5321030positionersasdiscussedabove.HRCFORM366A(5-92)
OFFICEOFMANAGEMENT AHDBUDGETllASHINGTON DC20503.FACILITYNAME1R.E.GinnaNuclearPowerPlantDOCKETNMBER205000244YEAR94LERNUMBER6SEQUENTIAL
NRCFORM366A(5-92)I.S.NUCLEARREGULATORYCQOIISSIOHLICENSEEEVENTREPORT(LER)TEXTCONTINUATIONPROVEDBYOMBNO.3150-0104EXPIRES5/31/95ESTIMATEDBURDENPERRESPONSETOCOMPLYWITHTHISINFORMATIONCOLLECTIOHREDUEST:50.0HRS.FORWARDCOMMENTSREGARDIHGBURDEHESTIMATETOTHEINFORMATIONANDRECORDSMANAGEMENTBRANCH(MHBB7714),U.S.NUCLEARREGULATORYCOMMISSION,WASHINGTON,DC20555-0001AHDTOTHEPAPERWORKREDUCTIONPROJECT(3140.0104),OFFICEOFMANAGEMENTANDBUDGETWASHINGTONDC20503.FACILITYNAME1R.E.GinnaNuclearPowerPlantDOCKETNUMBER205000244YEAR94LERNUMBER6SEOUENTIALM--007--REVISION00PAGE39OF9TEXT(Ifmorespaceisrequired,useadditionalcopiesofHRCForm366A)(17)VI.ADDITIONALINFORMATIONA.FAILEDCOMPONENTS:Thefailedcomponentwasthestrokeadjustallenheadsetscrewforthevalvepositionersignaldiaphragmassemblyforthe"A"MFRV.ThepositionerisaModelAV112100positioner,manufacturedbyBaileyControlsInc.B.PREVIOUSLERsONSIMILAREVENTS:AsimilarLEReventhistoricalsearchwasconductedwiththefollowingresults:nodocumentationofsimilarLEReventswiththesamerootcauseatGinnaNuclearPowerPlantcouldbeiden-tified;however,LER93-006wasasimilarevent,inthattherewaslossofabilitytocontrolthe"A"MFRV;andLERs88-005,90007Iand90-010weresimilareventswithdifferentrootcauses.C.SPECIALCOMMENTS:NoneHRCFORM366A(5-92)}}
--007--REVISION00PAGE32OF9TEXT(Ifmorespaceisrequired, useadditional copiesofHRCForm366A)(17)PRE-EVENT PLANTCONDITIONS Theplantachievedfullpoweroperation onApril23,1994,aftercompletion ofthe1994annualrefueling andmaintenance outage.OnApril26,1994,theplantwasmanuallyshutdowntorepairasmallsteamleakonaninstrument fittingonthehighpressure(HP)turbine.Duetostability problemswithcontrol,offeedwater flowtothe"A"SteamGenerator (S/G)atsteadystateconditions, thevalvepositioner forthe"A"mainfeedwater regulating valve(MFRV)wasreplacedduringthisbriefshutdown.
OnApril27,1994,aloadincreasewasinprogress, controlled byPlantOperating Procedure 0-1.2,"Plant-StartupfromHotShutdowntoFullLoad".Theplantwasatapproximately 45%reactorpower.Preparations werebeingmadetostartasecondmainfeedwater pump,perSystemOperating Procedure T-4.F,"Restoring 1BFeedwater PumptoServiceAfterMaintenance orPowerReduction".
II.DESCRIPTION OFEVENTA.DATESANDAPPROXIMATE TIMESOFMAJOROCCURRENCES:
oApril27,1994,1410EDST:Eventdateandtime.oApril27,1994,1410EDST:Discovery dateandtime.oApril27,1994,1410EDST:ControlRoomoperators verifybothreactortripbreakersopen,andallcontrolandshutdownrodsinserted.
oApril27,1994,1412EDST:ControlRoomoperators manuallystoptheoperating mainfeedwater pumptolimitareactorcoolantsystemcooldown.
oApril27,1994,1416EDST:ControlRoomoperators manuallyclosebothmainsteamisolation valvestolimitareactorcoolantsystemcooldown.
oApril27,1994,1440EDST:Plantstabilized athotshutdowncondition.
NRCFORM366A(5-92)
NRCFORM366A(5-92)U.S.NUCLEARREGULATORY CQOIISSION LICENSEEEVENTREPORT(LER)TEXTCONTINUATION APPROVEDBYQ(BHO.3150-0104 EXPIRES5/31/95ESTIMATED BURDENPERRESPONSETOCOMPLYWITHTHISIHFORMATION COLLECTIOH REQUEST:50.0HRS.FORWARDCOMMENTSREGARDING BURDENESTIMATETOTHEINFORMATION ANDRECORDSMANAGEMENT BRANCH(MNBB7714),U.S.NUCLEARREGULATORY COMMISSION, WASHINGTON, DC20555-0001 ANDTOTHEPAPERWORK REDUCTION PROJECT(31/0-0104),
OFFICEOFMANAGEMENT ANDBUDGETWASHINGTON DC20503.FACILITYNAME1R.E.GinnaNuclearPowerPlantDOCKETHQIBER2YEAR0500024494LERNUMBER6SEOUENTIAL M--007--REVISION00PAGE33OF9TEXT(Ifmorespaceisrequired, useadditional copiesofHRCForm366A)(17)B.EVENT:OnApril27,1994,aloadincreasewasinprogress, following thebriefplantshutdownonApril26,1994.PlantOperating Procedure 0-1.2wasbeingfollowedtocontroltheloadincrease.
Onlyonemainfeedwater pumpwasinoperation, andpreparations werebeingmadetostartthesecondmainfeedwater pumpandtocontinuewiththeloadincrease.
OnApril27,1994,atapproximately 1407EDST,theControlRoomoperators noticedaslightdecreaseinfeedwater flowtothe"A"S/G.Theyattempted tomanuallyincreasefeedwater flow,butthe"A"MFRVdidnotrespondtothedemandsignaltoopenthevalvefromtheMainControlBoard.Atapproximately 1408EDST,MainControlBoardannunciator G-22,"ADFCSSystemTrouble"alarmed,duetoadeviation betweenthedemandsignalandactualpositionofthe"A"MFRV.Levelcontinued todecreaseinthe"A"S/G.TheShiftSupervisor orderedarapidloadreduction, inanattempttodecreasetheneedforfeedwater flow.Withintwominutes,powerhadbeendecreased byapproximately 15%,andactualfeedwater flowbeingdelivered tothe"A"S/Gexceededsteamflow.However,levelinthe"A"S/Gdecrea'sed to(17oIresulting inareactortriponS/GLoLolevel,at1410EDST.TheControlRoomoperators performed theimmediate actionsofEmergency Operating Procedure E-O,"ReactorTriporSafetyInjection",
andtransitioned toEmergency Operating Procedure ES-0.1',"ReactorTripResponse",
whenitwasverifiedthatbothreactortripbreakerswereopen,allcontrolandshutdownrodswereinserted, andsafetyinjection wasnotactuatedorrequired.
Duringperformance ofES-0.1,theControlRoomoperators notedthatananticipated reactorcoolantsystem(RCS)cooldownwasoccurring, andmanuallystoppedtheoperating mainfeedwater pump.Inaddition, bothmainsteamisolation valves(MSIVs)weremanuallyclosedbytheControlRoomoperators.
Theseactionsmitigated theRCScooldown.
Duringthisevent,pressurizer (PRZR)leveldecreased belowthesetpointforletdownisolation, closingtheletdownisolation valvesanddeenergizing thePRZRheaters.AfterPRZRlevelwasrestoredabovethesetpoint, theControlRoomForemandirectedthatletdownandPRZRheatersberestoredtoservice.Theplantwassubsequently stabilized inhotshutdown(atapproximately 1440EDST)usingPlantOperating Procedures 0-3,"HotShutdownwithXenonPresent",
and0-2,"PlantShutdown".
HRCFORM366A(5-92)
HRCFORM366A(5-92).S.NUCLEARREGUULTORY COMMISSION LICENSEEEVENTREPORT(LER)TEXTCONTINUATION PROVEDBYOIBNO.3150-0104 EXPIRES5/31/95ESTIMATED BURDENPERRESPONSETOCOMPLYWITHTHISINFORMATION COLLECTIOH REQUEST:50.0HRS.FORWARDCOMMENTSREGARDING BURDENESTIMATETOTHEINFORMATIOH AHDRECORDSMANAGEMENT BRANCH(MNBB7714),U.S.NUCLEARREGULATORY COMMISSION, WASHINGTON, DC20555-0001 ANDTOTHEPAPERWORK REDUCTION PROJECT(3140-0104),
OFFICEOFMANAGEMENT ANDBUDGETWASHINGTON DC20503.FACILITYNAME1R.E.GinnaNuclearPowerPlantDOCKETNMBER205000244iLERNMBER6YEARSEQUEH'TIAL 94--007REVISION00PAGE34OF9TEXT(Ifmorespaceisrequired, useadditional copiesofNRCForm366A)(17)C~INOPERABLE STRUCTURES ICOMPONENTS IORSYSTEMSTHATCONTRIBUTED TOTHEEVENT:NoneD.OTHER'YSTEMS ORSECONDARY FUNCTIONS AFFECTED:
NoneE.METHODOFDISCOVERY:
ThiseventwasapparentduetoMainControlBoardindications ofthelossofabilitytocontrolfeedwater flowtothe"A"S/G.Thereactortripwasimmediately apparentduetoalarmsandindications intheControlRoom.F.OPERATORACTION:Afterthereactortrip,theControlRoomoperators performed theactionsofEmergency Operating Procedures E-O,"ReactorTriporSafetyInjection" andES-0.1,"ReactorTripResponse".
Theoperating mainfeedwater pumpwasmanuallystopped,andtheMSIVsweremanuallyclosedtolimitfurtherRCScooldown.
Theplantwasstabilized athotshutdown.
Subsequently, theControlRoomoperators notifiedhighersupervision andtheNuclearRegulatory Commission per10CFR50.72, Non-Emergency, 4HourNotification.
G.SAFETYSYSTEMRESPONSES:
NoneIII.CAUSEOFEVENTA.IMMEDIATE CAUSE:Thereactortripwasdueto"A"S/GLoLolevel((/=17%),causedbydecreased feedwater flowtothe"A"S/G.B.INTERMEDIATE CAUSE:Thedecreased feedwater flowtothe"A"S/Gwasduetolossofabilitytocontrolthe"A"MFRV,causedbythevalvepositioner forthe"A"MFRVnotresponding tothedemandopensignal.HRCFORM366A(5-92)
HRCFORM366A(5-92)U.S.NUCLEARREGULATORY COMMISSION LICENSEE.
EVENTREPORT(LER)TEXTCONTINUATION PROVEDBYOMBNO.3150-0104 EXPIRES5/31/95ESTIMATED BURDENPERRESPONSETOCOMPLYWITHTHISINFORMATION COLLECTION REQUEST:50.0HRS.'ORWARD COMMENTSREGARDING BURDENESTIMATETOTHEINFORMATION ANDRECORDSMANAGEMENT BRANCH(MNBB7714),U.S.NUCLEARREGULATORY COMMISSIOH, WASHINGTON, DC20555-0001, ANDTOTHEPAPERWORK REDUCTION PROJECT(31500104),OFFICEOFMANAGEMENT ANDBUDGETWASHINGTON DC20503.FACILITYNAME1'R.E.GinnaNuclearPowerPlantDOCKETNWBER205000244LERNI&#xc3;BER6)YEARSEQUENTIAL 94--007--REVISION,00PACE35OF9TEXT(lfmorespaceisrequired, useadditional copiesofHRCForm366A)(17)C.ROOTCAUSE:Theunderlying causeofthevalvepositioner forthe"A"MFRVnotproperlyresponding toachangeininput,demandsignalfromthecontroller ontheMainControlBoardwasanimproperly securedstrokeadjustsetscrew.Thesetscrewwasfoundinabackedoutcondition inthevalvepositionsignaldiaphragm assemblyforthe"A"MFRV.Itispostulated thatthisstrokeadjustallenheadsetscrewdidnothaveadequatethreadsealanttopreventitfrombackingoutofthesignaldiaphragm assemblycoverwhensubjected-tovibration.
Withthesetscrewbackedout,thesignaldiaphragm wasrestricted fromresponding toaninputdemandsignaltoopentheMFRV.Notethatthesetscrewisafactory-set adjustment.
Thisparticular setscrewbackedoutwhensubjected tolessthantwelvehoursofoperation, andthisfailuremodehasnotoccurredinothervalvepositioners thathave'accumulated thousands ofhoursofoperation.
ThiseventisNUREG-1022 CauseCode(B),"Design,Manufacturing, Construction/Installation."
IV.ANALYSISOFEVENTThiseventisreportable inaccordance with10CFR50.73,LicenseeEventReportSystem,item(a)(2)(iv),whichrequiresareportof,"anyeventorcondition thatresultedinmanualorautomatic actuation ofanyengineered safetyfeature(ESF)including thereactorprotection system(RPS)".The"A"S/GLoLolevelreactortripwasanautomatic actuation oftheRPS.Anassessment wasperformed considering boththesafetyconsequen-cesandimplications ofthiseventwiththefollowing resultsandconclusions:
oTherewerenosafetyconsequences orimplications attributed tothereactortripbecause:*Thetworeactortripbreakersopenedasrequired.
*Allcontrolandshutdownrodsinsertedasdesigned.
*Theplantwasstabilized athotshutdown.
HRCFORM366A(5-92)
NRCFORH366A(5-92)U.SNUCLEARREGULATORY COMMISSION LICENSEEEVENTREPORT(LER)TEXTCONTINUATION APPROVEDBY(HGINO.3150-0104 EXPIRES5/31/95ESTIMATED BURDENPERRESPONSETOCOMPLYWITHTHISINFORMATION COLLEC'IIOH REQUEST:50.0HRS~FORNARDCOMMENTSREGARDING BURDENESTIMATETOtHEINFORMATION ANDRECORDSMANAGEMENT BRANCH(MNBB7714),U.S.NUCLEARREGULATORY COMMISSION, MASHIHGTON, DC20555-0001, ANDTOTHEPAPERNORK REDUCTION PROJECT(3150-0104),
OFFICEOFMANAGEMENT ANDBUDGETMASHINGTON DC20503.FACILITYNAME1R.E.GinnaNuclearPowerPlantDOCKETHINSER2I05000244YEAR94--00700LERNIMBER6SEQUENTIAL REVISIONPAGE36OF9TEXT(Ifmorespaceisrequired, useadditional copiesofNRCForm366A)(17)oTheGinnaUpdatedFinalSafetyAnalysisReport(UFSAR)transient, asdescribed inChapter15.2.6,"LossofNormalFeedwater",
describes acondition wherethereactortripsonLoLoS/Glevel.ThisUFSARtransient wasreviewedandcomparedtotheplantresponseforthisevent.TheUFSARtransient isacompletelossofMainFeedwater (MFW)atfullpower,withonlyoneauxiliary feedwater (AFW)pumpavailable one(1)minuteafterthelossofMFW,andsecondary steamrelief(i.e.,decayheatremoval)throughthesafetyvalvesonly.Theprotection againstalossofMFWincludesthereactortriponLoLoS/GlevelandthestartoftheAFWpumps.Theseprotection featuresoperatedasdesigned.
Basedontheaboveevaluation, theplanttransient ofApril27,1994,isboundedbytheUFSARSafetyAnalysisassumptions.
oTechnical Specifications (TS)werereviewedwithrespecttotheposttripreviewdata.'hefollowing aretheresultsofthatreview:*Following thereactortrip,PRZRwaterleveldecreased
'oapproximately 12.5%duetoamoderateRCScooldown.
Thiscooldownoccurredduringtheposttriprecoveryperiod.Thiscooldownwasboundedbytheplantaccidentanalysis, anddidnotexceedtheTSlimitof100degreesFperhour.Additional mitigation wasprovidedbyclosingtheMSIVsandstopping-themainfeedwater pump.TS3.1.1.5states,inpart,thatwhentheRCStemperature isatorabove350degreesF,atleast100KWofPRZRheaterswillbeoperable.
TS3.1.1.5alsostates,inpart,thatifthePRZR,isinoperable duetoheaters,restorethePRZR'tooperablestatuswithinsix(6)hours.PRZRwaterlevelwasrestoredabovethesetpointforletdownisolation withintwo(2)minutes,restoring thePRZRheaterstooperablestatus,wellbeforethesix'(6)houractionstatement.
NRCFORM366A(5-92)
NRCFORH366A(5.92)U.S.NUCLEARREGULATORY COMHISSION LICENSEEEVENTREPORT(LER)TEXTCONTINUATION APPROVEDBYQGINO.3150-0104 EXPIRES5/31/95ESTIHATED BURDENPERRESPONSETOCOMPLYWITHTHISINFORMATION COLLECTION REOUEST:50.0HRS.FORWARDCOMMENTSREGARDING BURDENESTIMATETOTHEINFORMATION ANDRECORDSMANAGEHENT BRANCH(MNBB7714),U.STNUCLEARREGULATORY COMMISSION, WASHINGTON, DC20555-0001 ANDTOTHEPAPERWORK REDUCTION PROJECT(31400104),OFFICEOFHANAGEMENT ANDBUDGETWASHINGTON DC20503.FACILITYNAHE1R.E.GinnaNuclearPowerPlantDOCKETNINBER205000244LERNUMBER6YEARSEOUENTIAL 94--007--REVISION00PAGE37OF9TEXT(Ifmorespaceisrequired, useadditional copiesofNRCForm366A)(17)*BothS/Glevelsdecreased following thereactortrip."A"S/Gleveldecreased to<04,and"B"S/Gleveldecreased to<14'.Thisisanexpectedtransient.
TS4.3.5.5statesthatinordertodemonstrate thatareactorcoolantloopisoperable, theS/Gwaterlevelshallbe>/=169.Thus,bothcoolantloopswere.inoperable, eventhoughbothloopswerestillinoperation andperforming theirintendedfunctionofdecayheatremoval.BothS/Gswereavailable asaheatsink,andsufficient AFWflowwasmaintained foradequatesteamreleasefrombothS/Gs.TS3.1.1.1(c) states,inpart,thatexceptforspecialtests,whentheRCStemperature isatorabove350degreesFwiththereactorpowerlessthanorequalto130MWT(8.5%),atleastonereactorcoolantloopanditsassociated S/Gandreactorcoolantpumpshallbeinoperation.
Bothreactorcoolantloopswereinoperation, buttheS/Gswereinoperable duetolevelindication.
BothloopswererestoredtooperablestatuswhenS/Glevelswererestoredto>/=164("B"S/Glevelinlessthanfour(4)minutes,and"A"S/Glevelinapproximately ten(10)minutes).
Basedontheaboveandareviewofposttripdataandpastplanttransients, itcanbeconcluded thattheplantoperatedasdesigned, thattherewerenounreviewed safetyquestions, andthatthepublic'shealthandsafetywasassuredatalltimes.NRCFORM366A(5-92)
NRCFORH366A(5-92)U.S.NUCLEARREGULATORY C(SOIISSIOH LICENSEEEVENTREPORT(LER)TEXTCONTINUATION APPROVEDBYMBNO.3150-0104 EXPIRES5/31/95ESTIMATED BURDENPERRESPONSETOCOMPLYWITHTHISINFORMATION COLLECTION REQUEST:50.0HRS.FORWARDCOMMENTSREGARDIHG BURDEN'STIMATE TOTHEINFORMATION ANDRECORDSMANAGEMENT BRANCH(MHBB7714),U.S.NUCLEARREGULATORY COMMISSION, WASHINGTON, DC20555-0001 ANDTOTHEPAPERWORK REDUCTION PROJECT(3140-0104),
OFFICEOFMANAGEMENT ANDBUDGET'WASHINGTON DC20503.FACILITYNAME1R.E.GinnaNuclearPowerPlantDOCKETNQIBER205000244YEAR94--007--00LERHINBER6SEQUENTIAL REVISIONMPAGE38OF9TEXT(Ifmorespaceisrequired, useadditional copiesofNRCForm366A)(17)V.CORRECTIVE ACTIONA.ACTIONTAKENTORETURNAFFECTEDSYSTEMSTOPRE-EVENT NORMALSTATUS:oThevalvepositioner forthe"A"MFRV(BaileyModelAV112100I or"TypeAV1")hadbeenreplacedonApril26,1994,withanotherTypeAV1positioner.
Thisspecificpositioner failedinlessthantwelvehoursofuseandwasreplacedafterthisevent(onApril28,1994)withaBaileyModel5321030A10 (or"5321030")
valvepositioner.
TheBaileyModel5321030istheoriginalmodelofvalvepositioner fortheMFRVapplication andhadoperatedsuccessfully sinceplantstartupin1969.Thispositioner modelwaschangedoutin1991aspartofEWR4773,whichinstalled theAdvancedDigitalFeedwater ControlSystem(ADFCS).TheTypeAV1positioners havehadahistoryofreliability andstability concernsinthisMFRVapplication.
oThevalvepositioner forthe"B"MFRVwasalsoreplacedonApril28,1994,forthereasonsdiscussed above.oValve.rampandstepchangediagnostic testingwasperformed forbothMFRVstoverifypropervalvepositioning andresponse.
B.ACTIONTAKENORPLANNEDTOPREVENTRECURRENCE:
oThepositioners forbothMFRVswerereplacedwithModel5321030positioners asdiscussed above.HRCFORM366A(5-92)
NRCFORM366A(5-92)I.S.NUCLEARREGULATORY CQOIISSIOH LICENSEEEVENTREPORT(LER)TEXTCONTINUATION PROVEDBYOMBNO.3150-0104 EXPIRES5/31/95ESTIMATED BURDENPERRESPONSETOCOMPLYWITHTHISINFORMATION COLLECTIOH REDUEST:50.0HRS.FORWARDCOMMENTSREGARDIHG BURDEHESTIMATETOTHEINFORMATION ANDRECORDSMANAGEMENT BRANCH(MHBB7714),U.S.NUCLEARREGULATORY COMMISSION, WASHINGTON, DC20555-0001 AHDTOTHEPAPERWORK REDUCTION PROJECT(3140.0104),
OFFICEOFMANAGEMENT ANDBUDGETWASHINGTON DC20503.FACILITYNAME1R.E.GinnaNuclearPowerPlantDOCKETNUMBER205000244YEAR94LERNUMBER6SEOUENTIAL M--007--REVISION00PAGE39OF9TEXT(Ifmorespaceisrequired, useadditional copiesofHRCForm366A)(17)VI.ADDITIONAL INFORMATION A.FAILEDCOMPONENTS:
Thefailedcomponent wasthestrokeadjustallenheadsetscrewforthevalvepositioner signaldiaphragm assemblyforthe"A"MFRV.Thepositioner isaModelAV112100positioner, manufactured byBaileyControlsInc.B.PREVIOUSLERsONSIMILAREVENTS:AsimilarLEReventhistorical searchwasconducted withthefollowing results:nodocumentation ofsimilarLEReventswiththesamerootcauseatGinnaNuclearPowerPlantcouldbeiden-tified;however,LER93-006wasasimilarevent,inthattherewaslossofabilitytocontrolthe"A"MFRV;andLERs88-005,90007Iand90-010weresimilareventswithdifferentrootcauses.C.SPECIALCOMMENTS:
NoneHRCFORM366A(5-92)}}

Revision as of 12:57, 29 June 2018

LER 94-007-00:on 940427,feedwater Transient Occurred Due to Loss of Ability to Control Feedwater Regulating Valve, Causing Lo Lo SG Level Reactor Trip.Caused by Improperly Secured Stroke Adjust Set screw.W/940527 Ltr
ML17263A667
Person / Time
Site: Ginna Constellation icon.png
Issue date: 05/27/1994
From: MECREDY R C, ST MARTIN J T
ROCHESTER GAS & ELECTRIC CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-94-007, LER-94-7, NUDOCS 9406030044
Download: ML17263A667 (11)
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ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEMREGULATORY INFORMATION DISTRIBUTION-SYSTEM(RIDS)ACCESSION NBR:9406030044 DOC.DATE:

94/05/27NOTARIZED:

NOFACIL:50-244 RobertEmmetGinnaNuclearPlant,Unit1,Rochester GAUTH.NAMEAUTHORAFFILIATION ST.MARTIN,J.T.

Rochester Gas&ElectricCorp.MECREDY,R.C.

Rochester Gas&ElectricCorp.RECIP.NAME RECIPIENT AFFILIATION I

SUBJECT:

LER94-007-00:on 940427,feedwater transient occurredduetolossofabilitytocontrolfeedwater regulatinq valve,causingloloSGlevelreactortrip.Causedbyimproperly securedstrokeadjustsetscrew.W/940527 ltr.DISTRIBUTION CODE:IE22TCOPIESRECEIVED:LTR jENCL/SIZE:TITLE:50.73/50.9 LicenseeEventReport(LER),IncidentRpt,etc.DOCKETg05000244.RD8NOTES:License Expdateinaccordance with10CFR2,2.109(9/19/72).

05000244ARECIPIENT IDCODE/NAME PD1-3PDINTERNAL:

AEOD/DOAAEOD/ROAB/DSP NRR/DE/EMEB NRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DRSS/PRPB NRR/DSSA/SRXB RES/DSIR/EIB IEXTERNAL:

EG&GBRYCE,J.H NRCPDRNSICPOOREiW~COPIESLTTRENCL111122111111221111221111RECIPIENT IDCODE/NAME JOHNSON,A AEOD/DSP/TPAB NRR/DE/EELB NRR/DORS/OEAB NRR/DRCH/HICB NRR/DRIL/RPEB NRR/~SSA/S PLBREGFFL~02G1FILE01LSTLOBBYWARDNSICMURPHY,G.A NUDOCSFULLTXTCOPIESLTTRENCL11111111111111111.11,11'11DDDNOTETOALL"RIDS"RECIPIENTS:

ADDPLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMPl-37(EXT.20079)TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEED!FULLTEXTCONVERSION REQUIREDTOTALNUMBEROFCOPIESREQUIRED:

LTTR27ENCL27 AsrROCHESTER GASANDELECTRICCORPORATION ROBERTC.MECREOYVicePreridrnrCinnaCrurlesrProducuon rrC~~~~vr4'rroerrScare89EASTAVENUE,ROCHESTER N.Y.14649-0001 TELEPHONE AicEAcoDE716546'2700May27,1994U.S.NuclearRegulatory Commission Attn:AllenR.JohnsonPWRProjectDirectorate I-3DocumentControlDeskWashington, DC20555

Subject:

LER94-007,Feedwater Transient, DuetoLossofAbilitytoControlFeedwater Regulating Valve,CausesaLoLoSteamGenerator LevelReactorTllpR.E.GinnaNuclearPowerPlantDocketNo.50-244Inaccordance with10CFR50.73,LicenseeEventReportSystem,item(a)(2)(iv),whichrequiresareportof,"anyeventorcondition thatresultedinamanualorautomatic actuation ofanyengineered safetyfeature(ESF),including thereactorprotection system(RPS)",theattachedLicenseeEventReportLER94-007isherebysubmitted.

Thiseventhasinnowayaffectedthepublic'shealthandsafety.Verytrulyyours,g.P~g'~/r X.C~RobertC.Mecredyxc:U.S.NuclearRegulatory Commission RegionI475Allendale RoadKingofPrussia,PA19406GinnaUSNRCSeniorResidentInspector 9406030044

'ss40527PDRADOCK05000244C~PDR NRCFORH366(5-92)U.S.NUCLEARREGULATORY C(NHISSIOHPROVEDBYMSNO.3150-0104 EXPIRES5/31/95LICENSEEEVENTREPORT(LER)(Seereverseforrequirednunberofdigits/characters foreachblock)ESTIHATED BURDENPERRESPONSETOCOMPLYWITHTHISINFORMATION COLLECTION REQUEST:50.0HRS.FORWARDCOMMENTSREGARDING BURDENESTIMA'IE TOTHEINFORMATION ANDRECORDSMANAGEMENT BRANCH(HNBB7714),U.S.NUCLEARREGULATORY COMMISSION, WASHINGTON, DC20555-000'I ANDTOTHEPAPERWORK REDUCTION PROJECT(31400104),OFFICEOFMANAGEHENT ANDBUDGETWASHINGTON DC20503.FAGILITYNAME(1)R.E~GinnaNuclearPowerPlantDOCKETHNNIER(2)05000244PAGE(3)10F9TITLE(4)Feedwater Transient, DuetoLossofAbilitytoControlFeedwater Regulating Valve,CausesaLoLoSteamGenerator LevelReactorTripHONTHDAYYEAREVENTDATE5YEARLERNINBER6SEQUENTIAL NUMBERREVISIONNUMBERMONTHDAYYEARREPORTDATE7OTHERFACILITIES INVOLVED8DOCKETNUMBERFACILITYNAME04279494--007--000527FACILITYHAHEDOCKETNUMBEROPERATING MODE(9)POWERLEVEL(10)N045THISREPORTISSUBMITTED PURSUANT20.402(b) 20.405(a)(1)(i)20.405(a)(1)(ii) 20.405(a)(1)(iii) 20.405(a)(1)(iv) 20.405(a)(1)(v) 20.405(c) 50.36(c)(1) 50.36(c)(2) 50.73(a)(2)(i) 50.73(a)(2)(ii) 50.73(a)(2)(iii)

X50.73(a)(2)(iv) 50.73(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(b)73~71(c)OTHER(SpecifyinAbstractbelo~andinText,NRCForm366ATOTHEREQUIREMENTS OF10CFR:(Checkoneormore11LICENSEECONTACTFORTHISLER12NAMEJohnT.St.Martin-Director, Operating Experience TELEPHONE NUMBER(IncludeAreaCode)(315)524.4446C(NPLETEONELINEFOREACHCOHPOHENT FAILUREDESCRIBED INTHISREPORT13CAUSESYSTEHBJBLCVB042COMPONENT MANUFACTURER REPORTABLE TONPRDSPj's)kj~';.CAUSESYSTEMCOMPONENT MANUFACTURER REPORTABLE TONPRDSSUPPLEMENTAL REPORTEXPECTED14YES(Ifyes,coapleteEXPECTEDSUBMISSION DATE).XNOEXPECTEDSUBHISSIONDATE(15)MONTHDAYYEARABSTRACT(Limitto1400spaces,i.e.,approximately 15single-spaced typewritten lines)(16)OnApril27,1994,atapproximately 1407EDST,withthereactoratapproximately 454reactorpower,theabilitytocontrolthe"A"mainfeedwater regulating valvewaslost.At1410EDST,thereactortrippedonLoLolevel((/=17%)inthe"A"SteamGenerator.

TheControlRoomoperators performed theactionsofprocedures E-0andES-0.1.Theunderlying causewasdetermined tobeanimproperly securedstrokeadjustsetscrewforthevalvepositioner signaldiaphragm assemblyforthe"A"mainfeedwater regulating valve.ThiseventisNUREG-1022 CauseCode(B),"Design,Manufacturing, Construction/Installation."

Immediate corrective actionwastoinstallanewvalvepositioner ofapreviousdesign.Corrective actiontoprecluderepetition isoutlinedinSectionV(B).NRCFORM366(5-92)

NRCFORM366A(5.92)U.S.NUCLEARREGULATORY COMMISSIOH LICENSEEEVENTREPORT(LER)TEXTCONTINUATION PROVEDBYQHINO.3150-0104 EXPIRES5/31/95ESTIMATED BURDENPERRESPONSETOCOMPLYMITHTHISINFORMATION COLLECTION REQUEST:50.0HRS.FORNARDCOMMENTSREGARDIHG BURDENESTIMATETOTHEINFORMATION AHDRECORDSMANAGEHENT BRANCH(MHBB7714),U.S.NUCLEARREGULATORY COMMISSION, NASHINGTON, DC20555-0001 ANDTOTHEPAPERHORK REDUCTION PROJECT(3140.0104),

OFFICEOFMANAGEMENT AHDBUDGETllASHINGTON DC20503.FACILITYNAME1R.E.GinnaNuclearPowerPlantDOCKETNMBER205000244YEAR94LERNUMBER6SEQUENTIAL

--007--REVISION00PAGE32OF9TEXT(Ifmorespaceisrequired, useadditional copiesofHRCForm366A)(17)PRE-EVENT PLANTCONDITIONS Theplantachievedfullpoweroperation onApril23,1994,aftercompletion ofthe1994annualrefueling andmaintenance outage.OnApril26,1994,theplantwasmanuallyshutdowntorepairasmallsteamleakonaninstrument fittingonthehighpressure(HP)turbine.Duetostability problemswithcontrol,offeedwater flowtothe"A"SteamGenerator (S/G)atsteadystateconditions, thevalvepositioner forthe"A"mainfeedwater regulating valve(MFRV)wasreplacedduringthisbriefshutdown.

OnApril27,1994,aloadincreasewasinprogress, controlled byPlantOperating Procedure 0-1.2,"Plant-StartupfromHotShutdowntoFullLoad".Theplantwasatapproximately 45%reactorpower.Preparations werebeingmadetostartasecondmainfeedwater pump,perSystemOperating Procedure T-4.F,"Restoring 1BFeedwater PumptoServiceAfterMaintenance orPowerReduction".

II.DESCRIPTION OFEVENTA.DATESANDAPPROXIMATE TIMESOFMAJOROCCURRENCES:

oApril27,1994,1410EDST:Eventdateandtime.oApril27,1994,1410EDST:Discovery dateandtime.oApril27,1994,1410EDST:ControlRoomoperators verifybothreactortripbreakersopen,andallcontrolandshutdownrodsinserted.

oApril27,1994,1412EDST:ControlRoomoperators manuallystoptheoperating mainfeedwater pumptolimitareactorcoolantsystemcooldown.

oApril27,1994,1416EDST:ControlRoomoperators manuallyclosebothmainsteamisolation valvestolimitareactorcoolantsystemcooldown.

oApril27,1994,1440EDST:Plantstabilized athotshutdowncondition.

NRCFORM366A(5-92)

NRCFORM366A(5-92)U.S.NUCLEARREGULATORY CQOIISSION LICENSEEEVENTREPORT(LER)TEXTCONTINUATION APPROVEDBYQ(BHO.3150-0104 EXPIRES5/31/95ESTIMATED BURDENPERRESPONSETOCOMPLYWITHTHISIHFORMATION COLLECTIOH REQUEST:50.0HRS.FORWARDCOMMENTSREGARDING BURDENESTIMATETOTHEINFORMATION ANDRECORDSMANAGEMENT BRANCH(MNBB7714),U.S.NUCLEARREGULATORY COMMISSION, WASHINGTON, DC20555-0001 ANDTOTHEPAPERWORK REDUCTION PROJECT(31/0-0104),

OFFICEOFMANAGEMENT ANDBUDGETWASHINGTON DC20503.FACILITYNAME1R.E.GinnaNuclearPowerPlantDOCKETHQIBER2YEAR0500024494LERNUMBER6SEOUENTIAL M--007--REVISION00PAGE33OF9TEXT(Ifmorespaceisrequired, useadditional copiesofHRCForm366A)(17)B.EVENT:OnApril27,1994,aloadincreasewasinprogress, following thebriefplantshutdownonApril26,1994.PlantOperating Procedure 0-1.2wasbeingfollowedtocontroltheloadincrease.

Onlyonemainfeedwater pumpwasinoperation, andpreparations werebeingmadetostartthesecondmainfeedwater pumpandtocontinuewiththeloadincrease.

OnApril27,1994,atapproximately 1407EDST,theControlRoomoperators noticedaslightdecreaseinfeedwater flowtothe"A"S/G.Theyattempted tomanuallyincreasefeedwater flow,butthe"A"MFRVdidnotrespondtothedemandsignaltoopenthevalvefromtheMainControlBoard.Atapproximately 1408EDST,MainControlBoardannunciator G-22,"ADFCSSystemTrouble"alarmed,duetoadeviation betweenthedemandsignalandactualpositionofthe"A"MFRV.Levelcontinued todecreaseinthe"A"S/G.TheShiftSupervisor orderedarapidloadreduction, inanattempttodecreasetheneedforfeedwater flow.Withintwominutes,powerhadbeendecreased byapproximately 15%,andactualfeedwater flowbeingdelivered tothe"A"S/Gexceededsteamflow.However,levelinthe"A"S/Gdecrea'sed to(17oIresulting inareactortriponS/GLoLolevel,at1410EDST.TheControlRoomoperators performed theimmediate actionsofEmergency Operating Procedure E-O,"ReactorTriporSafetyInjection",

andtransitioned toEmergency Operating Procedure ES-0.1',"ReactorTripResponse",

whenitwasverifiedthatbothreactortripbreakerswereopen,allcontrolandshutdownrodswereinserted, andsafetyinjection wasnotactuatedorrequired.

Duringperformance ofES-0.1,theControlRoomoperators notedthatananticipated reactorcoolantsystem(RCS)cooldownwasoccurring, andmanuallystoppedtheoperating mainfeedwater pump.Inaddition, bothmainsteamisolation valves(MSIVs)weremanuallyclosedbytheControlRoomoperators.

Theseactionsmitigated theRCScooldown.

Duringthisevent,pressurizer (PRZR)leveldecreased belowthesetpointforletdownisolation, closingtheletdownisolation valvesanddeenergizing thePRZRheaters.AfterPRZRlevelwasrestoredabovethesetpoint, theControlRoomForemandirectedthatletdownandPRZRheatersberestoredtoservice.Theplantwassubsequently stabilized inhotshutdown(atapproximately 1440EDST)usingPlantOperating Procedures 0-3,"HotShutdownwithXenonPresent",

and0-2,"PlantShutdown".

HRCFORM366A(5-92)

HRCFORM366A(5-92).S.NUCLEARREGUULTORY COMMISSION LICENSEEEVENTREPORT(LER)TEXTCONTINUATION PROVEDBYOIBNO.3150-0104 EXPIRES5/31/95ESTIMATED BURDENPERRESPONSETOCOMPLYWITHTHISINFORMATION COLLECTIOH REQUEST:50.0HRS.FORWARDCOMMENTSREGARDING BURDENESTIMATETOTHEINFORMATIOH AHDRECORDSMANAGEMENT BRANCH(MNBB7714),U.S.NUCLEARREGULATORY COMMISSION, WASHINGTON, DC20555-0001 ANDTOTHEPAPERWORK REDUCTION PROJECT(3140-0104),

OFFICEOFMANAGEMENT ANDBUDGETWASHINGTON DC20503.FACILITYNAME1R.E.GinnaNuclearPowerPlantDOCKETNMBER205000244iLERNMBER6YEARSEQUEH'TIAL 94--007REVISION00PAGE34OF9TEXT(Ifmorespaceisrequired, useadditional copiesofNRCForm366A)(17)C~INOPERABLE STRUCTURES ICOMPONENTS IORSYSTEMSTHATCONTRIBUTED TOTHEEVENT:NoneD.OTHER'YSTEMS ORSECONDARY FUNCTIONS AFFECTED:

NoneE.METHODOFDISCOVERY:

ThiseventwasapparentduetoMainControlBoardindications ofthelossofabilitytocontrolfeedwater flowtothe"A"S/G.Thereactortripwasimmediately apparentduetoalarmsandindications intheControlRoom.F.OPERATORACTION:Afterthereactortrip,theControlRoomoperators performed theactionsofEmergency Operating Procedures E-O,"ReactorTriporSafetyInjection" andES-0.1,"ReactorTripResponse".

Theoperating mainfeedwater pumpwasmanuallystopped,andtheMSIVsweremanuallyclosedtolimitfurtherRCScooldown.

Theplantwasstabilized athotshutdown.

Subsequently, theControlRoomoperators notifiedhighersupervision andtheNuclearRegulatory Commission per10CFR50.72, Non-Emergency, 4HourNotification.

G.SAFETYSYSTEMRESPONSES:

NoneIII.CAUSEOFEVENTA.IMMEDIATE CAUSE:Thereactortripwasdueto"A"S/GLoLolevel((/=17%),causedbydecreased feedwater flowtothe"A"S/G.B.INTERMEDIATE CAUSE:Thedecreased feedwater flowtothe"A"S/Gwasduetolossofabilitytocontrolthe"A"MFRV,causedbythevalvepositioner forthe"A"MFRVnotresponding tothedemandopensignal.HRCFORM366A(5-92)

HRCFORM366A(5-92)U.S.NUCLEARREGULATORY COMMISSION LICENSEE.

EVENTREPORT(LER)TEXTCONTINUATION PROVEDBYOMBNO.3150-0104 EXPIRES5/31/95ESTIMATED BURDENPERRESPONSETOCOMPLYWITHTHISINFORMATION COLLECTION REQUEST:50.0HRS.'ORWARD COMMENTSREGARDING BURDENESTIMATETOTHEINFORMATION ANDRECORDSMANAGEMENT BRANCH(MNBB7714),U.S.NUCLEARREGULATORY COMMISSIOH, WASHINGTON, DC20555-0001, ANDTOTHEPAPERWORK REDUCTION PROJECT(31500104),OFFICEOFMANAGEMENT ANDBUDGETWASHINGTON DC20503.FACILITYNAME1'R.E.GinnaNuclearPowerPlantDOCKETNWBER205000244LERNIÃBER6)YEARSEQUENTIAL 94--007--REVISION,00PACE35OF9TEXT(lfmorespaceisrequired, useadditional copiesofHRCForm366A)(17)C.ROOTCAUSE:Theunderlying causeofthevalvepositioner forthe"A"MFRVnotproperlyresponding toachangeininput,demandsignalfromthecontroller ontheMainControlBoardwasanimproperly securedstrokeadjustsetscrew.Thesetscrewwasfoundinabackedoutcondition inthevalvepositionsignaldiaphragm assemblyforthe"A"MFRV.Itispostulated thatthisstrokeadjustallenheadsetscrewdidnothaveadequatethreadsealanttopreventitfrombackingoutofthesignaldiaphragm assemblycoverwhensubjected-tovibration.

Withthesetscrewbackedout,thesignaldiaphragm wasrestricted fromresponding toaninputdemandsignaltoopentheMFRV.Notethatthesetscrewisafactory-set adjustment.

Thisparticular setscrewbackedoutwhensubjected tolessthantwelvehoursofoperation, andthisfailuremodehasnotoccurredinothervalvepositioners thathave'accumulated thousands ofhoursofoperation.

ThiseventisNUREG-1022 CauseCode(B),"Design,Manufacturing, Construction/Installation."

IV.ANALYSISOFEVENTThiseventisreportable inaccordance with10CFR50.73,LicenseeEventReportSystem,item(a)(2)(iv),whichrequiresareportof,"anyeventorcondition thatresultedinmanualorautomatic actuation ofanyengineered safetyfeature(ESF)including thereactorprotection system(RPS)".The"A"S/GLoLolevelreactortripwasanautomatic actuation oftheRPS.Anassessment wasperformed considering boththesafetyconsequen-cesandimplications ofthiseventwiththefollowing resultsandconclusions:

oTherewerenosafetyconsequences orimplications attributed tothereactortripbecause:*Thetworeactortripbreakersopenedasrequired.

  • Allcontrolandshutdownrodsinsertedasdesigned.
  • Theplantwasstabilized athotshutdown.

HRCFORM366A(5-92)

NRCFORH366A(5-92)U.SNUCLEARREGULATORY COMMISSION LICENSEEEVENTREPORT(LER)TEXTCONTINUATION APPROVEDBY(HGINO.3150-0104 EXPIRES5/31/95ESTIMATED BURDENPERRESPONSETOCOMPLYWITHTHISINFORMATION COLLEC'IIOH REQUEST:50.0HRS~FORNARDCOMMENTSREGARDING BURDENESTIMATETOtHEINFORMATION ANDRECORDSMANAGEMENT BRANCH(MNBB7714),U.S.NUCLEARREGULATORY COMMISSION, MASHIHGTON, DC20555-0001, ANDTOTHEPAPERNORK REDUCTION PROJECT(3150-0104),

OFFICEOFMANAGEMENT ANDBUDGETMASHINGTON DC20503.FACILITYNAME1R.E.GinnaNuclearPowerPlantDOCKETHINSER2I05000244YEAR94--00700LERNIMBER6SEQUENTIAL REVISIONPAGE36OF9TEXT(Ifmorespaceisrequired, useadditional copiesofNRCForm366A)(17)oTheGinnaUpdatedFinalSafetyAnalysisReport(UFSAR)transient, asdescribed inChapter15.2.6,"LossofNormalFeedwater",

describes acondition wherethereactortripsonLoLoS/Glevel.ThisUFSARtransient wasreviewedandcomparedtotheplantresponseforthisevent.TheUFSARtransient isacompletelossofMainFeedwater (MFW)atfullpower,withonlyoneauxiliary feedwater (AFW)pumpavailable one(1)minuteafterthelossofMFW,andsecondary steamrelief(i.e.,decayheatremoval)throughthesafetyvalvesonly.Theprotection againstalossofMFWincludesthereactortriponLoLoS/GlevelandthestartoftheAFWpumps.Theseprotection featuresoperatedasdesigned.

Basedontheaboveevaluation, theplanttransient ofApril27,1994,isboundedbytheUFSARSafetyAnalysisassumptions.

oTechnical Specifications (TS)werereviewedwithrespecttotheposttripreviewdata.'hefollowing aretheresultsofthatreview:*Following thereactortrip,PRZRwaterleveldecreased

'oapproximately 12.5%duetoamoderateRCScooldown.

Thiscooldownoccurredduringtheposttriprecoveryperiod.Thiscooldownwasboundedbytheplantaccidentanalysis, anddidnotexceedtheTSlimitof100degreesFperhour.Additional mitigation wasprovidedbyclosingtheMSIVsandstopping-themainfeedwater pump.TS3.1.1.5states,inpart,thatwhentheRCStemperature isatorabove350degreesF,atleast100KWofPRZRheaterswillbeoperable.

TS3.1.1.5alsostates,inpart,thatifthePRZR,isinoperable duetoheaters,restorethePRZR'tooperablestatuswithinsix(6)hours.PRZRwaterlevelwasrestoredabovethesetpointforletdownisolation withintwo(2)minutes,restoring thePRZRheaterstooperablestatus,wellbeforethesix'(6)houractionstatement.

NRCFORM366A(5-92)

NRCFORH366A(5.92)U.S.NUCLEARREGULATORY COMHISSION LICENSEEEVENTREPORT(LER)TEXTCONTINUATION APPROVEDBYQGINO.3150-0104 EXPIRES5/31/95ESTIHATED BURDENPERRESPONSETOCOMPLYWITHTHISINFORMATION COLLECTION REOUEST:50.0HRS.FORWARDCOMMENTSREGARDING BURDENESTIMATETOTHEINFORMATION ANDRECORDSMANAGEHENT BRANCH(MNBB7714),U.STNUCLEARREGULATORY COMMISSION, WASHINGTON, DC20555-0001 ANDTOTHEPAPERWORK REDUCTION PROJECT(31400104),OFFICEOFHANAGEMENT ANDBUDGETWASHINGTON DC20503.FACILITYNAHE1R.E.GinnaNuclearPowerPlantDOCKETNINBER205000244LERNUMBER6YEARSEOUENTIAL 94--007--REVISION00PAGE37OF9TEXT(Ifmorespaceisrequired, useadditional copiesofNRCForm366A)(17)*BothS/Glevelsdecreased following thereactortrip."A"S/Gleveldecreased to<04,and"B"S/Gleveldecreased to<14'.Thisisanexpectedtransient.

TS4.3.5.5statesthatinordertodemonstrate thatareactorcoolantloopisoperable, theS/Gwaterlevelshallbe>/=169.Thus,bothcoolantloopswere.inoperable, eventhoughbothloopswerestillinoperation andperforming theirintendedfunctionofdecayheatremoval.BothS/Gswereavailable asaheatsink,andsufficient AFWflowwasmaintained foradequatesteamreleasefrombothS/Gs.TS3.1.1.1(c) states,inpart,thatexceptforspecialtests,whentheRCStemperature isatorabove350degreesFwiththereactorpowerlessthanorequalto130MWT(8.5%),atleastonereactorcoolantloopanditsassociated S/Gandreactorcoolantpumpshallbeinoperation.

Bothreactorcoolantloopswereinoperation, buttheS/Gswereinoperable duetolevelindication.

BothloopswererestoredtooperablestatuswhenS/Glevelswererestoredto>/=164("B"S/Glevelinlessthanfour(4)minutes,and"A"S/Glevelinapproximately ten(10)minutes).

Basedontheaboveandareviewofposttripdataandpastplanttransients, itcanbeconcluded thattheplantoperatedasdesigned, thattherewerenounreviewed safetyquestions, andthatthepublic'shealthandsafetywasassuredatalltimes.NRCFORM366A(5-92)

NRCFORH366A(5-92)U.S.NUCLEARREGULATORY C(SOIISSIOH LICENSEEEVENTREPORT(LER)TEXTCONTINUATION APPROVEDBYMBNO.3150-0104 EXPIRES5/31/95ESTIMATED BURDENPERRESPONSETOCOMPLYWITHTHISINFORMATION COLLECTION REQUEST:50.0HRS.FORWARDCOMMENTSREGARDIHG BURDEN'STIMATE TOTHEINFORMATION ANDRECORDSMANAGEMENT BRANCH(MHBB7714),U.S.NUCLEARREGULATORY COMMISSION, WASHINGTON, DC20555-0001 ANDTOTHEPAPERWORK REDUCTION PROJECT(3140-0104),

OFFICEOFMANAGEMENT ANDBUDGET'WASHINGTON DC20503.FACILITYNAME1R.E.GinnaNuclearPowerPlantDOCKETNQIBER205000244YEAR94--007--00LERHINBER6SEQUENTIAL REVISIONMPAGE38OF9TEXT(Ifmorespaceisrequired, useadditional copiesofNRCForm366A)(17)V.CORRECTIVE ACTIONA.ACTIONTAKENTORETURNAFFECTEDSYSTEMSTOPRE-EVENT NORMALSTATUS:oThevalvepositioner forthe"A"MFRV(BaileyModelAV112100I or"TypeAV1")hadbeenreplacedonApril26,1994,withanotherTypeAV1positioner.

Thisspecificpositioner failedinlessthantwelvehoursofuseandwasreplacedafterthisevent(onApril28,1994)withaBaileyModel5321030A10 (or"5321030")

valvepositioner.

TheBaileyModel5321030istheoriginalmodelofvalvepositioner fortheMFRVapplication andhadoperatedsuccessfully sinceplantstartupin1969.Thispositioner modelwaschangedoutin1991aspartofEWR4773,whichinstalled theAdvancedDigitalFeedwater ControlSystem(ADFCS).TheTypeAV1positioners havehadahistoryofreliability andstability concernsinthisMFRVapplication.

oThevalvepositioner forthe"B"MFRVwasalsoreplacedonApril28,1994,forthereasonsdiscussed above.oValve.rampandstepchangediagnostic testingwasperformed forbothMFRVstoverifypropervalvepositioning andresponse.

B.ACTIONTAKENORPLANNEDTOPREVENTRECURRENCE:

oThepositioners forbothMFRVswerereplacedwithModel5321030positioners asdiscussed above.HRCFORM366A(5-92)

NRCFORM366A(5-92)I.S.NUCLEARREGULATORY CQOIISSIOH LICENSEEEVENTREPORT(LER)TEXTCONTINUATION PROVEDBYOMBNO.3150-0104 EXPIRES5/31/95ESTIMATED BURDENPERRESPONSETOCOMPLYWITHTHISINFORMATION COLLECTIOH REDUEST:50.0HRS.FORWARDCOMMENTSREGARDIHG BURDEHESTIMATETOTHEINFORMATION ANDRECORDSMANAGEMENT BRANCH(MHBB7714),U.S.NUCLEARREGULATORY COMMISSION, WASHINGTON, DC20555-0001 AHDTOTHEPAPERWORK REDUCTION PROJECT(3140.0104),

OFFICEOFMANAGEMENT ANDBUDGETWASHINGTON DC20503.FACILITYNAME1R.E.GinnaNuclearPowerPlantDOCKETNUMBER205000244YEAR94LERNUMBER6SEOUENTIAL M--007--REVISION00PAGE39OF9TEXT(Ifmorespaceisrequired, useadditional copiesofHRCForm366A)(17)VI.ADDITIONAL INFORMATION A.FAILEDCOMPONENTS:

Thefailedcomponent wasthestrokeadjustallenheadsetscrewforthevalvepositioner signaldiaphragm assemblyforthe"A"MFRV.Thepositioner isaModelAV112100positioner, manufactured byBaileyControlsInc.B.PREVIOUSLERsONSIMILAREVENTS:AsimilarLEReventhistorical searchwasconducted withthefollowing results:nodocumentation ofsimilarLEReventswiththesamerootcauseatGinnaNuclearPowerPlantcouldbeiden-tified;however,LER93-006wasasimilarevent,inthattherewaslossofabilitytocontrolthe"A"MFRV;andLERs88-005,90007Iand90-010weresimilareventswithdifferentrootcauses.C.SPECIALCOMMENTS:

NoneHRCFORM366A(5-92)

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