ML18030A078

Transmits Powerplex Response Data Comparisons to Support Approval of Topical Rept PL-NF-90-001, Application of Reactor Analysis Methods for BWR Design & Analysis Dtd Aug 1990.Encl Data Comparisons Withheld (Ref 10CFR2.790)(b))

ML18030A078
Person / Time
Site:	Susquehanna
Issue date:	10/17/1991
From:	KEISER H W PENNSYLVANIA POWER & LIGHT CO.
To:	BUTLER W R Office of Nuclear Reactor Regulation
Shared Package
ML17157A903	List: ML18030A078
References
PLA-3663, NUDOCS 9110280248
Download: ML18030A078 (8)

Text

LERATEDDIHUBUTIONDEMONTIONSYSTEMt~S~eREGULATORYINFORMATIONDISTRIBUTIONSYSTEM(RIDS)ACCESSIONNBR:9110280248DOC.DATE:91/10/17NOTARIZED:YESFACIL:50-387SusquehannaSteamElectricStation,Unit1,Pennsylva50-'388SusquehannaSteamElectricStation,Unit2,PennsylvaAUTH.NAMEAUTHORAFFILIATIONKEISER,H.W.PennsylvaniaPower&LightCo.RECIP.NAMERECIPIENTAFFILIATIONBUTLER,W.R.ProjectDirectorateI-2DOCKET0500038705000388

SUBJECT:

TransmitsPowerplexresponsedatacomparisonstosupportapprovalofutilapplicationtopicalreptPL-NF-90-001,"ApplicationofReactorAnalysisMethodsforBWRDesign&AnalysisforAug1990."DISTRIBUTIONCODE:APOIDCOPIESRECEIVED:LTRiENCLQSIZE:Q+TITLE:ProprietaryReviewDistribution-OperatingReactorDSRECIPIENTIDCODE/NAMEPDl-2LARALEIGH,J.COPIESLTTRENCL11'3NOTES:LPDR1cyTranscripts.LPDR1cyTranscripts.RECIPIENTIDCODE/NAMEPD1-2PDCOPIESLTTRENCL1105000387A05000388'DDINTERNAL:ACRSOGC/HDS2EXTERNAL:NRCPDRNOTES:66101022AEODE01RIDNOTETOALL"RIDS"RECIPIENTS:PLEASEHELPUSTOREDUCEWAS'ONTACTTHEDOCUMENTCONTROLDESK,ROOMPl-37(EXT.20079)TOELIMINATEYOURNAMEFROMDISTRIBUTIONLINISFORDOCUMENTSYOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED:LTTR17ENCL15ADDS 04 4ywPennsylvaniaPower8LightCompanyTwoNorthNinthStreet~Allentown,PA18101-1179~215/774-5151HaroldW.KeiserSeniorVicePresident-Nuclear215/7744194OCTl7$81DirectorofNuclearReactorRegulationAttention:Dr.W.R.Butler,ProjectDirectorProjectDirectorateI-2DivisionofReactorProjectsU.S.NuclearRegulatoryCommissionWashington,D.C.20555SUSQUEIIANNASTEAMELECTRICSTATIONLICENSINGMETHODS:SUPPORTINGINFORMATIONDocketNos.50-387PLA-6FILR41-2Aand50-388irW

References:

1."ApplicationofReactorAnalysisMethodsfor,BWRDesignandAnalysis",PINF-90-001,August1990.2."QualificationofTransientAnalysis'MethodsforBWRDesignandAnalysis",PINF-89-00$,December1989.3.PLA-3641,H.W.Ket'sertoW.R.Butler,"LicensingMethods:PlanforU1C7",datedAugust29,1991.

DearDr.Butler:

TosupporttheNRC'sapprovalofPP&L'sApplicationsTopicalReport(Reference1),wearetransmittingdatacomparisonswhichPP&LdiscussedinameetingwithNRCandBNLrepresentativesonOctober4,1991attheNRC'sWhiteFlintoffice.ThisdatawasusedtodemonstratethatthecurrentSiemensNuclearPowerCorporation(SNP)coremonitoringsystemuncertaintiesareconservativeformonitoringthecorewithPP&LgeneratedinputintheSusquehannaPOWERPLEXcoremonitoringsystem.AfterdiscussionwiththeNRCstaffandthereviewer,however,PP&LhasagreedtousethemoreconservativeSNPuncertainties,ratherthanthePP&Lgenerateduncertainties.PleasenotethatthedatacomparisonswhichareincludedinAtta'chment1areconsideredproprietarybySNP.Asrequiredby10CFR2.790(b)anaffidavittosupportwithholdingthisinformationfrompublicdisclosureiscontainedinAttachment2.TheproprietaryportionofAttachment1willnotbeincludedintheapprovedversionofthePP&LApplicationsTopicalReport.l91102S0248',91'10'17,?tt'DR'AGOCK05000387PPDR lr(IIKII 0~~eI FILESR41-2/A7-8CPLA-3663Dr.W.R.ButlerAsconveyedtoMessrs.JohnEmmettandAndrewDyszel,thetransmittaloftheenclosedmaterialclosesthelastremainingissueidentifiedduringthereviewofPP&L'sApplicationsTopicalReport.Further,itisourunderstandingthattheNRCwillproceedwithissuanceofSafetyEvaluationReportsforPP&L'sApplicationsTopicalReport(Reference1)andTransientAnalysisTopicalReport(Reference2).PP&L,inturn,isproceedingwiththeperformanceoftheUnit1Cycle7reloadanalysesusingtheapproachagreedtobyPP&LandNRC(asdescribedinReference3andherein).Inclosing,PP&LwouldliketocomplimenttheNRCandBNLrepresentativesfortheirpromptresponseandcooperationinresolvingthislastremainingissue.AnyquestionsonthissubmittalshouldbedirectedtoMr.R.Sgarroat(215)774-7916.Verytrulyyours,H.W.KeiserAttachmentscc:QgRCDocumentContro13)eak.(original)NRCRegionIMr.G.S.Barber,NRCSr.ResidentInspector-SSESMr.J.J.Raleigh,NRCProjectManager-OWFNMr.L.I.Kopp,NRR/SRXB-OWFN 4i ATI'ACIIMENT1TOPLA-3663FILESR41-2/A7-8CATTACHMENT1POWERPLEXTIPRESPONSECOMPARISONSTOSUPPORTAPPROVALOFPP&L'SAPPLICATIONSTOPICALREPORT(PL-NF-90-001)TheSusquehannadatacomparisonscalculatedbyPP&Lthatareshowninthisattachmentsupporttheconclusionsthat:1)thePOWERPLEXcoremonitoringsystemwithPP&LgeneratedCPM-2inputyieldsmoreaccurateresultsthanthePOWERPLEXcoremonitoringsystemwithSNPgeneratedXFYREinput,and2)thecurrentlyapprovedSNPpowerdistributionuncertaintiesareconservativeforSusquehannawhenPP&LdevelopstheinputtothePOWERPLEXcoremonitoringsystem.PP&L'scoremonitoringsystem,POWERPLEX,wasdevelopedbySNPandusesXTGBWRasthecoresimulationcodeandmeasuredLPRMdatatomodifytheXTGBWRcalculated"base"powerdistributiontoobtaina"measured"powerdistribution(i.e.,UPDATE).ThePOWERPLEXnodalTIPRMSdatapresentedinthefollowingfiguresisanindicationofhowaccuratethe3-DTIPresponse(i.e.,powershape)iscalculatedbythecoremonitoringsystempriortoUPDATE.AllthenodalTIPRMSvaluesintheattachedfigureswerecalculatedbyPP&Lfromthe"base"data.Inallbutafewcases,thenodalTIPRMSforPOWERPLEXwithCPM-2inputislessthanthatofPOWERPLEXwithXFYREinput,Theseresultsindicatethat,forSusquehanna,POWERPLEXwithCPM-2inputismoreaccurateincalculatingthepowershapethanPOWERPLEXwithXFYREinput.ThisconclusioncorroboratesthePP&LuncertaintycalculationspresentedinReference1-2.However,afterdiscussionswiththestaff,PP&LhasagreedtousethecurrentlyapprovedSNPsetofpowerdistributionuncertaintiesfromReference1-3.Basedontheabovedatacomparisons,theSNPpowerdistributionuncertaintiesareconservativeformonitoringthecorewithCPM-2inputintheSusquehannaPOWERPLEXcoremonitoringsystem.Therefore,theSNPuncertaintiesfromReference1-3willbeusedintheSafetyLimitMCPRcalculationsinlieuofPP&L'sproposeduncertainties.PleasenotethatthePP&LresultsbasedonXFYREareconsideredproprietarybySiemensNuclearPowerCorporation(SNP)andwillnotbeincludedintheapprovedversionofthePP&LApplicationsTopicalReport.

References:

1-1"ApplicationofReactorAnalysisMethodsforBWRDesignandAnalysis",PINF-90-001,August1990.1-2PI'A-3578,H.W.KeisertoW.R.Butler,"FinalResponsetoRAIonPINF-90-001",datedJune4,1991.1-3"ExxonNuclearMethodologyforBoilingWaterReactors-NeutronicMethodsforDesignandAnalysis",XN-NF-80-19(P)(A),Volume1andXN-NF40-19(P)(A),Volume1,Supplements1&2,March1983.

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