ML17256A831

Submits Preliminary Evaluation of Capability of Safety & Relief Valves to Operate Under Expected Operating & Accident Conditions,Per NUREG-0578 & NUREG-0737,Item II.D.1. Evaluation Based on EPRI Valve Test Program Results

ML17256A831
Person / Time
Site:	Ginna
Issue date:	04/15/1982
From:	MAIER J E ROCHESTER GAS & ELECTRIC CORP.
To:	CRUTCHFIELD D Office of Nuclear Reactor Regulation
References
RTR-NUREG-0578, RTR-NUREG-0737, RTR-NUREG-578, RTR-NUREG-737, TASK-2.D.1, TASK-TM NUDOCS 8204230351
Download: ML17256A831 (8)

Text

REGULATORYORNATIONDISVRISUTIONSYl(RIDE)'AOCESSIONNBR:8204230351,DOC.DATE:92/00/t5NOTARZZEDp,.NODOCKET0FACILp50"244"'RobertEmmetGfnnaNuclear'..Plantg'Un<<f<<tii"Rochester"-G05000244AUTH,N)HgAUTHORAFFILIATIONHAIERrJ~E~~RochesterGas,5"ElectricCorTpsRECIP~NAME,RECIPIENTAFFIlIA'TION'ORUTCHFIELDg0sOperatinaReactorsBranch"5

SUBJECT:

'SubpftsIPnel;imfnery,evaluationofqawabfli<<ty.Of<<Safety8relief.-valvestooperate"underegpeotedaperatfng'faccident"conditfopsipyr,NURE0~0578'$NUREG(737pI<<tern'$I~D~1'Evaluation-basedon'.EPRIvalve"testprogramresult<<s.DISTRIBUTIONiCODE:'AOASS.<COPIESiRBDBIVED:LTRjiENCLQSXZE:,TITLE:ResponsetoNUREG.'737/NUREG0660YTHIActionPlanRrrmts(OL's)NOTES;NRR/RL/SEPicy,05000204,'RECXPIENT-IOCODE/NA'HE,ORB05ABC'01INTERNAl!<<ELDIE/DEP.DIRI33,IE/DEP/EPLBNRR/DE/ADCSE"22NRR/OE/ADSA17NRR/DHFS/DEPY?9NRR/DL/ADL16NRR/DL/ORAB18NRR/DSIDIR24NRR/DSI/ADPS?5NRR/DSI/AEBNRR/DSI/RABNRR/OST/ADT32'GN1FXTERNAL':ACRST34'INPOUR'J,'STARNBSNRCPDR'02"NTI'SrCOPIES.LTTRENC711111111111101111IREOIPIENT-ID~CODE/NAMEIE.1'2XE/DEP/EPOSNRR/DEDER'21NRR/DE/ADHQE"23NRR/DHFSDIR28NRR/DLDIR14NRR/DL'/AOOR.1'5NRR/OSIAORS2L7NRR/DSI/ADGPI31NRR/OSI'/ADRP'26NRR/D8I/678B~NIR30EG"FILE'04F<<EHA~REP,DIVLPDR03NSIC05tCOPIES'L"7T'RENCL1;1111aTOTALNUMBER,OFCOPIESREQUIRED'TTR~'ENCl 4>>Htl,II~~C)4>>gr>l)nl>>3a0(3$>>>>fIPiff>If(,$">>('>>ktp'>>t(~'!p9f>>tftttQCQ~mrna~~'I>><Ifllfi~lt>>(Hnt'iti.$>>H'0LP(,it,lCTiiII>>t'If4f(Vg"-3fifPIIIy)J$~lln tiiiiiiriiiiiiiiiiiiiiiiiiiIiiiiiIiiiiiiIiiiiit4t~Oettattts/tYORKROCHESTERGASANDELECTRICCORPORATION~89EASTAVENUE,ROCHESTER,N.Y.I4649JOHNEMAILERvitePresidentTCI.CttHONC*tie*cooc7io546-2700April15,1982DirectorofNuclearReactorRegulationAttention:MrsDennisM.Crutchfield,ChiefOperatingReactorsBranchNo.5U.S.NuclearRegulatoryCommissionWashington,D.C.20555RIRCBVga~pa22)98<~t0OlrIKLIKKlstttStttttsMlN49ggg

Subject:

PWRSafetyandReliefValveTestProgramR.E.GinnaNuclearPowerPlantDocketNo.50-244

DearMr.Crutchfield:

InaccordancewiththeinitialrecommendationofNUREG0578,Section2.1.2aslaterclarifiedbyNUREG0737,ItemII.D.landrevisedSeptember29,1981,eachPressurizedWaterReactor(PWR)UtilityonorbeforeApril1,1982wastosubmitinformationrelativetothepressurizersafetyandreliefvalvesinuseattheirplant.Specificallythissubmittalshouldincludeapreliminaryevaluationsupportedbytestresultswhichdemonstratesthecapabilityofthereliefandsafetyvalvestooperateunderexpectedoperatingandaccidentconditions.ThisletterreferencesreportsprovidedtoyoubythePWRSafetyandReliefValveTestProgramSubcommitteeandprovidesadditionalinformationapplicabletotheGinnaPlant.RochesterGasandElectricCorporationhasactivelypursuedresolutionofthisissuethroughdirect.participationintheElectricPowerResearchInstitute(EPRI)valvetestprogram.TheprimaryobjectiveoftheTestProgramwastoprovidefullscaletestdataconfirmingthefunctionabilityoftheprimarysystempoweroperatedreliefvalvesandsafetyvalvesforexpectedoperatingandaccidentconditions.Thesecondobjectiveoftheprogramwastoobtainsufficientpipingthermalhydraulicloaddatatopermitconfirmationofmodelswhichmaybeutilizedforplantuniqueanalysisofsafetyandreliefvalvedischargepipingsystems.ReliefvalvetestswerecompletedinAugust1981,.andsafetyvalvetestswerecompletedinDecember1981.ThereportspreparedfortheEPRITestProgramandreferencedinthissubmittalincluded:

'hh<q~]PQIJ<</p<<"/lyhfIfrrIfhf,4 ROCHESTERGASANDELRICCORP-DATEApril15,1982TOMr.DennisM.CrutchfieldHEETNO.2(1)"ValveSelection/JustificationReort",December1981ThisreportdocumentsthattheselectedtestvalvesrepresentallparticipatingPWRsafetyandreliefvalves.(2)"TestConditionJustificationReort",Aril1982andthe(3)"ValveInletFluidConditions'or'ressurizerSafetandRelief'ValvesxnWestinhouseDesinedPlants",Februar1982ThesereportsdocumentthebasisandjustificationofthevalvetestconditionsforallparticipatingPWRplants.(4)"SafetandReliefValveTestReort",Aril1982ThisreportprovidesevidencedemonstratingthefunctionabilityoftheselectedtestvalvesundertheselectedtestconditionsforallparticipatingPWRplants.AllofthesedocumentshavebeenreceivedbyRochesterGasandElectricCorporation.Additionally,theyhavebeentrans-mittedtoyouonbehalfoftheparticipatingPWRUtilitiesfromDavidHoffmanofConsumersPowerCompany,ChairmanofthePWRSafetyandReliefValveTestProgramSubcommitteeinaletterdatedApril1,1982.RochesterGasandElectricCorporationhasundertakenreviewofthesedocumentsbutthereview,atpresent,ispreliminaryduetothepreliminarynatureofthetestdatareceivedtodate.PowerOperated-Relief'alve(PORV)ThePORVsatGinnaare:Manufacturer-CopesVulcanModelNo.-Globe,D-100-160SizeSDescription-3"NPS,316w/StellitePlugand17-4PHCageQuantity-,2tr,ThesevalveshavebeentestedbyEPRIinatestconfigurationsimilartothatoftheactualpressurizerconfigurationattheplant.ThefluidconditionsforthePORV's,whilenotspecificallyaddressedintheGinnaSafetyAnalysisReport,wereidentifiedbyWestinghouseandarediscussedintheFluidConditionsJustifica-tionReport,EPRIReport(3).Thefluidconditionsforthetestswereselectedonthebasisofenvelopingthosefluidconditionsforallplantsutilizingthesamevalvetype.TestswereperformedbothattheMarshallSteamStationandattheWyletestfacility(PhaseIII).Atotalof20testswereconductedutilizingsteam,water,andsteam-to-watertransitionfluidconditions.Thesetestsconfirmedthatthevalveopened 8',+~ll'"/)trtP 4ROCHESTERGASANDELRICCORP.DATEApril15,1982TOMr.DennisM.CrutchfieldHEETNO.3H.andclosedondemandandthatthevalvesufferednodamagethat,wouldprecludefutureoperationsSpecificinformationrelatedtothesetestsisgiveninSection4.6ofthe"SafetyandReliefValveTestReport",EPRIReport(4)~SafetValvesThesafetyvalvesatGinnaare-.Manufacturer-CrosbyValveandGageModelNo.-HB-BP-86Size-4K26AssemblyNo.-51249Quantity-2ThesevalveshavenotbeentestedbyEPRI.Howeversafetyvalvessimilarindesignandoperationhavebeentestedinatestconfigurationsimilartothatoftheactualpressurizerconfigurationattheplant.JustificationthatthevalvestestedenvelopethosevalvesatGinnaisgivenintheValveJustificationReport,EPRIReport(1).JustificationthatthefluidconditionsforthetestsenvelopetheactualplantconditionsispresentedinEPRIReport(3).Thesafetyvalveshavebeenshowntoopenandclose.Certainareasofsystemperformancearestillundergoingreview,specificallyaddressingtheinletpiping,outletpipingandthevalves.TheRochesterGasandElectricCorporationisactivelyinvolvedwiththeWestinghouseOwnersGroupprogramandhasadditionallycontractedWestinghousetoevaluatethespecificGinnasystem,includingdownstreampiping.AllrelevantEPRIresultswillbeemployedintheevaluation.ClarificationofconcernsandtheirimpactonplantperformanceisexpectedpriortotheJuly1,1982informationsubmittaldate.OurpreliminaryevaluationoftheEPRIworkisthatthevalvestestedrepresenttheGinnasafetyandreliefvalvedesignsandthattheconditionstestedenvelopetherangeofexpectedoperatingandaccidentconditionsfortheGinnaPlant-TheEPRIreportsprovidetheevidencerequiredbyNUREG0737,ItemII.D.l.Awhichwillbeusedtoperformthefinalplantspecificevaluations.TheSeptember29,1981USNRCletterrequestedthatplantspecificfinalevaluationsbesubmittedbyJuly1,1982'nordertomeetthatdate,evaluationshavebeeninitiated.DependingontheoutcomeoftheevaluationsitmaybenecessarytocontinuetheevaluationbeyondJuly1,1982-Ifalongerevaluationperiodisrequired,youwillbenotified.Verytrulyyours,~/u+.~~JohnE.Maier glI@IIr,~qr~rw,l'qgIII'I