ML18030A078

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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  Talen Energy icon.png
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:
References
PLA-3663, NUDOCS 9110280248
Download: ML18030A078 (8)


Text

LERATEDDIHUBUTIONDEMONTIONSYSTEMt~S~eREGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9110280248 DOC.DATE:

91/10/17NOTARIZED:

YESFACIL:50-387 Susquehanna SteamElectricStation,Unit1,Pennsylva 50-'388Susquehanna SteamElectricStation,Unit2,Pennsylva AUTH.NAMEAUTHORAFFILIATION KEISER,H.W.

Pennsylvania Power&LightCo.RECIP.NAME RECIPIENT AFFILIATION BUTLER,W.R.

ProjectDirectorate I-2DOCKET0500038705000388

SUBJECT:

Transmits Powerplex responsedatacomparisons tosupportapprovalofutilapplication topicalreptPL-NF-90-001, "Application ofReactorAnalysisMethodsforBWRDesign&AnalysisforAug1990."DISTRIBUTION CODE:APOIDCOPIESRECEIVED:LTR iENCLQSIZE:Q+TITLE:Proprietary ReviewDistribution

-Operating ReactorDSRECIPIENT IDCODE/NAME PDl-2LARALEIGH,J.

COPIESLTTRENCL11'3NOTES:LPDR 1cyTranscripts.

LPDR1cyTranscripts.

RECIPIENT IDCODE/NAME PD1-2PDCOPIESLTTRENCL1105000387A05000388'DDINTERNAL:

ACRSOGC/HDS2EXTERNAL:

NRCPDRNOTES:66101022AEODE01RIDNOTETOALL"RIDS"RECIPIENTS:

PLEASEHELPUSTOREDUCEWAS'ONTACT THEDOCUMENTCONTROLDESK,ROOMPl-37(EXT.20079)TOELIMINATE YOURNAMEFROMDISTRIBUTION LINISFORDOCUMENTS YOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED:

LTTR17ENCL15ADDS 04 4ywPennsylvania Power8LightCompanyTwoNorthNinthStreet~Allentown, PA18101-1179

~215/774-5151 HaroldW.KeiserSeniorVicePresident-Nuclear 215/7744194 OCTl7$81DirectorofNuclearReactorRegulation Attention:

Dr.W.R.Butler,ProjectDirectorProjectDirectorate I-2DivisionofReactorProjectsU.S.NuclearRegulatory Commission Washington, D.C.20555SUSQUEIIANNA STEAMELECTRICSTATIONLICENSING METHODS:SUPPORTING INFORMATION DocketNos.50-387PLA-6FILR41-2Aand50-388irW

References:

1."Application ofReactorAnalysisMethodsfor,BWRDesignandAnalysis",

PINF-90-001, August1990.2."Qualification ofTransient Analysis'Methods forBWRDesignandAnalysis",

PINF-89-00$

,December1989.3.PLA-3641, H.W.Ket'sertoW.R.Butler,"Licensing Methods:PlanforU1C7",datedAugust29,1991.

DearDr.Butler:

TosupporttheNRC'sapprovalofPP&L'sApplications TopicalReport(Reference 1),wearetransmitting datacomparisons whichPP&Ldiscussed inameetingwithNRCandBNLrepresentatives onOctober4,1991attheNRC'sWhiteFlintoffice.Thisdatawasusedtodemonstrate thatthecurrentSiemensNuclearPowerCorporation (SNP)coremonitoring systemuncertainties areconservative formonitoring thecorewithPP&Lgenerated inputintheSusquehanna POWERPLEX coremonitoring system.Afterdiscussion withtheNRCstaffandthereviewer, however,PP&Lhasagreedtousethemoreconservative SNPuncertainties, ratherthanthePP&Lgenerated uncertainties.

Pleasenotethatthedatacomparisons whichareincludedinAtta'chment 1areconsidered proprietary bySNP.Asrequiredby10CFR2.790(b) anaffidavit tosupportwithholding thisinformation frompublicdisclosure iscontained inAttachment 2.Theproprietary portionofAttachment 1willnotbeincludedintheapprovedversionofthePP&LApplications TopicalReport.l91102S0248',91'10'17,?

tt'DR'AGOCK05000387PPDR lr(IIKII 0~~eI-2-FILESR41-2/A7-8C PLA-3663Dr.W.R.ButlerAsconveyedtoMessrs.JohnEmmettandAndrewDyszel,thetransmittal oftheenclosedmaterialclosesthelastremaining issueidentified duringthereviewofPP&L'sApplications TopicalReport.Further,itisourunderstanding thattheNRCwillproceedwithissuanceofSafetyEvaluation ReportsforPP&L'sApplications TopicalReport(Reference 1)andTransient AnalysisTopicalReport(Reference 2).PP&L,inturn,isproceeding withtheperformance oftheUnit1Cycle7reloadanalysesusingtheapproachagreedtobyPP&LandNRC(asdescribed inReference 3andherein).Inclosing,PP&Lwouldliketocompliment theNRCandBNLrepresentatives fortheirpromptresponseandcooperation inresolving thislastremaining issue.Anyquestions onthissubmittal shouldbedirectedtoMr.R.Sgarroat(215)774-7916.

Verytrulyyours,H.W.KeiserAttachments cc:QgRCDocumentContro13)eak.(original)

NRCRegionIMr.G.S.Barber,NRCSr.ResidentInspector

-SSESMr.J.J.Raleigh,NRCProjectManager-OWFNMr.L.I.Kopp,NRR/SRXB-OWFN 4i ATI'ACIIMENT 1TOPLA-3663FILESR41-2/A7-8C ATTACHMENT 1POWERPLEX TIPRESPONSECOMPARISONS TOSUPPORTAPPROVALOFPP&L'SAPPLICATIONS TOPICALREPORT(PL-NF-90-001)

TheSusquehanna datacomparisons calculated byPP&Lthatareshowninthisattachment supporttheconclusions that:1)thePOWERPLEX coremonitoring systemwithPP&Lgenerated CPM-2inputyieldsmoreaccurateresultsthanthePOWERPLEX coremonitoring systemwithSNPgenerated XFYREinput,and2)thecurrently approvedSNPpowerdistribution uncertainties areconservative forSusquehanna whenPP&LdevelopstheinputtothePOWERPLEX coremonitoring system.PP&L'scoremonitoring system,POWERPLEX, wasdeveloped bySNPandusesXTGBWRasthecoresimulation codeandmeasuredLPRMdatatomodifytheXTGBWRcalculated "base"powerdistribution toobtaina"measured" powerdistribution (i.e.,UPDATE).ThePOWERPLEX nodalTIPRMSdatapresented inthefollowing figuresisanindication ofhowaccuratethe3-DTIPresponse(i.e.,powershape)iscalculated bythecoremonitoring systempriortoUPDATE.AllthenodalTIPRMSvaluesintheattachedfigureswerecalculated byPP&Lfromthe"base"data.Inallbutafewcases,thenodalTIPRMSforPOWERPLEX withCPM-2inputislessthanthatofPOWERPLEX withXFYREinput,Theseresultsindicatethat,forSusquehanna, POWERPLEX withCPM-2inputismoreaccurateincalculating thepowershapethanPOWERPLEX withXFYREinput.Thisconclusion corroborates thePP&Luncertainty calculations presented inReference 1-2.However,afterdiscussions withthestaff,PP&Lhasagreedtousethecurrently approvedSNPsetofpowerdistribution uncertainties fromReference 1-3.Basedontheabovedatacomparisons, theSNPpowerdistribution uncertainties areconservative formonitoring thecorewithCPM-2inputintheSusquehanna POWERPLEX coremonitoring system.Therefore, theSNPuncertainties fromReference 1-3willbeusedintheSafetyLimitMCPRcalculations inlieuofPP&L'sproposeduncertainties.

PleasenotethatthePP&LresultsbasedonXFYREareconsidered proprietary bySiemensNuclearPowerCorporation (SNP)andwillnotbeincludedintheapprovedversionofthePP&LApplications TopicalReport.

References:

1-1"Application ofReactorAnalysisMethodsforBWRDesignandAnalysis",

PINF-90-001, August1990.1-2PI'A-3578, H.W.KeisertoW.R.Butler,"FinalResponsetoRAIonPINF-90-001",

datedJune4,1991.1-3"ExxonNuclearMethodology forBoilingWaterReactors-Neutronic MethodsforDesignandAnalysis",

XN-NF-80-19 (P)(A),Volume1andXN-NF40-19 (P)(A),Volume1,Supplements 1&2,March1983.

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