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| {{#Wiki_filter: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 | | {{#Wiki_filter: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 |
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| ==SUBJECT:== | | ==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
| | 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$81DirectorofNuclearReactorRegulation Attention: |
| | Dr.W.R.Butler,ProjectDirectorProjectDirectorate I-2DivisionofReactorProjectsU.S.NuclearRegulatory Commission Washington, D.C.20555SUSQUEIIANNA STEAMELECTRICSTATIONLICENSING METHODS:SUPPORTING INFORMATION DocketNos.50-387PLA-6FILR41-2Aand50-388irW |
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| ==References:== | | ==References:== |
| 1."ApplicationofReactorAnalysisMethodsfor,BWRDesignandAnalysis",PINF-90-001,August1990.2."QualificationofTransientAnalysis'MethodsforBWRDesignandAnalysis",PINF-89-00$,December1989.3.PLA-3641,H.W.Ket'sertoW.R.Butler,"LicensingMethods:PlanforU1C7",datedAugust29,1991. | | |
| | 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. |
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| |
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| ==DearDr.Butler:== | | ==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-2-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. | | 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:== | | ==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. | | |
| | 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. |
| 04I<<f}} | | 04I<<f}} |
|
|---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARPLA-5120, Forwards Change J to SSES Security Training & Qualification Plan.Without Encl1999-10-22022 October 1999
Forwards Change J to SSES Security Training & Qualification Plan.Without Encl
ML18040B2951999-09-0808 September 1999
Requests Info Re Any NRC or Susquehanna Documented Concerns with MSIV Reliability Prior to Plant Trip & Assurance to Public That NRC Able to Detect Mgt Problems Early
PLA-5094, Forwards,For Review,Change 00 to SSES Physical Security Plan.Without Encl1999-08-24024 August 1999
Forwards,For Review,Change 00 to SSES Physical Security Plan.Without Encl
ML18040A9741999-07-0808 July 1999
Forwards Rev 30 to SSES Emergency Plan, Adding EAL to Account for Potential Conditions Associated with Dry Cask Storage Sys Being Installed at Plant
ML20207G5051999-06-0707 June 1999
Informs That NRC Office of NRR Reorganized Effective 990328.As Part of Reorganization,Divison of Licensing Project Management Created
PLA-5072, Forwards Change Nn to SSES Physical Security Plan.Util Determined That Changes Do Not Decrease Safeguards Effectiveness of Plan,Per 10CFR50.54(p).Encl Withheld from Public Disclosure,Per 10CFR73.211999-06-0404 June 1999
Forwards Change Nn to SSES Physical Security Plan.Util Determined That Changes Do Not Decrease Safeguards Effectiveness of Plan,Per 10CFR50.54(p).Encl Withheld from Public Disclosure,Per 10CFR73.21
ML18040A9731999-05-24024 May 1999
Submits Response to RAI Re Exemption from Biennial Exercise Schedule.Changing of Drill Date Will Not Reduce Level of Emergency Preparedness at Plant
ML20195B2181999-05-20020 May 1999
Forwards Proprietary Decommissioning Status Rept for 10% Interest in Sses,Units 1 & 2.Proprietary Info Withheld,Per 10CFR2.790
ML18040B2901999-04-30030 April 1999
Forwards Summary Rept of Safety Evaluations Approved During Period from 961024-981029,per 10CFR50.59(b).Format of Rept, Listed
PLA-5041, Forwards Proprietary & Redacted Decommissioning Rept of Financial Assurance for Util 90% Interest in Sses,Units 1 & 2,per 10CFR50.75(f)(1).Proprietary Info Withheld,Per 10CFR2.7901999-03-29029 March 1999
Forwards Proprietary & Redacted Decommissioning Rept of Financial Assurance for Util 90% Interest in Sses,Units 1 & 2,per 10CFR50.75(f)(1).Proprietary Info Withheld,Per 10CFR2.790
ML18040A9691999-03-12012 March 1999
Forwards Revised Proposed Amend 227 to License NPF-14, Proposing Changes to ANFB-10 Critical Power Correlation & MCPR Safety Limits
ML17164A9891999-03-12012 March 1999
Informs That Util 990312 Ltr (PLA-5040) Submitted to NRC, Missing Encl C.Requests to Replace Package in Entirety with Encl
ML18040A9721999-03-11011 March 1999
Requests That Date for full-participation SSES Exercise, Scheduled for Week of 991115,be Changed Due to FEMA Region III Scheduling Conflicts.Fema Requests That Exercise Date Be Changed to Week of 001031
PLA-4852, Forwards non-redacted Version of Pp&L,Inc Corporate Auditing Rept 739459-2-98,dated 980210.Informs That Document Contains Info to Be Withheld IAW 10CFR2.7901999-02-18018 February 1999
Forwards non-redacted Version of Pp&L,Inc Corporate Auditing Rept 739459-2-98,dated 980210.Informs That Document Contains Info to Be Withheld IAW 10CFR2.790
ML20203G5821999-02-17017 February 1999
Second Final Response to FOIA Request for Documents. Documents Listed in App C Being Released in Entirety. Documents Listed in App D Being Withheld in Part (Ref FOIA Exemption 5)
ML20202F4761999-01-29029 January 1999
First Partial Response to FOIA Request for Documents.Records in App a Encl & Being Released in Entirety.App B Records Being Withheld in Part (Ref FOIA Exemption 7C)
ML18040A9671999-01-29029 January 1999
Notifies That Util Implemented Severe Accident Mgt Strategy in Accordance with Ltr Dtd 950327.Emegency Plan Revs Which Were Required to Implement Strategy Were Submitted by Ltr Dtd 981125
ML18040A9681999-01-29029 January 1999
Requests Exemption from Requirements of 10CFR50 App E,Items IVF.2.b & C,To Allowed to Reschedule Federally Observed Full Participation Emergency Exercise for SSES from Wk of 991115 to Wk of 001031
ML18040A9651999-01-12012 January 1999
Submits Addl Info Re Proposed Amend 184 to License NPF-22 for ANFB-10 Critical Power Correlation & MCPR Safety Limits
ML18030A1021998-12-16016 December 1998
Forwards Tables as Requested During 981202 Telcon Re Proposed Amend 184,dtd 980804,re ANFB-10 Critical Power Correlation & MCPR Safety Limits.Tables Provide Roadmap Identifying Applicability of References to TSs
ML18030A4331998-11-25025 November 1998
Forwards Rev 29 to SSES Emergecny Plan.Changes Has Been Made Without Commission Approval as It Does Not Decrease Effectiveness of Plan & Plan as Changed Continues to Satisfy Applicable Requirements of App E to 10CFR50
ML20195J9101998-11-18018 November 1998
Forwards Notice of Withdrawal of Application for Amends to Facility Operating Licenses (Notice).Notice Has Been Filed with Ofc of Fr.Amends Would Have Revised TS to Eliminate HPCI Pump auto-transfer on High Suppression Pool Level
ML20155F7201998-11-0303 November 1998
Final Response to FOIA Request for Documents.Documents Listed in App B Being Encl & Being Released in Entirety. Documents Listed in App C Being Withheld in Part (Ref Exemption 7C)
ML18026A2941998-10-19019 October 1998
Forwards SSES ISI Outage Summary Rept for Unit 1 Tenth Refueling & Insp Outage
ML18030A4321998-10-12012 October 1998
Forwards Rev 28 to SSES Emergency Plan, IAW Requirements of 10CFR50.54q.Change Is Summarized
PLA-4993, Forwards Change Mm to SSES Physical Security Plan.Encl Withheld,Per 10CFR73.211998-10-12012 October 1998
Forwards Change Mm to SSES Physical Security Plan.Encl Withheld,Per 10CFR73.21
ML18030A1001998-10-12012 October 1998
Forwards Rev 27 to SSES Emergency Plan. Changes Become Effective Upon Implementation of Improved Tech Specs
ML18030A4311998-09-29029 September 1998
Forwards Rev 27 & 28 to SSES Emergency Plan
ML20151W4951998-09-10010 September 1998
Informs That as Part of NRC Probabilistic Risk Assessment Implementation Plan,Commission Assigned Two Senior Reactor Analysts (Sras) to Each Regional Ofc.T Shedlosky & J Trapp Has Been Assigned SRAs for Region I
IR 05000387/19980081998-09-0808 September 1998
Provides Response to Violations Noted in Insp Repts 50-387/98-08 & 50-388/98-08.Corrective Actions:Current Administrative Controls on Fuel Level in EDG Day Tanks Will Remain in Effect Until TS Change is Approved
ML18030A0991998-09-0808 September 1998
Provides Response to Violations Noted in Insp Repts 50-387/98-08 & 50-388/98-08.Corrective Actions:Current Administrative Controls on Fuel Level in EDG Day Tanks Will Remain in Effect Until TS Change Is Approved
ML18026A4961998-08-31031 August 1998
Responds to NRC 980731 Ltr Re Violations Noted in Insp Repts 50-387/98-03 & 50-388/98-03.Corrective Actions:Procurement & Affected User Group Personnel Visited EDG Vendor Facilities to Appraise Vendor Work Practices & Discuss Expectations
IR 05000387/19980031998-08-31031 August 1998
Responds to NRC 980731 Ltr Re Violations Noted in Insp Repts 50-387/98-03 & 50-388/98-03.Corrective Actions:Procurement & Affected User Group Personnel Visited EDG Vendor Facilities to Appraise Vendor Work Practices & Discuss Expectations
ML20202F5501998-07-17017 July 1998
Responds to PP&L Corp Auditing Repts 739459-97,739459-1-97 & 739459-2-98 Re SSES Investigations Into Missed Alarm Tests
ML20236P9451998-07-15015 July 1998
Forwards Emergency Response Data Sys Implementation Documents Including Data Point Library Updates for Oconee (Number 255),Dresden (Number 257) & Susquehanna (Number 258)
ML18030A4291998-07-0808 July 1998
Forwards Final Version of SSES TS Implementing Improved TS of NUREG-1433.Implementation of Proposed Amend Is Predicted on NRC Issuance of Amends & Proposed to Not Exceed 90 Days from Date of Amend Issue
ML18017A2181998-07-0808 July 1998
Forwards Final Version of SSES TS Implementing Improved Tech Specs of NUREG 1433.Implementation of Proposed Amend Is Predicated on NRC Issuance of Amends & Is Proposed to Not Exceed 90 Days from Date of Amend Issuance
ML18026A2901998-06-0909 June 1998
Forwards Rev 26 to Emergency Plan IAW 10CFR50.54q.Summary of Changes Listed
ML18026A2891998-05-22022 May 1998
Submits Withdrawal of Expedited Review/Approval of Tech Specs/Bases 3/4.3.7.11 & 3/4.11.2.6 & Response to Request for Addl Info Re Offgas Sys Mods
ML18026A4941998-05-12012 May 1998
Responds to NRC Request to Resubmit Proposal to Change TS for Plant,Units 1 & 2,to Support Implementation of Improved TS & to Implement Provisions of GL 86-10 Re Relocation of Plant'S Fire Protection Program from TS to Another Document
ML20202H1331998-04-16016 April 1998
Partially Deleted Ltr Re Concerns Raised to NRC Concerning PP&L Susquehanna Facility
NUREG-0619, Informs That Staff Finds PP&L 980330 Request for Relief from Requirements of Section 4.3 of NUREG-0619,exams of Feedwater Nozzle Bore & Inner Radius for Another Operating Cycle to Be Acceptable1998-04-15015 April 1998
Informs That Staff Finds PP&L 980330 Request for Relief from Requirements of Section 4.3 of NUREG-0619,exams of Feedwater Nozzle Bore & Inner Radius for Another Operating Cycle to Be Acceptable
ML20216B6811998-04-0101 April 1998
First Partial Response to FOIA Request for Documents. Forwards Documents Listed in App a Being Released in Entirety
ML17159A2341998-03-30030 March 1998
Forwards LER 97-007-01,per 10CFR50.73(a)(2)(i)(B).Revised LER Submitted to Modify Previous Position W/Regards to Entry Into TS 3.0.3 for Event
PLA-4865, Forwards Listed non-redacted Pp&L,Inc Corporate Auditing Repts.Informs That Document Contains Info to Be Withheld IAW 10CFR2.7901998-03-11011 March 1998
Forwards Listed non-redacted Pp&L,Inc Corporate Auditing Repts.Informs That Document Contains Info to Be Withheld IAW 10CFR2.790
ML17159A1781998-03-0202 March 1998
Forwards Proposed Amends 203 & 161 to License NPF-14 & NPF-22,revising Tech Specs to Be Consistent w/NUREG-1433,rev 1, Std Tech Specs for GE Plants,Bwr 4.
PLA-4856, Forwards Proposed Amends to Licenses NPF-14 & NPF-22, Revising TS to Be Consistent w/NUREG-1433,rev 1, Std TS for GE Plants,Bwr 4. Proposed TS Consistent w/NUREG-1433,rev 1, Encl1998-03-0202 March 1998
Forwards Proposed Amends to Licenses NPF-14 & NPF-22, Revising TS to Be Consistent w/NUREG-1433,rev 1, Std TS for GE Plants,Bwr 4. Proposed TS Consistent w/NUREG-1433,rev 1, Encl
PLA-4854, Provides Summary of Investigations That PP&L Performed in Response to Concerns Identified by Former Nuclear Plant Operator.Summary Requested by Cj Anderson on 9802131998-02-27027 February 1998
Provides Summary of Investigations That PP&L Performed in Response to Concerns Identified by Former Nuclear Plant Operator.Summary Requested by Cj Anderson on 980213
ML20203M5071998-02-26026 February 1998
Final Response to FOIA Request for Documents.Records in App a Being Placed in PDR & Encl.Records in App B Partially Withheld (Ref FOIA Exemption 6)
ML20203B5931998-02-23023 February 1998
Ack Receipt of & Wire in Amount of $55,000 in Payment for Civil Penatly Proposed by NRC Ltr . Corrective Actions Will Be Examined During Future Inspections
1999-09-08
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARPLA-5120, Forwards Change J to SSES Security Training & Qualification Plan.Without Encl1999-10-22022 October 1999
Forwards Change J to SSES Security Training & Qualification Plan.Without Encl
ML18040B2951999-09-0808 September 1999
Requests Info Re Any NRC or Susquehanna Documented Concerns with MSIV Reliability Prior to Plant Trip & Assurance to Public That NRC Able to Detect Mgt Problems Early
PLA-5094, Forwards,For Review,Change 00 to SSES Physical Security Plan.Without Encl1999-08-24024 August 1999
Forwards,For Review,Change 00 to SSES Physical Security Plan.Without Encl
ML18040A9741999-07-0808 July 1999
Forwards Rev 30 to SSES Emergency Plan, Adding EAL to Account for Potential Conditions Associated with Dry Cask Storage Sys Being Installed at Plant
PLA-5072, Forwards Change Nn to SSES Physical Security Plan.Util Determined That Changes Do Not Decrease Safeguards Effectiveness of Plan,Per 10CFR50.54(p).Encl Withheld from Public Disclosure,Per 10CFR73.211999-06-0404 June 1999
Forwards Change Nn to SSES Physical Security Plan.Util Determined That Changes Do Not Decrease Safeguards Effectiveness of Plan,Per 10CFR50.54(p).Encl Withheld from Public Disclosure,Per 10CFR73.21
ML18040A9731999-05-24024 May 1999
Submits Response to RAI Re Exemption from Biennial Exercise Schedule.Changing of Drill Date Will Not Reduce Level of Emergency Preparedness at Plant
ML20195B2181999-05-20020 May 1999
Forwards Proprietary Decommissioning Status Rept for 10% Interest in Sses,Units 1 & 2.Proprietary Info Withheld,Per 10CFR2.790
ML18040B2901999-04-30030 April 1999
Forwards Summary Rept of Safety Evaluations Approved During Period from 961024-981029,per 10CFR50.59(b).Format of Rept, Listed
PLA-5041, Forwards Proprietary & Redacted Decommissioning Rept of Financial Assurance for Util 90% Interest in Sses,Units 1 & 2,per 10CFR50.75(f)(1).Proprietary Info Withheld,Per 10CFR2.7901999-03-29029 March 1999
Forwards Proprietary & Redacted Decommissioning Rept of Financial Assurance for Util 90% Interest in Sses,Units 1 & 2,per 10CFR50.75(f)(1).Proprietary Info Withheld,Per 10CFR2.790
ML17164A9891999-03-12012 March 1999
Informs That Util 990312 Ltr (PLA-5040) Submitted to NRC, Missing Encl C.Requests to Replace Package in Entirety with Encl
ML18040A9691999-03-12012 March 1999
Forwards Revised Proposed Amend 227 to License NPF-14, Proposing Changes to ANFB-10 Critical Power Correlation & MCPR Safety Limits
ML18040A9721999-03-11011 March 1999
Requests That Date for full-participation SSES Exercise, Scheduled for Week of 991115,be Changed Due to FEMA Region III Scheduling Conflicts.Fema Requests That Exercise Date Be Changed to Week of 001031
PLA-4852, Forwards non-redacted Version of Pp&L,Inc Corporate Auditing Rept 739459-2-98,dated 980210.Informs That Document Contains Info to Be Withheld IAW 10CFR2.7901999-02-18018 February 1999
Forwards non-redacted Version of Pp&L,Inc Corporate Auditing Rept 739459-2-98,dated 980210.Informs That Document Contains Info to Be Withheld IAW 10CFR2.790
ML18040A9681999-01-29029 January 1999
Requests Exemption from Requirements of 10CFR50 App E,Items IVF.2.b & C,To Allowed to Reschedule Federally Observed Full Participation Emergency Exercise for SSES from Wk of 991115 to Wk of 001031
ML18040A9671999-01-29029 January 1999
Notifies That Util Implemented Severe Accident Mgt Strategy in Accordance with Ltr Dtd 950327.Emegency Plan Revs Which Were Required to Implement Strategy Were Submitted by Ltr Dtd 981125
ML18040A9651999-01-12012 January 1999
Submits Addl Info Re Proposed Amend 184 to License NPF-22 for ANFB-10 Critical Power Correlation & MCPR Safety Limits
ML18030A1021998-12-16016 December 1998
Forwards Tables as Requested During 981202 Telcon Re Proposed Amend 184,dtd 980804,re ANFB-10 Critical Power Correlation & MCPR Safety Limits.Tables Provide Roadmap Identifying Applicability of References to TSs
ML18030A4331998-11-25025 November 1998
Forwards Rev 29 to SSES Emergecny Plan.Changes Has Been Made Without Commission Approval as It Does Not Decrease Effectiveness of Plan & Plan as Changed Continues to Satisfy Applicable Requirements of App E to 10CFR50
ML18026A2941998-10-19019 October 1998
Forwards SSES ISI Outage Summary Rept for Unit 1 Tenth Refueling & Insp Outage
ML18030A4321998-10-12012 October 1998
Forwards Rev 28 to SSES Emergency Plan, IAW Requirements of 10CFR50.54q.Change Is Summarized
ML18030A1001998-10-12012 October 1998
Forwards Rev 27 to SSES Emergency Plan. Changes Become Effective Upon Implementation of Improved Tech Specs
PLA-4993, Forwards Change Mm to SSES Physical Security Plan.Encl Withheld,Per 10CFR73.211998-10-12012 October 1998
Forwards Change Mm to SSES Physical Security Plan.Encl Withheld,Per 10CFR73.21
ML18030A4311998-09-29029 September 1998
Forwards Rev 27 & 28 to SSES Emergency Plan
ML18030A0991998-09-0808 September 1998
Provides Response to Violations Noted in Insp Repts 50-387/98-08 & 50-388/98-08.Corrective Actions:Current Administrative Controls on Fuel Level in EDG Day Tanks Will Remain in Effect Until TS Change Is Approved
IR 05000387/19980081998-09-0808 September 1998
Provides Response to Violations Noted in Insp Repts 50-387/98-08 & 50-388/98-08.Corrective Actions:Current Administrative Controls on Fuel Level in EDG Day Tanks Will Remain in Effect Until TS Change is Approved
ML18026A4961998-08-31031 August 1998
Responds to NRC 980731 Ltr Re Violations Noted in Insp Repts 50-387/98-03 & 50-388/98-03.Corrective Actions:Procurement & Affected User Group Personnel Visited EDG Vendor Facilities to Appraise Vendor Work Practices & Discuss Expectations
IR 05000387/19980031998-08-31031 August 1998
Responds to NRC 980731 Ltr Re Violations Noted in Insp Repts 50-387/98-03 & 50-388/98-03.Corrective Actions:Procurement & Affected User Group Personnel Visited EDG Vendor Facilities to Appraise Vendor Work Practices & Discuss Expectations
ML18017A2181998-07-0808 July 1998
Forwards Final Version of SSES TS Implementing Improved Tech Specs of NUREG 1433.Implementation of Proposed Amend Is Predicated on NRC Issuance of Amends & Is Proposed to Not Exceed 90 Days from Date of Amend Issuance
ML18030A4291998-07-0808 July 1998
Forwards Final Version of SSES TS Implementing Improved TS of NUREG-1433.Implementation of Proposed Amend Is Predicted on NRC Issuance of Amends & Proposed to Not Exceed 90 Days from Date of Amend Issue
ML18026A2901998-06-0909 June 1998
Forwards Rev 26 to Emergency Plan IAW 10CFR50.54q.Summary of Changes Listed
ML18026A2891998-05-22022 May 1998
Submits Withdrawal of Expedited Review/Approval of Tech Specs/Bases 3/4.3.7.11 & 3/4.11.2.6 & Response to Request for Addl Info Re Offgas Sys Mods
ML18026A4941998-05-12012 May 1998
Responds to NRC Request to Resubmit Proposal to Change TS for Plant,Units 1 & 2,to Support Implementation of Improved TS & to Implement Provisions of GL 86-10 Re Relocation of Plant'S Fire Protection Program from TS to Another Document
ML17159A2341998-03-30030 March 1998
Forwards LER 97-007-01,per 10CFR50.73(a)(2)(i)(B).Revised LER Submitted to Modify Previous Position W/Regards to Entry Into TS 3.0.3 for Event
PLA-4865, Forwards Listed non-redacted Pp&L,Inc Corporate Auditing Repts.Informs That Document Contains Info to Be Withheld IAW 10CFR2.7901998-03-11011 March 1998
Forwards Listed non-redacted Pp&L,Inc Corporate Auditing Repts.Informs That Document Contains Info to Be Withheld IAW 10CFR2.790
PLA-4856, Forwards Proposed Amends to Licenses NPF-14 & NPF-22, Revising TS to Be Consistent w/NUREG-1433,rev 1, Std TS for GE Plants,Bwr 4. Proposed TS Consistent w/NUREG-1433,rev 1, Encl1998-03-0202 March 1998
Forwards Proposed Amends to Licenses NPF-14 & NPF-22, Revising TS to Be Consistent w/NUREG-1433,rev 1, Std TS for GE Plants,Bwr 4. Proposed TS Consistent w/NUREG-1433,rev 1, Encl
ML17159A1781998-03-0202 March 1998
Forwards Proposed Amends 203 & 161 to License NPF-14 & NPF-22,revising Tech Specs to Be Consistent w/NUREG-1433,rev 1, Std Tech Specs for GE Plants,Bwr 4.
PLA-4854, Provides Summary of Investigations That PP&L Performed in Response to Concerns Identified by Former Nuclear Plant Operator.Summary Requested by Cj Anderson on 9802131998-02-27027 February 1998
Provides Summary of Investigations That PP&L Performed in Response to Concerns Identified by Former Nuclear Plant Operator.Summary Requested by Cj Anderson on 980213
ML20216B7031998-02-22022 February 1998
Partially Deleted Ltr Requesting Copy of OI Rept on Plant, Unit 2,case 1-96-039
PLA-4851, Provides Info That Was Requested by Cj Anderson on 980213 Re Former Util Employee Concern on Radwaste Control Room Offgas Panel Alarm Testing1998-02-18018 February 1998
Provides Info That Was Requested by Cj Anderson on 980213 Re Former Util Employee Concern on Radwaste Control Room Offgas Panel Alarm Testing
ML20203M5791998-02-10010 February 1998
Enters Appeal Due to Lack of Response to FOIA Request 97-473
ML18030A0971998-02-0202 February 1998
Forwards Proprietary Response to RAI Re Proposed License Amend 209 to TS Supporting Cycle 11 Reload.Proprietary Info Withheld,Per 10CFR2.790
ML20203G6071998-01-26026 January 1998
Forwards Redacted Version of Pp&L,Inc Corporate Auditings Interim Rept 739459-97,dtd 971015 & Affidavit Pursuant to 10CFR2.790 Justifying That Redacted Portions Be Withheld from Public Disclosure.Without Rept
IR 05000387/19970031998-01-0606 January 1998
Provides Updated Response to Violations Noted in Insp Repts 50-387/97-03 & 50-388/97-03.Corrective Actions:Util Currently Scheduling Issuance of All Procedural Revs by End of First Quarter 1998
ML18017A2931998-01-0606 January 1998
Provides Responses to Improved TS Section 3.8 Per 970324 NRC Rai.Schedule 980628 for Improved TS Implementation. Submittal of Revised Specifications Is Planned for Jan 1998
ML18030A4071998-01-0606 January 1998
Provides Updated Response to Violations Noted in Insp Repts 50-387/97-03 & 50-388/97-03.Corrective Actions:Util Currently Scheduling Issuance of All Procedural Revs by End of First Quarter 1998
PLA-4828, Expresses Appreciation for Support Received by Former Project Manager C Poslusny1997-12-29029 December 1997
Expresses Appreciation for Support Received by Former Project Manager C Poslusny
IR 05000387/19970041997-12-22022 December 1997
Resolves Commitments Made in Response to NOV Issued As Part of NRC Insp Repts 50-387/97-04 & 50-388/97-04 Dtd 970805. Proposed FSAR QA Program Description Changes,Reason for Changes & Basis Included for Approval
ML18026A4901997-12-22022 December 1997
Resolves Commitments Made in Response to NOV Issued as Part of NRC Insp Repts 50-387/97-04 & 50-388/97-04 Dtd 970805. Proposed FSAR QA Program Description Changes,Reason for Changes & Basis Included for Approval
ML20203M5741997-12-0505 December 1997
FOIA Request for Copy of Latest OI Rept on Susquehanna Ses Including All Exhibits & for Any Other Communication Between NRC & Susquehanna Ses/Pp&L
PLA-4818, Forwards Redacted Version of Pp&L,Inc Corporate Auditings Rept 739459-1-97,dtd 971201 & Affidavit Pursuant to 10CFR2.790 Justifying That Redacted Portions Be Withheld from Public Disclosure.Without Rept1997-12-0404 December 1997
Forwards Redacted Version of Pp&L,Inc Corporate Auditings Rept 739459-1-97,dtd 971201 & Affidavit Pursuant to 10CFR2.790 Justifying That Redacted Portions Be Withheld from Public Disclosure.Without Rept
1999-09-08
[Table view] |
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.
04I<<f
