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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML17265A6921999-06-28028 June 1999 Application for Amend to License DPR-18 to Revise ITS Associated with RCS Leakage Detection Instrumentation.Lar Proposed as Result of Commitment That Rg&E Submit as Part of Staff Review of Application of leak-before-break Status ML17265A5691999-03-0101 March 1999 Application for Amend to License DPR-18,proposing Change in ITS to Revise Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6) ML17265A4651998-11-24024 November 1998 Application for Amend to License DPR-18,revising Improved Tech Spec Description of Fuel Cladding Matl (TS 4.2.1) & Updating References Provided in TS 5.6.5 for COLR ML17265A2431998-04-27027 April 1998 Application for Amend to License DPR-18,revising Requirements Associated W/Sfp to Reflect Planned Mod to Storage Racks & Temporarily Addressing Boraflex Degradation within Pool ML17264B0431997-09-29029 September 1997 Application for Amend to License DPR-18,revising Administrative Controls W/Respect to RCS Pressure & Temp Limits Rept ML17264B0381997-09-29029 September 1997 Application for Amend to License DPR-18,revising TS Re Allowable Value & Trip Setpoint for High Steam Flow Input Into LCO Table 3.3.2-1,Function 4d (Main Steam Isolation) to Address Issues Identified in Revised Setpoint Analysis ML17264B0021997-08-19019 August 1997 Application for Amend to License DPR-18,allowing Testing of Certain ECCS motor-operated Valves in Mode 4 Which Currently Requires Entry in LCO 3.0.3 ML17264A9981997-08-19019 August 1997 Application for Amend to License DPR-18,correcting Specified Accumulator Borated Water Volume Values in SR 3.5.1.2 to Match Associated Accumulator Percent Level Values ML17264A8661997-04-24024 April 1997 Application for Amend to License DPR-18,revising RCP PT & Administrative Control Requirements ML17264A8471997-03-31031 March 1997 Application for Amend to License DPR-18,revising Spent Fuel Pool Storage Requirements ML20134D9911996-10-29029 October 1996 Application for Amend to License DPR-18,requesting Change to Mode of Applicability for Auxiliary Feedwater Pump Actuation on Main Feedwater Pump ML17264A7121996-10-29029 October 1996 Application for Amend to License DPR-18 Requesting Change to Required Actions for Inoperable Channels Associated with Auxiliary Feedwater Pump ML17264A5991996-09-13013 September 1996 Application for Amend to License DPR-18,revising RCS Pressure & Temp Limits Rept ML17264A4701996-05-0808 May 1996 Application for Amend to License DPR-18,correcting Typos ML17264A4041996-03-15015 March 1996 Application for Amend to License DPR-18,revising TS to Incorporate Methodology for Determining RCS P/T Limits & LTOP Limits in Administrative Controls Section of RCS P/T Limits Rept ML17264A3441996-02-0909 February 1996 Application for Amend to License DPR-18,revising TS Table 3.3.2-1,Function 5b, Feedwater Isolation,Sg Water Level - High to Raise Allowable Value & Trip Setpoint ML17264A3381996-02-0909 February 1996 Application for Amend to License DPR-18,revising TS to Incorporate Ref to Methodology for Determining LTOP Limits Into Administrative Controls Section for RCS PT Limits Rept ML17264A3331996-02-0909 February 1996 Application for Amend to License DPR-18,revising Requirements for Containment Closure During Mode 6 to Allow Use of Installed Overhead Door Assembly to Isolate Equipment Hatch Opening ML17264A3221996-01-26026 January 1996 Application for Amend to License DPR-18,incorporating Changes Necessary to Reflect Revised Nuclear Fuel Loading ML17264A2521995-11-27027 November 1995 Application for Amend to License DPR-18,revising TS to Implement 10CFR50,App J,Option B ML17264A2551995-11-20020 November 1995 Application for Amend to License DPR-18,submitting Changes to TS Instrumentation Requirements & Conversion to Improved TS ML17264A1501995-08-31031 August 1995 Application for Amend to License DPR-18,proposing Ts,By Implementing WCAP-10271,its Assoc Suppls & Other Re Changes W/Respect to RTS & ESFAS ML17263B0671995-05-26026 May 1995 Application for Amend to License DPR-18,revising TSs in Entirety to Convert to Improved TSs ML17263A9771995-03-13013 March 1995 Application for Amend to License DPR-18,to Revise TS 4.4.2.4.a to Replace Specific Leakage Testing Frequencies for Containment Isolation Valves ML17309A5501994-07-15015 July 1994 Application for Amend to License DPR-18,proposing TS 3.5, Providing NRC W/Opportunity to Communicate at Early Stage Any Concerns W/Respect to Differences from NUREG-1431 ML17263A7141994-06-24024 June 1994 Application for Amend to License DPR-18,re Upgrading of Administrative Controls Section 6 ML17263A7071994-06-15015 June 1994 Notarized Application for Amend to License DPR-18 Re Reactor Coolant Activity ML17263A6551994-05-23023 May 1994 Application for Amend to License DPR-18,increasing Allowable Reactor Coolant Activity Levels to Improved TS (NUREG-1431) ML17263A6411994-05-13013 May 1994 Application for Amend to License DPR-18,revising TS Administrative Controls Section 6.0 Consistent W/Improved TS ML17263A3181993-07-13013 July 1993 Application for Amend to License Revisions for License DPR-18 Re Removing Containment Isolation Valve Table 3.6-1 from TS ML17263A2081993-04-0505 April 1993 Application for Amend to License DPR-18,revising TS to Remove Containment Isolation Valve Table 3.6-1 & Maintain Required Listing in Updated FSAR ML17262B1171992-12-17017 December 1992 Application for Amend to License DPR-19,revising TS Sections 3.2 & 3.3 to Eliminate Use of High Concentration Boric Acid as safety-related Source of SI Pumps & Increasing Allowable Outage Times ML17262B0991992-11-30030 November 1992 Application for Amend to License DPR-18,revising TS to Remove Table of Containment Isolation Valves & Provide Ref in Bases to UFSAR ML17262B0571992-10-0808 October 1992 Corrected Application for Amend to License DPR-18,adding Addl Requirements to Auxiliary Electrical Sys TS & Action Statements for Instrument Bus Sys,Consisting of Notarized Page Two ML17262B0431992-10-0808 October 1992 Application for Amend to License DPR-18,adding Addl Requirements to Auxiliary Electrical Sys TS & Action Statements for Instrument Bus Sys,Per Guidance Provided in GL 91-11 Re Resolution of GI 48 ML17262B0201992-09-15015 September 1992 Application for Amend to License DPR-18,revising TS Sections 3.1.1.4,3.1.1.6,4.3.4 & Adding site-specific Basis Sections to Address GL 90-06 Re Resolution of Generic Issues 70 & 94 ML17262A9121992-06-22022 June 1992 Application for Amend to License DPR-18,revising TS 4.3.1 Per Guidance Provided in Generic Ltr 91-01, Removal of Schedule for Withdrawal of Reactor Vessel Matl Specimens from Ts. ML17262A8311992-04-23023 April 1992 Application for Amend to License DPR-18,changing TSs to Redefine Snubber Visual Insp Schedule,Per Generic Ltr 90-09 Guidance ML17262A8211992-04-21021 April 1992 Application for Amend to License DPR-18,instituting Std License Condition for Fire Protection Program & Removing Requirements for Fire Protection Sys from Tss,Per Guidance in Generic Ltrs 86-10 & 88-12 ML17262A7861992-03-23023 March 1992 Application for Amend to License DPR-18,revising Tech Spec Section 6.5.1, Plant Operations Review Committee Function. ML17262A7801992-03-20020 March 1992 Application for Amend to License DPR-18,revising TS 5.1 Figure 5.1-1 to Describe Rather than Depict Site Area Boundary to Evaluate Radiological Releases to Unrestricted Area ML17262A7901992-03-20020 March 1992 Application for Amend to License DPR-18,revising Tech Specs 6.9.1.2 & 6.9.2.5 ML17262A6321991-10-25025 October 1991 Application for Amend to License DPR-18 to Delete TS 5.1 & Figure 5.1-1 ML17262A5331991-06-20020 June 1991 Application for Amend to License DPR-18,to Incorporate Changes to Specifications & Action Statements for Offsite & Onsite Power Sources Available for Operation of Plant Auxiliaries ML17262A4121991-03-0808 March 1991 Application for Amend to License DPR-18,removing Table 3.6-1 Re Containment Isolation Valves from Tech Specs ML17262A3831991-02-15015 February 1991 Application for Amend to License DPR-18,revising Tech Specs to Modify Method of Locking Open Motor Operated Valve 856, Refueling Water Storage Tank Delivery Valve When Reactor Coolant Sys at or Above 350 F ML17262A3751991-02-15015 February 1991 Application for Amend to License DPR-18,revising Heatup/Cooldown Curves & Associated Low Temp Overpressure Protection Setpoint to Implement Reg Guide 1.99,Rev 2 Methodology ML17262A3721991-02-15015 February 1991 Application for Amend to License DPR-18,providing Clarification of Which QA Activities Subj to Audit Considerations & Changing Audit Frequency Described in Tech Spec 6.5.2.8d ML17262A3871991-02-15015 February 1991 Application for Amend to License DPR-18,revising Tech Spec Tables 3.5-5 & 4.1-5 Based on Mods to Radiation Monitoring Sys ML17262A2951991-01-14014 January 1991 Application for Amend to License DPR-18,changing Tech Specs to Limit Containment Internal Pressure to 1 Psig Vs 6 Psig Per Initial Condition Assumptions in Containment Integrity Analysis 1999-06-28
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML17265A6921999-06-28028 June 1999 Application for Amend to License DPR-18 to Revise ITS Associated with RCS Leakage Detection Instrumentation.Lar Proposed as Result of Commitment That Rg&E Submit as Part of Staff Review of Application of leak-before-break Status ML17265A5691999-03-0101 March 1999 Application for Amend to License DPR-18,proposing Change in ITS to Revise Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6) ML17265A4651998-11-24024 November 1998 Application for Amend to License DPR-18,revising Improved Tech Spec Description of Fuel Cladding Matl (TS 4.2.1) & Updating References Provided in TS 5.6.5 for COLR ML17265A2431998-04-27027 April 1998 Application for Amend to License DPR-18,revising Requirements Associated W/Sfp to Reflect Planned Mod to Storage Racks & Temporarily Addressing Boraflex Degradation within Pool ML17264B0431997-09-29029 September 1997 Application for Amend to License DPR-18,revising Administrative Controls W/Respect to RCS Pressure & Temp Limits Rept ML17264B0381997-09-29029 September 1997 Application for Amend to License DPR-18,revising TS Re Allowable Value & Trip Setpoint for High Steam Flow Input Into LCO Table 3.3.2-1,Function 4d (Main Steam Isolation) to Address Issues Identified in Revised Setpoint Analysis ML17264B0021997-08-19019 August 1997 Application for Amend to License DPR-18,allowing Testing of Certain ECCS motor-operated Valves in Mode 4 Which Currently Requires Entry in LCO 3.0.3 ML17264A9981997-08-19019 August 1997 Application for Amend to License DPR-18,correcting Specified Accumulator Borated Water Volume Values in SR 3.5.1.2 to Match Associated Accumulator Percent Level Values ML17264A8661997-04-24024 April 1997 Application for Amend to License DPR-18,revising RCP PT & Administrative Control Requirements ML17264A8471997-03-31031 March 1997 Application for Amend to License DPR-18,revising Spent Fuel Pool Storage Requirements ML20134D9911996-10-29029 October 1996 Application for Amend to License DPR-18,requesting Change to Mode of Applicability for Auxiliary Feedwater Pump Actuation on Main Feedwater Pump ML17264A7121996-10-29029 October 1996 Application for Amend to License DPR-18 Requesting Change to Required Actions for Inoperable Channels Associated with Auxiliary Feedwater Pump ML17264A5991996-09-13013 September 1996 Application for Amend to License DPR-18,revising RCS Pressure & Temp Limits Rept ML17264A4701996-05-0808 May 1996 Application for Amend to License DPR-18,correcting Typos ML17264A4041996-03-15015 March 1996 Application for Amend to License DPR-18,revising TS to Incorporate Methodology for Determining RCS P/T Limits & LTOP Limits in Administrative Controls Section of RCS P/T Limits Rept ML17264A3441996-02-0909 February 1996 Application for Amend to License DPR-18,revising TS Table 3.3.2-1,Function 5b, Feedwater Isolation,Sg Water Level - High to Raise Allowable Value & Trip Setpoint ML17264A3381996-02-0909 February 1996 Application for Amend to License DPR-18,revising TS to Incorporate Ref to Methodology for Determining LTOP Limits Into Administrative Controls Section for RCS PT Limits Rept ML17264A3331996-02-0909 February 1996 Application for Amend to License DPR-18,revising Requirements for Containment Closure During Mode 6 to Allow Use of Installed Overhead Door Assembly to Isolate Equipment Hatch Opening ML17264A3221996-01-26026 January 1996 Application for Amend to License DPR-18,incorporating Changes Necessary to Reflect Revised Nuclear Fuel Loading ML17264A2521995-11-27027 November 1995 Application for Amend to License DPR-18,revising TS to Implement 10CFR50,App J,Option B ML17264A2551995-11-20020 November 1995 Application for Amend to License DPR-18,submitting Changes to TS Instrumentation Requirements & Conversion to Improved TS ML17264A1501995-08-31031 August 1995 Application for Amend to License DPR-18,proposing Ts,By Implementing WCAP-10271,its Assoc Suppls & Other Re Changes W/Respect to RTS & ESFAS ML17263B0671995-05-26026 May 1995 Application for Amend to License DPR-18,revising TSs in Entirety to Convert to Improved TSs ML17263A9771995-03-13013 March 1995 Application for Amend to License DPR-18,to Revise TS 4.4.2.4.a to Replace Specific Leakage Testing Frequencies for Containment Isolation Valves ML17309A5501994-07-15015 July 1994 Application for Amend to License DPR-18,proposing TS 3.5, Providing NRC W/Opportunity to Communicate at Early Stage Any Concerns W/Respect to Differences from NUREG-1431 ML17263A7141994-06-24024 June 1994 Application for Amend to License DPR-18,re Upgrading of Administrative Controls Section 6 ML17263A7071994-06-15015 June 1994 Notarized Application for Amend to License DPR-18 Re Reactor Coolant Activity ML17263A6551994-05-23023 May 1994 Application for Amend to License DPR-18,increasing Allowable Reactor Coolant Activity Levels to Improved TS (NUREG-1431) ML17263A6411994-05-13013 May 1994 Application for Amend to License DPR-18,revising TS Administrative Controls Section 6.0 Consistent W/Improved TS ML17263A3181993-07-13013 July 1993 Application for Amend to License Revisions for License DPR-18 Re Removing Containment Isolation Valve Table 3.6-1 from TS ML17263A2081993-04-0505 April 1993 Application for Amend to License DPR-18,revising TS to Remove Containment Isolation Valve Table 3.6-1 & Maintain Required Listing in Updated FSAR ML17262B1171992-12-17017 December 1992 Application for Amend to License DPR-19,revising TS Sections 3.2 & 3.3 to Eliminate Use of High Concentration Boric Acid as safety-related Source of SI Pumps & Increasing Allowable Outage Times ML17262B0991992-11-30030 November 1992 Application for Amend to License DPR-18,revising TS to Remove Table of Containment Isolation Valves & Provide Ref in Bases to UFSAR ML17262B0571992-10-0808 October 1992 Corrected Application for Amend to License DPR-18,adding Addl Requirements to Auxiliary Electrical Sys TS & Action Statements for Instrument Bus Sys,Consisting of Notarized Page Two ML17262B0431992-10-0808 October 1992 Application for Amend to License DPR-18,adding Addl Requirements to Auxiliary Electrical Sys TS & Action Statements for Instrument Bus Sys,Per Guidance Provided in GL 91-11 Re Resolution of GI 48 ML17262B0201992-09-15015 September 1992 Application for Amend to License DPR-18,revising TS Sections 3.1.1.4,3.1.1.6,4.3.4 & Adding site-specific Basis Sections to Address GL 90-06 Re Resolution of Generic Issues 70 & 94 ML17262A9121992-06-22022 June 1992 Application for Amend to License DPR-18,revising TS 4.3.1 Per Guidance Provided in Generic Ltr 91-01, Removal of Schedule for Withdrawal of Reactor Vessel Matl Specimens from Ts. ML17262A8311992-04-23023 April 1992 Application for Amend to License DPR-18,changing TSs to Redefine Snubber Visual Insp Schedule,Per Generic Ltr 90-09 Guidance ML17262A8211992-04-21021 April 1992 Application for Amend to License DPR-18,instituting Std License Condition for Fire Protection Program & Removing Requirements for Fire Protection Sys from Tss,Per Guidance in Generic Ltrs 86-10 & 88-12 ML17262A7861992-03-23023 March 1992 Application for Amend to License DPR-18,revising Tech Spec Section 6.5.1, Plant Operations Review Committee Function. ML17262A7801992-03-20020 March 1992 Application for Amend to License DPR-18,revising TS 5.1 Figure 5.1-1 to Describe Rather than Depict Site Area Boundary to Evaluate Radiological Releases to Unrestricted Area ML17262A7901992-03-20020 March 1992 Application for Amend to License DPR-18,revising Tech Specs 6.9.1.2 & 6.9.2.5 ML17262A6321991-10-25025 October 1991 Application for Amend to License DPR-18 to Delete TS 5.1 & Figure 5.1-1 ML17262A5331991-06-20020 June 1991 Application for Amend to License DPR-18,to Incorporate Changes to Specifications & Action Statements for Offsite & Onsite Power Sources Available for Operation of Plant Auxiliaries ML17262A4121991-03-0808 March 1991 Application for Amend to License DPR-18,removing Table 3.6-1 Re Containment Isolation Valves from Tech Specs ML17262A3831991-02-15015 February 1991 Application for Amend to License DPR-18,revising Tech Specs to Modify Method of Locking Open Motor Operated Valve 856, Refueling Water Storage Tank Delivery Valve When Reactor Coolant Sys at or Above 350 F ML17262A3751991-02-15015 February 1991 Application for Amend to License DPR-18,revising Heatup/Cooldown Curves & Associated Low Temp Overpressure Protection Setpoint to Implement Reg Guide 1.99,Rev 2 Methodology ML17262A3721991-02-15015 February 1991 Application for Amend to License DPR-18,providing Clarification of Which QA Activities Subj to Audit Considerations & Changing Audit Frequency Described in Tech Spec 6.5.2.8d ML17262A3871991-02-15015 February 1991 Application for Amend to License DPR-18,revising Tech Spec Tables 3.5-5 & 4.1-5 Based on Mods to Radiation Monitoring Sys ML17262A2951991-01-14014 January 1991 Application for Amend to License DPR-18,changing Tech Specs to Limit Containment Internal Pressure to 1 Psig Vs 6 Psig Per Initial Condition Assumptions in Containment Integrity Analysis 1999-06-28
[Table view] |
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UNITEDSTATESOFAMERICANUCLEARREGULATORYCOMMISSIONIntheMatterofRochesterGasandElectricCorporation(R.E.GinnaNuclearPowerPlant))))DocketNo.50-244)APPLICATIONFORAMENDMENTPursuanttoSection50.90oftheregulationsoftheU.S.NuclearRegulatoryCommission(NRC),RochesterGasandElectricCorporation(RG&E),holderofFacilityOperatingLicenseNo.DPR-18,herebyrequeststhattheTechnicalSpecificationssetforthinAppendixAtothat~~license,beamended.ThisrequestforchangeistorevisetheAdministrativeControlswithrespecttotheReactorCoolantSystem(RCS)PressureandTemperatureLimitsReport(PTLR)tomakethenecessarychangesinorderplacethisdocumentunderlicenseecontrol,makeseveralchangestothePTLR,andtorevisetheLTOPenabletemperaturemethodology.Adescriptionoftheamendmentrequest,necessarybackgroundinformation,justificationoftherequestedchanges,andanosignificanthazardsandenvironmentalconsiderationsareprovidedinAttachmentI.Thisevaluationdemonstratesthattheproposedchangesdonotinvolveasignificantchangeinthetypesorasignificantincreaseintheamountsofeffluentsoranychangeintheauthorizedpowerlevelofthefacility.Theproposedchangesalsodonotinvolveasignificanthazardsconsideration.97<0Dggg05000244020%73970929PDRADPDRp
AmarkedupcopyoftheGinnaStationTechnicalSpecificationswhichshowtherequestedchangesissetforthinAttachmentII.TheproposedrevisedtechnicalspecificationsareprovidedinAttachmentIII.TherevisedPTLRisprovidedinAttachmentIV.AttachmentVcontainsaredlinedversionofthelowtemperatureoverpressureprotection(LTOP)setpointmethodologywithrespecttothecurrentlyapprovedversion.AttachmentVIcontainsafinalversionoftheLTOPsetpointmethodology.AttachmentVIIcontainsthefirstuseoftheLTOPenabletemperaturemethodologywhileAttachmentVIIIcontainsa'copyofWCAP-14684asreferencedwithinthePTLR.AttachmentIXcontainsresponsestoNRCquestionsconcerningtheGinnaStationLTOPanalysis.WHEREFORE,ApplicantrespectfullyrequeststhatFacilityOperatingLicenseNo.DPR-18,andAttachmentAtothatlicense,beamendedintheformattachedheretoasAttachmentIII.RochesterGasandElectricCorporationByRobertC.MecredyVicePresidentNuclearOperationsSubscribedandsworntobeforemeonthis29thdayofSeptember1997.NotaryPublicDEBORAHA.PIPERNINotaryPublicmtheStateofNmYorkONTARIOCOUNTYCommasonExpiresNov.23,19,3.3
~I AttachmentIR.E.GinnaNuclearPowerPlantLicenseAmendmentRequestRevisionofReactorCoolantSystem(RCS)PressureandTemperatureLimitsReport(PTLR)AdministrativeControlsRequirementsThisattachmentprovidesadescriptionofthelicenseamendmentrequest(LAR)andthenecessaryjustificationstosupportarevisiontotheGinnaStationPTLRandrelatedrequirementscontainedwithintheAdministrativeControlssectionoftechnicalspecifications.Thisattachmentisdividedintosixsectionsasfollows.SectionAsummarizesallchangestotheGinnaStationTechnicalSpecificationswhileSectionBprovidesthebackgroundandhistoryassociatedwiththechangesbeingrequested.SectionCprovidesthejustificationsassociatedwiththeseproposedchanges.AnosignificanthazardsconsiderationevaluationandenvironmentalconsiderationoftherequestedchangestotheGinnaStationTechnicalSpecificationsareprovidedinSectionsDandE,respectively.SectionFlistsallreferencesusedinthisattachment.A.DESCRIPTIONOFTECHNICALSPECIFICATIONCHANGESThisLARproposestorevisetheGinnaStationTechnicalSpecificationstoreflectanewPTLRintheAdministrativeControlssection.ThechangeissummarizedbelowandshowninAttachmentII.1.AdministrativeControls5.6.6ItemcwillberevisedtoicplacethereferencetotheMay23,1996NRCletterwithanewNRCreferencethatapprovesthefirstuseofthePTLRmethodologyincludedasAttachmentVItothisLAR.Inaddition,Reference1isrevisedtoreferencethisLARasthesourceforthelowtemperatureoverpressureprotection(LTOP)methodologywhileReference2isrevisedtoreferencethefinalNRCapprovedWCAP-14040-NP-AwhichisthebasisforthenewP/Tcurves.Reference3isnolongerrequiredandisthereforedeleted.Finally,atypographicalerrorinitemdiscorrected.
BACKGROUNDDuringtheconversiontoimprovedstandardtechnicalspecifications(ISTS)forGinnaStation,RG&EproposedtorelocatetheLTOPandRCSpressureandtemperature(P/T)limitstothePTLR(Ref.1).AssociatedwiththischangewastheadditionofareferencetotheAdministrativeControlssectionoftechnicalspecificationsrelatedtothePTLRdocumentingtheNRCapprovalofthemethodologyusedinthePTLR.However,theonlyNRCapprovedmethodologywouldbe"new"withrespecttodeterminationofboththeLTOPandRCSP/TlimitsatGinnaStation.Duetotimeconstraints,RG&EinformedtheNRCthatuseofthisnewmethodologywouldbeburdensomeandinstead,RG&Ewishedtoretaintheexistingvalues.TheNRCagreedwiththisconcernandallowedtheexistinglimitstoberelocatedtothePTLRbutrequiredchangestotheselimitstobereviewedandapprovedbytheNRCasdocumentedinReference2.SubsequenttotheconversiontoISTS,theNRCcompleteditsreviewofthelatestreactorvesselcapsuledataandtheassociatedimpactonthepressurizedthermalshock(PTS)evaluationforGinnaStation(Ref.3).IncorporationofthisinformationintothePTLRrequiredareassessmentoftheP/TcurvesandLTOPsetpointsthatareincludedinthePTLR.However,thefluencefactormethodologyusedfortheGinnaStationPTSevaluationwasanearlierversionthanthatrequiredbyWCAP-14040-NP-A(Ref.4)whichwastobethebasisfortheP/Tmethodology.Sinceanupdateoftheassociateddocumentscouldnotbecompletedinthetimeframerequiredtosupportstart-upfromthe1996refuelingoutage,theNRCapprovedaPTLRforuseatGinnaStationuntilDecember31,1996usinganestimatedfluencefactorvalue(Ref.5).Subsequenttothis,whileattemptingtocloseoutthefluencefactormethodologies,theNRCquestionedRG&E'sapproachfordeterminingLTOPenabletemperature.Specifically,theNRCidentifiedthatthedeterminationoftheLTOPenabletemperaturerequiredconsiderationofRCSliquidtemperaturemeasurementaccuracyperthemethodologycurrentlyspecifiedinSpecification5.6.6.Uponfurtherevaluation,RG&Eagreedtoaddressthisconcernbyfirstsubmittingareliefrequest(Ref.6)andthenbyrequestinganexemptiontoregulations(Ref.7).Subsequently,theNRCidentifiedthattheliquidtemperatureaccuracyquestionshouldbeinsteadaddressedbyanewLARwhichupdatedthemethodologyinSpecification5.6.6andincorporatedanexemptionto10CFR50.60(Ref.8).ToallowRG&Esufficienttimetoaddressthisissue,thePTLRexpirationdatewaschangedtoDecember31,1997(Ref.9).
ThepurposeofthisLARistocompleteimplementationofGenericLetter96-03forGinnaStationandtorespondtotheDecember31,1997timelimitontheexistingPTLR.GenericLetter96-03requiresthatlicenseesreferencetheP/TandLTOPmethodologiesinthetechnicalspecificationsandprovideaproposedPTLRusingthemethodologyforNRCreview.Sections1,2,and4ofWCAP-14040-NP-A(Ref.4)havebeengenericallyapprovedforusebytheNRCforP/TlimitsandisbeingproposedastheP/TlimitmethodologyforGinnaStation.ThecurrentLTOPmethodologyforGinnaStation(Ref.1)replacedthatprovidedinSection3ofWCAP-14040duetoRGBspecificissuesandwaspreviouslyreviewedbytheNRCandfoundtobeacceptable(Ref.5).However,theLTOPenabletemperaturemethodologyisbeingrevisedtoclarifythespecificRCStemperatureaccuracyrequirementsandallowtheuseofASMEXICodeCaseN-514fortemperaturedetermination(Ref.8).AredlinedversionoftheLTOPmethodologyshowingallchangesfromthepreviousNRCapprovedversionisprovidedinAttachmentVwhileafinalversionisprovidedin.AttachmentVItothisLAR.Therefore,thisLARprovidesaproposedPTLR(andsupportingdocumentationasprovidedinWCAP-14684)andincludesareferencetoWCAP-14040-NP-AandthisLARintheAdministrativeControlsasthebasisforthemethodology.ItshouldbenotedthateventhoughthetechnicalspecificationsdonotrequirereactorvesselmaterialinformationtobelocatedwithinthePTLR,thisinformationisprovidedconsistentwithGenericLetter96-03.ThisincludesarevisedRT~,valuebasedontheattachedWCAP-14684.TherevisedRT~valuealsoincludeschangesmadeasaresultofadditionalsurveillancecapsulechemistryanalyses.C.JUSTIFICATIONOFCHANGESThissectionprovidesthejustificationforallchangesdescribedinSectionAaboveandshowninAttachmentII.Thejustificationsareorganizedbasedonwhetherthechangeis:morerestrictive(M),lessrestrictive(L),administrative(A),ortherequirementisrelocated(R).Thejustificationslistedbelowarealsoreferencedinthetechnicalspecification(s)whichareaffected(seeAttachmentII).
C.1AdministrativeControlsSection5.6.6.cisrevisedto:(1)replacereferencetotheMay23,1996submittalwithanewreferencethatapprovesthefirstuseofthePTLRmethodologyascontainedinAttachmentVItothisLAR;(2)updatetheAdminstrativeControlscontentconsistent.withGL96-03;and,(3)updatethereferencesforPTLRmethodologywithrespecttoRCSP/Tlimits.Item(1)onlychangesthedateoftheNRCapprovalofthePTLR,includingthePTLRmethodologysinceGinnaStationcurrentlyhasaNRCapprovedPTLR.Item(2)makestheGinnaStationTechnicalSpecificationsconsistentwithISTSinorderforthelicenseetomakefuturechangeswithoutNRCreviewandapproval.Item(3)updatesthePTLRmethodologyusedforP/TlimitstoreferenceWCAP-14040-NP-AinsteadofreferencingWCAP-14040andtheassociatedNRCapprovalletter(i.e.,WCAP-14040-NP-AincludestheNRCapprovalletterandallNRCrequiredchanges).ThesethreechangesareadministrativeinnaturesincetheRCSP/TlimitswerepreviouslyrelocatedfromtechnicalspecificationstothePTLR;onlyminordetailsarebeingclarified.2.AdministrativeControlsSection5.6.6.c.lisrevisedtoreplacethepreviouslyapprovedLTOPmethodology(Ref.1)withthatprovidedinAttachmentVItothisLAR(AttachmentVprovidesa"red-line"comparisontothepreviouslyapprovedmethodologytoshowalldifferences).TheonlydifferenceintheproposednewLTOPmethodologyfromthatapprovedpreviouslyistoprovideadditionalclarificationsconsistentwithNRCandRG&EcommunciationsandtoallowtheLTOPenabletemperatureandpressurelimitstobedeterminedusingASMESectionXICodeCaseN-514.ThiscodecasedesignatestheallowablereactorcoolantpressureboundarypressureduringLTOPeventstobe110%ofthatspecifiedby10CFR50,AppendixG.Useofthiscodecaserequiresanexemptionto10CFR50.60whichwasgrantedtoRG&EinReference8.Therefore,thischangeincorporatestheuseofCodeCaseN-514intotheLTOPmethodologyspecifiedwithintheAdminstrativeControlssectionofTechnicalSpecificationsconsistentwithReference8.3.AtypographicalerrorinAdministrativeControlsSection5.6.6.discorrectedtoprovideconsistencywithNUREG-1431.Therearenotanymorerestrictive(M),lessrestrictive(L),orrelocated(R)changesassociatedwiththisLAR.
D.SIGNIFICANTHAZARDSCONSIDERATIONEVALUATIONTheproposedchangestotheGinnaStationTechnicalSpecificationsasidentifiedinSectionAandjustifiedinSectionChavebeenevaluatedwithrespectto10CFR50.92(c)andshowntonotinvolveasignificanthazardsconsiderationasdescribedbelow.ThissectionisorganizedbasedonSectionCabove.D.1TheadministrativechangesdiscussedinSectionC.1donotinvolveasignificanthazardsconsiderationasdiscussedbelow:OperationofGinnaStationinaccordance,withtheproposedchangesdoesnotinvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated.TheproposedchangesreviseAdministrativeControlsSection5.6.6.ctoupdatethereferencetotheNRC'sapprovalofthefirstuseofthePTLRmethodology,updatetheRCSP/TmethodologytothefinalNRCapprovedversion,allowuseofASMECodeCaseN-514forLTOPenabletemperaturemethodology,andtocorrectatypographicalerror.ThesechangescompleteimplementationofGenericLetter96-03byreferencingNRCapprovedmethodologywithintheAdministrativeControls.TheupdatedRCSP/TmethodologyhasbeengenericallyapprovedbytheNRCwhiletheuseofASMECodeCaseN-514forLTOPenabletemperaturemethodologywaspreviouslyapprovedforuseatGinnaStationbytheNRC.Assuch,thesechangesareadministrativeinnatureanddonotimpactinitiatorsoranalyzedeventsorassumedmitigationofaccidentortransientevents.Therefore,thesechangesdonotinvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyanalyzed.2.OperationofGinnaStationinaccordancewiththeproposedchangesdoesnotcreatethepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated.Theproposedchangesdonotinvolveaphysicalalterationoftheplant(i.e.,nonewordifferenttypeofequipmentwillbeinstalled)orchangesinthemethodsgoverningnormalplantoperation.Theproposedchangeswillnotimposeanynewordifferentrequirements.Thus,thischangedoesnotcreatethepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated.
3.OperationofGinnaStationinaccordancewiththeproposedchangesdoesnotinvolveasignificantreductioninamarginofsafety.TheproposedchangeswillnoteduceamarginofplantsafetybecausethemethodologyhavebeenshowntoensurethattheP/TandLTOPlimitsinthePTLRcontinuetomeetallnecessaryrequirementsforreactorvesselintegrity.ThesechangesareadministrativeinnaturesincethelimitswerepreviouslyrelocatedtothePTLRunderaseparateLAR.Assuch,noquestionofsafetyisinvolved,andthechangedoesnotinvolveasignificantreductioninamarginofsafety.Basedupontheaboveinformation,ithasbeendeterminedthattheproposedadministrativechangestotheGinnaStationTechnicalSpecificationsdonotinvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated,doesnotcreatethepossibilityofanewordifferentkindofaccidentpreviouslyevaluated,anddoesnotinvolveasignificantreductioninamarginofsafety.Therefore,itisconcludedthattheproposedchangesmeettherequirementsof10CFR50.92(c)anddonotinvolveasignificanthazardsconsideration.E.ENVIRONMENTALCONSIDERATIONRG&Ehasevaluatedtheproposedchangesanddeterminedthat:1.ThechangesdonotinvolveasignificanthazardsconsiderationasdocumentedinSectionDabove;2.Thechangesdonotinvolveasignificantchangeinthetypesorsignificantincreaseintheamountsofanyeffluentsthatmaybereleasedoffsitesincenospecificationsrelatedtooffsitereleasesareaffected;and3.ThechangesdonotinvolveasignificantincreaseinindividualorcumulativeoccupationalradiationexposuresincenonewordifferenttypeofequipmentarerequiredtobeinstalledasaresultofthisLAR.Accordingly,theproposedchangesmeettheeligibilitycriteriaforcategoricalexclusionsetforthin10CFR51.22(c)(9).Therefore,pursuantto10CFR51.22(b),anenvironmentalassessmentoftheproposedchangesisnotrequired.F.REFERENCESLetterfromR.C.Mecredy,RG&E,toA.R.Johnson,NRC,
Subject:
TechnicalSpectjicatt'onsImprovementProgram,ReactorCoolantSystem(RCS)PressureandTemperatureLimitsReport(PTLR),datedDecember8,1995.
LetterfromL.B.Marsh,NRC,toR.C.Mecredy,RG&B,
Subject:
R.E.Ginna-AcceptanceforReferencingofPressureTemperatureLimitsReport(TACNo.M92320),datedDecember26,1995.LetterfromA.R.Johnson,NRC,toR.C.Mecredy,RG&B,
Subject:
R.E.GinnaNuclearPowerPlant-PressurizedThermal'ShockEvaluation(TACNo.M93827),datedMarch22,1996.WCAP-14040-NP-A,MethodologyUsedtoDevelopColdOverpressureMitigatingSystemSetpointsandRCSHeatupandCooldownLimitCurves,January1996.LetterfromG.S.VissingNRC,toR.C.Mecredy,RG&E,
Subject:
IssuanceofAmendmentNo.6'4toFacilityOperatingLicenseNo.DPR-I8,R.E.GinnaNuclearPowerPlant(TACNo.M94770),datedMay23,1996.LetterfromR.C.Mecredy,RG&B,toG.S.Vissing,NRC,
Subject:
RequesttoUseASMECodeCaseN-514intheDeterminationofLowTemperatureOverpressureProtection(LTOP)EnableTemperature,datedDecember18,1996.LetterfromR.C.Mecredy,RG&E,toG.S.Vissing,NRC,
Subject:
RequestforExemprionto10CFR50.60toUseAmericanSocietyofMechanicalEngineers(ASME)CodeCaseN-514intheDeterminationofLowTemperatureOverpressureProtection(LTOP)EnableTemperature,datedFebruary10,1997.LetterfromG.S.Vissing,NRC,toR.C.Mecredy,RG&B,
Subject:
ExemptionfronttheRequirementsof10CFRPart50.60,AcceptanceCriteriaforFracturePreventionMeasuresforLightwaterNuclearPowerReactorsforNormalOperation-R.E.GinnaNuclearPlant(TACNo.M98993),datedJuly28,1997.LetterfromG.S.Vissing,NRC,toR.C.Mecredy,RG&E,
Subject:
R.E.Ginna-AcceptanceofRequesttoExtendTimeforApprovalofRevisionofPressureandTemperatureLimitsReport(PTLR)(TACNo.M97313),datedDecember10,1996.
AttachmentIIMarkedUpCopyofR.E.GinnaNuclearPowerPlantTechnicalSpecificationsIncludedPages:5.0-22