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| | number = ML17264A402 | | | number = ML17264A402 |
| | issue date = 03/15/1996 | | | issue date = 03/15/1996 |
| | title = Forwards Application for Amend to License DPR-18,to Incorporate Methodology for Determining Ltop Limits Into Administrative Controls Section 5.6.6,RCS Pressure Temp Limits Rept | | | title = Forwards Application for Amend to License DPR-18,to Incorporate Methodology for Determining LTOP Limits Into Administrative Controls Section 5.6.6,RCS Pressure Temp Limits Rept |
| | author name = MECREDY R C | | | author name = Mecredy R |
| | author affiliation = ROCHESTER GAS & ELECTRIC CORP. | | | author affiliation = ROCHESTER GAS & ELECTRIC CORP. |
| | addressee name = JOHNSON A R | | | addressee name = Johnson A |
| | addressee affiliation = NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) | | | addressee affiliation = NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| | docket = 05000244 | | | docket = 05000244 |
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| | document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE | | | document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE |
| | page count = 5 | | | page count = 5 |
| | | project = |
| | | stage = Request |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:CATEGORYj.REGULATCIINFORMATIONDISTRIBUTIONSTEM(RIDE)r~ACCESSIONNBR:9603210226DOC.DATE:96/03/3."5NOTARIZED:NO''FACIL:50-244RobertEmmetGinnaNuclearPlant,Unit1,RochesterG!tAUTH.NAMEAUTHORAFFILIATiONMECREDY,R.C.RochesterGas&ElectricCorp.RECIP.NAMERECIPIENTAFFILIATIONJOHNSON,A.R. | | {{#Wiki_filter:CATEGORY j. |
| | r~ |
| | REGULATCI INFORMATION DISTRIBUTIONSTEM (RIDE) |
| | ACCESSION NBR:9603210226 DOC.DATE: 96/03/3."5 NOTARIZED: NO DOCKET |
| | ''FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 |
| | !tAUTH.NAME AUTHOR AFFILIATiON MECREDY,R.C. Rochester Gas & Electric Corp. |
| | RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R. |
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| ==SUBJECT:== | | ==SUBJECT:== |
| ForwardsapplicationforamendtolicenseDPR-18,toincorporatemethodologyfordeterminingLTOPlimitsintoAdministrativeControlsSection5.6.6,RCSPressureTempLimitsRept.DISTRIBUTIONCODE:A001DCOPIESRECEIVED:LTRENCLSIZE:TITLE:ORSubmittal:GeneralDistributionDOCKET05000244ENOTES:LicenseExpdateinaccordancewithlOCFR2,2.109(9/19/72).05000244QRECIPIENTIDCODE/NAMEPD1-1LAJOHNSON,AINTERNAL:pLECE~lNRRQDRHHICBNRR/DSSA/SRXBOGC/HDS3EXTERNAL:NOACCOPIESLTTRENCL11111111111011RECIPIENTIDCODE/NAMEPD1-1PDNRR/DE/EMCBNRR/DSSA/SPLBNUDOCS-ABSTRACTNRCPDRCOPIESLTTRENCL1111111111D0UENNOTETOALL"RIDS"RECIPIENTS:PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMOWFN5D"5(EXT.415-2083)TOELIMINATEYOURNAMEFROMDISTRIBUTIONLISTSFORDOCUMENTSYOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED:LTTR12ENCLllI ANDROCHESTERGASANDElECTRICCORPORA71ON~89EASTAV&IUE,ROCHESTER,N.Y.146d9-0001AREACODE71rS$6-2700ROBERTC.MECREDYVicePresidentNvdeoroperationsMarch15,1996U.S.NuclearRegulatoryCommissionDocumentControlDeskAttn:AllenR.JohnsonProjectDirectorateI-3Washington,D.C.20555
| | Forwards application for amend to license DPR-18,to incorporate methodology for determining LTOP limits into Administrative Controls Section 5.6.6,RCS Pressure Temp Limits Rept. |
| | DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE: |
| | TITLE: OR Submittal: General Distribution E |
| | NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 Q |
| | RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-1 LA 1 1 PD1-1 PD 1 1 JOHNSON,A 1 1 INTERNAL:p LE CE ~l 1 1 NRR/DE/EMCB 1 1 NRRQDR H HICB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS3 1 0 EXTERNAL: NOAC 1 1 NRC PDR 1 1 D |
| | 0 U |
| | E N |
| | NOTE TO ALL "RIDS" RECIPIENTS: |
| | PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN 5D"5(EXT. 415-2083) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED! |
| | TOTAL NUMBER OF COPIES REQUIRED: LTTR I |
| | 12 ENCL ll |
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| | AND ROCHESTER GAS ANDElECTRIC CORPORA71ON ~ 89 EASTAV&IUE,ROCHESTER, N.Y. 146d9-0001 AREA CODE71rS $ 6-2700 ROBERT C. MECREDY Vice President Nvdeor operations March 15, 1996 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Allen R. Johnson Project Directorate I-3 Washington, D.C. 20555 |
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| ==Subject:== | | ==Subject:== |
| ApplicationforAmendmenttoFacilityOperatingLicenseImplementationofGenericLetter96-03RochesterGas&ElectricCorporationR.E.GinnaNuclearPowerPlantDocketNo.50-244
| | Application for Amendment to Facility Operating License Implementation of Generic Letter 96-03 Rochester Gas & Electric Corporation R.E. Ginna Nuclear Power Plant Docket No. 50-244 |
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| ==References:== | | ==References:== |
| (a)LetterfromR.C.Mecredy,RG&E,toA.R.Johnson,NRC, | | (a) Letter from R.C. Mecredy, RG&E, to A.R. Johnson, NRC, |
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| ==Subject:== | | ==Subject:== |
| ApplicationforAmendmenttoFacilityOperatingLicense,MethodologyforLowTemperatureOverpressureProtection(LTOP)Limits,datedFebruary9,1996.(b)GenericLetter96-03,RelocationofthePressureTemperatureLi1nitCurvesandLoivTeniperatureOverpressureProtectionSystemLimits(c)LetterfromL.T.Marsh,NRC,toR.C.Mecredy,RG&E,
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| | Application for Amendment to Facility Operating License, Methodology for Low Temperature Overpressure Protection (LTOP) Limits, dated February 9, 1996. |
| | (b) Generic Letter 96-03, Relocation of the Pressure Temperature Li1nit Curves and Loiv Teniperature Overpressure Protection System Limits (c) Letter from L.T. Marsh, NRC, to R.C. Mecredy, RG&E, |
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| ==Subject:== | | ==Subject:== |
| RLr.Ginna-AcceptanceforReferencingofPressureTemperatureLimitsReport(TACI/M92320),datedDecember26,1995. | | RLr. Ginna |
| | - Acceptance for Referencing ofPressure Temperature Limits Report (TAC I/M92320), dated December 26, 1995. |
| | |
| | ==Dear Mr. Johnson,== |
| | |
| | By Reference (a), RG&E proposed to revise the Ginna Station Technical Specifications to incorporate the methodology for determining the low temperature overpressure protection (LTOP) limits into Administrative Controls Section 5.6.6, RCS Pressure and Temperature Limits Report (PTLR). This change would allow RG&E to perform future LTOP evaluations using NRC approved methodology without requiring a potential technical specification change. However, any changes to the RCS pressure temperature (P/T) limits, which are also included in the PTLR, would still require prior NRC review and approval. Incorporation of the methodology for the P/T limits was not requested at the time since the NRC's review of the latest reactor vessel capsule data (which would provide input into the P/T limit determination) was incomplete. |
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| | However, the NRC's review of the latest reactor vessel capsule data is nearing completion which would allow use of previously NRC approved methodology. In addition, Generic Letter 96-03 (Ref. |
| | (b)) has been released by the NRC. This generic letter provides guidance for licensees to relocate the P/T limits and LTOP limits from technical specifications and to provide a mechanism for licensees to make changes to the limits using NRC approved methodology. RG8cE has previously relocated these limits; however, a license amendment is still required for all changes to the actual limits since the methodology for determining these limits has not been approved for future applications (Ref. (c)). As such, RGB is submitting this license amendment request (LAR) to incorporate the methodology for determining both LTOP limits and RCS P/T limits into Administrative Controls Section 5.6.6 consistent with Generic Letter 96-03. Therefore, this LAR supersedes that provided in Reference (a). |
| | Generic Letter 96-03 requests that licensees provide the following in their LAR: |
| | : 1. Provide a reference to the NRC approved P/T limit and LTOP limit methodology in the technical specifications; |
| | : 2. Develop a PTLR or similar document that contains the figures, values, parameters, and any explanations derived from the methodology; and |
| | : 3. Provide other required changes to various technical specifications (e.g., definitions section) to support the relocation of the P/T and LTOP limits. |
| | The purpose of this LAR is to provide the reference to the P/T limit and LTOP limit methodology in the technical specifications (item 1). A PTLR has been previously developed as part of the conversion to improved standard technical specifications (Ref. (c)). However, the revised PTLR required to support use of the proposed methodology is dependant upon the input data which is used, including that derived from the latest reactor vessel capsule. Once the NRC's review of the reactor vessel capsule is complete, RG&:E willprovide the revised PTLR using the proposed methodology. |
| | Therefore, item 2 is not being provided at this time. No other technical specification changes are required to implement Generic Letter 96-03 (item 3) since this was addressed during the conversion to the improved technical specifications. |
| | Following the NRC's review of the latest reactor vessel capsule data, it is anticipated that the P/T limits may not be valid for startup from the 1996 refueling outage. As such, RGkE requests NRC consideration of this LAR in order to support a planned startup date of May 30, 1996. To provide a necessary implementation period, RGB should receive NRC acceptance of this LAR by May 10, 1996. The revised PTLR using the proposed methodology will be submitted shortly after receipt of the NRC's review of the latest reactor vessel capsule in order to support this short schedule. |
| | Very truly yours, Robert C. Mecredy |
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| ==DearMr.Johnson,==
| | MDF>817 Attachments xc: U.S. Nuclear Regulatory Commission Mr. Allen R. Johnson (Mail Stop 14B2) |
| ByReference(a),RG&EproposedtorevisetheGinnaStationTechnicalSpecificationstoincorporatethemethodologyfordeterminingthelowtemperatureoverpressureprotection(LTOP)limitsintoAdministrativeControlsSection5.6.6,RCSPressureandTemperatureLimitsReport(PTLR).ThischangewouldallowRG&EtoperformfutureLTOPevaluationsusingNRCapprovedmethodologywithoutrequiringapotentialtechnicalspecificationchange.However,anychangestotheRCSpressuretemperature(P/T)limits,whicharealsoincludedinthePTLR,wouldstillrequirepriorNRCreviewandapproval.IncorporationofthemethodologyfortheP/TlimitswasnotrequestedatthetimesincetheNRC'sreviewofthelatestreactorvesselcapsuledata(whichwouldprovideinputintotheP/Tlimitdetermination)wasincomplete.21AAct"'tttrt032i0226cst603i5PDRADQCK05000244PPDR 0~ltgpss However,theNRC'sreviewofthelatestreactorvesselcapsuledataisnearingcompletionwhichwouldallowuseofpreviouslyNRCapprovedmethodology.Inaddition,GenericLetter96-03(Ref.(b))hasbeenreleasedbytheNRC.ThisgenericletterprovidesguidanceforlicenseestorelocatetheP/TlimitsandLTOPlimitsfromtechnicalspecificationsandtoprovideamechanismforlicenseestomakechangestothelimitsusingNRCapprovedmethodology.RG8cEhaspreviouslyrelocatedtheselimits;however,alicenseamendmentisstillrequiredforallchangestotheactuallimitssincethemethodologyfordeterminingtheselimitshasnotbeenapprovedforfutureapplications(Ref.(c)).Assuch,RGBissubmittingthislicenseamendmentrequest(LAR)toincorporatethemethodologyfordeterminingbothLTOPlimitsandRCSP/TlimitsintoAdministrativeControlsSection5.6.6consistentwithGenericLetter96-03.Therefore,thisLARsupersedesthatprovidedinReference(a).GenericLetter96-03requeststhatlicenseesprovidethefollowingintheirLAR:1.ProvideareferencetotheNRCapprovedP/TlimitandLTOPlimitmethodologyinthetechnicalspecifications;2.DevelopaPTLRorsimilardocumentthatcontainsthefigures,values,parameters,andanyexplanationsderivedfromthemethodology;and3.Provideotherrequiredchangestovarioustechnicalspecifications(e.g.,definitionssection)tosupporttherelocationoftheP/TandLTOPlimits.ThepurposeofthisLARistoprovidethereferencetotheP/TlimitandLTOPlimitmethodologyinthetechnicalspecifications(item1).APTLRhasbeenpreviouslydevelopedaspartoftheconversiontoimprovedstandardtechnicalspecifications(Ref.(c)).However,therevisedPTLRrequiredtosupportuseoftheproposedmethodologyisdependantupontheinputdatawhichisused,includingthatderivedfromthelatestreactorvesselcapsule.OncetheNRC'sreviewofthereactorvesselcapsuleiscomplete,RG&:EwillprovidetherevisedPTLRusingtheproposedmethodology.Therefore,item2isnotbeingprovidedatthistime.NoothertechnicalspecificationchangesarerequiredtoimplementGenericLetter96-03(item3)sincethiswasaddressedduringtheconversiontotheimprovedtechnicalspecifications.FollowingtheNRC'sreviewofthelatestreactorvesselcapsuledata,itisanticipatedthattheP/Tlimitsmaynotbevalidforstartupfromthe1996refuelingoutage.Assuch,RGkErequestsNRCconsiderationofthisLARinordertosupportaplannedstartupdateofMay30,1996.Toprovideanecessaryimplementationperiod,RGBshouldreceiveNRCacceptanceofthisLARbyMay10,1996.TherevisedPTLRusingtheproposedmethodologywillbesubmittedshortlyafterreceiptoftheNRC'sreviewofthelatestreactorvesselcapsuleinordertosupportthisshortschedule.Verytrulyyours,RobertC.Mecredy MDF>817Attachmentsxc:U.S.NuclearRegulatoryCommissionMr.AllenR.Johnson(MailStop14B2)PWRProjectDirectorateI-1Washington,D.C.20555U.S.NuclearRegulatoryCommissionRegionI475AllendaleRoadKingofPrussia,PA19406GinnaSeniorResidentInspectorMr.F.WilliamValentine,PresidentNewYorkStateEnergy,Research,andDevelopmentAuthority2RockefellerPlazaAlbany,NY12223-1253}}
| | PWR Project Directorate I-1 Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector Mr. F. William Valentine, President New York State Energy, Research, and Development Authority 2 Rockefeller Plaza Albany, NY 12223-1253}} |
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[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML17250B3041999-10-20020 October 1999 Forwards Changes to Tech Specs Bases for Re Ginna Nuclear Power Plant.Change Bars Indicate Those Revs Which Have Been Incorporated ML17265A7651999-10-0808 October 1999 Forwards Fifteen Relief Requests That Will Be Utilized for Ginna NPP Fourth Interval ISI Program That Will Start on Jan 1,2000.Attachment 1 Includes Summaries & Detailed Description of Each Relief Request ML17265A7631999-10-0505 October 1999 Requests Approval for Use of Relief Request Number 43 to Address Volumetric Examination Limitations (Less than 90%) Associated with a & B RHR Heat Exchanger Outlet Nozzle to Shell Welds.Approval Is Requested by Dec 31,2000 ML17265A7641999-10-0505 October 1999 Requests Approval for Use of Relief Request Number 42 to Address Volumetric Examinations Limitations (Less than 90%) Associated with Eight Class 1 Identified Welds or Areas of Reactor Pressure Vessel ML20212J3561999-09-30030 September 1999 Forwards Four Copies of Re Ginna NPP Training & Qualification Plan for Security Officers, Rev 7,dtd 990930. Synopsis of Changes,Encl.Encl Withheld Per 10CFR73.21 ML20212J3801999-09-30030 September 1999 Forwards Four Copies of Rev to Re Ginna NPP Security Plan.Rev Changes Contingency Weapons Available to Response Force to Those Most Effective in Current Defensive Strategy.Encl Withheld Per 10CFR73.21 IR 05000244/19990051999-09-24024 September 1999 Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs ML17265A7571999-09-24024 September 1999 Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs ML17265A7461999-08-31031 August 1999 Submits Response to NRC Administrative Ltr 95-03,rev 2, Availability of Reactor Vessel Integrity Database,Version, Dtd 990726 ML17265A7401999-08-26026 August 1999 Requests Approval for Use of Relief Request Number 35 Re Use of ASME Section XI Code,1995 Edition,1996 Addenda.Code Will Be Used to Develop Plant Fourth 10-year Interval ISI Program on Class 1,2 & 3 Components ML17265A7411999-08-26026 August 1999 Forwards LER 99-004-01 Re Plant Being Outside Design Basis Due to Containment Recirculation Fan Moisture Separator Vanes Being Incorrectly Installed.Part 21 Notification of 990512 Is Being Rescinded ML17250B3021999-08-23023 August 1999 Informs That Util & NRC Had Conference Call on 990816 to Review Approach in Responding to Questions,As Result of Questions Re Main Steam Check Valve Performance Included in Insp Rept 50-244/99-05,dtd 990806 ML17265A7451999-08-23023 August 1999 Forwards fitness-for-duty Performance Data Rept for Six Months Ending 990630,per 10CFR26.71(d) ML17265A7271999-07-30030 July 1999 Forwards 10CFR21 Interim Rept Per Reporting of Defects & Noncompliance,Section 21 (a) (2).Interim Rept Prepared Because Evaluation Cannot Be Completed within 60 Days from Discovery of Deviation or Failure to Comply ML17265A7151999-07-23023 July 1999 Forwards LER 99-007-01 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Reactor Trip.Further Investigation of Event Identified Addl Corrective Actions ML17265A7061999-07-22022 July 1999 Forwards LER 98-003-02,re Actuations of CR Emergency Air Treatment Sys.All Creats Actuations,Including Those Originally Believed to Be Valid Actuations,Were,In Fact Invalid Actuations ML17265A7191999-07-21021 July 1999 Forwards Ginna Station ISI Rept for Refueling Outage Conducted in 1999 ML17265A7141999-07-21021 July 1999 Withdraws Relief Request 35 for Plant Inservice Insp Program Section XI Requirements,Submitted on 980806.Licensee Plans to Resubmit Relief Request,Which Includes Addl Level of Detail,In Near Future ML17265A7041999-07-16016 July 1999 Submits Info Re Specific Licensing Actions Which May Be Expected to Generate Complex Reviews,In Response to Administrative Ltr 99-02,dtd 990603 ML17265A6911999-06-30030 June 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Readiness Disclosure Attached ML17265A6871999-06-22022 June 1999 Forwards Response to RAI Made During 990225 Telcon Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves. Calculation Encl. Encl ML17265A6841999-06-21021 June 1999 Informs That Util Wishes to Amend Extend of Alternate Exams Provided for Relief Request Re ISI Program ASME Section XI Require Exams for First 10-Yr Interval for Containment ML17265A6741999-06-15015 June 1999 Submits Annual ECCS Rept IAW 10CFR50.46(a)(3)(ii) Requirements.No Changes Have Been Made to Large Break LOCA PCT & Small Break LOCA PCT ML17265A6751999-06-11011 June 1999 Responds to NRC RAI Re Licensee GL 96-05 Program.Encl Info Verifies That Util Is Implementing Provisions of JOG Program on MOV Periodic Verification ML17309A6551999-06-0707 June 1999 Responds to NRC 990310 RAI Re Verification of Seismic Adequacy of Mechanical & Electrical Equipment ML17265A6671999-06-0101 June 1999 Requests Approval of Ginna QA Program for Radioactive Matl Packages,Form 311,approval Number 0019.Ginna QA Program for Station Operation, Was Most Recently Submitted to NRC by Ltr Dtd 981221 & Supplemented on 990301 ML17265A6641999-05-25025 May 1999 Forwards Addl Info on Use of GIP Method a for Re Ginna Nuclear Power Plant.Copy of Re Ginna Station USI A-46 Outlier Resolution Table as Requested ML17265A6611999-05-24024 May 1999 Forwards LER 99-007-00 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Rt.Util Is Planning to Submit Suppl to LER by 990730 ML20206U0921999-05-13013 May 1999 Forwards Four Copies of Rev R to Gnpp Security Plan,Per Provisions of 10CFR50.54(p).Rev Clarifies Armed Response Team Assignments & Does Not Degrade Physical Security Effectiveness.Rev Withheld,Per 10CFR73.21 ML17265A6461999-05-12012 May 1999 Forwards 1998 Annual Radioactive Effluent Release Rept & 1998 Annual Radiological Environ Operating Rept, for Re Ginna NPP ML17265A6411999-05-12012 May 1999 Forwards LER 99-004-00 IAW 10CFR50.73 & 10CFR21.Further Assessment Will Be Provided in Suppl to LER by 990630 ML20206E7221999-04-29029 April 1999 Forwards Four Copies of Rev Q to Re Ginna Nuclear Power Plant Security Plan,Per 10CFR50.54(p).Changes Do Not Degrade Physical Security Effectiveness.Encl Withheld,Per 10CFR73.21 ML20206H6911999-04-22022 April 1999 Forwards Info Requested During Informal Telcon on 980408 Concerning Upcoming Osre at Ginna Station.Info Requested Listed.Without Encls ML17265A6271999-04-19019 April 1999 Forwards Rev 0 & Rev 1 to Colr,Cycle 28 for Re Ginna NPP, Per TS 5.6.5 ML17309A6501999-04-14014 April 1999 Forwards Revised Ginna Station EOPs & Procedures Index ML17265A6121999-03-29029 March 1999 Forwards Rept on Status of Decommissioning Funding for Re Ginna Npp,For Which Rg&E Is Sole Owner,Per 10CFR50.75. Data Presented Herein,Current as of 981231 ML17265A6041999-03-24024 March 1999 Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(ii)(B) & 10CFR21.Addl Analyses Are Being Performed to Support Future Cycle Operation & Supplemental LER Is Scheduled to Be Submitted by 990618 ML17265A5641999-03-0101 March 1999 Forwards Response to NRC 990217 RAI Concerning Changes to QA Program for Re Ginna Station Operation.Rg&E Is Modifying Changes Requested in 981221 Submittal.Modified QA Program,Encl ML17265A5671999-03-0101 March 1999 Forwards Application for Amend to License DPR-18,to Revise TSs Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6).Supporting Tss,Encl ML17265A5551999-02-25025 February 1999 Informs That Util Is in Process of Revising fitness-for-duty Program,Developed in Accordance with 10CFR26.Util Will Continue to Use Dept of Health & Human Svcs Certified Test Facility for Majority of Tests During Yr ML17265A5561999-02-22022 February 1999 Forwards FFD Performance Data Rept for Six Months Ending 981231,per 10CFR26.71(d) ML17265A5451999-02-12012 February 1999 Forwards Simulator Four Year Certification Rept,Per 10CFR55.45(b)(5)(ii) ML17309A6491999-02-12012 February 1999 Forwards Ginna Station EOPs ML17265A5431999-02-0909 February 1999 Supplements 980806 Relief Request with Attached Table.Util Third 10-Yr ISI of Reactor Vessel Being Performed During 1999 Refueling Outage,Beginning on 990301 ML17265A5361999-02-0202 February 1999 Forwards Response to NRC 981203 RAI Re Resolution of Unresolved Safety Issue USI A-46.Util Does Not Agree with NRCs Interpretation.Detailed Bases,Encl ML17311A0691999-01-25025 January 1999 Forwards Revs to Ginna Station Emergency Plan Implementing Procedures (Epips).Previous Rev Had Incorrect Effective Date ML17311A0671999-01-14014 January 1999 Forwards Revised Emergency Operating Procedures for Re Ginna NPP ML17265A5131999-01-12012 January 1999 Forwards Revised Cover Page for Ginna Station Technical Requirements Manual (Trm), Rev 7,correcting Error in Effective Date ML17265A5111999-01-11011 January 1999 Requests Relief Per 10CFR50.55a(a)(3)(ii) from Certain Requirements of Section XI of ASME Bp&V Code for ISI Program.Relief Requests 37,38 & 39 Encl ML17265A5101999-01-11011 January 1999 Requests Relief Per to 10CFR50.55a(a)(3)(ii) from Certain Requirements of Section XI of ASME B&PV Code for ISI Program.Relief Request 40 Encl 1999-09-30
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CATEGORY j.
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REGULATCI INFORMATION DISTRIBUTIONSTEM (RIDE)
ACCESSION NBR:9603210226 DOC.DATE: 96/03/3."5 NOTARIZED: NO DOCKET
FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244
!tAUTH.NAME AUTHOR AFFILIATiON MECREDY,R.C. Rochester Gas & Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R.
SUBJECT:
Forwards application for amend to license DPR-18,to incorporate methodology for determining LTOP limits into Administrative Controls Section 5.6.6,RCS Pressure Temp Limits Rept.
DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR Submittal: General Distribution E
NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 Q
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-1 LA 1 1 PD1-1 PD 1 1 JOHNSON,A 1 1 INTERNAL:p LE CE ~l 1 1 NRR/DE/EMCB 1 1 NRRQDR H HICB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS3 1 0 EXTERNAL: NOAC 1 1 NRC PDR 1 1 D
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NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN 5D"5(EXT. 415-2083) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR I
12 ENCL ll
AND ROCHESTER GAS ANDElECTRIC CORPORA71ON ~ 89 EASTAV&IUE,ROCHESTER, N.Y. 146d9-0001 AREA CODE71rS $ 6-2700 ROBERT C. MECREDY Vice President Nvdeor operations March 15, 1996 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Allen R. Johnson Project Directorate I-3 Washington, D.C. 20555
Subject:
Application for Amendment to Facility Operating License Implementation of Generic Letter 96-03 Rochester Gas & Electric Corporation R.E. Ginna Nuclear Power Plant Docket No. 50-244
References:
(a) Letter from R.C. Mecredy, RG&E, to A.R. Johnson, NRC,
Subject:
Application for Amendment to Facility Operating License, Methodology for Low Temperature Overpressure Protection (LTOP) Limits, dated February 9, 1996.
(b) Generic Letter 96-03, Relocation of the Pressure Temperature Li1nit Curves and Loiv Teniperature Overpressure Protection System Limits (c) Letter from L.T. Marsh, NRC, to R.C. Mecredy, RG&E,
Subject:
RLr. Ginna
- Acceptance for Referencing ofPressure Temperature Limits Report (TAC I/M92320), dated December 26, 1995.
Dear Mr. Johnson,
By Reference (a), RG&E proposed to revise the Ginna Station Technical Specifications to incorporate the methodology for determining the low temperature overpressure protection (LTOP) limits into Administrative Controls Section 5.6.6, RCS Pressure and Temperature Limits Report (PTLR). This change would allow RG&E to perform future LTOP evaluations using NRC approved methodology without requiring a potential technical specification change. However, any changes to the RCS pressure temperature (P/T) limits, which are also included in the PTLR, would still require prior NRC review and approval. Incorporation of the methodology for the P/T limits was not requested at the time since the NRC's review of the latest reactor vessel capsule data (which would provide input into the P/T limit determination) was incomplete.
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However, the NRC's review of the latest reactor vessel capsule data is nearing completion which would allow use of previously NRC approved methodology. In addition, Generic Letter 96-03 (Ref.
(b)) has been released by the NRC. This generic letter provides guidance for licensees to relocate the P/T limits and LTOP limits from technical specifications and to provide a mechanism for licensees to make changes to the limits using NRC approved methodology. RG8cE has previously relocated these limits; however, a license amendment is still required for all changes to the actual limits since the methodology for determining these limits has not been approved for future applications (Ref. (c)). As such, RGB is submitting this license amendment request (LAR) to incorporate the methodology for determining both LTOP limits and RCS P/T limits into Administrative Controls Section 5.6.6 consistent with Generic Letter 96-03. Therefore, this LAR supersedes that provided in Reference (a).
Generic Letter 96-03 requests that licensees provide the following in their LAR:
- 1. Provide a reference to the NRC approved P/T limit and LTOP limit methodology in the technical specifications;
- 2. Develop a PTLR or similar document that contains the figures, values, parameters, and any explanations derived from the methodology; and
- 3. Provide other required changes to various technical specifications (e.g., definitions section) to support the relocation of the P/T and LTOP limits.
The purpose of this LAR is to provide the reference to the P/T limit and LTOP limit methodology in the technical specifications (item 1). A PTLR has been previously developed as part of the conversion to improved standard technical specifications (Ref. (c)). However, the revised PTLR required to support use of the proposed methodology is dependant upon the input data which is used, including that derived from the latest reactor vessel capsule. Once the NRC's review of the reactor vessel capsule is complete, RG&:E willprovide the revised PTLR using the proposed methodology.
Therefore, item 2 is not being provided at this time. No other technical specification changes are required to implement Generic Letter 96-03 (item 3) since this was addressed during the conversion to the improved technical specifications.
Following the NRC's review of the latest reactor vessel capsule data, it is anticipated that the P/T limits may not be valid for startup from the 1996 refueling outage. As such, RGkE requests NRC consideration of this LAR in order to support a planned startup date of May 30, 1996. To provide a necessary implementation period, RGB should receive NRC acceptance of this LAR by May 10, 1996. The revised PTLR using the proposed methodology will be submitted shortly after receipt of the NRC's review of the latest reactor vessel capsule in order to support this short schedule.
Very truly yours, Robert C. Mecredy
MDF>817 Attachments xc: U.S. Nuclear Regulatory Commission Mr. Allen R. Johnson (Mail Stop 14B2)
PWR Project Directorate I-1 Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector Mr. F. William Valentine, President New York State Energy, Research, and Development Authority 2 Rockefeller Plaza Albany, NY 12223-1253