ML20156A281

TVA Slides for June 8, 2020, ATRIUM-11 Presubmittal Meeting

ML20156A281
Person / Time
Site:	Browns Ferry
Issue date:	06/08/2020
From:	Tennessee Valley Authority
To:	Office of Nuclear Reactor Regulation
References
Download: ML20156A281 (24)

Text

BrownsFerryATRIUM11FuelTransition LicenseAmendmentRequest:PreApplicationMeeting June8,2020

BrownsFerryATRIUM11FuelTransition LicenseAmendmentRequest:PreApplicationMeeting

2 Background

• TVAintendstotransitiontoATRIUM11fuelatBrownsFerry Firstreloadtargetedforunit2reload22inFebruary2023

• TVAhasexperiencewithATRIUM11fuel EightLUAswereinsertedintounit2in2015 Havecompletednearlythreetwoyearcyclesofirradiation Noadverseoperatingexperience

• FramatomeadvancedmethodsareneededtosupportATRIUM11

• TVAwilldocketaLicensingAmendmentRequest(LAR)torequest approvaltoaddthemethodstotheTechnicalSpecifications Implementationaddressedunder10CFR50.59

BrownsFerryATRIUM11FuelTransition LicenseAmendmentRequest:PreApplicationMeeting 3

LicensingApproach

• TVAwillfollowtheBrunswickandSusquehannaLARapproaches

• LARwilldemonstrateapplicationofnewmethodsusingan equilibriumBrownsFerryATRIUM11core

• Selectcyclespecificreportswillbeprovidedforinformationpost LARfortheimplementationcycle

• LARwillalsoaddressRAIsreceivedduringBrunswickand SusquehannaLARreviews,asapplicable

BrownsFerryATRIUM11FuelTransition LicenseAmendmentRequest:PreApplicationMeeting 4

LARContentOverview

• Fuelcycledesignreport

- DocumentBFNequilibriumATRIUM11coredesign

• Nuclearfueldesignreport

- Documentbundledesigndetailsofequilibriumcycleassemblies

• Assemblymechanicaldesignreport

- CompliancewithSRPandFramatomemechanicaldesigncriteria

- CompatibilityofATRIUM11withBFNcoresidentfuelandreactorinternals

• Fuelrodthermalmechanicaldesignreport

- DemonstrateapplicationofRODEX4toATRIUM11usingequilibriumcycle design

BrownsFerryATRIUM11FuelTransition LicenseAmendmentRequest:PreApplicationMeeting 5

LARContentOverview(cont)

• Thermalhydraulicreport

- DemonstrationofthermalhydrauliccompatibilityofATRIUM10XMand ATRIUM11atBFN

• Methodsapplicabilitysupplement

- AddresstopicsrelatedtoATRIUM11andnewmethods

- SimilarincontenttoBrunswickreportANP3705P

• LOCAreport

- AnalysisofBFNbreakspectrumwithNRCapprovedAURORABLOCAmethod

- DerivationofexposuredependentMAPLHGRlimits

• Stabilityreport BEOIIIwithCDAdemonstrationanalysis

BrownsFerryATRIUM11FuelTransition LicenseAmendmentRequest:PreApplicationMeeting 6

LARContentOverview(cont)

• ATWSIreport DemonstrateapplicationofRAMONA5FAmethodusingequilibriumATRIUM11core

• Controlroddropaccidentreport DemonstrateapplicationofAURORABCRDAusingBFNequilibriumATRIUM11core

• Transientdemonstrationreport DemonstrateapplicationofAURORABAOOusingBFNequilibriumATRIUM11core

• LimitationsandConditions(L&C)Report BrunswickandSusquehannaLARsdidnotaddressL&Csupfront ResultedinRAIs AddressL&CsofthenewFramatomemethodsSERs SomeL&Cswillneedtobeaddressedaspartofimplementationcyclereports

BrownsFerryATRIUM11FuelTransition LicenseAmendmentRequest:PreApplicationMeeting 7

ATWSI

• LARwillrequestchangingthelicensingbasismethodfromGEH TRACG04totheFramatomeRAMONA5FAmethod

• FramatomemethodnowNRCapproved

- ANP-10346P-A Revision 0, ATWS-I Analysis Methodology for BWRs Using RAMONA5-FA

• KeyplantinputswillbeunchangedfromtheanalysisintheMELLLA+

LAR

- Feedwatertemperaturereductionrate

- Operatorresponsetimes

• DoesNRCplanonperformingconfirmatoryTRACEanalyses?

- ATRIUM11coreandthermalhydraulicinformationonly

- NRCneeddate?

BrownsFerryATRIUM11FuelTransition LicenseAmendmentRequest:PreApplicationMeeting 8

BEOIIIwithCDA

• TVAintendstofollowtheBrunswickprecedentforstability

- StabilityanalysiswillutilizetheRAMONA5FAmethodologytoanalyze eventsandgeneratetimedependentLPRMresponsesforeachtrialcase

- LPRMresponseswillbefedintoaseparatecodeforevaluationwiththe confirmationdensityalgorithm(CDA)

- Timeoftripwillbedeterminedbythiscode

• FramatomewillusetimeoftripvaluestodetermineCPR responseforeachtrialandmargintoSLMCPR

BrownsFerryATRIUM11FuelTransition LicenseAmendmentRequest:PreApplicationMeeting 9

BEOIIIwithCDA(cont)

• ImplementationwilldifferfromBrunswickinoneregard

• Brunswickusedascreeningprocesstoreducethenumberof casesanalyzedwithCDA

• TVAapproachwillintegratetheCDAevaluationintothe Framatomeanalysisprocess

- CDAutilizedforallaspectsoftheevaluation

- EverystabilitytrialcaseevaluatedbyRAMONA5FAwillhaveaCDA evaluation

- Noscreeningoutofcases

- NoissuesofPBDAtrippingbeforeCDA TimeoftripalwaysbasedonCDA

BrownsFerryATRIUM11FuelTransition LicenseAmendmentRequest:PreApplicationMeeting 10 BEOIIIwithCDA(cont)

• Currentbackupcapabilitieswillberetained ManualBSPregionsretained ABSPretainedandfunctional ValidityofBSPregionsandABSPsetpointsconfirmedeachreload

• NochangestotheTechSpecactionsforaninoperableOPRMrequired

BrownsFerryATRIUM11FuelTransition LicenseAmendmentRequest:PreApplicationMeeting 11 PreferredStabilityApproachforLAR

• GenericBEOIIItopicalstillunderNRCreview TVAdesirestoreferencethegenericintheBrownsFerryLAR

• UseofCDAwillrequireaplantspecificreport

• Plantspecificreport WouldreferencethegenericreportfortheoverallBEOIIImethodology DescribetheincorporationofCDAwithinthecalculationframework DescribehowtheCDAcodeusedbyFramatomecomplieswiththeapprovedCDA andBrownsFerryimplementation DescribehowtheCDAisvalidatedontheFramatomecomputationalplatforms

BrownsFerryATRIUM11FuelTransition LicenseAmendmentRequest:PreApplicationMeeting 12 BackupStabilityApproachforLAR

• TwooptionsifgenericBEOIIItopicalnotapprovedpriortoLAR Optionsdifferintermsofhowthegenerictopicalultimatelygetsreferenced CDAaspectsstillincludedasdiscussedonthepriorslide

• Option1 genericreportapprovalimminentatLARsubmittal Plantspecificreportduplicatesthemethodologydescriptioninthegenericreport PlantspecificreportwilladdressdraftLimitationsandConditionsfromgenericreport OncegenericapprovedtheLARwouldbeamendedtoreferencetheapprovedreport Avoidshavingidenticalgenericandplantspecifictopicalreports Option2 genericreportreviewextendswellbeyondLARsubmittal Plantspecificreportduplicatesthemethodologydescriptioninthegenericreport UseRAIprocesstoaddressanyLimitationsandConditionsifnotavailableatthetimeof LARsubmittal PlantspecificmethodologytopicalwouldremainasBrownsFerrylicensingbasis

BrownsFerryATRIUM11FuelTransition LicenseAmendmentRequest:PreApplicationMeeting 13 ControlRodDropAccident

• ApplicationofNRCapprovedAURORABCRDAmethod ANP10333PARevision0,AURORAB:AnEvaluationModelforBoilingWater Reactors;ApplicationtoControlRodDropAccidentScenarios Methodologyappliedonacyclespecificbasis DemonstrationanalysisbaseduponATRIUM11equilibriumcore.

• WilladdressRIAcriteriainRegGuide1.236 ByendofOctober2020TVAwilluseavailableRG1.236(draftorfinal)

• Showcurrentdoseanalysisforeventremainsbounding Doseaspectswillconsidersteadystateandtransientreleasecriteria TransientreleasefractionfromDG1327Rev1(July2019)

ApartofthismaterialdidnotremaininRG1.236 SteadystatereleasefractionsbasedonRegGuide1.183,July2000

BrownsFerryATRIUM11FuelTransition LicenseAmendmentRequest:PreApplicationMeeting 14 TransientDemonstrationAnalysis

• AdemonstrationanalysisusingtheATRIUM11equilibriumcore willbeperformedusingNRCapprovedAURORABAOOmethod ANP10300PARevision1,AURORAB:AnEvaluationModelforBoilingWater Reactors;ApplicationtoTransientandAccidentScenarios

• CasematrixsimilartoBrunswick Basecaseanalysesforturbinetrip,loadrejection,andfeedwatercontrollerfailure RatedpowerandselectoffratedpowersincludingbelowPbypass EventdispositionforUFSARChapter14events BrunswickRAIonequipmentoutofservicewillbeaddressed Tableofratedpowercaseresultsforeachcurrentlylicensedequipmentoutofservice domain(aloneandincombination)willbepresented Reportwilldiscussspecificsonscramtimes,cycleexposurepoints,andfullrangeof powerflowpointsthatwillbeanalyzedforthefullreloadreport

BrownsFerryATRIUM11FuelTransition LicenseAmendmentRequest:PreApplicationMeeting 15 TransientDemonstrationAnalysis(cont)

• Additionalcases TVAisconsideringextendingtheARTSthermallimitsadministrationusedbelow PbypasstothepowerrangeabovePbypass BelowPbypass MCPRp limitsdependonbothpowerandcoreflow MCPRp limitsataspecifiedpowerbelowPbypassdependonwhethercoreflowis aboveorbelowaspecifiedvalue(50%flowforBFN)

Thisisreferredtoasaflowflag AbovePbypass asingleMCPRp limitatagivenpowerissetbythetransientresultsat thelimitingcoreflow TypicallyICFsetsthelimit IfasimilarflowflagconceptisappliedabovePbypass,youwouldhavetwoMCPRp limitsforagivenpower Onelimitforflowsabovetheflagvalue,andanotherlimitforflowsbelowtheflagvalue

BrownsFerryATRIUM11FuelTransition LicenseAmendmentRequest:PreApplicationMeeting 16 TransientDemonstrationAnalysis(cont)

• Additionalcases(cont)

ThepurposeofapplyingtheflowflagconceptabovePbypass isforoperatingthermal margingain Verybeneficialduringstartupandmaneuveringwhenxenontransientscanerodemargins UsingincreasedcoreflowbasedMCPRp limitsintheMELLLA+regionisrestrictive UsingaMCPRp limitsetbyanalysisattheintermediateflowflagvalueprovidesaless restrictiveMCPRlimitthantheincreasedcoreflowbasedlimit ImprovesoperatingmarginwhileatreducedflowintheMELLLA+regionespeciallyfornon steadystateconditions Coremonitoringsystemwillbemodifiedtoenforcetheflowdependenceofthe MCPRp limitsabovePbypassjustasitdoestodaybelowPbypass Conceptillustratedonthenextslide

BrownsFerryATRIUM11FuelTransition LicenseAmendmentRequest:PreApplicationMeeting 17 FlowFlagAbovePbypass Concept MCPRp abovePbypass MCPRp Flow95%

MCPRp Flow<95%

MCPRp belowPbypass Flow50%

MCPRp belowPbypass Flow<50%

AbovePbypasspowerrange Forillustrativepurposes only-95%flowflag assumedabovePbypass

BrownsFerryATRIUM11FuelTransition LicenseAmendmentRequest:PreApplicationMeeting 18 TransientDemonstrationAnalysis(cont)

• Overpressureanalysis ThereportwillincludebothASMEandATWSoverpressurecases ASMEanalysisbasedonMSIVclosurewithfluxscram 102%EPUpoweratincreasedcoreflowandMELLLA+minflow ATWSanalysiswillevaluateMSIVclosureandpressureregulatorfailureopen transients 100%EPUpoweratincreasedcoreflowandMELLLA+minflow

BrownsFerryATRIUM11FuelTransition LicenseAmendmentRequest:PreApplicationMeeting 19 TechnicalSpecificationChanges

• ThefollowingapprovedmethodstopicalswillbeaddedtoTS5.6.5.b BAW10247PA,Supplement1PA,Revision0,RealisticThermalMechanicalFuelRodMethodologyforBoilingWater ReactorsSupplement1:QualificationofRODEX4forRecrystallizedZircaloy2Cladding-ApprovedApril2017 BAW10247PA,Supplement2PA,Revision0,RealisticThermalMechanicalFuelRodMethodologyforBoilingWater ReactorsSupplement2:MechanicalMethods-ApprovedAugust2018 ANP10340PARevision0,IncorporationofChromiumDopedFuelinAREVAApprovedMethods-ApprovedMay2018 ANP10335PARevision0,ACE/ATRIUM11CriticalPowerCorrelation-ApprovedMay2018 ANP10300PARevision1,AURORAB:AnEvaluationModelforBoilingWaterReactors;ApplicationtoTransientand AccidentScenarios-ApprovedJanuary2018 ANP10332PARevision0,AURORAB:AnEvaluationModelforBoilingWaterReactors;ApplicationtoLossofCoolant AccidentScenarios-ApprovedMarch2019 ANP10333PARevision0,AURORAB:AnEvaluationModelforBoilingWaterReactors;ApplicationtoControlRodDrop AccidentScenarios-ApprovedMarch2018 Theplantspecificstabilitytopicalreportwillalsobeadded DescriptionoftheoverallstabilitymethodologywilldependontimingofNRCreviewandapprovalofANP10344P Revision0,FramatomeBestEstimateEnhancedOptionIIIMethodology,

BrownsFerryATRIUM11FuelTransition LicenseAmendmentRequest:PreApplicationMeeting 20 TechnicalSpecificationChanges(cont)

• TVAdesirestoincludeTSTF564relatedchangestotheTechSpecs

• FramatomehasestablishedMCPR95/95 valuesfortheATRIUM10XM andtheATRIUM11fueltypes

• AreportdocumentingthederivationoftheMCPR95/95 valueswillbe includedintheLAR MethodusedtoderivethevaluesisinaccordancewiththeNRCapprovedprocessintheTSTF TwoassociatedTechSpecchangeswillbemade:

TS2.1.1.2willbemodifiedtoreflecttheMCPR95/95 value,applicabletobothtwoloopand singleloopoperation TS5.6.3willbemodifiedtorequirethattheMCPR99.9% valuesfortwoloopandsingleloop operationbeincludedintheCOLR ModifiedlanguageofTS5.6.3willbeconsistentwiththatshownintheTSTF

BrownsFerryATRIUM11FuelTransition LicenseAmendmentRequest:PreApplicationMeeting 21 ImplementationCycleReports

• TVAwillprovidecyclespecificreportsforinformationforthe implementationcycle

• ReportswillbeprovidedonaschedulespecifiedintheLAR

• Reportsinclude:

FuelCycleDesignReport NuclearFuelBundleDesignReport SafetyLimitMCPRReport Mayincludecycleexposuredependentvalues FuelRodDesignReport ReloadSafetyAnalysisReport Includedispositionofeventssummary AddressremainingFramatomemethodologyLimitationsandConditions

BrownsFerryATRIUM11FuelTransition LicenseAmendmentRequest:PreApplicationMeeting 22 CriticalityReportLAR NRCreviewedtheBFNrackcriticalityreportaspartoftheEPULAR EPUsafetyevaluationnotedthecriticalityanalysisreviewedforfueltypesup toandincludingATRIUM10XM TVAbelievesaddingATRIUM11tothespentfuelpoolrequiresadditionalNRC review TVAwilldocketthisreportasaseparateLAR ApprovalneededearlierthanthetransitionLARtosupportreceiptoffirstATRIUM11 reloadbatchinearlyfallof2022 ApprovalofthisLARonlygrantstheabilitytoreceiveandstoreATRIUM11fuelin thefuelpoolracks LARwillnotchangetheexistingTechnicalSpecificationkinfinitylimit TVAdoesnotviewthisLARashavinglinkagewiththetransitionLAR

BrownsFerryATRIUM11FuelTransition LicenseAmendmentRequest:PreApplicationMeeting 23 Schedule

• ProposeddateforcriticalityreportLARsubmittal-5/28/2021

• ProposeddatefortransitionLARsubmittal 6/9/2021

• SafetyevaluationneeddateforcriticalityreportLAR-5/30/2022 12monthreview

• SafetyevaluationneeddatefortransitionLAR-12/9/2022 18monthreview Outagestartdate2/25/2023

• AllbutoneofthenewmethodsisNRCapproved LARreviewcanfocusonapplicationoftheapprovedmethodstoBFN

• CriticalNRCactionisapprovalofBEOIIItopicalreportbyMarch2021 AllowsavoidanceofsupplementingtheLARorhavingapermanentplantspecificmethodology topicalreport