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~MHCSDo HUCIt.EAR FUSMCORPORATION SUSQUEHANNA UNIT2CYCLE3RELOADANALYSISDESIGNANDSAFETYANALYSES.
NOVEMBER198787i2310i58 87i223PORADOCK0500058]~ANAFFII.IATE OFKRAFTWERKUNIONQ~KRU ADVANCEDNUCLEARFUELSCORPORATION ANF-87-126 Revision1IssueDate:11/25/87SUSQUEHANNA UNIT2CYCLE3RELOADANALYSISDesignandSafetyAnalysesPreparedBy:J.A.WhiteBWRSafetyAnalysisLicensing andSafetyEngineering FuelEngineering andTechnical ServicesAIIAFFILIATE OFKRAFTWERK UNIONQxsvu CUSTOMERDISCLAIMER IMPORTANT NOTICEREGARDING CONTENTSANDUSEOFTHISDOCUMENTPLEASEREADCAREFULLY AdvancedNuclearFuelsCorporation's warranties andrepresentations con-cemingthesubjectmatterofthisdocumentarethosesetforthintheAgreement betweenAdvancedNuclearFuelsCorporation andtheCustomerpursuanttowhichthisdocumentisissued.Accordingly, exceptasotherwise expressly pro-videdInsuchAgreement, neitherAdvancedNuclearFuelsCorporation noranypersonactingonitsbehalfmakesanywarrantyorrepresentation, expressed orimplied,withrespecttotheaccuracy, completeness, orusefulness oftheinfor-mationcontained Inthisdocument, orthattheuseofanyinformation, apparatus, methodorprocessdisclosed lnthisdocumentwillnotinfringeprivately ownedrights:orassumesanyliabilities withrespecttotheuseofanyinformation, ap-paratus,methodorprocessdisclosed inthisdocument.
Theinformation contained hereinisforthesoleuseofCustomer.
InordertoavoidImpairment ofrightsofAdvancedNuclearFuelsCorporation inpatentsorinventions whichmaybeincludedintheinformation contained inthisdocument, therecipient, byitsacceptance ofthisdocument, agreesnottopublishormakepublicuse(inthepatentuseoftheterm)ofsuchinformation untilsoauthorized inwritingbyAdvancedNuclearFuelsCorporation oruntilaftersix(6)monthsfollowing termination orexpiration oftheaforesaid Agreement andanyextension thereof,unlessotherwise expressly providedintheAgreement.
NorightsorlicensesInortoanypatentsareimpliedbythefurnishing ofthisdocu-ment.XNNFF00.765(1 ANF-87-126 Revision1TABLEOFCONTENTSSection1.02.0PacaeINTRODUCTION.
~..............,....,................................
1FUELMECHANICAL DESIGNANALYSIS...................................
23.03.23.2.13.2.33.2.5THERMALHYDRAULIC DESIGNANALYSIS..............
~..................
3HydraulicCharacteri zation........................................
3HydraulicCompatibility...........................................
3FuelCenterline Temperature.......................................
3BypassFlowe~~~~~~~~~~~~~~~~~~~~~~~~\~~~~~~~~~~~~~~~~~~~~~~~~~~~~33.33.3.13.3.2.3.34.0MCPRFuelCladdingIntegrity SafetyLimit...........
CoolantThermodynamic Conditions DesignBasisRadialPowerDistribution.
DesignBasisLocalPowerDistribution.
NUCLEARDESIGNANALYSIS..
~~~~~~~~~0~~~~33~~~~~~~~~~~~~4~~~~~~~\~~~~~~~~~~~~~~~54.14.24.2.14.2.24.2.45.0FuelBundleNuclearDesignAnalysis.......
CoreNuclearDesignAnalysisCoreConfiguration.......
CoreReactivity Characteristics...,....,..
CoreHydrodynamic Stability.....
~.ANTICIPATED OPERATIONAL OCCURRENCES......,
~~~~~~~~~~~~~~~~~~~~~~~~5~~~~~~~556~~~~~~~~~~~~~~~~~~~~~~~~75.15.25.35.45.55.65.76.06.1F1.1itlons~~~~~~~~~7~~~~~~~~~~~~~~~~~~~~~~~~7~~~~~~~~~~~~~~~~~~~~~~~~8~~~~~~~~~~~~~~~~~~~~~~~~8~~~~~~~~~~~~~~~~~~~~~~~~9~~~~~~~~~~~~~~~~~~~~~~~~91010Loss-Of-Coolant Accident....,,......
BreakLocationSpectrum........
10AnalysisOfPlantTransients AtRatedCondAnalysesForReducedFlowOperation.......
AnalysesForReducedPowerOperation......
ASMEOverpressurization Analysis..........
ControlRodWithdrawal Error(CRWE)FuelLoadingError........
Determination OfThermalMargins..........
POSTULATED ACCIDENTS...
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......
HCPRFuelCladdingIntegrity SafetyLSteamDomePressureSafetyLimitLimitingConditions ForOperation.
AveragePlanarLinearHeatGeneration MinimumCriticalPowerRatio~~~~~~~~~~~~~~~~~~~~~~~~~~~~~imitRateimits.................
L'HGRLlmlts~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~o~~~~~~~Surveillance Requirements......
.....ScramInsertion TimeSurveillance....
Stability Surveillance..........
METHODOLOGY REFERENCES..........
9.0 ADDITIONAL
REFERENCES.......
reakSizeSpectrum...............................................
BAPLHGRAnalyses.............................'.....................
HControlRodDropAccident........,...
TECHNICAL SPECIFICATIONS........
Pacae101011121212121212111414141516APPENDICES A.SINGLELOOPOPERATION.............
A-1B.SEISMIC-LOCA EVALUATION....,.................,.........,..........
B-1 ANF-87-126 Revision1LISTOFTABLESTablePacae4.1Neutronic DesignValues...........................................
23B.1Comparison OfPhysicalAndStructural Characteristics For8x8And9x9FuelAssemblies.........................
.....B-2LISTOFFIGURESFiciure3.1Susquehanna Unit2Powervs.Flow....Cycle3Hydraulic DemandCurvePacae173.23.33.5Susquehanna Unit2DesignBasisLocalDesignBasisLocalDesignBasisLocalFuel.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~~~~Susquehanna Unit2Cycle3Enrichment Distribution ForANF92-344L-9G4 XN-2FuelLattice.Susquehanna Unit2Cycle3Enrichment Distribution ForANF92-344L-10G5 XN-2FuelLattice.Susquehanna Unit2Cycle3Reference CoreLoadingPlan...Susquehanna Unit2Cycle3-CorePowervs.CoreFlow......
Susquehanna Unit2Cycle3ControlRodWithdrawal ErrorAnalysisLimitingInitialControlRodPattern..
Susquehanna Unit2Cycle3FlowMCPROperating Limit.......
~fj ANF-87-126 Revision
11.0INTRODUCTION
Thisreportprovidestheresultsoftheanalysesperformed byAdvancedNuclearFuelsCorporation (ANF)*insupportoftheCycle3reloadforSusquehanna Unit2,whichisscheduled tocommenceoperation inthespringof1988.Thisreportisintendedtobeusedinconjunction withANFtopicalreport~XN-Np--191A,914,R111,Nppti1111NCompanyMethodology toBWRReloads,"
whichdescribes theanalysesperformed insupportofthisreload,identifies themethodology usedforthoseanalyses, andprovidesagenericreference list.However,LHGRmechanical designlimits(Reference 9.1)andplanttransient simulation modeldevelopments (Reference 9.141b1dbyANFb4tNRNP1F~F-Volume4,Revi'sion 1.BothReferences 9.1and9.2havebeenapprovedbytheNRCforuseinreferencing inlicenseapplications.
Sectionnumbersinthis9t19dtdttb1X-N--fNJ,olume4,Revision1.TheSusquehanna Unit2Cycle3corewillcompriseatotalof764fuelassemblies, including 236unirradiated ANFXN-29x9assemblies, 324irradiated ANFXN-19x9assemblies, 112irradiated GeneralElectric8x8Rfuelassemblies (centralregion),and92irradiated GE8x8Rassemblies intheperipheral region.Thereference coreconfiguration isdescribed inSection4.2.Thedesignandsafetyanalysesreportedinthisdocumentwerebasedonthedesignandoperational assumptions ineffectforSusquehanna Unit2duringthepreviousoperating cycle.Additional information andtheresultsofdesignstudiescoveringthedevelopment of9x9fuelassemblies forBWRreloadsarecontained inReference 9.3.
f ANF-87-126 Revision12.0FUELMECHANICAL DESIGNANALYSISApplicable ANFFuelDesignReport:Reference 9.1Toassurethattheexpectedpowerhistoryforthefuelstobeirradiated duringCycle3ofSusquehanna Unit2isboundedbytheassumedpowerhistoryinthefuelmechanical designanalysis, LHGRoperating limits(Figure3.3ofReference 9.1)havebeenspecified.
Inaddition, anLHGRtransient operating'imit forAnticipated Operating Occurrences (Figure3.4ofReference 9.1)hasbeenspecified forANF9x9fuel.Additional information onrodbow,asrequested intheNRC'ssafetyevaluation reportforReference 9.1,hasbeentransmitted inReference 9.4.
ANF-87-126 Revision13.0THERMALHYDRAULIC DESIGNANALYSIS3.2HdraulicCharaeterization3.2.1HdraulicComatibilitComponent hydraulic resistances fortheconstituent fueltypesintheSusquehanna Unit2Cycle3corehavebeendetermined insinglephaseflowtestsoffullscaleassemblies.
Figure3.1showsthehydraulic demandcurvesforANF9x9fuelandGE8x8RfuelintheSusquehanna Unit2core.Thesimilarhydraulic performance indicates compatibility forco-residence in'heSusquehanna Unit2core.Applicable GenericReport3.2'FuelCenterline Temerature~~Reference 9.1.2.2~21Calculated BypassFlowFractionat104%Power/100%
Flow10.1%3.3MCPRFuelCladdinInteritSafetLimitSafetyLimitMCPR=1.063.3.1CoolantThermodnamicCondition RatedThermalPowerFeedwater Flowrate(atSLMCPR)CorePressure(atSLMCPR)Feedwater Temperature 3293Mwt16.1Mlbm/hr1042.9psia383'F ANF-87-1Revision3.3.2DesinBasisRadialPowerDistribution SeeFigure3.23.3.3DesinBasisLocalPowerDistribution SeeFigures3.3through3.6 ANF-87-126 Revision14.0NUCLEARDESIGNANALYSIS4.1FueBundeNucleaDesinAnalsisAssemblyAverageEnrichment RadialEnrichment Distribution AxialEnrichment Distribution BurnablePoisonsNote:Burnablepoisonsaredistributed uniformly overtheenrichedlengthofthedesignated rods.Thenaturaluraniaaxialblanketsectionsdonotcontainburnableabsorbermaterial.
Non-Fueled RodsNeutronic DesignParameters 3.33%Figure4.1and4.2Uniform3.44%with6"naturaluraniumtopblanketFigure4.1and4.2Figure4.1and4.2Table4.14.2CoreNuclearDesinAnalsis';2.1CoreConfiorationFigure4.3CoreExposureatEOC2,HWd/HTUCoreExposureatBOC3,MWd/HTUCoreExposureatEOC3,HWd/MTUMaximumCycle3Licensing ExposureLimit,HWd/MTU18350.710911.221740.822076 ANF-87-12 Revision4.2.2oreReactiv't Characteris icsBOCColdK-effective, AllRodsOutBOCColdK-effective, Strongest RodOut1.113530.98524Reactivity Defect(R-Value) 0.00%rho4.2.4StandbyLiquidControlSystemReactivity, ColdConditions, 660ppmICoreHdrodnamicStabilit0.98348Power/flow MapFigure4.4PowerFlowStatePoints64/42*69/47**66/45**DecaRatioCOTRA0.820.750.75*Twopumpminimumflow-APRNRodBlockintercept point.Extendedoperation atlowerflowisnotallowedbyTechnical Specifications.
- Operation atlessthan45%flowrequiresAPRH/LPRN surveillance.
Inaddition, operation atpower/flow, combinations aboveandtotheleftofthelineconnecting thesetwopointsrequiresAPRH/LPRtl surveillance.
SeeFigbre4.4.
ANF-87-126 Revision15.0ANTICIPATED OPERATIONAL OCCURRENCES Applicable GenericTransient AnalysisMethodology ReportReferences 9.559.75.1AnalsisOfPlantTransients AtRatedConditions Reference 9.6LimitingTransient(s):
LoadRejection WithoutBypass(LRWB)Feedwater Controller Failure(FWCF)LossofFeedwater Heating(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:
AppendixA5.2AnalsesForReducedFlow0erationReference 9.6LimitingTransient(s):
Recirculation FlowIncreaseTransient (RFIT)*104%powerusedinanalysisasdesignbases.**Delta-CPR resultsformostlimitingfueltype.
ANF-87-1Revision5.3AnalsesForReducedPower0erationReference 9.6LimitingTransient(s):
Feedwater Controller Failure(FWCF)%PowerTransient DeltaCPRANF9x9GE8x8R104806540FWCFFWCFFWCFFWCF0.230.250.280.310.200.230.260.285.4ASMEOverressurization AnalsisReference 9.6LimitingEventWorstSingleFailureMaximumPressureMaximumSteamDomePressureFullMSIVIsolation DirectSera1297psig1281psig5.5ControlRodWithdrawal ErrorCRWEStartingControlRodPatternforAnalysisFigure5.1RodBlockSettin105106*107108*100%FlowDistanceWithdrawn
~ft4.04.55.05.0DeltaCPR0.220.240.260.26*RodBlockMonitorsettingsrecommended forCycle3operation.
ANF-87-126 Revision15.6FuelLoadinErrorMaximumDeltaCPR0.165.7Determination OfThermalHarinsSummaryofThermalMarginRequirements EventLRWBFWCFLFWHCRWEPower1P0%**1PP%**1PP%9c*100%Flow100%100%100%100%DeltaCPR*0.240.230.160.24at106%RBH0.26at108%RBMMCPRLimit1.301.291.221.301.32HCPROperating LimitsatRatedConditions MCPR0eratinLimit1.30at106%RBM1.32at108%RBMReducedFlowMCPRLimitsFigure5.2PowerDependent HCPROperating LimitResultsforCycle3:100*+/100 80/10065/10040/100LimitingTransient LRWBFWCFFWCFFWCFANF9x91.301.311.341.37GE8x8R1.271.291.321.34,i*DeltaCPRresultsformostlimitingfueltype.**104%powerusedinanalysisasdesignbases.
10ANF-87-126 Revision16.0POSTULATED ACCIDENTS 6.1Loss-Of-Coolant AccidentSeismic-LOCA:AppendixB6.1.1BreakLocationSectrumReference 9.86.1.2BreakSizeSectrumReference 9.86.1.3MAPLHGRAnalsesANF9x9FuelReference 9.9LimitingBreak:Double-ended guillotine pipebreakRecirculation pumpdischarge line0.4Discharge Coefficient BundleAverageExposureGWDMTU0510152025303540MAPLHGR~kwft10.210.210.210.210.29.68.98.27.5PeakCladTemperature*
~F206020692121214021472016183917521676PeakLocalMWR**~Percent3.93.73.74.85.22.71.00.70.5*Peakcladtemperatures forXN-1andXN-2fuelareboundedbytheseresults.**MetalWaterReaction.
llANF-87-1Revision6.2ControlRodDroAccidentSection8.0DroppedControlRodWorth,mkDopplerCoefficient, 1/kdk/dTEffective DelayedNeutronFractionFour-Bundle LocalPeakingFactormaximumDeposited FuelRodEnthalpy, cal/gmNumberofRodsExceeding 170cal/gm13.5-10.6x(10)60.00581.34205(250 12ANF-87-126 Revision17.0TECHNICAL SPECIFICATIONS 7.1LimitinSafetSstemSettins7.1.1MCPRFuelCladdinInteritSafetLimitMCPRSafetyLimit1.067.1.2SteamDomePressureSafetLimitPressureSafetyLimit(asmeasuredinsteamdome)1325psigAnalysisshowsthatasteamdomepressuresafetylimitof1358psigisallowedbutthe1325psigvalueusedinCycle2istobeconservatively retained.
7.2LimitinConditions For0eration7.2.1AveraePlanarLinearHeatGeneration RateLimitsBundleAverageExposureGWDMT0510152025303540MAPLHGRLimitskwftANF9x9Fuel10.210.210.210.210.29.68.98.27.5 13ANF-87-1Revision7.2.2MinimumCriticalPowerRatioMCPROperating LimitsatRatedConditions:
MCPR0eratinLimit1.30at106%RBM1.32at108%RBMMCPROperating LimitsatOff-Rated Conditions:
AtReducedFlowFigure5.2TotalCoreRecirculation Flow%Rated10096928376605040ReducedFlowMCPR0eratinLimit1.121.141.161,201.231.311.441.61AtReducedPowerPowerLevel%Rated100*806540ReducedPowerMCPR0eratinLimit1.301.311.341.37*104%powerusedinanalysisasdesignbases.
ANF-87-126 RevisionI7.2.3LHGRLimitsLHGRLimitsFigures3.3and3.4ofReference 9.17.3Surveillance Reuirements 7.3.1ScramInsertion TimeSurveillance Thermallimitsestablished inSection5.0arebasedonminimumacceptable scraminsertion performance asdefinedintheTechnical Specifications.
Noadditional surveillance forscraminsertion isrequiredforvalidation ofthermallimits..3.2StabilitSurveillance
~~Power/Flow MapFigure4.4TheUnit2Cycle2Technical Specifications requireAPRM/LPRM surveillance totheleftofthe45%ConstantFlowlineandabovethe80%RodBlockline.Basedoncorehydrodynamic stability
- analyses, operation atpower/flow combinations aboveandtotheleftofthelineconnecting the66%Power/45%
Flowand69%Power/47%
FlowpointsbutbelowtheAPRMRodBlocklineneedstobeaddedtotheAPRM/LPRM surveillance requirement (seeSection4.2.4).
15ANF-87-126 Revision18.0METHODOLOGY REFERENCES SeeXN-NF-80-19(P)(A),
Volume4,Revision1forcompletebibliography.
\q,"~r0~)644-I 16ANF-87-126 Revision19.0ADDITIONAL REFERENCES 9.1"GenericMechanical DesignforExxonNuclearJetPumpBWRReloadFuel,"~X---F,R.X,Addll 1FXCFl,lhhld,Washington, September 4,1986.9.2"ExxonNuclearMethodology forBoilingWaterReactors, THERMEX:Thermal111<<Nhd1dPRevision2,AdvancedNuclearFuelsCorporation,
- Richland, Washington, January,1987.9.3"Demonstration of9x9Assemblies forBWRs,"EPRINP-3468,ElectricPowerResearchInstitute, PaloAlto,California, Hay1,1984.9.4Letter,G.N.Ward(ANF)toG.C.Lainas(NRC),"Additional Information onRodBow,"serialno.GNW:021:87, datedMarch11,1987.9.5"ExxonNuclearPlantTransient Methodology forBoilingWaterReactors,"
~h-p--,h11X,AddN1F1C l,ltlhld,Washington, November16,1981.~~~9.6"Susquehanna Unit2Cycle3PlantTransient Analysis,"
ANF-87-125,Rev.2,AdvancedNuclearFuelsCorporation,
- Richland, Washington, November1987.9.79~8"XCOBRA-T:
AComputerCodeforBWRTransient Thermal-Hydraulic CoreA1i,"X~,1>>d2,AdvancedNuclearFuelsCorporation,
- Richland, Washington, February1987."GenericLOCABreakSpectrumAnalysisBWR384withHodifiedLowPressureCoolantInjection LogicUsingtheEXEHEvaluation Model,"XN-NF-~84-117P,AdvancedNuclearFuelsCorporation,
- Richland, Washington, December1984.9.9"Susquehanna LOCA-ECCS AnalysisHAPLHGRResultsforENC9x9Fuel,"XN-NF-86-65,AdvancedNuclearFuelsCorporation,
- Richland, Washington, May1986.9.10"Principal ReloadFuelDesignParameters, FuelDesign,Susquehanna Unit2ReloadXN-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%5.00150.00Figure3.1Susquehanna Unit2Cycle3Hydraulic OemandCurvePowervs.Flow 8070605000C)CLSo2010000.20.00.60.811.2RRDIFILPOHERPERKINGFigure3.2Susquehanna 2Cycle3OesignBasisRadialPower 19ANF-87-126 Revision1*~: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*~*~1.04:1.07:1.04:1.00:0.98:0.00:1.03:0.94:1.05:0.96:0'7:1'4:1.05:1.05:1.03:1.06:1.00:0,971.00:1.04:0.99:0,94:1.07:0.94:1.00:0.941.010.96:1.01:0.96:1.04:1.04:1.05:0.97:1.010.97Figure3.3DesignBasisLocalPowerDistribution AdvancedNuclearFuelsXN-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:F05:1.05:1.03:0.00:1.01:1.07:1.06:1.01101'951.06:1.04:1.01:0F00:1.04:0.96:1.020.96:0.991.05:1.07:1.07:1.04:1.06:1.00:0.960.98:0.95:0.97:1.06:1.06:0.961.00:0.95:0.980.95:0.98:0.96:1.02:1.01:1.02:0.96:0.98:0.96Figure3.4DesignBasisLocalPowerDistribution AdvancedNuclearFuelsXN-19X9Fuel 21ANF-87-126 Revision1**~*~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*~*1.03:0.901.01:1.01:0.98:1.00:1.001.01:1.00:1.03:1.020.99:1.00:0.98:1.001.03:1.01:1.00:1.00:1.001.00:1.00:1.03Figure3.5DesignBasisLocalPowerDistribution GeneralElectric(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*~*1.00:1.00:1.001.00:1.00:1.00:1.001.00:1.00:1.00:1.00:1.00:1.00:1.00:1.00:1.00:1.00:1.00:1.00:1.00:1.00:1.00:1.00Figure3.6DesignBasisLocalPowerDistribution GeneralElectric(Peripheral)
SXSRFuel 23ANF-87-126 Revision1TABLE4.1NEUTRONIC DESIGNVALUESFuelPelletReference 9.10FuelRodReference 9.10FuelAssemblReference 9.10CoreDataNumberoffuelassemblies Ratedthermalpower,HWRatedcoreflow,Hlbm/hrCoreinletsubcooling, Btu/ibmHoderator temperature, FChannelthickness, inchFuelassemblypitch,inchWidewatergapthickness, inchNarrowwatergapthickness, inch'64329310024.0548.8.0806.000.5620.562ControlRodDataAbsorbermaterialTotalbladespan,inchTotalbladesupportspan,inchBladethickness, inchBladeface,-to-face internaldimension, inchAbsorberrodsperbladeAbsorberrodoutsidediameter, inchAbsorberrodinsidediameter, inchAbsorberdensity,%oftheoretical B4C9.751.580.2600.200760.1880.13870.0 24ANF-87-126 Revision**: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/0GD203INERTWATERRODFigure4.1Susquehanna Unit2Cycle3Enrichment Distribution fortheANF92-344L-9G4 Xi4-2FuelLattice 25*************
9:*0**********
ANF-87-126 Revision1*\*~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/0GD203INERTWATERRODigure4.2Susquehanna Unit2Cycle3Enrichment Distribution fortheANF92-344L-IOG5 XN-2FuelLattice 26ANF-87-12 RevisioA2C1A2C1A2C1A2C1DOC1A2CiEOC1A2C1DOC1DOC1A2C1DOC1A2C1FOC1C1A2A2C1DOA2DOCiDOA200C1~DOC1EOC1A2C100A2DOCi0000A200C1EOC1C1A2A2C1DOC1A2C1DOC1DOA2DOC1EOC1A2C1A2C1DOO'IC1A2DOA2EOEOCiC1A2A2C100C100A2C1C100C1EOC1EOC1A2C100A2DOCiDOC1EOC1EOC100C1A2DOC100A200A200C1EOC1EOA282C1A2DOA2EOC1EOC1C1C1A2A2A2Ci00DOEOC1EOC1A2C1EO80CiEOC1DOA2A2EOC1EOCiEOC1EOC182A2C1C1C1CiC1C1C1A2A2A2A2A2A2A2A2XY=FuelTypeXBurnedYCycles~FuelTeHo.ofBuouieoDescritionA8C'E196832414096GEBX8TypeIII2.19w/oU~235GEBX8TypeII1.76M/oU.235XN.1ENC92.3318.7G4 XN.2ANF92.333B.904 XN.2ANF92.3338.
10G5Figure4.3Susquehanna Unit2Cycle3Reference CoreI.eading 27ANF-87-126 Revision1120110~~~~~~~~~~~~~~~~~~~~~~~~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,%RATED100Figure4.4Susquehanna Unit.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
=--Figure5.1Susquehanna Unit2Cycle3ControlRodWithdrawal ErrorAnalysisLimitingInitialControlRodPattern 1.601.601.40f41.30ONote:TheMCPRoperating limitshallbethemaximumofthiscurve,thefullflowMCPRoperating limitorthepoorerdependent MCPRoperating limit.A1.80OA1.10405060708090100TOTALCORERECIRCULATION FLOW(%RATED)figure5.2Susquehanna Unit2Cycle3FlowMCPROperating Limit Ah+C" A-1ANF-87-126 Revision1APPENDIXAUSINGLELOOPOPERATION ThisAppendixprovideslimitsandjustification ofthoselimitsforSingleLoopOperation (SLO).A.lANTICIPATED OPERATIONAL OCCURRENCES Reference A.1TheNSSSsupplierhasprovidedanalyseswhichdemonstrate thesafetyofplantoperation withasinglerecirculation loopoutofserviceforanextendedVperiodoftime.Theseanalysesrestricttheoveralloperation oftheplanttolowerbundlepowerlevelsandlowernodalpowerlevelsthanareallowed.whenothrecirculation systemsareinoperation.Thephysicalinterdependence betweencorepowerandrecirculation flowrateinherently limitsthecoretolessthanratedpower.ANFfuelwasdesignedtobecompatible withtheco-residentfuelinthermalhydraulic, nuclear,andmechanical designperformance.
TheANFmethodology hasgivenresultswhichareconsistent withthoseofpreviousanalysesfornormaltwo-loopoperation.
Manyanalysesperformed bytheNSSSsupplierforsingleloopoperation arealsoapplicable tosingleloopoperation withfuelandanalysesprovidedbyANF.Forsingleloopoperation, theNSSSvendorfoundthatanincreaseof0.01intheHCPRsafetylimitwasneededtoaccountfortheincreased flowmeasurement uncertainties andincreased tipuncertainties associated withsinglepumpoperation.
ANFhasevaluated theeffectsoftheincreased flowmeasurement uncertainties onthesafetylimitHCPRandfoundthattheNSSSvendordetermined increaseintheallowedsafetylimitMCPRisalsoapplicable toANFfuelduringsingleloopoperation.
Thus,increasing thesafetylimitHCPRby0.01forsingleloopoperation (1.07)withANFfuelissufficiently onservative toalsoboundtheincreased flowmeasurement uncertainties forsingleloopoperation.
A-2ANF-87-RevisioThelimitingMCPRoperating limitforsingleloopoperation isconservatively setusingthelimitingpumpseizureaccidentdeltaCPRplusthesingleloopoperation HCPRsafetylimit.Thislimittogetherwiththe.HCPRfcurvefortwoloopoperation plus.OlandtheMCPRpcurvefortwoloopoperation plus.Olconservatively boundalltransients.
TheTechnical Specifications requireAPRH/LPRH surveillance totheleftofthe45%ConstantFlowlineandabovethe80%RodBlockline.Basedoncorehydrodynamic stability analysesforCycle3,operation atpower/flow combinations aboveandtotheleftofthelineconnecting the66%Power/45%
Flowand69%Power/47%
FlowpointsneedstobeaddedtotheAPRM/LPRM surveillance requirements.
Figure4.4showsthecorepowerversuscoreflowestablished forCycle3.
A-3ANF-87-126 Revision1A.2POSTULATED ACCIDENTS Reference A.2ANFperformed LOCAanalysesforsingleloopconditions andhasdetermined thattheMAPLHGRlimitcurve(Section7.2)fortwo-loopoperation isalsoapplicable tosingleloopoperation forANF9x9fuels.
A-4ANF-87-RevisioREFERENCES A.1"Susquehanna Unit2Cycle2SingleLoopOperation Analysis,"
XN-NF 146,AdvancedNuclearFuelsCorporation;
- Richland, WA99352,November1986.A.2"Susquehanna LOCAAnalysisforSingleLoopOperation,"
XN-NF-86-125, AdvancedNuclearFuelsCorporation,
- Richland, WA99352,November1986.
B-1ANF-87-126 RevisionIAPPENDIXBSEISMIC-LOCAEVALUATION Thestructural responseofAdvancedNuclearFuelsCorporation's (ANF's)9x9fuelissimilartothestructural responseoftheGEBxBRfuelitreplacesintheSusquehanna Unit2core.Therefore, theseismic-LOCA structural responseevaluation performed insupportoftheinitialcoreremainsapplicable andcontinues toprovideassurance thatcontrolbladeinsertion willnotbeinhibited following theoccurrence ofthedesignbasisseismic-LOCA event.Thephysicalandstructural properties ofthe9x9andtheBx8fueltypeswhichareimportant tothedynamicresponseofthefuelaresummarized inTableB.l.hecloseagreement betweentheimportant parameters fortheANF9x9andGEx8Rfueltypesindicates thatthestructural responsewouldbeverysimilarforbothfueltypes.Similarity inthenaturalfrequencies ofthetwofueltypesmentioned aboveisfurtherassuredbythestiffness ofthefuelassemblychannelbox.Bothfueltypesusethesamefuelassemblychannelbox,andthechannelboxdominates theoveralldynamicresponseoftheincorefuel.ANFcalculations showthatapproximately 97%ofthestiffness ofafuelassemblyisattributable tothestiffness ofthechannelbox.Forthisreason,thedynamicstructural responseofthereloadcoreisessentially thatoftheinitialcore,andtheoriginalseismic-LOCA analysisremainsapplicable.
Deformation ofthechanneltothepointthatcontrolbladeinsertion isinhibited isnotpredicted tooccur.
B-2ANF-87-RevisioTABLEB.1COMPARISON OFPHYSICALANDSTRUCTURAL CHARACTERISTICS FOR8X8AND9X9FUELASSEMBLIES
~ProertAssemblyWeight,lbsNumberofSpacersOverallAssemblyLength,inAssemblyFrequencies, cpsMode123567ANF9x9580171.291.93.76.510.415.521.929.1FuelTesGE8x8R600171.40*GEproprietary ANF-87-126 Revision1IssueDate:11/25/87SUS(UEHANNA UNIT2CYCLE3RELOADANALYSISDesignandSafetyAnalysesDistribution:
D.D.R.L.S.R.K.H.S.T.J.L.D.G.C.J.H.A.AdkissonJ.BraunE.Collingham J.FedericoF.GainesG.GrummerD.HartleyJ.HibbardE.JensenH.KeheleyN.MorganA.NielsenF.RicheyL.RitterJ.VolmerADWhiteE.Williamson H.G.Shaw/PP8L (20)DocumentControl(5)