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| {{#Wiki_filter:DEMONSTRATIONOFTHECONFORMANCEOFEXXONNUCLEARCOMPANYFUELTOTHEWESTINGHOUSEK(Z)OPERATINGENVELOPEFORTHEROBERTE.GINNANUCLEARPOWERPLANTWestinghouseElectricCorporationNuclearTechnologyDivisionNuclearSafetyDepartmentSafeguardsEngineeringandDevelopmentSeptember19858512200249851216PDRADOCK05000244',P'DR I.ntroductionThisdocumentreportstheresultsofasensitivitystudythatwasperformedinordertodemonstrateconformanceofExxonNuclearCompanynuclearfuelintheRobertE.GinnanuclearpowerplanttotheWestinghouseK(z)operatingenvelope.Inparticular,theresultsof.thisanalysisshowthatforskewedtothetoppowershapes,inadditiontothepowershapepeakedatthemid-coreelevation,thattheworstpeakcladdingtemperature(PCT)intheunlikelyeventofaLoss-Of-Coolant-Accident(LOCA)remainsbelowthe2200deg-FlimitasspecifiedbyAppendixKof10CFR50.46.II.MethodofAnalsisThesensitivitystudywasperformedusingtheLOCTAcomputercodeoftheWestinghouse1981LargeBreakLOCAEvaluationModel(WEM)tocalculatethePCTforExxonfuelforthreepowershapes.Thepower.shapesinvestigatedIwerepeakedat6.0ft.,8.0ft.,andat10.5ft.ThepowershapesusedintheLOCAanalysesareshowninFigures1-3.ThepeakpowerofeachpowershapeislimitedbythecurrentK(z)envelopefortheRobertE.Ginna(RGE)powerplant.ThecurrentK(z)envelopeforRGEassumesamaximumtotalpeakingfactorof2.32,andahotchannelenthalpyrisefactorof1.66. | | {{#Wiki_filter:DEMONSTRATION OFTHECONFORMANCE OFEXXONNUCLEARCOMPANYFUELTOTHEWESTINGHOUSE K(Z)OPERATING ENVELOPEFORTHEROBERTE.GINNANUCLEARPOWERPLANTWestinghouse ElectricCorporation NuclearTechnology DivisionNuclearSafetyDepartment Safeguards Engineering andDevelopment September 19858512200249 851216PDRADOCK05000244',P'DR I.ntroduction Thisdocumentreportstheresultsofasensitivity studythatwasperformed inordertodemonstrate conformance ofExxonNuclearCompanynuclearfuelintheRobertE.GinnanuclearpowerplanttotheWestinghouse K(z)operating envelope. |
| | Inparticular, theresultsof.thisanalysisshowthatforskewedtothetoppowershapes,inadditiontothepowershapepeakedatthemid-coreelevation, thattheworstpeakcladdingtemperature (PCT)intheunlikelyeventofaLoss-Of-Coolant-Accident (LOCA)remainsbelowthe2200deg-Flimitasspecified byAppendixKof10CFR50.46. |
| | II.MethodofAnalsisThesensitivity studywasperformed usingtheLOCTAcomputercodeoftheWestinghouse 1981LargeBreakLOCAEvaluation Model(WEM)tocalculate thePCTforExxonfuelforthreepowershapes.Thepower.shapesinvestigated Iwerepeakedat6.0ft.,8.0ft.,andat10.5ft.ThepowershapesusedintheLOCAanalysesareshowninFigures1-3.ThepeakpowerofeachpowershapeislimitedbythecurrentK(z)envelopefortheRobertE.Ginna(RGE)powerplant.ThecurrentK(z)envelopeforRGEassumesamaximumtotalpeakingfactorof2.32,andahotchannelenthalpyrisefactorof1.66. |
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| ThefueldesignparametersfortheExxonfuelwereobtainedfromtheExxonNuclearCompanythroughathree-partyproprietaryagreementbetweenWestinghouse,RochesterGas6Electric,an'dExxon.ThefuelparametersspecifictoeachpowershapeweregeneratedbyExxonandtransmittedtoWestinghouse.Thefuelparameters,whichincludedfuelpellettemperaturesandgappressures,werethenusedasinputineachoftheLOCTAcalculations.TheresultsoftheLOCTAcalculationsaresummarizedinthefollowingtable:'IComarisonofExxonFuelPeakCladdinTemeraturesPowerShapePeakPCTOFPCTElevationPCTTimesec.6~08'10'1781159815287.257'510.001065..14'TheseresultsdemonstratethatfortheRobertE.GinnaUnit,thatthechoppedcosinepowershape(i.e.6.0ft.peakedshape)generatesthemostlimitingpeakcladtemperature.Figures4-6showthecladtemperatureresponseforthepeaknodeforthe6.0,8.0,and10.5ft.powershapesrespectively.Animportantobservationoftheseresultsisthatforthetop-skewedshapes,thepeakcladdingtemperatureoccursduringtheblowdownphase.ThisisimportantbecausemostoftheAppendixKprescribedanalyticalmodelshavetheirgreatestinfluenceduringtherefloodphase.Apeak
| | Thefueldesignparameters fortheExxonfuelwereobtainedfromtheExxonNuclearCompanythroughathree-party proprietary agreement betweenWestinghouse, Rochester Gas6Electric, an'dExxon.Thefuelparameters specifictoeachpowershapeweregenerated byExxonandtransmitted toWestinghouse. |
| '~cladtemperaturewhichoccursduringrefloodissensitivetocore-wideandsystem-widehydraulicphenomena,whileablowdownpeakisastrongerfunctionofinitialfuelstoredenergy.AcomparisonofthepeakcladtemperaturesduringtheblowdownandrefloodphasesforeachofthesepowershapesprovidesamoreconclusivedemonstrationthatthechoppedcosinepowershapeproducesthemostlimitingLOCAresults.ComarisonofPeakCladdinTemeraturesDurinBlowdownPowerShapePeakPCT-BlowdownopPCTElevationTimesec.6.08'10'1635159815286~007'510.005'5'4'ThecomparisonofpeakcladtemperaturesduringblowdownshowsthatthehighestPCToccursforthechoppedcosinepowershape.Thisisreasonable.,because6.0ft.shapepermitsthehighesttotallocalpeakingfactor(2.32).ThefactthatthePCTforthetop-skewedshapesoccursbelowthepeakpowerlocationisduetothebetterheattransferathigherelevationsthatoccursduringtheperiodofnegativecoreflow. | | Thefuelparameters, whichincludedfuelpellettemperatures andgappressures, werethenusedasinputineachoftheLOCTAcalculations. |
| ComarisonofPeakCladdinTemeraturesDurinRefloodPowerShapePeakPCT-RefloodOFPCTElevationTimesec.6~08~010'1781158514587'5F0010.001067468Thecomparisonofrefloodpeakcladtemperaturesshowsanevenwidermarginbetweenthechoppedcosineshapeandthetop-skewedpowershapes.Znadditiontoshowingthatthechoppedcosinepowershape,isthe"worst"powershapeforaLOCAanalysisofRGEwithExxonfuel,italsodemonstratesalargemargintothe2200deg-Flimitforthetop-skewedshapesforthisplant.III.UseofNon-ExxonFuelHdraulicsThissensitivitystudywasperformedbyre-calculatingthecladVItemperatureresponseforExxonforthethreepowershapesusingtheLOCTAcomputercode.Thehotassemblyhydraulicswasnotre-calculatedfortheExxonfuel.TheblowdownandrefloodhydraulictransientsaregeneratedusingtheSATAN,WREFLOODandCOCOcomputercodes.ExistingblowdownandrefloodhydraulicsfromapreviousRGEplantspecificanalysiswithW-OFAfuelwereusedashotassemblyboundaryconditionsfortheLOCTAcalculations.UseoftheOFAhydraulicsarejustifiableforthissensitivitystudyonthefollowingbasis: | | TheresultsoftheLOCTAcalculations aresummarized inthefollowing table:'IComarisonofExxonFuelPeakCladdinTemeraturesPowerShapePeakPCTOFPCTElevation PCTTimesec.6~08'10'1781159815287.257'510.001065..14'Theseresultsdemonstrate thatfortheRobertE.GinnaUnit,thatthechoppedcosinepowershape(i.e.6.0ft.peakedshape)generates themostlimitingpeakcladtemperature. |
| (l)TheW-OFArodsizeissmallerthantheExxonrodsize.ThiswillresultinaslowerrefloodofafullcoreofW-OFAfuel.Thus,foragivenpowershape,theuseoftheOFAcorerefloodrateprovidesaconservative'efloodratefortheExxonfuelheat-upcalculation.(2)Previoussensitivitieswithtop-skewedpowershapesinSATANhavehotshownalargeeffectontheend-of-blowdownfueltemperatures.Thus,theuseofSATANchoppedcosinepowershaperesultsfortop-skewedLOCTAcalculationscanbeconsideredsufficientlyaccurateforaroughsensitivitystudy.Becauseofthewidemarginbetweenthecosineandthetop-skewedshapePCTsinthisanalysis,re-calculationoftheSATANtransientisnotexpectedtochangetheconclusionsofthisanalysis.IV.ConclusionsTheWestinghouseLargeBreakLOCAEvaluationModelcladheat-upcomputercode,LOCTA,wasusedtoanalyzeExxonfuelforthreepowershapes.Theresultsconfirmedthatthepowershapepeaked..atthecenterofthecoreproducesthehighestpeakcladdingtemperature.ThisresultfortheExxonfuelisconsistentwithpowershapestudiesperformedbyWestinghousewiththesamecomputercodesforWestinghousefuel.TheresultsofthisstudydemonstratethattheExxonfuelintheRobertE.GinnanuclearpowerplantconformstothecurrentoperatingK(z)envelopefortop-skewedpowershapes.Whiletheentiretransientwasnotrecalculatedforthisanalysis,acompletere-analysiswouldnotbeexpectedtochangetheconclusionsofthissensitivitystudy.\ | | Figures4-6showthecladtemperature responseforthepeaknodeforthe6.0,8.0,and10.5ft.powershapesrespectively. |
| 0.03.04.25,.4.755.255.75-6.256.757.257.759.012.1.S4.04.55.05.56.06.57.07.58.010.5COREHEIGHT(FEET)Figure1.AxialPowerShapePeakedat6.0ft.(ChoppedCosinePowerShape) 0.01.02.03.04.05.06.07.08.09.010.011.012.0.51.52.53.54.55.56.57.58.59.510.511.5COREHEIGHT(FEET)Figure2.AxialPowerShapePeakedat8.0ft; 2.S2.0M~1.SC51.0.5.0.01.02.03.04.05.06.07.08.09.010.011.012.0.51.52.53.54.55.56.57.58.59.510.511.5COREHEIGHT(FEET)Figure3.AxialPowerShapePeakedat10.5ft. | | Animportant observation oftheseresultsisthatforthetop-skewed shapes,thepeakcladdingtemperature occursduringtheblowdownphase.Thisisimportant becausemostoftheAppendixKprescribed analytical modelshavetheirgreatestinfluence duringtherefloodphase.Apeak |
| c~tlctl~clvbttt~ovtv[5tovlt5vttl51u0tO.~Cl(IC.C0tlte~OvltSvttlll~0~vC1[vt<<01~00IutlfiC00t'llItlJt~tot5tll~ItW>.OCC5'AO.Ovoltd.O50vAOS<lvl~55C>Figure4.CladTemperatureResponseforPCTLocationforthe6.0ft.PowerShape. | | '~cladtemperature whichoccursduringrefloodissensitive tocore-wide andsystem-wide hydraulic phenomena, whileablowdownpeakisastrongerfunctionofinitialfuelstoredenergy.Acomparison ofthepeakcladtemperatures duringtheblowdownandrefloodphasesforeachofthesepowershapesprovidesamoreconclusive demonstration thatthechoppedcosinepowershapeproducesthemostlimitingLOCAresults.ComarisonofPeakCladdinTemeraturesDurinBlowdownPowerShapePeakPCT-Blowdown opPCTElevation Timesec.6.08'10'1635159815286~007'510.005'5'4'Thecomparison ofpeakcladtemperatures duringblowdownshowsthatthehighestPCToccursforthechoppedcosinepowershape.Thisisreasonable., |
| ~Oll~lC~CllilCt~00lulltOOC~SwltlS'IUOt0'OCClCO,O~CaatOol~SsstlCCAOArt.lllit.wOS000~VOS'i~tCSlitl~CitySy$0tll+lVlC000.0C\SSOO.ONXol000.00.088SINSISCCIFigure5.-CladTemperatureResponseforPCTLocationfor8.0ft.PowerShape | | because6.0ft.shapepermitsthehighesttotallocalpeakingfactor(2.32).ThefactthatthePCTforthetop-skewed shapesoccursbelowthepeakpowerlocationisduetothebetterheattransferathigherelevations thatoccursduringtheperiodofnegativecoreflow. |
| ~OltV<C,CIVVVt<<OV<Vt<VOVtV5Vatt5<VDV0,~Ott<C10.5VtvvVOvtV5vVVtC<JDAVC.1t<<V,<<0<VODOvv51~0.00<1<<Vtvv~O,DOA<~<W~0000.0o1500.0XE<Co1000.0lr0.0CII<t<5CCISg8Figure6.CladTemperatureResponseforPCTLocationforthe10.5ft.PowerShape-11}} | | ComarisonofPeakCladdinTemeraturesDurinRefloodPowerShapePeakPCT-Reflood OFPCTElevation Timesec.6~08~010'1781158514587'5F0010.001067468Thecomparison ofrefloodpeakcladtemperatures showsanevenwidermarginbetweenthechoppedcosineshapeandthetop-skewed powershapes.Znadditiontoshowingthatthechoppedcosinepowershape,isthe"worst"powershapeforaLOCAanalysisofRGEwithExxonfuel,italsodemonstrates alargemargintothe2200deg-Flimitforthetop-skewed shapesforthisplant.III.UseofNon-Exxon FuelHdraulicsThissensitivity studywasperformed byre-calculating thecladVItemperature responseforExxonforthethreepowershapesusingtheLOCTAcomputercode.Thehotassemblyhydraulics wasnotre-calculated fortheExxonfuel.Theblowdownandrefloodhydraulic transients aregenerated usingtheSATAN,WREFLOODandCOCOcomputercodes.Existingblowdownandrefloodhydraulics fromapreviousRGEplantspecificanalysiswithW-OFAfuelwereusedashotassemblyboundaryconditions fortheLOCTAcalculations. |
| | UseoftheOFAhydraulics arejustifiable forthissensitivity studyonthefollowing basis: |
| | (l)TheW-OFArodsizeissmallerthantheExxonrodsize.ThiswillresultinaslowerrefloodofafullcoreofW-OFAfuel.Thus,foragivenpowershape,theuseoftheOFAcorerefloodrateprovidesaconservative'eflood ratefortheExxonfuelheat-upcalculation. |
| | (2)Previoussensitivities withtop-skewed powershapesinSATANhavehotshownalargeeffectontheend-of-blowdown fueltemperatures. |
| | Thus,theuseofSATANchoppedcosinepowershaperesultsfortop-skewed LOCTAcalculations canbeconsidered sufficiently accurateforaroughsensitivity study.Becauseofthewidemarginbetweenthecosineandthetop-skewed shapePCTsinthisanalysis, re-calculation oftheSATANtransient isnotexpectedtochangetheconclusions ofthisanalysis. |
| | IV.Conclusions TheWestinghouse LargeBreakLOCAEvaluation Modelcladheat-upcomputercode,LOCTA,wasusedtoanalyzeExxonfuelforthreepowershapes.Theresultsconfirmed thatthepowershapepeaked..at thecenterofthecoreproducesthehighestpeakcladdingtemperature. |
| | ThisresultfortheExxonfuelisconsistent withpowershapestudiesperformed byWestinghouse withthesamecomputercodesforWestinghouse fuel.Theresultsofthisstudydemonstrate thattheExxonfuelintheRobertE.Ginnanuclearpowerplantconformstothecurrentoperating K(z)envelopefortop-skewed powershapes.Whiletheentiretransient wasnotrecalculated forthisanalysis, acompletere-analysis wouldnotbeexpectedtochangetheconclusions ofthissensitivity study.\ |
| | 0.03.04.25,.4.75 5.255.75-6.25 6.757.257.759.012.1.S4.04.55.05.56.06.57.07.58.010.5COREHEIGHT(FEET)Figure1.AxialPowerShapePeakedat6.0ft.(ChoppedCosinePowerShape) 0.01.02.03.04.05.06.07.08.09.010.011.012.0 |
| | .51.52.53.54.55.56.57.58.59.510.511.5COREHEIGHT(FEET)Figure2.AxialPowerShapePeakedat8.0ft; 2.S2.0M~1.SC51.0.5.0.01.02.03.04.05.06.07.08.09.010.011.012.0 |
| | .51.52.53.54.55.56.57.58.59.510.511.5COREHEIGHT(FEET)Figure3.AxialPowerShapePeakedat10.5ft. |
| | c~tlctl~clvbttt~ovtv[5tovlt5vttl51u0tO.~Cl(IC.C0tlte~OvltSvttlll~0~vC1[vt<<01~00IutlfiC00t'llItlJt~tot5tll~ItW>.OCC5'AO.Ovoltd.O50vAOS<lvl~55C>Figure4.CladTemperature ResponseforPCTLocationforthe6.0ft.PowerShape. |
| | ~Oll~lC~CllilCt~00lulltOOC~SwltlS'IUOt0'OCClCO,O~CaatOol~SsstlCCAOArt.lllit.wOS 000~VOS'i~tCSlitl~CitySy$0tll+lVlC000.0C\SSOO.ONXol000.00.088SINSISCCIFigure5.-CladTemperature ResponseforPCTLocationfor8.0ft.PowerShape |
| | ~OltV<C,CIVVVt<<OV<Vt<VOVtV5Vatt5<VDV0,~Ott<C10.5VtvvVOvtV5vVVtC<JDAVC.1t<<V,<<0< |
| | VODOvv51~0.00<1<<Vtvv~O,DOA<~<W~0000.0o1500.0XE<Co1000.0lr0.0CII<t<5CCISg8Figure6.CladTemperature ResponseforPCTLocationforthe10.5ft.PowerShape-11}} |
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Interim Rept Re W2 Control Switch,Procured from W,Did Not Operate Satisfactorily When Drawn from Stock to Be Installed in Main Control Board for 1C2 Safety Injection Pump. Estimated That Evaluation Will Be Completed by 991001
ML17309A6541999-05-27027 May 1999
LER 99-008-00:on 990427,overtemperature Delta T Reactor Trip Occurred Due to Faulted Bistable During Calibr of Redundant Channel.Plant Was Stabilized in Mode 3 & Faulted Bistable Was Subsequently Replaced.With 990527 Ltr
ML17265A6631999-05-24024 May 1999
LER 99-007-00:on 990423,technicians Inadvertently Pulled Fuses from Wrong Nuclear Instrument Cahnnel,Causing Reactor Trip,Due to High Range Flux Trip.Caused by Personnel Error. Labeling Scheme Improved
ML17265A6601999-05-21021 May 1999
LER 99-006-00:on 990421,start of turbine-driven Auxiliary Feedwater Pump Was Noted.Caused by MOV Being Left in Open Position.Closed Manual Isolation Valve to Secure Steam to Pump.With 990521 Ltr
ML17265A6591999-05-17017 May 1999
Part 21 Rept Re Relay Deficiency Detected During pre-installation Testing.Caused by Incorrectly Wired Relay Coil.Relays Were Returned to Eaton Corp for Investigation. Relays Were Repaired & Retested
ML17265A6441999-05-13013 May 1999
LER 99-005-00:on 990413,undervoltage Signal of Safeguards Bus During Testing Resulted in Automatic Start of B Edg. Caused by Personnel Error.Blown Fuse Was Replaced & Offsite Power Was Restored to Safeguards Bus 17.With 990513 Ltr
ML17265A6431999-05-12012 May 1999
LER 99-004-00:on 990412,discovered That Containment Recirculation Fan Moisture Separator Vanes Were Incorrectly Installed,Per 10CFR21.Caused by Improper Assembly by Mfg. Subject Vanes Were Dismantled & Correctly re-installed
ML17265A6381999-05-0707 May 1999
Part 21 Rept Re Replacement Turbocharger Exhaust Turbine Side Drain Port Not Functioning as Design Intended.Caused by Manufacturing Deficiency.Turbocharger Was Reaasembled & Reinstalled on B EDG
ML17265A6391999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for Re Ginna Nuclear Power Plant.With 990510 Ltr
ML17265A6361999-04-23023 April 1999
Part 21 Rept Re Power Supply That Did Not Work Properly When Drawn from Stock & Installed in -25 Vdc Slot.Power Supply Will Be Sent to Vendor to Perform Failure Mode Assessment.Evaluation Will Be Completed by 991001
ML17265A6301999-04-18018 April 1999
Rev 1 to Cycle 28 COLR for Re Ginna Npp.
ML17265A6251999-04-15015 April 1999
Special Rept:On 990309,halon Systems Were Removed from Svc & Fire Door F502 Was Blocked Open.Caused by Mods Being Made to CR Emergency Air Treatment Sys.Continuous Fire Watch Was Established with Backup Fire Suppression Equipment
ML17265A6551999-04-0909 April 1999
Initial Part 21 Rept Re Mfg Deficiency in Replacement Turbocharger for B EDG Supplied by Coltec Industries. Deficiency Consisted of Missing Drain Port in Intermediate Casing.Required Oil Drain Port Machined Open
ML17265A6291999-03-31031 March 1999
Rev 0 to Cycle 28 COLR for Re Ginna Npp.
ML17265A6241999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for Ginna Station.With 990409 Ltr
ML17265A6141999-03-31031 March 1999
LER 99-003-00:on 990301,two Main Steam non-return Check Valves Were Declared Inoperable Due to Exceedance of Acceptance Criteria.Caused by Changes in Methodology & Matls.Packing Gland Torque Will Be Adjusted.With 990331 Ltr
ML17265A6131999-03-29029 March 1999
LER 99-002-00:on 990227,discovered That Surveillance Had Not Been Performed at Frequency,Per Ts.Caused by Personnel Error.Procedure O-6.13 Will Be Evaluated for Enhancement Documentation of Completion of ITS Srs.With 990329 Ltr
ML17265A6061999-03-24024 March 1999
LER 99-001-00:on 990222,plant Was Noted Outside Design Basis.Caused by Deficiencies in NSSS Vendor Slb Mass & Energy Release.Placed Temporary Administrative Restriction 40 Degrees F Max on Screenhouse Bay Temp
ML17265A5661999-03-0101 March 1999
Rev 26 to QA Program for Station Operation.
ML17265A5961999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for Ginna Nuclear Power Plant.With 990310 Ltr
ML17265A5371999-01-31031 January 1999
Monthly Operating Rept for Jan 1999 for Re Ginna Nuclear Power Plant.With 990205 Ltr
ML17265A5951998-12-31031 December 1998
Rg&E 1998 Annual Rept.
ML17265A5001998-12-21021 December 1998
Rev 26 to QA Program for Station Operation.
ML17265A4951998-12-21021 December 1998
LER 98-005-00:on 981120,loss of 34.5 Kv Offsite Power Circuit 751,resulted in Automatic Start of B Edg.Caused by Faulted Cable Splice.Performed Appropriate Actions of Abnormal Procedure AP-ELEC.1.With 981221 Ltr
ML17265A4931998-12-17017 December 1998
LER 98-004-00:on 971030,determined That Improperly Performed Surveillance Resulted in Condition Prohibited by Ts.Caused by Procedure non-adherence.Appropriate Calibr Procedures Were Properly Performed with 24 H of Condition Discovery
ML17265A4761998-11-30030 November 1998
Monthly Operating Rept for Nov 1998 for Re Ginna Nuclear Power Plant.With 981210 Ltr
ML17265A4691998-11-25025 November 1998
LER 98-003-01:on 980904,actuations of CR Emergency Air Treatment Systems (Creats) Occurred.Caused by Radon build-up During Temp Inversion.Creats Actuation Signal Was Reset & Normal Ventilation Was Restored to CR
ML17265A4531998-10-31031 October 1998
Monthly Operating Rept for Oct 1998 for Re Ginna Nuclear Power Plant.With 981110 Ltr
ML17265A4271998-10-0505 October 1998
LER 98-003-00:on 980904,actuations of CR Emergency Air Treatment Sys Occurred.Caused by Radon build-up During Temp Inversion.Air Samples Were Taken & Determined That Source of Radiation Was Naturally Occurring Radon.With 981005 Ltr
ML17265A4291998-09-30030 September 1998
Monthly Operating Rept for Sept 1998 for Re Ginna Nuclear Power Plant.With 981009 Ltr
1999-09-30
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Text
DEMONSTRATION OFTHECONFORMANCE OFEXXONNUCLEARCOMPANYFUELTOTHEWESTINGHOUSE K(Z)OPERATING ENVELOPEFORTHEROBERTE.GINNANUCLEARPOWERPLANTWestinghouse ElectricCorporation NuclearTechnology DivisionNuclearSafetyDepartment Safeguards Engineering andDevelopment September 19858512200249 851216PDRADOCK05000244',P'DR I.ntroduction Thisdocumentreportstheresultsofasensitivity studythatwasperformed inordertodemonstrate conformance ofExxonNuclearCompanynuclearfuelintheRobertE.GinnanuclearpowerplanttotheWestinghouse K(z)operating envelope.
Inparticular, theresultsof.thisanalysisshowthatforskewedtothetoppowershapes,inadditiontothepowershapepeakedatthemid-coreelevation, thattheworstpeakcladdingtemperature (PCT)intheunlikelyeventofaLoss-Of-Coolant-Accident (LOCA)remainsbelowthe2200deg-Flimitasspecified byAppendixKof10CFR50.46.
II.MethodofAnalsisThesensitivity studywasperformed usingtheLOCTAcomputercodeoftheWestinghouse 1981LargeBreakLOCAEvaluation Model(WEM)tocalculate thePCTforExxonfuelforthreepowershapes.Thepower.shapesinvestigated Iwerepeakedat6.0ft.,8.0ft.,andat10.5ft.ThepowershapesusedintheLOCAanalysesareshowninFigures1-3.ThepeakpowerofeachpowershapeislimitedbythecurrentK(z)envelopefortheRobertE.Ginna(RGE)powerplant.ThecurrentK(z)envelopeforRGEassumesamaximumtotalpeakingfactorof2.32,andahotchannelenthalpyrisefactorof1.66.
Thefueldesignparameters fortheExxonfuelwereobtainedfromtheExxonNuclearCompanythroughathree-party proprietary agreement betweenWestinghouse, Rochester Gas6Electric, an'dExxon.Thefuelparameters specifictoeachpowershapeweregenerated byExxonandtransmitted toWestinghouse.
Thefuelparameters, whichincludedfuelpellettemperatures andgappressures, werethenusedasinputineachoftheLOCTAcalculations.
TheresultsoftheLOCTAcalculations aresummarized inthefollowing table:'IComarisonofExxonFuelPeakCladdinTemeraturesPowerShapePeakPCTOFPCTElevation PCTTimesec.6~08'10'1781159815287.257'510.001065..14'Theseresultsdemonstrate thatfortheRobertE.GinnaUnit,thatthechoppedcosinepowershape(i.e.6.0ft.peakedshape)generates themostlimitingpeakcladtemperature.
Figures4-6showthecladtemperature responseforthepeaknodeforthe6.0,8.0,and10.5ft.powershapesrespectively.
Animportant observation oftheseresultsisthatforthetop-skewed shapes,thepeakcladdingtemperature occursduringtheblowdownphase.Thisisimportant becausemostoftheAppendixKprescribed analytical modelshavetheirgreatestinfluence duringtherefloodphase.Apeak
'~cladtemperature whichoccursduringrefloodissensitive tocore-wide andsystem-wide hydraulic phenomena, whileablowdownpeakisastrongerfunctionofinitialfuelstoredenergy.Acomparison ofthepeakcladtemperatures duringtheblowdownandrefloodphasesforeachofthesepowershapesprovidesamoreconclusive demonstration thatthechoppedcosinepowershapeproducesthemostlimitingLOCAresults.ComarisonofPeakCladdinTemeraturesDurinBlowdownPowerShapePeakPCT-Blowdown opPCTElevation Timesec.6.08'10'1635159815286~007'510.005'5'4'Thecomparison ofpeakcladtemperatures duringblowdownshowsthatthehighestPCToccursforthechoppedcosinepowershape.Thisisreasonable.,
because6.0ft.shapepermitsthehighesttotallocalpeakingfactor(2.32).ThefactthatthePCTforthetop-skewed shapesoccursbelowthepeakpowerlocationisduetothebetterheattransferathigherelevations thatoccursduringtheperiodofnegativecoreflow.
ComarisonofPeakCladdinTemeraturesDurinRefloodPowerShapePeakPCT-Reflood OFPCTElevation Timesec.6~08~010'1781158514587'5F0010.001067468Thecomparison ofrefloodpeakcladtemperatures showsanevenwidermarginbetweenthechoppedcosineshapeandthetop-skewed powershapes.Znadditiontoshowingthatthechoppedcosinepowershape,isthe"worst"powershapeforaLOCAanalysisofRGEwithExxonfuel,italsodemonstrates alargemargintothe2200deg-Flimitforthetop-skewed shapesforthisplant.III.UseofNon-Exxon FuelHdraulicsThissensitivity studywasperformed byre-calculating thecladVItemperature responseforExxonforthethreepowershapesusingtheLOCTAcomputercode.Thehotassemblyhydraulics wasnotre-calculated fortheExxonfuel.Theblowdownandrefloodhydraulic transients aregenerated usingtheSATAN,WREFLOODandCOCOcomputercodes.Existingblowdownandrefloodhydraulics fromapreviousRGEplantspecificanalysiswithW-OFAfuelwereusedashotassemblyboundaryconditions fortheLOCTAcalculations.
UseoftheOFAhydraulics arejustifiable forthissensitivity studyonthefollowing basis:
(l)TheW-OFArodsizeissmallerthantheExxonrodsize.ThiswillresultinaslowerrefloodofafullcoreofW-OFAfuel.Thus,foragivenpowershape,theuseoftheOFAcorerefloodrateprovidesaconservative'eflood ratefortheExxonfuelheat-upcalculation.
(2)Previoussensitivities withtop-skewed powershapesinSATANhavehotshownalargeeffectontheend-of-blowdown fueltemperatures.
Thus,theuseofSATANchoppedcosinepowershaperesultsfortop-skewed LOCTAcalculations canbeconsidered sufficiently accurateforaroughsensitivity study.Becauseofthewidemarginbetweenthecosineandthetop-skewed shapePCTsinthisanalysis, re-calculation oftheSATANtransient isnotexpectedtochangetheconclusions ofthisanalysis.
IV.Conclusions TheWestinghouse LargeBreakLOCAEvaluation Modelcladheat-upcomputercode,LOCTA,wasusedtoanalyzeExxonfuelforthreepowershapes.Theresultsconfirmed thatthepowershapepeaked..at thecenterofthecoreproducesthehighestpeakcladdingtemperature.
ThisresultfortheExxonfuelisconsistent withpowershapestudiesperformed byWestinghouse withthesamecomputercodesforWestinghouse fuel.Theresultsofthisstudydemonstrate thattheExxonfuelintheRobertE.Ginnanuclearpowerplantconformstothecurrentoperating K(z)envelopefortop-skewed powershapes.Whiletheentiretransient wasnotrecalculated forthisanalysis, acompletere-analysis wouldnotbeexpectedtochangetheconclusions ofthissensitivity study.\
0.03.04.25,.4.75 5.255.75-6.25 6.757.257.759.012.1.S4.04.55.05.56.06.57.07.58.010.5COREHEIGHT(FEET)Figure1.AxialPowerShapePeakedat6.0ft.(ChoppedCosinePowerShape) 0.01.02.03.04.05.06.07.08.09.010.011.012.0
.51.52.53.54.55.56.57.58.59.510.511.5COREHEIGHT(FEET)Figure2.AxialPowerShapePeakedat8.0ft; 2.S2.0M~1.SC51.0.5.0.01.02.03.04.05.06.07.08.09.010.011.012.0
.51.52.53.54.55.56.57.58.59.510.511.5COREHEIGHT(FEET)Figure3.AxialPowerShapePeakedat10.5ft.
c~tlctl~clvbttt~ovtv[5tovlt5vttl51u0tO.~Cl(IC.C0tlte~OvltSvttlll~0~vC1[vt<<01~00IutlfiC00t'llItlJt~tot5tll~ItW>.OCC5'AO.Ovoltd.O50vAOS<lvl~55C>Figure4.CladTemperature ResponseforPCTLocationforthe6.0ft.PowerShape.
~Oll~lC~CllilCt~00lulltOOC~SwltlS'IUOt0'OCClCO,O~CaatOol~SsstlCCAOArt.lllit.wOS 000~VOS'i~tCSlitl~CitySy$0tll+lVlC000.0C\SSOO.ONXol000.00.088SINSISCCIFigure5.-CladTemperature ResponseforPCTLocationfor8.0ft.PowerShape
~OltV<C,CIVVVt<<OV<Vt<VOVtV5Vatt5<VDV0,~Ott<C10.5VtvvVOvtV5vVVtC<JDAVC.1t<<V,<<0<
VODOvv51~0.00<1<<Vtvv~O,DOA<~<W~0000.0o1500.0XE<Co1000.0lr0.0CII<t<5CCISg8Figure6.CladTemperature ResponseforPCTLocationforthe10.5ft.PowerShape-11
