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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] |
Text
UNITEDSTATESOFAMERICANUCLEARREGULATORY COMMISSION IntheMatterof))Rochester GasandElectricCorporation
)(R.E.GinnaNuclearPowerPlant)))DocketNo.50-244APPLICATION FORAMENDMENT TOOPERATING LICENSEPursuanttoSection50.90oftheregulations oftheU.S.NuclearRegulatory Commission (the"Commission"
),Rochester GasandElectricCorporation
("RG&E"),
holderofFacilityOperating LicenseNo.DPR-18,herebyrequeststhattheTechnical Specifications setforthinAppendixAtothatlicensebeamended.ThisrequestforchangeinTechnical Specifications istoincreaseallowable reactorcoolantactivitylevelstotheImprovedTechnical Specification values(NUREG-1431).
Adescription oftheamendment request,necessary background information, justification oftherequested change,safety'valuation andnosignificant hazardsandenvironmental considerations areprovidedinAttachment A.Amarkedupcopyofthecurrent.GinnaStationTechnical Specifications whichshowstherequested changeissetforthinAttachment B.TheproposedrevisedTechnical Specifications areprovidedinAttachment C.Thesechangesareconsistent withWestinghouse ImprovedTechnical Specifications (NUREG1431)3.4.16.a,b andfigure3.4.16-1.
94053iOih7 940523PDRADOCK05000244.P'.,PDR
WHEREFORE, Applicant respectfully requeststhatAppendixAtoFacilityOperating LicenseNo.DPR-18beamendedintheformattachedheretoasAttachment C.Rochester GasandElectricCorporation ByRobertC.MecredyVicePresident GinnaNuclearProduction Subscribed andsworntobeforemeonthis23rddayofMay,1994.
ATTACHMENT AR.E.GINNAPOWERPLANTLICENSEAMENDMENT REQUESTTECHNICAL SPECIFICATION 3.1.4,MAXIMUMCOOLANTACTIVITYThisattachment providesadescription oftheamendment requestandnecessary justification fortheproposedchanges.Theattachment isdividedintosevensectionsasfollows.SectionAidentifies allchangestothecurrentGinnaStationTechnical Specifications whileSectionBprovidesthebackground andhistoryassociated withthechangesbeingrequested.
SectionCprovidesdetailedjustification fortheproposedchangesincluding acomparison toImprovedTechnical Specifications asapplicable.
Asafetyevaluation, significant hazardsconsideration evaluation, andenvironmental consideration oftherequested changesareprovidedinSectionsD,E,andF,respectively.
SectionGlistsallreferences usedinthisattachment.
A.Description ofAmendment RequestThisLicenseAmendment Request(LAR)proposestoreviseGinnaStationTechnical Specifications 3.1.4.1.a, 3.1.4.1.b, figure3.1.4-1andassociated Basesasfollows:1.Technical Specification 3.1.4.1.a i.Therequirement ischangedto"Thetotalspecificactivityofthereactorcoolantshallnotexceed100/EpCi/gm,..."
ii.Thebasesarerevisedtochangethereferenced analysis(Reference 3)to"UFSARSection15.'6.3."
2.Technical Specification 3.1.4.1.b i.Therequirement isrevisedto"TheI-131doseequivalent oftheiodineactivityinthereactorcoolantshallnotexceed1.0pCi/gm."ii.Thebasesarerevisedtochangethereferenced analysis(Reference 3)to"UFSARSection15.6.3."3.Technical Specification Figure3.1.4-1i.Theallowable operation regionismodifiedconsistent withImprovedTechnical Specifications (seeAttachments BandCforrevisedfigure).ii.Thebasesarerevisedtochangethereferenced analysis(Reference 3)to"UFSARSection15.6.3."B~Background HistoryPriortotheJanuary25,1982,steamgenerator tuberuptureeventatGinnaStation,reactorcoolantactivitylimitswerebasedontheoriginal(1969)steamgenerator tuberuptureanalysisfortheGinnaStation.TheCommission's reviewofthe1982tuberuptureincident resulteintherequirement foraresedsteamgenerator tuberuptureanalysis.
Thestaffrequiredthatthisbecompleted withinsixmonthsoftheplantrestart(NUREG-0916,Section9.0),andimposedreducedallowable activitylevelsintheinterim(Amendment No.51toProvisional Operating LicenseNo.DPR-18,May22,1982).Aboundinganalysisusingthesereducedallowable activitylevelswasperformed inordertosatisfythesixmonthrequirement, whileamoredetailedanalysissupporting thestandardtechnical specification valueswouldfollow.'he methodology forthisnewanalysis(WCAP-10698-P-A) wassubmitted andapprovedbytheCommission for'useon'estinghouse PWRsprovidedfiveplantspecificinputswereverifiedtobeconsistent withtheassumptions inthemethodology (Reference a).RG&Ehascompleted thisverification, andtherefore intendstoupdateitsanalysisofrecordforthesteamgenerator tuberupturetoreflectuseofthisnewmethodology (UFSARSection15.6.3).ThisnewanalysissupportstheactivitylimitsproposedinthisAmendment.
2.HardwareModifications ThisLARinvolvesnohardwarechangestoGinnaStation.Justification ThisproposedAmendment imposesreactorcoolantactivitylimitsconsistent withNUREG-1431, "Westinghouse StandardTechnical Specifications."
Theapplicability oftheselimitsforGinnaStationareestablished byaplantspecificsteamgenerator tuberuptureandradiological consequences
- analysis, WCAP-11668, whichisconsistent withtheapprovedmethodology ofWCAP-10698-P-A foranalysisofsteamgenerator tuberupturetransients.
Allcontingencies forusageofWCAP-10698-P-A methodology (Reference a)havebeensatisfied forGinnaStationasdescribed insectionDbelow.SafetyEvaluation Potential environmental consequences ofasteamgenerator tuberuptureeventattheR.E.Ginnanuclearpowerplanthavebeenevaluated toverifythattheImprovedTechnical Specification limitonprimarycoolantactivityisadequateforGinna.'Thisanalysis, WCAP-11668 (attached) isconsistent withthemethodology described inWCAP-10698-P-A.
TheCommission requiresthatfivecontingencies bemetinordertousethismethodology, specifically:
1~Demonstration thatcriticaloperatoractiontimesusedintheanalysisarerealistic andconsistent withthoseobservedduringsimulator exercises.
2~3~AsitespecificSteamGenerator TubeRuptureradiological offsiteconsequence analysis.
Astructural analysisofthemainsteamlinesdemonstrating adequacyunderwater-filled conitions.4~Alistofsystems,components, andinstrumentation creditedforaccidentmitigation andthespecified safetygradeforeach.5.Acomparison oftheplanttothe"bounding plant"usedinWCAP-10698.
Compliance withthosecontingencies forGinnaStationhasbeensatisfied andisdescribed below.1~Demonstration thatcriticaloperatoractiontimesusedintheanalysisarerealistic andconsistent withthoseobservedduringsimulator exercises.
DuringtheweekofAugust19through23,1991,simulator exercises wereperformed attheGinnaStationsimulator toverifytheassumptions usedforbothanalysescasespresented inWCAP-11668.
Theresultsaretabulated below.CASE1,INTACTSGPORVFAILSCLOSEDOPERATORACTION1.Recognize andIsolateRupturedSG2.Recognize andlocallyopenintactSGPORVopen3.Terminate SI4.Terminate breakflowWCAP11668TIME(SEC)600180427983428SIMULATOR TIME(SEC)4231460*19162541*Thesimulator exerciseimposeda15min.delayfromwhentheoperatoridentified thefailedPORVtowhenthePORVwaslocallyopenedtoaccountforoperatoractionsoutsidethecontrolroomwhichcouldnotbeverifiedonthesimulator.
Thisdelayisconsistent withtheassumptions inWCAP-11668.
Simulation oftheseactionsintheactualplanthavedemonstrated thatthesetimesareconservative.
.<5.%e)J CASE2RUPTUREDSGPORVFAILSOPENOPERATORACTION1.RupturedSGIsolated2.Recognize andLocallyIsolateFailedPORV3.Terminate SI4.Terminate BreakFlowWCAP-11668 TIME(SEC)652155830663438SIMULATOR TIME(SEC)2141116*20732424*Thesimulator exerciseimposeda15min.delayfromwhentheoperatoridentified thefailedPORVtowhenthePORVwaslocallyisolatedtoaccountforoperatoractionsoutsidethecontrolroomwhichcouldnotbeverifiedonthesimulator.
Thisdelayisconsistent withtheassumptions inWCAP-11668.
Simulation oftheseactionsintheactualplanthavedemonstrated thatthesetimesareconservative.
Thesesimulator exercises demonstrate thatthecriticaloperatoractiontimesassumedinWCAP-11668 arerealistic andconservative andtherefore thiscontingency issatisfied.
ProvideasitespecificSteamGenerator TubeRuptureradiological offsiteconsequences analysis.
WCAP-11668, providedwiththisLARprovidesaGinnasitespecificSteamGenerator TubeRuptureradiation offsiteconsequences
- analysis, andtherefore, thiscontingency issatisfied.
Provideastructural analysisofthemainsteamlinesdemonstrating adequacyunderwater-filled conditions.
PriortorestartofGinnaStationfollowing theJanuary25,1982,tuberuptureincident, amainsteamlinestructural analysisunderwater-filled conditions wasperformed andprovidedtotheCommission.
Theacceptability ofthisanalysisisdocumented inthere@tartSER(NUREG-0916(
section6.0.Therefore, thiscontingency ismet.Alistofsystems,components, andinstrumentation creditedforaccidentmitigation andthespecified safetygradeforeach.InresponsetoNUREG-0737, Supplement 1Item6.2,RG&Ehasprovidedpostaccidentinstrumentation qualification information.
Acomprehensive tablelistingthecreditedequipment, itsqualification, andallotherattributes listedinRegulatory Guide1.97,revision3,wasprovidedtotheNRCbyletterR.MecredytoA.Johnson"Emergency cn ResponseCapability",
datedOctober4,1992.AnSERfor~uthissubmittal wasprovidedtoRGGEbyletterA.JohnsontoR.Mecredy,"Emergency ResponseCapability,"
datedFebruary24,1993.Therefore, thiscontingency hasbeensatisfied.
Acomparison oftheplanttothe"bounding plant"usedinWCAP-10698.
/Plantparameters forthereference plantusedinWCAP-10698-P-A areprovidedinTable4.3-3oftheWCAP.WCAP-11668,theGinnaspecificanalysis, utilizesGinnaspecificparameters.
AllGinnaspecificparameters fallwithintheboundsoftheparameters listedinWCAP-10698-P-Aasdetailedbelow:PLANTPARAMETER RCSPressure, siaPressurizer WaterVolume,ft~SGSecondary Mass,ibmReactorTripDelay,secTurbineTripDelay,secPressurizer PressureforSI,siaPressurizer PressureforReactorTrip,psiaSGRelievePressure, psiaSISPumpDelay,secAFWDelay,secAFWFlowRate,gpmAFWTemerature,4FfDecayHeatWCAP-10698 BASECASE22507501077592.00.31864196011001260183940100'tANS,WCAP-10698 CONSERVATIVE 22208681185350.00.01889198510500.00.01839120120%ANSWCAP-11668 GINNA22208001032562.00.31750190210600.00.0800120120%ANSItshouldbenotedthatthemethodology ofWCAP-10698-P-A providesabenchmark againstthe1982Ginnatuberuptureincident, and,therefore, itsapplicability toGinnaisexplicit.
Therefore, thiscontingency issatisfied.
Basedontheabove,themethodology described inWCAP-10698-P-A canbeappliedtoGinna.WCAP-11668 (enclosed) providestheresultsofthisapplication, anddemonstrates theacceptability ofImprovedTechnical Specification coolantactivitylimitsforGinna.Therefore, theproposedamendment doesnotinvolveanunreviewed safetyquestionandwillnotadversely affectorendangerthehealthandsafetyofthegeneralpublic.
E.Significant zardsConsideration EvaluaionTheproposedchanges~totheGinnaStationTechnical Specifications donotinvolveasignificant hazardsconsideration asdiscussed below:Operation ofGinnaStationinaccordance withtheproposedchangesdoesnotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated.
Theproposedchangesdonotaffectanyaccidentinitiators andtherefore theprobability ofanyaccidentisnotincreased.
Consequences ofthechangesareanalyzedandshownacceptable intheenclosedanalysis, WCAP-11668, SectionIII.2~Operation ofGinnaStationinaccordance withtheproposedchangesdoesnotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated.
Theproposedchangesinvolvenophysicalmodifications totheplant;therefore, nonewaccidentcanbepostulated.
3~Operation ofGinnaStationinaccordance withtheproposedchangesdoesnotinvolveasignificant reduction inamarginofsafety,asnomarginofsafetyisreducedbytheproposedchanges,asshowninWCAP-11668.
Basedupontheaboveinformation, ithasbeendetermined thattheproposedchangestotheGinnaStationTechnical Specifications donotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated, doesnotcreatethepossibility ofanewordifferent kindofaccidentpreviously evaluated, anddoesnotinvolveasignificant reduction inamarginofsafety.Therefore, itisconcluded thattheproposedchangesmeettherequirements of10CFR50.92(c)anddonotinvolveasignificant hazardsconsideration.
F.Environmental Consideration RGGEhasevaluated theproposedchangesanddetermined that:1.Thechangesdonotinvolveasignificant hazardsconsideration asdocumented inSectionEabove;2~Thechangesdonotinvolveasignificant changeinthetypesorsignificant increaseintheamountsofanyeffluents thatmaybereleasedoffsiteasdemonstrated intheenclosedanalysis, WCAP11668.3.Thechangesdonotinvolveasignificant increaseinindividual orcumulative occupational radiation exposuresincethechangedoesnotaffectallowable limits.Accordingly, theproposedchangesmeettheeligibility criteriaforcategorical exclusion setforthin10CFR
.00<<4l 51.22(c)(9).Therefore, pursuantto10CFR51.22(h),
anenvironmental assessment oftheproposedchangesisnotrequired.
References (a):NRCLetter,C.RossitoA.Ladieu(WOG),"Acceptance forReferencing ofLicensing TopicalReportWCAP-10698...",
March30,1987.(b):NUREG-0916, "SafetyEvaluation ReportRelatedtotheRestartofR.E.GinnaNuclearPowerPlant",May1982.4(c):RG&ELetter,R.MecredytoA.Johnson(NRC),"Emergency ResponseCapability...",
October14,1992.(d):NRCLetter,A.JohnsontoR.Mecredy(RGGE),Emergency ResponseCapability
-Conformance toRegulatory Guide1.97,revision3",February24,1993.