ML17146B095
| ML17146B095 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 11/30/1987 |
| From: | WHITE J A ADVANCED MEDICAL SYSTEMS, INC. |
| To: | |
| Shared Package | |
| ML17146B090 | List: |
| References | |
| ANF-87-126, ANF-87-126-R01, ANF-87-126-R1, NUDOCS 8712310158 | |
| Download: ML17146B095 (47) | |
Text
ANF-87-126REVIStON1AD~MHCSDoHUCIt.EARFUSMCORPORATIONSUSQUEHANNAUNIT2CYCLE3RELOADANALYSISDESIGNANDSAFETYANALYSES.NOVEMBER198787i2310i5887i223PORADOCK0500058]~ANAFFII.IATEOFKRAFTWERKUNIONQ~KRU ADVANCEDNUCLEARFUELSCORPORATIONANF-87-126Revision1IssueDate:11/25/87SUSQUEHANNAUNIT2CYCLE3RELOADANALYSISDesignandSafetyAnalysesPreparedBy:J.A.WhiteBWRSafetyAnalysisLicensingandSafetyEngineeringFuelEngineeringandTechnicalServicesAIIAFFILIATEOFKRAFTWERKUNIONQxsvu CUSTOMERDISCLAIMERIMPORTANTNOTICEREGARDINGCONTENTSANDUSEOFTHISDOCUMENTPLEASEREADCAREFULLYAdvancedNuclearFuelsCorporation'swarrantiesandrepresentationscon-cemingthesubjectmatterofthisdocumentarethosesetforthintheAgreementbetweenAdvancedNuclearFuelsCorporationandtheCustomerpursuanttowhichthisdocumentisissued.Accordingly,exceptasotherwiseexpresslypro-videdInsuchAgreement,neitherAdvancedNuclearFuelsCorporationnoranypersonactingonitsbehalfmakesanywarrantyorrepresentation,expressedorimplied,withrespecttotheaccuracy,completeness,orusefulnessoftheinfor-mationcontainedInthisdocument,orthattheuseofanyinformation,apparatus,methodorprocessdisclosedlnthisdocumentwillnotinfringeprivatelyownedrights:orassumesanyliabilitieswithrespecttotheuseofanyinformation,ap-paratus,methodorprocessdisclosedinthisdocument.TheinformationcontainedhereinisforthesoleuseofCustomer.InordertoavoidImpairmentofrightsofAdvancedNuclearFuelsCorporationinpatentsorinventionswhichmaybeincludedintheinformationcontainedinthisdocument,therecipient,byitsacceptanceofthisdocument,agreesnottopublishormakepublicuse(inthepatentuseoftheterm)ofsuchinformationuntilsoauthorizedinwritingbyAdvancedNuclearFuelsCorporationoruntilaftersix(6)monthsfollowingterminationorexpirationoftheaforesaidAgreementandanyextensionthereof,unlessotherwiseexpresslyprovidedintheAgreement.NorightsorlicensesInortoanypatentsareimpliedbythefurnishingofthisdocu-ment.XNNFF00.765(1 ANF-87-126Revision1TABLEOFCONTENTSSection1.02.0PacaeINTRODUCTION.~..............,....,................................1FUELMECHANICALDESIGNANALYSIS...................................23.03.23.2.13.2.33.2.5THERMALHYDRAULICDESIGNANALYSIS..............~..................3HydraulicCharacterization........................................3HydraulicCompatibility...........................................3FuelCenterlineTemperature.......................................3BypassFlowe~~~~~~~~~~~~~~~~~~~~~~~~\~~~~~~~~~~~~~~~~~~~~~~~~~~~~33.33.3.13.3.2.3.34.0MCPRFuelCladdingIntegritySafetyLimit...........CoolantThermodynamicConditionsDesignBasisRadialPowerDistribution.DesignBasisLocalPowerDistribution.NUCLEARDESIGNANALYSIS..~~~~~~~~~0~~~~33~~~~~~~~~~~~~4~~~~~~~\~~~~~~~~~~~~~~~54.14.24.2.14.2.24.2.45.0FuelBundleNuclearDesignAnalysis.......CoreNuclearDesignAnalysisCoreConfiguration.......CoreReactivityCharacteristics...,....,..CoreHydrodynamicStability.....~.ANTICIPATEDOPERATIONALOCCURRENCES......,~~~~~~~~~~~~~~~~~~~~~~~~5~~~~~~~556~~~~~~~~~~~~~~~~~~~~~~~~75.15.25.35.45.55.65.76.06.1F1.1itlons~~~~~~~~~7~~~~~~~~~~~~~~~~~~~~~~~~7~~~~~~~~~~~~~~~~~~~~~~~~8~~~~~~~~~~~~~~~~~~~~~~~~8~~~~~~~~~~~~~~~~~~~~~~~~9~~~~~~~~~~~~~~~~~~~~~~~~91010Loss-Of-CoolantAccident....,,......BreakLocationSpectrum........10AnalysisOfPlantTransientsAtRatedCondAnalysesForReducedFlowOperation.......AnalysesForReducedPowerOperation......ASMEOverpressurizationAnalysis..........ControlRodWithdrawalError(CRWE)FuelLoadingError........DeterminationOfThermalMargins..........POSTULATEDACCIDENTS...
ANF-87-1RevisionTABLEOFCONTENTS(Continued)Section6.1.26.1.36.27.07.1T.1.17.1.27.27.2.17.2.27.2.3737.3.17.3.28.0LimitingSafetySystemSettings......HCPRFuelCladdingIntegritySafetyLSteamDomePressureSafetyLimitLimitingConditionsForOperation.AveragePlanarLinearHeatGenerationMinimumCriticalPowerRatio~~~~~~~~~~~~~~~~~~~~~~~~~~~~~imitRateimits.................L'HGRLlmlts~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~o~~~~~~~SurveillanceRequirements...........ScramInsertionTimeSurveillance....StabilitySurveillance..........METHODOLOGYREFERENCES..........9.0ADDITIONALREFERENCES.......reakSizeSpectrum...............................................BAPLHGRAnalyses.............................'.....................HControlRodDropAccident........,...TECHNICALSPECIFICATIONS........Pacae101011121212121212111414141516APPENDICESA.SINGLELOOPOPERATION.............A-1B.SEISMIC-LOCAEVALUATION....,.................,.........,..........B-1 ANF-87-126Revision1LISTOFTABLESTablePacae4.1NeutronicDesignValues...........................................23B.1ComparisonOfPhysicalAndStructuralCharacteristicsFor8x8And9x9FuelAssemblies..............................B-2LISTOFFIGURESFiciure3.1SusquehannaUnit2Powervs.Flow....Cycle3HydraulicDemandCurvePacae173.23.33.5SusquehannaUnit2DesignBasisLocalDesignBasisLocalDesignBasisLocalFuel.Cycle3DesignBasisRadialPower..............18PowerDistribution-ANFXN-29x9Fuel.........19PowerDistribution-ANFXN-19x9Fuel.........20PowerDistribution-GE8x8R(Central)213.64.14.24.34.45.15.2~~......2224~~~~~~~~25~~~~~~~~~26272829DesignBasisLocalPowerDistribution-GE(Peripheral)8x8RFuel..........~~0~~~~SusquehannaUnit2Cycle3EnrichmentDistributionForANF92-344L-9G4XN-2FuelLattice.SusquehannaUnit2Cycle3EnrichmentDistributionForANF92-344L-10G5XN-2FuelLattice.SusquehannaUnit2Cycle3ReferenceCoreLoadingPlan...SusquehannaUnit2Cycle3-CorePowervs.CoreFlow......SusquehannaUnit2Cycle3ControlRodWithdrawalErrorAnalysisLimitingInitialControlRodPattern..SusquehannaUnit2Cycle3FlowMCPROperatingLimit.......
~fj ANF-87-126Revision
11.0INTRODUCTION
ThisreportprovidestheresultsoftheanalysesperformedbyAdvancedNuclearFuelsCorporation(ANF)*insupportoftheCycle3reloadforSusquehannaUnit2,whichisscheduledtocommenceoperationinthespringof1988.ThisreportisintendedtobeusedinconjunctionwithANFtopicalreport~XN-Np--191A,914,R111,Nppti1111NCompanyMethodologytoBWRReloads,"whichdescribestheanalysesperformedinsupportofthisreload,identifiesthemethodologyusedforthoseanalyses,andprovidesagenericreferencelist.However,LHGRmechanicaldesignlimits(Reference9.1)andplanttransientsimulationmodeldevelopments(Reference9.141b1dbyANFb4tNRNP1F~F-Volume4,Revi'sion1.BothReferences9.1and9.2havebeenapprovedbytheNRCforuseinreferencinginlicenseapplications.Sectionnumbersinthis9t19dtdttb1X-N--fNJ,olume4,Revision1.TheSusquehannaUnit2Cycle3corewillcompriseatotalof764fuelassemblies,including236unirradiatedANFXN-29x9assemblies,324irradiatedANFXN-19x9assemblies,112irradiatedGeneralElectric8x8Rfuelassemblies(centralregion),and92irradiatedGE8x8Rassembliesintheperipheralregion.ThereferencecoreconfigurationisdescribedinSection4.2.ThedesignandsafetyanalysesreportedinthisdocumentwerebasedonthedesignandoperationalassumptionsineffectforSusquehannaUnit2duringthepreviousoperatingcycle.Additionalinformationandtheresultsofdesignstudiescoveringthedevelopmentof9x9fuelassembliesforBWRreloadsarecontainedinReference9.3.
f ANF-87-126Revision12.0FUELMECHANICALDESIGNANALYSISApplicableANFFuelDesignReport:Reference9.1ToassurethattheexpectedpowerhistoryforthefuelstobeirradiatedduringCycle3ofSusquehannaUnit2isboundedbytheassumedpowerhistoryinthefuelmechanicaldesignanalysis,LHGRoperatinglimits(Figure3.3ofReference9.1)havebeenspecified.Inaddition,anLHGRtransientoperating'imitforAnticipatedOperatingOccurrences(Figure3.4ofReference9.1)hasbeenspecifiedforANF9x9fuel.Additionalinformationonrodbow,asrequestedintheNRC'ssafetyevaluationreportforReference9.1,hasbeentransmittedinReference9.4.
ANF-87-126Revision13.0THERMALHYDRAULICDESIGNANALYSIS3.2HdraulicCharaeterization3.2.1HdraulicComatibilitComponenthydraulicresistancesfortheconstituentfueltypesintheSusquehannaUnit2Cycle3corehavebeendeterminedinsinglephaseflowtestsoffullscaleassemblies.Figure3.1showsthehydraulicdemandcurvesforANF9x9fuelandGE8x8RfuelintheSusquehannaUnit2core.Thesimilarhydraulicperformanceindicatescompatibilityforco-residencein'heSusquehannaUnit2core.ApplicableGenericReport3.2'FuelCenterlineTemerature~~Reference9.1.2.2~21CalculatedBypassFlowFractionat104%Power/100%Flow10.1%3.3MCPRFuelCladdinInteritSafetLimitSafetyLimitMCPR=1.063.3.1CoolantThermodnamicConditionRatedThermalPowerFeedwaterFlowrate(atSLMCPR)CorePressure(atSLMCPR)FeedwaterTemperature3293Mwt16.1Mlbm/hr1042.9psia383'F ANF-87-1Revision3.3.2DesinBasisRadialPowerDistributionSeeFigure3.23.3.3DesinBasisLocalPowerDistributionSeeFigures3.3through3.6 ANF-87-126Revision14.0NUCLEARDESIGNANALYSIS4.1FueBundeNucleaDesinAnalsisAssemblyAverageEnrichmentRadialEnrichmentDistributionAxialEnrichmentDistributionBurnablePoisonsNote:Burnablepoisonsaredistributeduniformlyovertheenrichedlengthofthedesignatedrods.Thenaturaluraniaaxialblanketsectionsdonotcontainburnableabsorbermaterial.Non-FueledRodsNeutronicDesignParameters3.33%Figure4.1and4.2Uniform3.44%with6"naturaluraniumtopblanketFigure4.1and4.2Figure4.1and4.2Table4.14.2CoreNuclearDesinAnalsis';2.1CoreConfiorationFigure4.3CoreExposureatEOC2,HWd/HTUCoreExposureatBOC3,MWd/HTUCoreExposureatEOC3,HWd/MTUMaximumCycle3LicensingExposureLimit,HWd/MTU18350.710911.221740.822076 ANF-87-12Revision4.2.2oreReactiv'tCharacterisicsBOCColdK-effective,AllRodsOutBOCColdK-effective,StrongestRodOut1.113530.98524ReactivityDefect(R-Value)0.00%rho4.2.4StandbyLiquidControlSystemReactivity,ColdConditions,660ppmICoreHdrodnamicStabilit0.98348Power/flowMapFigure4.4PowerFlowStatePoints64/42*69/47**66/45**DecaRatioCOTRA0.820.750.75*Twopumpminimumflow-APRNRodBlockinterceptpoint.ExtendedoperationatlowerflowisnotallowedbyTechnicalSpecifications.**Operationatlessthan45%flowrequiresAPRH/LPRNsurveillance.Inaddition,operationatpower/flow,combinationsaboveandtotheleftofthelineconnectingthesetwopointsrequiresAPRH/LPRtlsurveillance.SeeFigbre4.4.
ANF-87-126Revision15.0ANTICIPATEDOPERATIONALOCCURRENCESApplicableGenericTransientAnalysisMethodologyReportReferences9.559.75.1AnalsisOfPlantTransientsAtRatedConditionsReference9.6LimitingTransient(s):LoadRejectionWithoutBypass(LRWB)FeedwaterControllerFailure(FWCF)LossofFeedwaterHeating(LFWH)EventLRWBPower*100%FWCF100%100%116.8%LFWH100%100%121'%233%123%11791078%Rated%RatedMaximumMaximumMaximumPressureFlowHeatFluxPower,~aiaI100%116.2%267%1194DeltaCPR**0.240.230.16ModelCOTRANSA/XCOBRA-TCOTRANSA/XCOBRA-TPTSBWR3/XCOBRASingleLoopOperation:AppendixA5.2AnalsesForReducedFlow0erationReference9.6LimitingTransient(s):RecirculationFlowIncreaseTransient(RFIT)*104%powerusedinanalysisasdesignbases.**Delta-CPRresultsformostlimitingfueltype.
ANF-87-1Revision5.3AnalsesForReducedPower0erationReference9.6LimitingTransient(s):FeedwaterControllerFailure(FWCF)%PowerTransientDeltaCPRANF9x9GE8x8R104806540FWCFFWCFFWCFFWCF0.230.250.280.310.200.230.260.285.4ASMEOverressurizationAnalsisReference9.6LimitingEventWorstSingleFailureMaximumPressureMaximumSteamDomePressureFullMSIVIsolationDirectSera1297psig1281psig5.5ControlRodWithdrawalErrorCRWEStartingControlRodPatternforAnalysisFigure5.1RodBlockSettin105106*107108*100%FlowDistanceWithdrawn~ft4.04.55.05.0DeltaCPR0.220.240.260.26*RodBlockMonitorsettingsrecommendedforCycle3operation.
ANF-87-126Revision15.6FuelLoadinErrorMaximumDeltaCPR0.165.7DeterminationOfThermalHarinsSummaryofThermalMarginRequirementsEventLRWBFWCFLFWHCRWEPower1P0%**1PP%**1PP%9c*100%Flow100%100%100%100%DeltaCPR*0.240.230.160.24at106%RBH0.26at108%RBMMCPRLimit1.301.291.221.301.32HCPROperatingLimitsatRatedConditionsMCPR0eratinLimit1.30at106%RBM1.32at108%RBMReducedFlowMCPRLimitsFigure5.2PowerDependentHCPROperatingLimitResultsforCycle3:100*+/10080/10065/10040/100LimitingTransientLRWBFWCFFWCFFWCFANF9x91.301.311.341.37GE8x8R1.271.291.321.34,i*DeltaCPRresultsformostlimitingfueltype.**104%powerusedinanalysisasdesignbases.
10ANF-87-126Revision16.0POSTULATEDACCIDENTS6.1Loss-Of-CoolantAccidentSeismic-LOCA:AppendixB6.1.1BreakLocationSectrumReference9.86.1.2BreakSizeSectrumReference9.86.1.3MAPLHGRAnalsesANF9x9FuelReference9.9LimitingBreak:Double-endedguillotinepipebreakRecirculationpumpdischargeline0.4DischargeCoefficientBundleAverageExposureGWDMTU0510152025303540MAPLHGR~kwft10.210.210.210.210.29.68.98.27.5PeakCladTemperature*~F206020692121214021472016183917521676PeakLocalMWR**~Percent3.93.73.74.85.22.71.00.70.5*PeakcladtemperaturesforXN-1andXN-2fuelareboundedbytheseresults.**MetalWaterReaction.
llANF-87-1Revision6.2ControlRodDroAccidentSection8.0DroppedControlRodWorth,mkDopplerCoefficient,1/kdk/dTEffectiveDelayedNeutronFractionFour-BundleLocalPeakingFactormaximumDepositedFuelRodEnthalpy,cal/gmNumberofRodsExceeding170cal/gm13.5-10.6x(10)60.00581.34205(250 12ANF-87-126Revision17.0TECHNICALSPECIFICATIONS7.1LimitinSafetSstemSettins7.1.1MCPRFuelCladdinInteritSafetLimitMCPRSafetyLimit1.067.1.2SteamDomePressureSafetLimitPressureSafetyLimit(asmeasuredinsteamdome)1325psigAnalysisshowsthatasteamdomepressuresafetylimitof1358psigisallowedbutthe1325psigvalueusedinCycle2istobeconservativelyretained.7.2LimitinConditionsFor0eration7.2.1AveraePlanarLinearHeatGenerationRateLimitsBundleAverageExposureGWDMT0510152025303540MAPLHGRLimitskwftANF9x9Fuel10.210.210.210.210.29.68.98.27.5 13ANF-87-1Revision7.2.2MinimumCriticalPowerRatioMCPROperatingLimitsatRatedConditions:MCPR0eratinLimit1.30at106%RBM1.32at108%RBMMCPROperatingLimitsatOff-RatedConditions:AtReducedFlowFigure5.2TotalCoreRecirculationFlow%Rated10096928376605040ReducedFlowMCPR0eratinLimit1.121.141.161,201.231.311.441.61AtReducedPowerPowerLevel%Rated100*806540ReducedPowerMCPR0eratinLimit1.301.311.341.37*104%powerusedinanalysisasdesignbases.
ANF-87-126RevisionI7.2.3LHGRLimitsLHGRLimitsFigures3.3and3.4ofReference9.17.3SurveillanceReuirements7.3.1ScramInsertionTimeSurveillanceThermallimitsestablishedinSection5.0arebasedonminimumacceptablescraminsertionperformanceasdefinedintheTechnicalSpecifications.Noadditionalsurveillanceforscraminsertionisrequiredforvalidationofthermallimits..3.2StabilitSurveillance~~Power/FlowMapFigure4.4TheUnit2Cycle2TechnicalSpecificationsrequireAPRM/LPRMsurveillancetotheleftofthe45%ConstantFlowlineandabovethe80%RodBlockline.Basedoncorehydrodynamicstabilityanalyses,operationatpower/flowcombinationsaboveandtotheleftofthelineconnectingthe66%Power/45%Flowand69%Power/47%FlowpointsbutbelowtheAPRMRodBlocklineneedstobeaddedtotheAPRM/LPRMsurveillancerequirement(seeSection4.2.4).
15ANF-87-126Revision18.0METHODOLOGYREFERENCESSeeXN-NF-80-19(P)(A),Volume4,Revision1forcompletebibliography.
\q,"~r0~)644-I 16ANF-87-126Revision19.0ADDITIONALREFERENCES9.1"GenericMechanicalDesignforExxonNuclearJetPumpBWRReloadFuel,"~X---F,R.X,Addll1FXCFl,lhhld,Washington,September4,1986.9.2"ExxonNuclearMethodologyforBoilingWaterReactors,THERMEX:Thermal111<<Nhd1dPRevision2,AdvancedNuclearFuelsCorporation,Richland,Washington,January,1987.9.3"Demonstrationof9x9AssembliesforBWRs,"EPRINP-3468,ElectricPowerResearchInstitute,PaloAlto,California,Hay1,1984.9.4Letter,G.N.Ward(ANF)toG.C.Lainas(NRC),"AdditionalInformationonRodBow,"serialno.GNW:021:87,datedMarch11,1987.9.5"ExxonNuclearPlantTransientMethodologyforBoilingWaterReactors,"~h-p--,h11X,AddN1F1Cl,ltlhld,Washington,November16,1981.~~~9.6"SusquehannaUnit2Cycle3PlantTransientAnalysis,"ANF-87-125,Rev.2,AdvancedNuclearFuelsCorporation,Richland,Washington,November1987.9.79~8"XCOBRA-T:AComputerCodeforBWRTransientThermal-HydraulicCoreA1i,"X~,1>>d2,AdvancedNuclearFuelsCorporation,Richland,Washington,February1987."GenericLOCABreakSpectrumAnalysisBWR384withHodifiedLowPressureCoolantInjectionLogicUsingtheEXEHEvaluationModel,"XN-NF-~84-117P,AdvancedNuclearFuelsCorporation,Richland,Washington,December1984.9.9"SusquehannaLOCA-ECCSAnalysisHAPLHGRResultsforENC9x9Fuel,"XN-NF-86-65,AdvancedNuclearFuelsCorporation,Richland,Washington,May1986.9.10"PrincipalReloadFuelDesignParameters,FuelDesign,SusquehannaUnit2ReloadXN-2,"XN-NF-1058,AdvancedNuclearFuelsCorporation,Richland,Washington,March1987,FormerlyExxonNuclearCompany.
AdvancedNuclearFuels9x90~)O~IGeneralElectric8x8R~opcooCp0OIQ~oLIp0q>vCiI.>oooIK100.00.105.00TIO.OO115.M120.00125.00QO.MQ5.M140.00AssemblyFlowRate,KLB/HR0CO%5.00150.00Figure3.1SusquehannaUnit2Cycle3HydraulicOemandCurvePowervs.Flow 8070605000C)CLSo2010000.20.00.60.811.2RRDIFILPOHERPERKINGFigure3.2Susquehanna2Cycle3OesignBasisRadialPower 19ANF-87-126Revision1*~:0.88:0.91:0.96:1.04:1.02:1.04:0.96:1.00:0.96:*~**~:0.91:0.93:0.98:1.07:0.91:1.07:0.97:1.04:1.01*~**~0.96:0.98:0.90:1.04:1.03:1.04:1.04:0.99:0.96:**~1.04:1.07:1.04:1.00:0.99:1,00:1.05:0.94:1.04**~*:1.02:*~0.91:1.030.99:0.00:0.98:1.05:1.07:1.04*~*~1.04:1.07:1.04:1.00:0.98:0.00:1.03:0.94:1.05:0.96:0'7:1'4:1.05:1.05:1.03:1.06:1.00:0,971.00:1.04:0.99:0,94:1.07:0.94:1.00:0.941.010.96:1.01:0.96:1.04:1.04:1.05:0.97:1.010.97Figure3.3DesignBasisLocalPowerDistributionAdvancedNuclearFuelsXN-29X9Fuel 20ANF-87-1Revisio*~*~0.91:0.92:0.95:1.01:1.01:1.01:0.96:0.98:0.95*~*~*~0.92:0.94:0.98:0.97;1.05:0.95:0.99:0.95:0.98*~*~*~*0.95:0.98:0,93:1.06:1.05:1.06:1.05:0.97:0.96*~**1.01:0.97:1,06:1.03:1,03:1.04:1.07:1.06:1.02*~*~1.01:F05:1.05:1.03:0.00:1.01:1.07:1.06:1.01101'951.06:1.04:1.01:0F00:1.04:0.96:1.020.96:0.991.05:1.07:1.07:1.04:1.06:1.00:0.960.98:0.95:0.97:1.06:1.06:0.961.00:0.95:0.980.95:0.98:0.96:1.02:1.01:1.02:0.96:0.98:0.96Figure3.4DesignBasisLocalPowerDistributionAdvancedNuclearFuelsXN-19X9Fuel 21ANF-87-126Revision1**~*~1.03:1.00:1.00:1.00:F00:1.00:1.01:1.03*~*:1.00:0.98:1.00*~*1.02:1.02:1.03:1.00:1.01*~*:1.00*~**~1.00:1.01:1.01:1.01:0.90:1.03:1.00:*:1.00:1.02*~*1.01:0.89:0.00:1.01:1.02:1.00*~*:1.00*~1.021.01:0.00:0.89:1.01:0.99:1.00*~*:1.00*~*1.03:0.901.01:1.01:0.98:1.00:1.001.01:1.00:1.03:1.020.99:1.00:0.98:1.001.03:1.01:1.00:1.00:1.001.00:1.00:1.03Figure3.5DesignBasisLocalPowerDistributionGeneralElectric(Central)SXSRFuel 22ANF-87-'evisio*~1.00:1,00:1.00:1.00:1.00:1.00:1.00:1.00:*~0*~1.00:1.00:1.00:1.00:1.00:1.00:1.00:1.00:*~**~*100*~**~1.00;1.00:1.00:1.00:1.00:1.00:1.00:*:1.00:1.00**~1.00:1.00:0.00:1.00:1.001.00:1.00:1.00:1.00:0.00:1.00:1.00:1.001.00**100*~*1.00:1.00:1.001.00:1.00:1.00:1.001.00:1.00:1.00:1.00:1.00:1.00:1.00:1.00:1.00:1.00:1.00:1.00:1.00:1.00:1.00:1.00Figure3.6DesignBasisLocalPowerDistributionGeneralElectric(Peripheral)SXSRFuel 23ANF-87-126Revision1TABLE4.1NEUTRONICDESIGNVALUESFuelPelletReference9.10FuelRodReference9.10FuelAssemblReference9.10CoreDataNumberoffuelassembliesRatedthermalpower,HWRatedcoreflow,Hlbm/hrCoreinletsubcooling,Btu/ibmHoderatortemperature,FChannelthickness,inchFuelassemblypitch,inchWidewatergapthickness,inchNarrowwatergapthickness,inch'64329310024.0548.8.0806.000.5620.562ControlRodDataAbsorbermaterialTotalbladespan,inchTotalbladesupportspan,inchBladethickness,inchBladeface,-to-faceinternaldimension,inchAbsorberrodsperbladeAbsorberrodoutsidediameter,inchAbsorberrodinsidediameter,inchAbsorberdensity,%oftheoreticalB4C9.751.580.2600.200760.1880.13870.0 24ANF-87-126Revision**:LL:L:HL:M:N*H:HL:HL*~4HLM:MH:N*HHN*'HL*~*:HL*M".H*H:HO':HHH:HL**:H:HH:H:H:H*\H:HMH:N*:H:H:W:HH:H:HH*'A'~.*N:MH:HHNHW:MHH*HL:H*:MH:HHMH:MHHLHL:H:H:M~MH:H*:MMLMLL:HL:HL:HM:HL:HL-:LLLRODS(1)LRODS(5)HLRODS(16)HRODS(20)MHRODS(13)HRODS(15)H*RODS(9)WRODS(2)1.45W/0U2351.95W/0U2352.55W/0U2353.27W/0U2354.23W/0U2354.66W/0U2353.27W/0U235+4.00W/0GD203INERTWATERRODFigure4.1SusquehannaUnit2Cycle3EnrichmentDistributionfortheANF92-344L-9G4Xi4-2FuelLattice 25*************9:*0**********ANF-87-126Revision1*\*~LLoL:MLMMLNLL*~*~*~N*MLNH:M*:MH:M*ML'*.ML.N*M**H:HMHM:NL*~*o*~MHH:HH-H:HN*:M~JN*~HW:"MHH:MHt*'*~*~M:NH:HHMHW:NH:M*:MML:N~:MH:H:H:NH:NHM:MLML:M:N:M*:MH:M*:MMLML:ML:NL:MM:MLMLLLRODS(1)LRODS(5)MLRODS(16)MRODS(19)MHRODS(13)HRODS(15)M*RODS(10)WRODS(2)1.45W/0U2351.95W/0U2352.55W/0U2353.27W/0U2354,23W/0U2354.66W/0U2353.27'W/0U235+5.00W/0GD203INERTWATERRODigure4.2SusquehannaUnit2Cycle3EnrichmentDistributionfortheANF92-344L-IOG5XN-2FuelLattice 26ANF-87-12RevisioA2C1A2C1A2C1A2C1DOC1A2CiEOC1A2C1DOC1DOC1A2C1DOC1A2C1FOC1C1A2A2C1DOA2DOCiDOA200C1~DOC1EOC1A2C100A2DOCi0000A200C1EOC1C1A2A2C1DOC1A2C1DOC1DOA2DOC1EOC1A2C1A2C1DOO'IC1A2DOA2EOEOCiC1A2A2C100C100A2C1C100C1EOC1EOC1A2C100A2DOCiDOC1EOC1EOC100C1A2DOC100A200A200C1EOC1EOA282C1A2DOA2EOC1EOC1C1C1A2A2A2Ci00DOEOC1EOC1A2C1EO80CiEOC1DOA2A2EOC1EOCiEOC1EOC182A2C1C1C1CiC1C1C1A2A2A2A2A2A2A2A2XY=FuelTypeXBurnedYCycles~FuelTeHo.ofBuouieoDescritionA8C'E196832414096GEBX8TypeIII2.19w/oU~235GEBX8TypeII1.76M/oU.235XN.1ENC92.3318.7G4XN.2ANF92.333B.904XN.2ANF92.3338.10G5Figure4.3SusquehannaUnit2Cycle3ReferenceCoreI.eading 27ANF-87-126Revision1120110~~~~~~~~~~~~~~~~~~~~~~~~h~~~~~~~~~~~~~~~~~~~1009080N70~~~~~~APPMRODBLOCK:eAPRNSCRAMLIN)~~~~~~4~~~~~~~~~~~~~~rr~/r~~r~/er/~/e/~~~~~~~~~~~~~~~~)~66/45)err~(~~/e100/vXeR00.'IN~4~~~~~~~~~$~~~ROOBiOCK~MONITOR80WE50~~ee~I~I~el'45K80KeCOREPLOWR00LINE403020e~~~~e~e~~~~~~~~~4'P~~~~~~~e~~~~~'I~~~~~~~~~~~~~~~~~~~~~4~~~~~~~4~~~~~~4~~~e10NTCIRC~~~M'-PUMP)NFLOW;00102030405060708090COREFLOW,%RATED100Figure4.4SusquehannaUnit.2Cycle3-CorePowervs.CoreFlow 28ANF-87-12Revision595551261014182226303438424650545812--00--1220--26--26--205955514743----20--202000--12--08--12--0020474339--12--08--08-,-00--0808--123935----264444263531--00--04--00--00--0027----26444423--12--08--08--00*--'819----20--202004--002608--12203127191500--12--08--12--0020--26--26--2012--00--122610141822263034384246505458CycleExposureControlRodDensity0.0HHD/HTU23.3%ControlRodBeingWithdrawn=00*RodFullyInserted=,00RodFullyWithdrawn=--Figure5.1SusquehannaUnit2Cycle3ControlRodWithdrawalErrorAnalysisLimitingInitialControlRodPattern 1.601.601.40f41.30ONote:TheMCPRoperatinglimitshallbethemaximumofthiscurve,thefullflowMCPRoperatinglimitorthepoorerdependentMCPRoperatinglimit.A1.80OA1.10405060708090100TOTALCORERECIRCULATIONFLOW(%RATED)figure5.2SusquehannaUnit2Cycle3FlowMCPROperatingLimit Ah+C" A-1ANF-87-126Revision1APPENDIXAUSINGLELOOPOPERATIONThisAppendixprovideslimitsandjustificationofthoselimitsforSingleLoopOperation(SLO).A.lANTICIPATEDOPERATIONALOCCURRENCESReferenceA.1TheNSSSsupplierhasprovidedanalyseswhichdemonstratethesafetyofplantoperationwithasinglerecirculationloopoutofserviceforanextendedVperiodoftime.Theseanalysesrestricttheoveralloperationoftheplanttolowerbundlepowerlevelsandlowernodalpowerlevelsthanareallowed.whenothrecirculationsystemsareinoperation.Thephysicalinterdependencebetweencorepowerandrecirculationflowrateinherentlylimitsthecoretolessthanratedpower.ANFfuelwasdesignedtobecompatiblewiththeco-residentfuelinthermalhydraulic,nuclear,andmechanicaldesignperformance.TheANFmethodologyhasgivenresultswhichareconsistentwiththoseofpreviousanalysesfornormaltwo-loopoperation.ManyanalysesperformedbytheNSSSsupplierforsingleloopoperationarealsoapplicabletosingleloopoperationwithfuelandanalysesprovidedbyANF.Forsingleloopoperation,theNSSSvendorfoundthatanincreaseof0.01intheHCPRsafetylimitwasneededtoaccountfortheincreasedflowmeasurementuncertaintiesandincreasedtipuncertaintiesassociatedwithsinglepumpoperation.ANFhasevaluatedtheeffectsoftheincreasedflowmeasurementuncertaintiesonthesafetylimitHCPRandfoundthattheNSSSvendordeterminedincreaseintheallowedsafetylimitMCPRisalsoapplicabletoANFfuelduringsingleloopoperation.Thus,increasingthesafetylimitHCPRby0.01forsingleloopoperation(1.07)withANFfuelissufficientlyonservativetoalsoboundtheincreasedflowmeasurementuncertaintiesforsingleloopoperation.
A-2ANF-87-RevisioThelimitingMCPRoperatinglimitforsingleloopoperationisconservativelysetusingthelimitingpumpseizureaccidentdeltaCPRplusthesingleloopoperationHCPRsafetylimit.Thislimittogetherwiththe.HCPRfcurvefortwoloopoperationplus.OlandtheMCPRpcurvefortwoloopoperationplus.Olconservativelyboundalltransients.TheTechnicalSpecificationsrequireAPRH/LPRHsurveillancetotheleftofthe45%ConstantFlowlineandabovethe80%RodBlockline.BasedoncorehydrodynamicstabilityanalysesforCycle3,operationatpower/flowcombinationsaboveandtotheleftofthelineconnectingthe66%Power/45%Flowand69%Power/47%FlowpointsneedstobeaddedtotheAPRM/LPRMsurveillancerequirements.Figure4.4showsthecorepowerversuscoreflowestablishedforCycle3.
A-3ANF-87-126Revision1A.2POSTULATEDACCIDENTSReferenceA.2ANFperformedLOCAanalysesforsingleloopconditionsandhasdeterminedthattheMAPLHGRlimitcurve(Section7.2)fortwo-loopoperationisalsoapplicabletosingleloopoperationforANF9x9fuels.
A-4ANF-87-RevisioREFERENCESA.1"SusquehannaUnit2Cycle2SingleLoopOperationAnalysis,"XN-NF-86-146,AdvancedNuclearFuelsCorporation;Richland,WA99352,November1986.A.2"SusquehannaLOCAAnalysisforSingleLoopOperation,"XN-NF-86-125,AdvancedNuclearFuelsCorporation,Richland,WA99352,November1986.
B-1ANF-87-126RevisionIAPPENDIXBSEISMIC-LOCAEVALUATIONThestructuralresponseofAdvancedNuclearFuelsCorporation's(ANF's)9x9fuelissimilartothestructuralresponseoftheGEBxBRfuelitreplacesintheSusquehannaUnit2core.Therefore,theseismic-LOCAstructuralresponseevaluationperformedinsupportoftheinitialcoreremainsapplicableandcontinuestoprovideassurancethatcontrolbladeinsertionwillnotbeinhibitedfollowingtheoccurrenceofthedesignbasisseismic-LOCAevent.Thephysicalandstructuralpropertiesofthe9x9andtheBx8fueltypeswhichareimportanttothedynamicresponseofthefuelaresummarizedinTableB.l.hecloseagreementbetweentheimportantparametersfortheANF9x9andGEx8Rfueltypesindicatesthatthestructuralresponsewouldbeverysimilarforbothfueltypes.Similarityinthenaturalfrequenciesofthetwofueltypesmentionedaboveisfurtherassuredbythestiffnessofthefuelassemblychannelbox.Bothfueltypesusethesamefuelassemblychannelbox,andthechannelboxdominatestheoveralldynamicresponseoftheincorefuel.ANFcalculationsshowthatapproximately97%ofthestiffnessofafuelassemblyisattributabletothestiffnessofthechannelbox.Forthisreason,thedynamicstructuralresponseofthereloadcoreisessentiallythatoftheinitialcore,andtheoriginalseismic-LOCAanalysisremainsapplicable.Deformationofthechanneltothepointthatcontrolbladeinsertionisinhibitedisnotpredictedtooccur.
B-2ANF-87-RevisioTABLEB.1COMPARISONOFPHYSICALANDSTRUCTURALCHARACTERISTICSFOR8X8AND9X9FUELASSEMBLIES~ProertAssemblyWeight,lbsNumberofSpacersOverallAssemblyLength,inAssemblyFrequencies,cpsMode123567ANF9x9580171.291.93.76.510.415.521.929.1FuelTesGE8x8R600171.40*GEproprietary ANF-87-126Revision1IssueDate:11/25/87SUS(UEHANNAUNIT2CYCLE3RELOADANALYSISDesignandSafetyAnalysesDistribution:D.D.R.L.S.R.K.H.S.T.J.L.D.G.C.J.H.A.AdkissonJ.BraunE.CollinghamJ.FedericoF.GainesG.GrummerD.HartleyJ.HibbardE.JensenH.KeheleyN.MorganA.NielsenF.RicheyL.RitterJ.VolmerADWhiteE.WilliamsonH.G.Shaw/PP8L(20)DocumentControl(5)