ML17329A670

Application for Amends to Licenses DPR-58 & DPR-74, Requesting Tech Specs Tables 4.7-1 & 3.7-4 Associated W/Tech Specs 3.7.1.1 Re Main Steam Safety Valve Tolerance

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: ML17329A670 ML17329A672 ML17329A673
References
AEP:NRC:1169, NUDOCS 9211170207
Download: ML17329A670 (14)

Text

SUBJECT:

Application foramendstoLicensesDPR-58&DPR-74,requesting TechSpecsTables4.7-1S3.7-4associated w/TechSpecs3.7.1.1remainsteamsafetyvalvetolerance.

DISTRIBUTION CODE:AOOZDCOPIESRECEIVEDILTR gENCL/SIZE:Ã+ITITLE:ORSubmittal:

GeneralDistribution NOTES:-/J.RECIPIENT COPIESCOPIESIDCODE/NAME LTTRENCLLTTRENCLPD3-1LA1111STANGFJ22RECIPIENT IDCODE/NAME PD3-1PDACCELERATED DISFRIBUTION DEMONSTR<TION'YSTEMREGULATINFORMATION DZSTRIBUTIO STEM(RIDE)ACCESSION NBR:9211170207 DOC.DATE:

92/ll/llNOTARIZED:

YESiDOCKETFACIL:50-315 DonaldC.CookNuclearPowerPlant,Unit1,IndianaM0500031550-316DonaldC.CookNuclearPowerPlant,Unit2,IndianaM05000316AUTH.NAMEAUTHORAFFILIATION FITZPATRICK,E.E IndianaMichiganPowerCo.(formerly Indiana6MichiganEleRECIP.NAME RECIPIENT AFFILIATION MURLEY,T.E.

DocumentControlBranch(Document ControlDesk)DINTERNAL:

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NRCPDR11NSIC11DNOTETOALL"RIDS"RECIPIENTS:

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TOELIMINATE YOURNAMEFROMiDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEED!rDDTOTALNUMBEROFCOPIESREQUIRED:

LTTR16ENCL14 indianaMichiganPowerCompanyP.O.Box16631Coiumbus, OH43216AEP:NRC:1169.

DonaldC.CookNuclearPlantUnits1and2DocketNos.50-315and50-316LicenseNos.DPR-58andDPR-74TECHNICAL SPECIFICATIONS CHANGETOINCREASETHEALLOWABLE TOLERANCE FORMAINSTEAMSAFETYVALVESU.S.NuclearRegulatory Commission DocumentControlDeskWashington, D.C.20555Attn:T.E.MurleyNovemberll,1992

DearDr.Murley:

Thisletteranditsattachments constitute anapplication foramendment totheTechnical Specifications (T/Ss)forDonaldC.CookNuclearPlantUnits1and2.Specifically, werequestthatT/SsTables4.7-1(Unit1)and3.7-4(Unit2)associated withT/S3.7.1.1beamendedtoreflectanincreased mainsteamsafetyvalvetolerance of+3%.Inaddition, werequestthatUnit2T/S3.5.2beamendedtoreflectathermalpowerlimitation resulting fromthesmallbreakLOCAanalysiswhenasafetyinjection cross-tie valveisclosed.Theliftsetpoints ofthemainsteamsafetyvalvesfrequently driftoutsideoftheoriginally intended+1$allowance overafuelcycle.Inattempting tominimizethesetpointdriftproblemanddetermine therootcause,severalvalveshavebeeninspected andrefurbished.

Theseactionshavebeenunsuccessful inkeepingthesetpoints withinspecification overthefuelcycle.Themanufacturer ofthesevalveshasrecommended anincreaseintheallowable tolerance to+3S.Thistolerance isconsistent withrecentASMEcoderequirements.

Consequently, wearemakingthissubmittal toimplement thechangesintheT/Ssidentified above.In1986,aNoticeofViolation wasissuedduetoconcernsnotedinInspection ReportNumbers50-315/86030 and50-316/86030 (reference AEP:NRC:1013) regarding thedriftinthesetpointforthesubjectvalves.Althoughthiswasnotfoundtobeasignificant safetyconcern,wecommitted tosubmitalicenseeeventreport(LER)whenanyofthevalveswerefoundoutsideofthe+1%range.Inadditiontorequesting yourapprovalofthisproposedT/Sschange,itisalsorequested thatthiscommitment becancelled.

Thisrequestisbasedontheoperating characteristics ofthesevalves,thatthevalvesoperateasabank,notindividually, andareanalyzedassuch.Inthefuture,therefore, itisconsidered moreappropriate tosubmit92111-70207,921111PDR'ADGCK05000815PDR

~O Dr.T.E.Murley2AEP:NRC:1169 anLERonlyifthe"as-found" condition ofthisbankofvalvesdoesnotsupporttheChapter14safetyanalysisofrecord.Althoughitispossible, basedonhistorical trends,thatsomevalvesmayexceedthe3%driftlimit,sufficient capacityfromtheremaining valvesinthebankwouldtypically beavailable toensurethattheplantwouldhaveresponded withintheanalyzedlimits.ThisT/Schangeisbeingrequested forimplementation beforethenextregularly scheduled Unit2refueling outageandassociated valvetesting.Tosupporttheschedule, werequestthattheamendment beapprovedforbothunitsbytheendofthethirdquarterof1993.WewillkeepNRCprojectmanagement informedofanyschedulechangethroughroutineprojectreviewmeetings.

Adetaileddescription oftheproposedchangesandouranalysesconcerning significant hazardsconsiderations areincludedinAttachment 1tothisletter.Attachment 2containstheproposedrevisedT/Sspages.Attachment 3containsmarked-up copiesoftheexistingT/Ss.Westinghouse ReportSECL-91-429, "DonaldC.CookUnits1and2,MainSteamSafetyValveLiftSetpointTolerance Relaxation,"

isfoundinAttachment 4.Webelievethattheproposedchangeswillnotresultin(1)asignificant changeinthetypesofeffluents orasignificant increaseintheamountofanyeffluentthatmaybereleasedoffsite,or(2)asignificant increaseinindividual orcumulative occupational radiation exposure.

TheseproposedchangeshavebeenreviewedbythePlantNuclearSafetyReviewCommittee andbytheNuclearSafetyandDesignReviewCommittee.

Incompliance withtherequirements of10CFR50.91(b)(1),

copiesofthisletteranditsattachments havebeentransmitted totheMichiganPublicServiceCommission andtheNFEMSectionChief.Thisletterissubmitted pursuantto10CFR50.54(f)and,assuch,anoathstatement isenclosed.

Sincerely, VicePresident tjwAttachments Dr.T.E.Murley3AEP:NRC:1169 cc:D.H.Williams, Jr.A.A.Blind-BridgmanJ.R.PadgettG.CharnoffA.B.Davis-RegionIIINRCResidentInspector

-BridgmanNFEMSectionChief Dr.T.E.Murley4AEP'NRC:1169 bc: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:1169 DC-N-6015.1 COUNTYOFFRANKLINE.E.Fitzpatrick, beingdulysworn,deposesandsaysthatheistheVicePresident oflicenseeIndianaMichiganPowerCompany,thathehasreadtheforegoing Technical Specifications ChangetoIncreasetheAllowable Tolerance forMainSteamSafetyValves,andknowsthecontentsthereof;andthatsaidcontentsaretruetothebestofhisknowledge andbelief.Subscribed andsworntobeforemethisdayof19~mNOTARYPUBLICRITADHILLNOTAIIYPUBLIC.STAlEOFOHI)

ATTACHMENT 1toAEP:NRC:1169 NOSIGNIFICANT HAZARDSCONSIDERATION EVALUATION INSUPPORTOFTHEINCREASED ALLOWABLE TOLERANCE ONMAINSTEAMSAFETYVALVES Attachment 1toAEP:NRC:1169 Page1I.INTRODUCTION ThereareatotaloftwentyDressermainsteamsafetyvalves(MSSV)installed onfourmainsteamheaders(fivevalvesperheader)ineachunitatCookNuclearPlant.ThesevalvesarerequiredtobesetpointtestedperSectionXIoftheASMEBoilerandPressureVesselCode,1974Edition.Thesetpoints (liftsettings) mustbewithinthe+1%tolerance specified intheTechnical Specifications.

Typically, one-third ofthevalvesaretestedeachrefueling outage.Onefailuretomeetthe+1%T/Scriteriacausesadditional valvestobetested.AtCookNuclearPlant,wehavehadtotestalltwentyvalvesduringeveryrecentrefueling outage.Sincethe1987"TreviTest,"animprovedtestingdevicehasbeenemployedtotesttheMSSVs.Evenwiththeimprovedtestmethods,thetestresultsdonotshowadefinitive trendofvalvedegradation.

Themanufacturer (Dresser) believesthat,ifthevalveswerecycledmorefrequently thanthe18-monthtest,the+1%tolerance couldbeachieved.

Cyclingthevalvesmoreoftenthanevery18months,,however,isnotfeasibleduetoplantoperational constraints.

Dresserrecommends anincreaseinthetolerance rangefrom+1%to+3%forMSSVsatCookNuclearPlant.Historical testresultsofMSSVsatCookNuclearPlantrevealthat90%ofthesetpointdrifthasbeenwithinthe+3%band.The+3%bandisconsistent withANSI/ASME OM-1,1981Edition(Standard forReliefDevices),

whichspecifies a+38testingtolerance forallISIsafetyandreliefvalves.Thetestingrequirements ofthi,sstandardareapplicable via1986andlatereditionsofASMESectionXI.II.DESCRIPTION OFPROPOSEDTECHNICAL SPECIFICATION CHANGESA.Unit11.Table4.7-1Table4.7-1isbeingchangedtoreflectthe+3%tolerance ratherthanthe+1%tolerance ontheMSSVs.2~Basespage3/47-1TheBasesarebeingchangedtoreflecttheallowable tolerance andtherequirement toresetthevalvestotheirnominalsetting.Thedescription ofthevalvefunctioninthefirstparagraph wasclarified tobeconsistent withtheequivalent description intheUnit2Bases.

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Attachment 1toAEP:NRC:1169 B.Unit2Page21.T/S3.5.2Technical Specification 3.5.2isbeingchangedtolimittheTHERMALPOWERto3250MW~whenasafetyinjection cross-tie valve(s)isclosed.Inanalyzing asmallbreakLOCA,theMSSVtolerance increaseresultsinanincreaseinsteamgenerator, andconsequently primarysystem,pressure.

Thisresultsinalowersafetyinjection flow.Theadditional loweringofthesafetyinjection flowforthecross-tie valveclosedconfiguration iscompensated forbyalowerthermalpowertoobtainacceptable smallbreakLOCAresults.2.Table3.7-4Table3.7-4isbeingchangedtoreflectthe+3%tolerance ratherthanthe+1%tolerance ontheMSSVs.3.Basespage5-1TheBasesarebeingchangedtoreflecttherequirement toreducepowerwhenasafetyinjection crosstievalveisclosed.4.Basespage3/47-1TheBasesarebeingchangedtoreflecttheallowable tolerance andtherequirement toresetthevalvestotheirnominalsetting.III.JUSTIFICATION FORCHANGEWestinghouse ReportSECL-91-429, "DonaldC.CookUnits1and2,MainSteamSafetyValveLiftSetpointTolerance Relaxation,"

foundinAttachment 4,summarizes theaccidentanalysesaffectedbyarelaxation intheallowable MSSVtolerance to+38.ThisWestinghouse reportprovidesajustification fortheT/Sschange.IV.NOSIGNIFICANT HAZARDSANALYSISWehaveevaluated theproposedT/Sschangesandhavedetermined thattheydonotrepresent asignificant hazardsconsideration basedonthecriteriaestablished in10CFR50.92(c).

Operation ofCookNuclearPlantinaccordance withtheproposedamendment willnot:1)Involveasinificantincreaseintherobabilit orconseuencesofanaccidentreviouslevaluated Basedontheanalysespresented inAttachment 4,alloftheapplicable LOCAandnon-LOCAdesignbasisacceptance criteriaaresatisfied.

Althoughincreasing thevalvesetpointmay 0o Attachment 1toAEP:NRC:1169 Page3resultinanincreaseinthesteamreleasefromtherupturedsteamgenerator intheeventofasteamgenerator tuberuptureabovethecurrentUFSARvaluefoundinChapter14.2.4forbothunitsbyapproximately 0.2%,theanalysisindicates thatthecalculated dosesarewithinasmallfractionofthe10CFR100doseguidelines.

Theevaluation alsoconcludes thattheexistingmassreleasesusedintheoffsitedosecalculations fortheremaining transients (i.e.,steamlinebreak,rodejection) arestillapplicable.

Therearenohardwaremodifications tothevalvesand,therefore, thereisnoincreaseintheprobability ofaspuriousopeningofaMSSV.Sufficient marginexistsbetweenthenormalsteamsystemoperating pressureandthevalvesetpoints withtheincreased tolerance toprecludeanincreaseintheprobability ofactuating thevalves.Basedontheabove,thereisnosignificant increaseintheprobability ofanaccidentpreviously evaluated intheUFSARorinthedoseconsequences.

2)Createtheossibilit ofanewordifferent kindofaccidentfromanreviouslanalzedIncreasing theliftsetpointtolerance ontheMSSVsdoesnotintroduce anewaccidentinitiator mechanism.

Nonewfailuremodeshavebeendefinedforanysystemorcomponent important tosafetynorhasanynewlimitingsinglefailurebeenidentified.

Noaccidentwillbecreatedthatwillincreasethechallenge totheMSSVsandresultinincreased actuation ofthevalves.Therefore, thepossibility ofanewordifferent kindofaccidentthananyalreadyevaluated intheUFSARisnotcreated.3)Involveasinificantreduction inamarinofsafetAsdiscussed inthesafetyevaluation (Attachment 4),theproposedincreaseintheMSSVliftsetpointtolerance willinvalidate neithertheLOCAnorthenon-LOCAconclusions presented intheUFSARaccidentanalysesofrecord.Thenewlossofload/turbine tripanalysisconcluded thatallapplicable acceptance criteriaarestillsatisfied.

ForalltheUFSARnon-LOCAtransients, theDNBdesignbasis,primaryandsecondary pressurelimits,anddoselimitscontinuetobemet.Peakcladdingtemperatures remainbelowthelimitsspecified in10CFR50.46fornormaloperation andwhenthethermalpowerisreducedtocompensate forclosureofthesafetyinjection crosstievalvesasrequiredbytheproposedTechnical Specifications.

Thecalculated dosesresulting fromasteamgenerator tuberuptureeventremainwithinasmallfractionofthe10CFR100permissible releases.

Thus,thereisnoreduction inthemargintosafety.

TABLE4-1STEAMLINESAFETYVALVESPERLOOPVALVENUMBERa.SV-1b.SV-1c.SV-2d.SV-2e.SV-3LIFTSETTING*3X*1065psig1065psig1075psig1075psig1085psigORIFICESIZE-16in.216in.216in.216in.216in.2*Theliftsettingpressureshallcorrespond toambientconditions ofthevalveatnominaloperating temperature andpressure.

COOKNUCLEARPLANT-UNIT13/47-4AMENDMENT NO.