ML17037C470

Nine Mile Point, Unit 1 - Letter Regarding Guidance for Proposed License Amendments Relating to Refuelings and an Enclosed List of Information Needed to Forecast Requirements for Reviews of Proposed License Amendments Relating to Refueling

ML17037C470
Person / Time
Site:	Nine Mile Point
Issue date:	06/18/1975
From:	Goller K R Office of Nuclear Reactor Regulation
To:	Rhode G K Niagara Mohawk Power Corp
References
Download: ML17037C470 (28)

Text

DocketNo.50-220rDXSTRZBUTXON;NRCPDRHVanderhfolen8(975Loc1PDRAGiambussoORB¹3RdgFSchroederDocketRSBoydKRGollerRCDeYoungTJCarterVhfooreGLearRDeniseDJaffeTAbernathySATeetsCJDeBevecOELD016E(3)ACRS(143GrayfilePCheckGentlemen:BSchemelDRossItisacontinuingobjectiveoftheNuclearRegulatoryCommission(NRC)toprovidecomplete,promptreviewsofallapplicationsforconstructionpermits,operating1icensesandlicenseamendments.Thelengthoftimenecessarytoactuponsuchapplicationsis,toalargeextent,afunctionofthecompletenessoftheinformationsuppliedbythelicenseeinsupportofitsapplication.Completenessisparticularlyimportantforproposedlicenseamendmentsthatrelatetoreactorrefuelingssincetheyoftenincludeawiderangeofproposedtechnicalspecificationchangesthatmustbedevelopedandapprovedbeforethefacilitycanreturntooperation.ThetiRChasdevelopedpreliminaryguidance(Enclosure1)foruseinpreparingproposedlicenseamendmentsthatrelatetorefuelingsthatmayhelptoassurethatyoursubmittalswill'includeallrequiredinformation.Anotherrelatedproblemisthatoflatenessoflicenseesubmittalswhichmakeitdifficultandsometimesimpossibleforthestafftocompleteitsreviewintimetoaccommodatescheduleddatesforresumptionofoperation.Thisproblembecomesparticularlydifficultforlicenseamendmentsthatrelatetorefuelingsthatinvolveanextensivenumberof"technicalspecificationchanges.Moreover,thegrowingnumberofoperatingfacilitiesrequestingsuchlicenseamendmentsistaxingthestaff'sabilitytoaccommodateindividualschedules,unlesstherequestsaresubmittedwithadequatetimeforreview.Inordertqimprovetheefficacyandschedulingofourreviewsofproposedlicenseamendmentsthatrelatetorefuelingswehavepreparedalistoftheinformationthat,weneedtoforecasttherequirementsforsuchreviews,(RefuelingInformationRequest,Enclosure2).PleasesubmitthisinformationforyourNineNilePointUnit1facilitywithin30daysofreceiptofthisletterandupdatethisinformationannuallythereafter,ormoreoftenifappropriate.We'uggestthatthisinformationbemadearegularpartofyourannualoperatingreportsOPPIC2~SVIINAML'WOATS~.,DJB.f5'.....,6I,...IL....,/73,.QRBI..3~.......QRBB3....,.....D.'AD/DRY.CJDeRevec...........GLear&4.--'..KRGo11er-.6/............/7S....6/...)......../.2S....-.S/.--l.E---/.7S--.PonshEC.318(Rcv.9.53)hECM0240NU,0'OOVSRNMSNTPRINTINOOPIIICEI1074020100

'I'E1iV'II~r Niagara1fohawkPowerCorporation-2-JUN181975Itis'ourhopethatwiththisinformationwecanassessyourplansforrefuelingandschedulesubmittaldateswhichrealisticallyreflectourreviewrequirementsandyourneedfortimely,licensingaction.ThisrequestforgenericinformationwasapprovedbyGAOunderablanketclearancenumberB-180225(R0072);thisclearanceexpiresJuly31,1977.Sincerely,(s/KarlR.Goller,AssistantDirectorforOperatingReactorsDivisionofReactorLicensing

Enclosures:

1.GuidanceforProposedLicenseAmendmentsRelatingtoRefueling2.RefuelingInformationRequestcc:w/enclsSeenextpageOERICE~SURNAME&DATE~FormhKC-318(Rcv.9.33)hECM02404U.OIOOVERNMENTPRINTINOORPICEIIOT4520IOe Pp'C",040alp U~~~Os~+NiagaraMohawkPowerCorporationJUNI8875~~lCC:ArvinE.Upton,Esquire'LeBoeuf,Lamb,LeibygMacRae1757NStreet,N.W.Washington,D.C.20036AnthonyZ.Roisman,EsquireBerlin,Roisman5Kessler1712NStreet,N.W.Washington,D.C.20036Dr.WilliamSeymour,StaffCoordinatorNewYorkStateAtomicEnergyCouncilNewYorkStateDepartmentofCommerce112StateStreetAlbany,NewYork12207'swegoCityLibrary120E.SecondStreetOswego,.NewYork13126

~-13 ENCLOSURE1GUIDANCEFORPROPOSEDLICENSEAMENDMENTSRELATINGTOREFUELINGA.INTRODUCTIONTherefuelingofapowerreactorrepresentsachange'inthefacilitywhichmayinvolveachangeinthetechnicalspecificationsoranunreviewedsafetyquestion.Title10,CFRPart50,Section50.59(a)permitsalicenseetomakechangesinthefacilityasdescribedintheSAR,changesintheproceduresasdescribedintheSARandconducttestsorexperimentsnotdescribedintheSARwithoutpriorCommissionapprovalunlesssuchchangesinvolveachangeinthe'technicalspeci-ficationsorinvolveanunreviewedsafetyquestion.TherequestforNRCauthorizationforanysuchchangemustincludeanappropriatesafetyanalysisreport(SAR).TheformatandcontentofsuchaSARisthesubjectofthisguide.B.DISCUSSIONThelicenseemustdemonstratethatsafeoperationwillcontinuewiththenewcore.Generally,arefuelingwillinvolveonlychangesinthecoreloading.Anychangesinfacilitydesignnotassociatedwiththerefueling(reload)designanditseffectonsubsequentoperationshouldbeaddressedbyaseparatedocument.Significantchangesinfueldesignorreactorcontrolproceduresmaybeaddressedbyreferencetotopicalreports.Twooperatingcyclesor"loads"areofinterestinareloadsubmittal.The"reloadcycle"istheupcomingcycle,whosesafetyistobeevaluated.The"referencecycle"isthecycletowhichtheproposed

reloadistobecompared.Theappropriatereferencecycleisthereforethecyclewhichhasthemostup-to-date,inclusivesafetyanalysisreportapprovedbytheCommission.Inmostcases,thiswillbethe"present",currentlyoperatingcycle.However,anapplicantmayuseanycycleor,analysisbacktotheFSARcycleforreference,ifthisanalysisboundstheparametersoftheproposedreloadandusescurrentlyapprovedanalyticalmethods.Thevarioussafetyanalysesmaybeexpeditedbysuchreferenceifthereloadcycleparametervaluesareboundedbythereferencecyclevalues.4tTheamountofdetailedanalysisrequiredinanysubmittaldependsonthetypeofreload.Forequilibriumcyclereloads,wheremechanicaldesignandenrichmentdonotchangeitisexpectedthataccidentparameterswillremainwithintheirpreviouslyanalyzedrangesandareanalysismaynotberequired.Conversely,fornon-equilibriumcyclereloads,thethermalandnuclearcharacteristicsgenerallyrequirenewanalysisandafullevaluation.1&enareloadinvolvesdifferentanalyticalmethodsordesignconcepts,acompletereviewofthesechangesandtheireffectsisnecessary.C.REGULATORYPOSITION5Changesindesign,analysistechniques,andotherinformationrelevanttoareloadareoftengenericinnature.GenericinformationmaybeprovidedbyreferencetogenericreportratherthangivingexplicitjustificationinareloadSARforaspecificplant.

Areloadsubmittalshouldbesubmittedatleast90daysbeforetheplannedstartupdate.Ifsignificantdifferentanalyticalmethodsordesignconceptsaretobeincorporatedintothereloadcoreandhavenot'eenjustifiedbygenericrevieworifthechangesotherwiseentailasignificanthazardsconsideration,asignificantlygreatertimeperiodmayberequired.Incaseswheretimingisaproblem,theremaybecasesinwhichthesubmittalmaybeprovidedinsectionssothatthestaffreviewcanbeexpedited.Thesubmittalshouldcontainthefollowing:l.IntroductionandSummarGivethepurposesofthesubmittalandsummarizethecontentsofthesubmittal.2.0eratinHistoryDiscussanyoperatinganomaliesinthecurrentcyclewhichmayaffectthefuelcharacteristicsinthe'reloadcycle.Itisrecognizedthatonlyinformationfromthefirstpartofthecyclewillbeavailable.3.GeneralDescritionProvideacoreloadingmapfortheplannedreloadcore,showingtheposition,byzone,ofnewandirradiatedfuel.Includethepositionofanyte.tassemblies.Showtheinitialenrichmentdistributionofthefreshfuel,theinitialburnupdistribution,andtheburnablepoisondistributionandconcentration(ifany).Deviationsfromthisplannedmapatactualreloadtimeareacceptableprovidedthefinalizedreloadcore'ssafetyparametersareboundedbythesafetyanalysis.

0 4.FuelSstemDesin4.Thereloadfuelsubmittalshouldprovideatablethatpresentsthefollowingitemsforboththeproposedandthereference(cyclefuel:,,fuelassemblytype,plannednumberofreloadandresidualassembliesinthecore,initialfuelenrichment,initialfueldensity,,initialfillgaspressure,regionburnupsatBOG,andcladcollapsetime.ForthenewcoreloadinginPWRs,thelimitingregionorfuelassembliesbasedonfuelperformanceconsiderationsshouldbeidentified.4.2MechanicalDesinHherefuelassembliesareconsiderednewinconcept,thefollowinginformationshouldbeprovided,byreferenceorcxpli'.citly,forthereloadfuelassemblies:Thevibration,flowandstructuralcharacteristicsincludingseismicresponseshouldbepresented.Thedimensionsandconfigurationoffuelassemblycomponentsshouldbepresentedintablesanddrawings.Particularattentionshouldbegiventothefollowingitems:(1)ForPHRs,controlrodassemblyaccommodationandassociatedoperationalfunctions(forexample,dampingandtravellimits).(2)Fuelcladdingmechanicalinteraction.(3)Fuelrodbowingasrelatedtofuelrodaxialpositionandspacergridflexibility.(4)Steady-statefuelassemblyhold-do'wnandlift-'offforces.

(5)Verificationtechniquesforlocationandorientationoffuelassembliesinthecore.(6)Specificdimensionalormaterialchangesfrompresentapprovedassemblies.(7)Designofspacergridsasrelatedtolocalfloweffects,DNBconsiderations,andmechanicalstrengthandintegrityoftheassembly.Demonstratebycalculationwithapprovedmethodsorteststhatthenewfueldesignsatisfiessuchdesignlimitsasstressintensity,strain,deflection,collapse,frettingwearandfatigueforallconditions,steady-state,normal,andabnormaltransients.Anychangesindesignlimitsshouldbeidentifiedand)ustified.DemonstratebycalculationwithapprovedmethodsorteststhatthenewfueldesignmeetstherequirementsofAppendixKof10CFR50.4.3ThermalDesinWherefuelassembliesareconsiderednewinconcept,fuelthermalperformancecalculationsbasedontheabovemechanicaldesignandthevendorsapprovedfuelperformancemodelshouldbeprovided.Fuelcladdingintegrityandcollapseconsiderationsshouldbeincluded.Thismaybeaccomplishedbysuitablereference.

4.4ChemicalDesinWherefuelassembliesareconsiderednqwinconceptorutilizecomponentImaterialsthatdifferfromthepresentdesign,chemicalcompatibilityofallpossiblefuel-cladding-coolant-assemblyinteractionsshouldbeanalyzed.Thismaybeaccomplishedbysuitablereference.4.50eratinExeriencePreviousoperatingexperienceasrelatedtosafetyconsiderationswithcomparablefuelrod/assemblydesignsshouldbepresented.Thismaybeaccomplishedbysuitablereference.5.NUCLEARDESIGN5.1PhsicsCharacteristicsProvideinformationregardinganychangesfromthereferencecycletothereloadcycleforthefollowingparametersusedinthesafetyanalysis:ForBOC,EOC,andanyextremumduringthecycle:(1)ModeratorCoefficients(e.g.,temperature,pressure,density,orvoid.Giveorreferencethepowerdistributionsusedintheirdevelopment.)(2)DopplerCoefficxent(3)MaximumRadialandAxial(orTotal)PeakingFactors(4)EgectedRodWorth(forPWRs)(5)RodDropParameters(forBWRs)'orBOCandEOC:(1)DelayedNeutronFraction(2)CriticalBoronConcentration(forPWRs)

C W7(3)BoronNorth(forPNRs)(4)StandbyLiquidControlSystem11(orth(forBNRs)(5)ScramFunction(forBNRs)ForPWRs,provide,intabularform,adetailedcalculationofthe1shutdownmarginfortheBOCandEOCandanymid-cycleminimumofthereferenceandreloadcycles.Thistableshouldalsoindicatetherequiredmargin.ForBNRs,provide.theshutdownmargincurve.ForPlNs,specifythecontrolrodpatternstobeusedduringthereloadcycle,includinganyrodinterchangesandanydifferencesfromthereferencecycle.5.2AnalticalInutDescribebrieflytheinformationgatheredontheburnuphistoryoftheexposedfuel,andhowitwasusedinthereloadanalysisonlyifrequiredtosupportreloaddesignchanges.Thismaybedonebyreference.Indicatehowtheincoremeasurementcalculationconstants(ormatrices)tobeusedincalculatingbundlepowerswerepreparedforthereloadcycle.Thismaybedonebyreference.5.3ChanesinNuclearDesinDescribeanychangesincoredesignfeatures,calculationalmethods,dataorinformationrelevanttodeterminingimportantnucleardesignparameterswhichdepartfrompriorpracticeforthisreactor,andlisttheaffectedparameters.Thisshouldbedonebyreferencewherepossible.Discussindetailorgiveareferencedescribinganysignificantchangesinoperationalprocedurefromthereferencecyclewithregardtoaxialpowershapecontrol,radialpowershapecontrol,xenoncontrol,andtiltcontrol.~l~4"0tVV(

~I\-8-Incaseswheredifferentanalyticalmethodsareused,detailedinformationI,onthenewanalyticalmethodsforevaluatingcoreneutronicbehaviorshouldbesupplied,andanyinterfacingbetweenthenewandIoldmethodsshouldbeiIIdescribed.Thisshouldbedonebyreferencewherepossible.6.ThermalHdraulicDesintIIntheeventtherearechangesinthefuelgeometry,suchasspacergriddesign,"spacergridaxialseparation,fuelpinspacing,orofthefuelpinoroontrolrodguidetube;oriftherearechangesintheradialoraxialdesignpowerdistributionsofthecore,evaluatetheeffectsofthesechangeson:(a)TheminimumDNBR/CHFR/CPRvaluesfornormaloperationandanticipatedtransients.(b)Thehydraulicstabilityoftheprimarycoolantsystemforallconditionsofsteady-stateoperation,foralloperationaltransientsincludingloadfollowingmaneuvers,andforpartialloopoperation.Thismaybedonebyappropriatereference.Incaseswheredifferentcalculationalproceduresforthermalhydraulicdesignareused,theseproceduresandappropriatecalculationsshouldbedescribedorreferenced.7.AccidentandTransientAnalsisThepotentialeffectofanychangesinthexeloadfueldesignoneachincidentlistedintheAccidentandTransientAnalysissectionofthereferencecycleanalysisshouldbeconsidered.r~~~

e Provideatableoftheinputparametersapplicabletoallaccidentsandtransients.Thistableof"common"parametersshouldlisttwocolumnsforeachparameter:thelimitingvaluesforthereferencecycleandthelimitingvaluesforthereloadcycle.-Asecondtableshouldbeprovidedwhichlistseachaccidentwithitsaccident-specificinput'parameters.Thetableshouldalsolistlimitingvaluesforthereferencecycleandthereloadcycle.Incaseanaccidentinputparameterfallsoutsideofboundspreviouslyanalyzed,provideorreferenceare-analysisoftheaccident.Justifyanychangesfromthereferencecycleinaccidentanalysistechniques,calculationalmethods,correlations,andcodes.Ifthisisnotdonebyreferencetoatopicalreport,anappropriatelylongertimeperiodwillberequiredforapprovalofthereloadsubmittal.8.Proosed14odificationstoTechnicalSecificationsPresenttheproposedmodificationstotheTechnicalSpecifications.Justifythechanges.9;StartuProramIList,andbrieflydescribetheplannedstartuptestsassociatedwithcoreperformance.Recommendedtestsinclude:ForPMRs:(1)ControlRodDriveTestsandDropTime(Hot)(2)CriticalBoronConcentration (3)ControlRodGroupWorth(4)EgectedRodWorth(5)DroppedRodWorth(6)ModeratorTemperatureCoefficient(7)PowerDopplerCoefficient(8)StartupPowerMapsForBWRs:(1)ControlRodDriveTestsandScramTime(ColdandHot)(2)ShutdownMarginWithHostReactiveRodWithdrawn(3)PatternsforCriticality

~.4 ENCLOSURE2REFUELINGINFOMfATIONREUESTl.Nameoffacility2.Scheduleddatefornextxefuelingshutdown3.Scheduleddateforrestartfollowingxefueling4.Willrefuelingorresumptionofoperationthereafterrequireatechnicalspecificationchangeorotherlicenseamendment?Ifanswerisyes,what,ingeneral,willthesebe?Ifanswerisno,hasthexeloadfueldesignandcoreconfigurationbeenreviewedbyyourPlantSafety'eviewCommitteetodeterminewhetheranyunx'eviewedsafetyquestionsareassociatedwiththecorereload(Ref.10CFRSection50.59)?Ifnosuchreviewhastakenplace,whenisitscheduled?5.Scheduleddate(s)forsubmittingpxoposedlicensingactionandsupportinginformation6.Importantlicensingconsiderationsassociatedwithrefueling,e.g.,newordifferentfueldesignorsupplier,unrevieweddesignorperformanc'eanalysismethods,significantchangesinfueldesign,newoperatingprocedures.Fll,'V~~~~~>>~