ML18040A969

From kanterella
Revision as of 03:19, 29 June 2018 by StriderTol (talk | contribs) (Created page by program invented by StriderTol)
Jump to navigation Jump to search
Forwards Revised Proposed Amend 227 to License NPF-14, Proposing Changes to ANFB-10 Critical Power Correlation & MCPR Safety Limits
ML18040A969
Person / Time
Site: Susquehanna Talen Energy icon.png
Issue date: 03/12/1999
From: BYRAM R G
PENNSYLVANIA POWER & LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17164A990 List:
References
PLA-5040, NUDOCS 9903290101
Download: ML18040A969 (4)


Text

RobertG.ByramSeniorVicePresident Generation andChiefNuclearOfficerTel.610.774.7502 Fax610.774.5019 E-mail:rgbyrame papl.corn BAR1:21999PPtLL,Inc.TwoNorthNinthStreetAllentown, PA18101-1179 Tel.610.774.51 51http:ltwww.pap!.corn/

gsrLsQ~w+emU.S.NuclearRegulatory Commission Attn.:DocumentControlDeskMailStationP1-137Washington, D.C.20555SUSQUEHANNA STEAMELECTRICSTATIONPROPOSEDAMENDMENT NO.227TOLICENSENPF-14:ANFB-10CRITICAL.

POWER.CORRELATION AND.MCPRSAFETYLIMITSPLA-5040%1IDocketNo.50-387

References:

1.LetterPom VictorNerses(NRC)toRobertG.Byram(PP&L),"Susquehanna SteamElectricStation,Unit2PACNo.MA2434),"February 17,1999.2.EMF-1997(P)(A)Revision0,"ANFB-10CriticalPowerCorrelation, "July1998,andEMF-1997(P)(A)Supplement 1Revision0,"ANFB-10Cr'itical PowerCorrelation:

HighLocalPeakingResults,"July1998.3.ANF-I125(P)(A)andANF-1125(P)(A),Supplement 1,"ANFBCriticalPowerCorrelation, "April1990.4.PL-NF-90-001-A, "Application ofReactorAnalysisMethodsforBWRDesignandAnalysis, "July1992,plusSupplements 1-A(August1995)and2-A(July1996).5.'MF-97-010(P),

Rev.1,"Application ofANFBtoATRlUMrM-10forSusquehanna Reloads,"March1997.6.PLA-4595, "Response toNRCRequestforAdditional Information onSiemens'eportEMF-97-'1'0,Revision1,"Mar'ch27,199'7.'.ANF-524(P)(A),

Revision2andSupplement 1,Revision2,"Advanced NuclearFuelsCorporation CriticalPowerMethodology forBoilingWaterReactors, "November1990.8.CENPD-300-P, "Reference SafetyReportforBoilingWaterReactorReloadFuel,"ABBCombustion Engineering NuclearOperations, November1994.~iThepurposeofthisletteristoproposechangestotheSusquehanna SteamElectricStationUnit1Technical Specifications, whicharesimilartothoserecentlyapprovedinFebruary1999forUnit2(Reference 1).Reference 2documents theNRCapprovedcriticalpower'correlation applicable toSiemensPowerCorporation (SPC)ATRIUMŽ-10 fuel(referred toasANFB-10).

Thisproposedchangeentailstheinclusion ofReference 2inSection5.6.5andtheinclusion ofrevisedMCPRSafetyLimitsinSection2.1.1.2.Anadministrative changetoSection5.6.5isincluded.

Anumberofreferences fromSection5.6.5areremovedinordertoincludeonlythosereferences whichdirectlysupportthegeneration oftheCoreOperating Limitsandtoremovethereference fortheABBLeadUseAssemblies (Reference 8),whichwillbedischarged duringthenextUnit1outage.Associated BASESchangesarealsoincluded.

9903290101.

9'70312PDRADOCK05000387I'PPDRbpPOIi PLA-5040DocumentControlDeskTheANFB-10correlation willbeusedintheanalysisofATRIUMŽ-10 fuelinplaceoftheANFBcriticalpowercorrelation andmethodology described inReferences 5and6.TheANFBcorrelation (Reference 3)willcontinuetobeusedintheanalysisofSPC9x9-2fuel.TheANFB(for9x9-2)andANFB-10(forATRIUM~-10) correlations willbeusedwithPP&L'sandSPC'sNRCapprovedmethods,andanalyseswillbeperformed (consistent withthosemethods)togenerateCoreOperating Limits.Therefore, PP&Lwillnotbesubmitting achangetoitsNRC-approvedTopicalReports(Reference 4)sincethemethodology isthesameexceptANFB-10willbeusedtoanalyzeATRIUM-10fuel.SPCreportEMF-1997, gggA),Rev.0andSupplement 1,Rev.0(proposed,to Qe.addedtothe,.Technical Specification Administrative Controlssection)describes theANFB-10criticalpowercorrelation, whichhasbeenapprovedby'theNRC.Enclosure Atothisletteristhe"SafetyAssessment" supporting thischange.Enclosure Bisthe"NoSignificant HazardsConsiderations andEnvironmental Assessment" evaluation performed inaccordance withthecriteriaof10CFR50.92.Enclosure Ctothislettercontainstheapplicable pagesoftheSusquehanna SESUnit1Technical Specifications, markedtoshowtheproposedchangesaswellastheassociated BASESchanges.TheproposedchangeshavebeenapprovedbytheSusquehanna SESPlantOperations ReviewCommittee, andreviewedbytheSusquehanna ReviewCommittee.

Toassistinyourreview,Attachments Unit1Cycle12CoreComposition.

Technical Specifications forthoseSpecifications.

DandEhavebeenprovided.

Attachment DprovidestheAttachment Eprovidesacross-reference toapplicable references specified inSection5.6.5ofTechnical

  • 'PP&Lplanstoimplement theproposedchangesinMay2000tosupportthestartupofUnit1Cycle12operation.

Therefore, werequestNRCcompleteitsreviewofthischangebyFebruary11,2000withthechangeseffective uponstartupfollowing theUnit111~Refueling andInspection Outagetosupportourscheduled implementation date.Anyquestions regarding thisrequestshouldbedirectedto.Mr.R.R.Sgarroat(610)774-7552.'ery trulyyours,R..By PLA-5040DocumentControlDeskcopy:NRCRegionIMr.V.Nerses,NRCSr.ProjectManager-QWFNMr.S.L.Hansell,ActingNRCSr.ResidentInspector-SSESMr.D.J.Allard,Pa.DEP 0l