ML17037C337

Nine Mile Point Unit 1 - Letter Enclosing Change Request No. 2 Requesting a Modification to the Safety Limit on Fuel Cladding Integrity and Advising That the Change Has Been Reviewed and Bears the Approval of the Station Operations Review C

ML17037C337
Person / Time
Site:	Nine Mile Point
Issue date:	12/09/1969
From:	Pratt M H Niagara Mohawk Power Corp
To:	Morris P A US Atomic Energy Commission (AEC)
References
Download: ML17037C337 (12)

Text

FROMI~~.Siagara-khhavtr.-PcwerCorPoration8~'gyrccccc,SccYork2320'~~ElcEcPgatt.TOI3r-Peter-Ac-NorrisLTR.XORIG.IMEMOiCCI0RTI0THERtDATEOFDOCUMENT'DATERECEIVED22++9is96'8.~5OTNERiACTIONNECESSARYQNOACTIONNECESSARYQCONCURRENCEQDATEANSWEREDCOMMENTCIBYICLASSIFiPOSTOFFICEREG.NOiFILECODE(gp-22O(Xmm)DESCRIPTIONI(MuStBOUnClaSSlfiad)Xtrtransthefollovfag:ENCLOSURESICHAI"EHWUE8PNO.2toTechSecsrequestingmc@ificationstosafetylimitonfue1cleMlina,integrity.sied.51conf'd.csrecsd)REMARKS(REFERREDTODATEDXS3RKBUTIOH:Rega2atoryfilAECPDRCompliance2)OGCamPO6AHPricekSkovholtDuhe/IevtneDThosoBoyCHSICBuchananZiemnn+~9vcsforACTXM2RECEIVEDBY9csadvDishVo(1cyea),DATE*U,B,OOVSRHIISNTrlllNTIHOOFFICSi$44WI~UWATOMICENERGYCOMMISSIONMQQtrPNTRPLFPRMFORMA<<->><<(860)

• Mlh~Fq~.4,2"A'>>~ItI,A.i')p",..i"'TgfggQII NIAGARAMOHAWKPOWERCORPORATIONRegufatoryFifet:y.NIAGARA~~MOHAWK300ERIEBOUIEVAROWESTSYRACUSE,N,Y.13202December9,1969Dr;PeterA.Morris,DirectorDivisionofReactorLicensingUnitedStatesAtomicEnergyCommissionWashington,D.C.20545

DearDr.Morris:

Re:ChangeRequestNo.2ProvisionalOperatingLicenseDPR-17Docket50-220EnclosedarethreesignedcopiesandnineteenreproducedsignaturecopiesofChangeRequestNo.2requestingamodificationtothesafetylimitonfuelcladdingintegrity.InaccordancewithTechnicalSpecificationrequirement6.1.C.2,thischangehasbeenreviewedbytheStationOperationsReviewCommitteeandtheSafetyReviewandAuditBoard,respec-tively,andbearstheapprovalofbothbodies.WeaskthattheCommissiongivepromptconsiderationtothisrequestforchange.VerytrulyyoursMHP/jclEnclosures,fI]o)/rPCKpEprU31ffCOECg1969k,-REGUIA)pRy'@L~CCffpe/KBCLERK/H.PratVicePresidentandExecutiveEngineer3815~

1l'aLTlP.f,CC Kl',/PP,<jCRINGEREVESTNO.2Qygg~gfg)gyj+,,gOJgPROVISIONALOPERATINGLICENSEDPR-17(DOCKET50-220)ApplicantherebyrequeststheCommissiontochangetheTechnical.Specification(AppendixAoftheabovecaptionedlicense)asfollows:1.SecificationToBeChangedSafetyLimit-FuelCladdingIntegrity,Figure2.1.1andSpecification2.1.1.b2.ExtentofChanea.Figure2.1.1-Extendthe1250psiaand1015psiasafetylimitcurvesfrom20percentrecirculationflowto5percentrecirculationflow.b.Specification2.l.l.b-h1odifyspecificationtopermitreactoroperationinaccordancewiththeadditionaldatathatisapplicablefrom5percentto20percentrecircu-lationflowasshownontheattachedfigure.3.ChaneReuesteda.Figure2.1.1-SupersedetheexistingTechnicalSpecificationFigure2.1.1withtheattachedfigure.b.Specification2.l.l.b-ftodifystatementtoread:"Whenthereactorpressureislessthan585psigorreactorrecirculationflowislessthan5percentofdesign,thereactorthermalpowershallnotexceed307h/Wt."c.References,Page8-AddReference(6)ChangeRequestNo.2-Discussion.

eh 4.DiscussionTheextensionofthefuelcladdingintegritysafetylimitcurves,Figure2.1.1,toflowsaslowas".percentofdesignwasperformedusingthesameassumptionsandinitialconditions~aswereemployedi.nthecurvespresentlyintheTechnicalSpeci-fications.ThedesignbasiscriticalheatfluxcorrelationgiveninAPED-3892wasused.ThepowershapewasbasedonaMCHFRof1.5at120percentoverpower,andresultsinatotalpeakingfactorof3.13.Maximumfeedwaterter;peraturewasassumedforthevariouspressuresandflowsandthecoreinletenthalpywasbasedonthesubcoolingres<<lt~ngfromequilibriumoperation.(EEvaluationofthefuelcladdingintegritysafetylimitinthelowflowregionwasperformedusingthedesignbasiscriti-calheatfluxcorrelationatthelowmass-'lowlimit.Thisevaluationisconservativeduetotheinverserelationshipbetweenmassflowandcriticalheatfluxinthehighqualityregionofthecorrelation.Cri.ticalheatfluxformassflowslowerthanthelowlimitofthedesignbasiscriticalheatfluxcorrelationaregreatertha'nthatpredictedbythecorre-lation.TheproposedchangeofSafetyLimit".l.l.bandFigure2.1.1doesnotreducethe.marginot'afetylimitprotectionsinceneutronmonitoringsystemrodblockandscramtripsmain-tainadequatemargintoproposedsafetylimitlinesonFigureE.JanssenandS.Levy,"BurnoutLimitCurvesforBoilingWaterReactors"APED-3892,April1,1962.

0F4, 4.Discussion(Continued)forallregionsofpossibleoperation.Thecorenaturalcircu-lationcharacteristic,thelowerlimitofcoreflowforpoweroperation,precludesoperationuptothesafetylimitwithouthavingfirstreachedtherodblocktripandthescramtrip.PriorsubmittaltotheFDSAR,AppendixE,hasshownthatthereactorisadequatelyprotectedbythe'pressurescramandfixed120percentfluxscramforalltransientsconsideredsuchasthecontinuousrodwithdrawalandturbinetripwithoutbypassoriginatingfromallnormaloperating.conditionsinclud-'ngthelowpowerandflowlevelsconsistent>>ithnaturalcirculation.NIAGARAM01(NOKP()I('ER.CORPORATIONbypinotfl.PrattVicePresidentExecutiveEngineer v~

~~~~~-AI~160NOTESFIGURE2.1.1FUELCLADDINGINTEGRITYSAFETYLIMIT140120I-C?U'0100UJI-C)I~w80Cl060II-C3W4020I.Ratedpowerisl538Mwt2.Designflowis67.5xIOIb/hr3.Totalpeakingfactoris<3.134.Corepressureis>585psig5.WaterlevelshallnotbemorethanI'-7II/16"belowmin.normallevel(El.302'-9").FORPEAKINGFACTORS>3.13SL=3.13XSLOPFWHERE:SL=SAFETYLIMITFORPEAKINGFACTORS>3.13PF=PEAKINGFACTOR>3.13SLO=SAFETYLIMITSHOWNABOVE1000PSIG1235PSIG001020304050607080RECIRCULATIONFLOW(%OFOESIGN)90'10011012010 0:+Egg~~