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| {{#Wiki_filter:g'O'RIDRITY 1ACCELERATED RlDSPl<OCESSli G)IREGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)~CCESSIONNBR:9506080198 DOC.DATE:-95/05/26 NOTARIZED: | | {{#Wiki_filter:g'O'RIDRITY 1 ACCELERATED Rl DS P l<OCESSli G)I REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)~CCESSION NBR:9506080198 DOC.DATE:-95/05/26 NOTARIZED: |
| YES'FACIL:50-244 RobertEmmetGinnaNuclearPlant,Unit1,Rochester GAUTH.NAMEAUTHOR.AFFILIATION MECREDY,R.C. | | YES'FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G AUTH.NAME AUTHOR.AFFILIATION MECREDY,R.C. |
| Rochester Gas&ElectricCorp.RECIP.NAME RECIPIENT AFFILIATION JOHNSONA.R.Pro'ectDirectorate I-1PD1-1Post941001DOCKET05000244W~pI3()() | | Rochester Gas&Electric Corp.RECIP.NAME RECIPIENT AFFILIATION JOHNSON A.R.Pro'ect Directorate I-1 PD1-1 Post 941001 DOCKET 05000244 W~p I 3 ()() |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Forwardsapplication foramendtolicenseDPR-18,revising TSsinentiretybyconverting toimprovedTSs.~:fo+>7oDTITLE:ORSubmittal:
| | Forwards application for amend to license DPR-18,revising TSs in entirety by converting to improved TSs.~: fo+>7oD TITLE: OR Submittal: |
| GeneralDistribution NOTES:License Expdateinaccordance with10CFR2,2.109(9/19/72).
| | General Distribution NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). |
| 05000244RECIPIENT IDCODE/NAME PD1-1LAJOHNSON,A INTERNAIBECENT0BNRR/DSSA/SRXB OGC/HDS3EXTERNAL:
| | 05000244 RECIPIENT ID CODE/NAME PD1-1 LA JOHNSON,A INTERNA IBE CENT 0 B NRR/DSSA/SRXB OGC/HDS3 EXTERNAL: NOAC COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 0 1 1 RECIPIENT ID CODE/NAME PD1-1 PD NRR/DE/EMCB NRR/DS SA/S PLB NUDOCS-ABSTRACT NRC PDR COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 D 0 C u N YOTE TO ALL"RIDS" RECIPIEYTS: |
| NOACCOPIESLTTRENCL11111111111011RECIPIENT IDCODE/NAME PD1-1PDNRR/DE/EMCB NRR/DSSA/SPLBNUDOCS-ABSTRACT NRCPDRCOPIESLTTRENCL1111111111D0CuNYOTETOALL"RIDS"RECIPIEYTS:
| | PLEASE HELP US TO REDUCE lVKSTE!COYTAC'f'I'I IE DOCL'IIEET CONTROL DESK, ROOKI Pl-37 (EXT.504-~083)TO ELI XIIX.ATE YOI.'R%ANIL FROW!DIS f Rl 8UTIOY LIS'I'S I'OR DOCI.5,1I.'X'I'S 0'Ol.'ON'"I'L'I'. |
| PLEASEHELPUSTOREDUCElVKSTE!COYTAC'f'I'IIEDOCL'IIEET CONTROLDESK,ROOKIPl-37(EXT.504-~083)TOELIXIIX.ATEYOI.'R%ANILFROW!DISfRl8UTIOYLIS'I'SI'ORDOCI.5,1I.'X'I'S 0'Ol.'ON'"I'L'I'.
| | D!TOTAL NUMBER OF COPIES REQUIRED: LTTR 12 ENCL 11 AND ROCHESTER GAS AND EIECTRIC CORPORATION |
| D!TOTALNUMBEROFCOPIESREQUIRED: | | ~89 FASTAtrrENUE, ROCHESTER, N.Y Id&f9-0001 ARFA CODE716 56-2700 ROBERT C.MECREDY Vice President Nucteor Operations Hay 26, 1995 U.S.Nuclear Regulatory Commission Document Control Desk Attn: Allen R.Johnson Project Directorate I-1 Washington, D.C.20555 |
| LTTR12ENCL11 ANDROCHESTER GASANDEIECTRICCORPORATION
| |
| ~89FASTAtrrENUE, ROCHESTER, N.YId&f9-0001 ARFACODE71656-2700ROBERTC.MECREDYVicePresident NucteorOperations Hay26,1995U.S.NuclearRegulatory Commission DocumentControlDeskAttn:AllenR.JohnsonProjectDirectorate I-1Washington, D.C.20555 | |
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| ==Subject:== | | ==Subject:== |
| Application forAmendment toFacilityOperating LicenseConversion toImprovedTechnical Specifications Rochester Gas&ElectricCorporation R.E.GinnaNuclearPowerPlantDocketNo.50-244 | | Application for Amendment to Facility Operating License Conversion to Improved Technical Specifications Rochester Gas&Electric Corporation R.E.Ginna Nuclear Power Plant Docket No.50-244 |
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| ==DearHr.Johnson,== | | ==Dear Hr.Johnson,== |
| TheenclosedLicenseAmendment Request(LAR)proposestorevisetheGinnaStationTechnical Specifications initsentiretybyconverting toImprovedTechnical Specifications (ITS).ThisLARalsoproposestorevisetheGinnaStationOperating License.Theproposedapplication isconsistent withtheoriginalpurposeoftheTechnical Specification Improvement ProgramasoutlinedinReference (a).Thetechnical specification changeswithdrawn byReference (b)arealsoaddressed inthisLAR.Inaddition, thechangesrequested byReference (c)areincludedwithinthissubmittal (i.e.,thisLARdoesnotsupersede Reference (c)butisconsistent withthechangesbeingrequested).
| | The enclosed License Amendment Request (LAR)proposes to revise the Ginna Station Technical Specifications in its entirety by converting to Improved Technical Specifications (ITS).This LAR also proposes to revise the Ginna Station Operating License.The proposed application is consistent with the original purpose of the Technical Specification Improvement Program as outlined in Reference (a).The technical specification changes withdrawn by Reference (b)are also addressed in this LAR.In addition, the changes requested by Reference (c)are included within this submittal (i.e., this LAR does not supersede Reference (c)but is consistent with the changes being requested). |
| TheproposedITScontained inthisLARarebasedonthecurrentGinnaStationTechnical Specifications (throughAmendment No.59),NUREG-1431 (Ref.(d)),andotherdocuments.
| | The proposed ITS contained in this LAR are based on the current Ginna Station Technical Specifications (through Amendment No.59), NUREG-1431 (Ref.(d)), and other documents. |
| TheproposedITSLimitingConditions forOperations (LCO)orSurveillance Requirements (SRs)whicharelessrestrictive thanthecurrentGinnaStationTechnical Specifications (TS)andwhicharenotconsistent withNUREG-1431 arelistedbelow(LCOsandSRsarethoselistedinAttachment Ctothisletter):a~b.c~Allrefueling intervalsurveillances werechangedfrom18monthsto24monthsconsistent withtheguidanceofGenericLetter91-04(Ref.(e)).Allowbothpost-accident charcoalfilterstoberemovedfromserviceatthesametimeprovidedthatbothcontainment spraytrainsareOPERABLE(LCO3.6.6andcurrentGinnaStationTS3.3.2.2).
| | The proposed ITS Limiting Conditions for Operations (LCO)or Surveillance Requirements (SRs)which are less restrictive than the current Ginna Station Technical Specifications (TS)and which are not consistent with NUREG-1431 are listed below (LCOs and SRs are those listed in Attachment C to this letter): a~b.c~All refueling interval surveillances were changed from 18 months to 24 months consistent with the guidance of Generic Letter 91-04 (Ref.(e)).Allow both post-accident charcoal filters to be removed from service at the same time provided that both containment spray trains are OPERABLE (LCO 3.6.6 and current Ginna Station TS 3.3.2.2).Only require one component cooling water heat exchanger to be OPERABLE when the system is required to be OPERABLE (LCO 3.7.7 and current Ginna Station TS 3.3.3.1).('st50b080 i'st8'st5052b, PDR ADOCK 05000244 P','DR o pV' 0'I rI I W N S/~t~J t t 1, Allow both motor driven auxiliary feedwater (AFW)pumps to be removed from service for up to 72 hours (LCO 3.7.5 and current Ginna Station TS 3.4.2.1.b). |
| Onlyrequireonecomponent coolingwaterheatexchanger tobeOPERABLEwhenthesystemisrequiredtobeOPERABLE(LCO3.7.7andcurrentGinnaStationTS3.3.3.1).('st50b080 i'st8'st5052b, PDRADOCK05000244P','DRopV' 0'IrIIWNS/~t~Jtt1, Allowbothmotordrivenauxiliary feedwater (AFW)pumpstoberemovedfromserviceforupto72hours(LCO3.7.5andcurrentGinnaStationTS3.4.2.1.b).
| | Increase the allowed outage times for certain reactor trip system and engineered safety feature actuation system functions up to 72 hours (LCO 3.3.1, LCO 3.3.2, and current Ginna Station TS 3.5.1 and 3.5.2).Allow an additional 48 hours to restore an inoperable reactor trip breaker or Automatic Trip Logic train in HODES 3, 4, and 5 after exiting HODE 2 with this condition (LCO 3.3.1 and current Ginna Station TS 3.5.1).Allow the use of a closed system to isolate a containment penetration with a failed containment isolation valve (LCO 3.6.3 and current Ginna Station TS 3.6.3).Only require one offsite power source to be OPERABLE during HODE changes (LCO 3.8.1 and current Ginna Station TS 3.7.2.l.b.2, 3.7.2.2.a, and 3.7.2.2.b). |
| Increasetheallowedoutagetimesforcertainreactortripsystemandengineered safetyfeatureactuation systemfunctions upto72hours(LCO3.3.1,LCO3.3.2,andcurrentGinnaStationTS3.5.1and3.5.2).Allowanadditional 48hourstorestoreaninoperable reactortripbreakerorAutomatic TripLogictraininHODES3,4,and5afterexitingHODE2withthiscondition (LCO3.3.1andcurrentGinnaStationTS3.5.1).Allowtheuseofaclosedsystemtoisolateacontainment penetration withafailedcontainment isolation valve(LCO3.6.3andcurrentGinnaStationTS3.6.3).OnlyrequireoneoffsitepowersourcetobeOPERABLEduringHODEchanges(LCO3.8.1andcurrentGinnaStationTS3.7.2.l.b.2,3.7.2.2.a, and3.7.2.2.b).
| | Allow 72 hours to reduce the Power Range Neutron Flux trip Function setpoint when Fo or F~is not within limits (LCO 3.2.1, LCO 3.2.2, and current Ginna Station TS 3.10.2.2).Remove the requirement to test certain reactor coolant system pressure isolation valves when the plant has been in cold shutdown for>7 days (SR 3.4.14.1 and current Ginna Station TS 4.3.3.1).Remove the requirement to test the motor driven AFW pump cross-over motor operated isolation valves (LCO 3.7.5 and current Ginna Station TS 4.8.3).Remove the requirement to verify that the AFW pumps and valves can actuate within 10 minutes (LCO 3.7.5 and current Ginna Station TS 4.8.10).Increase the allowed tolerances for the pressurizer safety valves setpoint (LCO 3.4.10 and current Ginna Station TS 3.3.1.3.a).Increase the allowed fuel enrichment limit from 4.25 weight percent to 5.05 weight percent (Specification 4.3.l.I.a and current Ginna Station TS 5.3.1.b).Relocate the following parameters and setpoints to the Core Operating Limits Report: Overpower~T and Overtemperature |
| Allow72hourstoreducethePowerRangeNeutronFluxtripFunctionsetpointwhenFoorF~isnotwithinlimits(LCO3.2.1,LCO3.2.2,andcurrentGinnaStationTS3.10.2.2).Removetherequirement totestcertainreactorcoolantsystempressureisolation valveswhentheplanthasbeenincoldshutdownfor>7days(SR3.4.14.1andcurrentGinnaStationTS4.3.3.1).Removetherequirement totestthemotordrivenAFWpumpcross-over motoroperatedisolation valves(LCO3.7.5andcurrentGinnaStationTS4.8.3).Removetherequirement toverifythattheAFWpumpsandvalvescanactuatewithin10minutes(LCO3.7.5andcurrentGinnaStationTS4.8.10).Increasetheallowedtolerances forthepressurizer safetyvalvessetpoint(LCO3.4.10andcurrentGinnaStationTS3.3.1.3.a).Increasetheallowedfuelenrichment limitfrom4.25weightpercentto5.05weightpercent(Specification 4.3.l.I.aandcurrentGinnaStationTS5.3.1.b).
| | ~T parameters (LCO 3.3.1 and current Ginna Station TS 2.3.1.2.d and 2.3.1.2.e). |
| Relocatethefollowing parameters andsetpoints totheCoreOperating LimitsReport:Overpower
| | Refueling water storage tank (RWST)boron concentration (LCO 3.5.4 and current Ginna Station TS 3.3.l.l.a and 3.3.1.2).Accumulator boron concentration (LCO 3.5.1 and current Ginna Station TS 3.3.1.l.b and 3.3.1.3). iv.SHUTDOWN MARGIN (LCO 3.1.1 and current Ginna Station TS 3.10.1.1 and Figure 3.10-2).p.Relocate the containment integrity requirements during refueling (i.e., NODE 6)from the technical specifications (current Ginna Station TS 3.5.2, 3.5.5, and 3.8.l.a).q.Relocate the Reactor Coolant Pump Underfrequency trip Function from technical specifications (current Ginna Station TS 2.3.1.2.g and 3.5.1).r.Relocate the AFW and Standby AFW system manual initiation functions from technical specifications (current Ginna Station TS 3.5.2).The above changes, while different from NUREG-1431 and the current Ginna Station TS, are consistent with the Final Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors (Ref.(f))and the accident analyses.The changes are discussed in detail i'n Attachment A.Revision 0 of NUREG-1431 was used for the preparation of this LAR since Revision 1 has only recently been issued.However, all approved Travellers which were used to generate Revision 1 are addressed in this submittal. |
| ~TandOvertemperature | | The only exception is Traveller BWR-26, C.1 related to LCO 3.0.4.This Traveller has not been generically evaluated for the Westinghouse plants as required by the Reviewer's Note added as part of this approved Traveller. |
| ~Tparameters (LCO3.3.1andcurrentGinnaStationTS2.3.1.2.d and2.3.1.2.e). | | Therefore, RG&E has elected to defer implementation of this Traveller until after this evaluation has been performed. |
| Refueling waterstoragetank(RWST)boronconcentration (LCO3.5.4andcurrentGinnaStationTS3.3.l.l.aand3.3.1.2).Accumulator boronconcentration (LCO3.5.1andcurrentGinnaStationTS3.3.1.l.b and3.3.1.3). iv.SHUTDOWNMARGIN(LCO3.1.1andcurrentGinnaStationTS3.10.1.1andFigure3.10-2).p.Relocatethecontainment integrity requirements duringrefueling (i.e.,NODE6)fromthetechnical specifications (currentGinnaStationTS3.5.2,3.5.5,and3.8.l.a).q.RelocatetheReactorCoolantPumpUnderfrequency tripFunctionfromtechnical specifications (currentGinnaStationTS2.3.1.2.gand3.5.1).r.RelocatetheAFWandStandbyAFWsystemmanualinitiation functions fromtechnical specifications (currentGinnaStationTS3.5.2).Theabovechanges,whiledifferent fromNUREG-1431 andthecurrentGinnaStationTS,areconsistent withtheFinalPolicyStatement onTechnical Specifications Improvements forNuclearPowerReactors(Ref.(f))andtheaccidentanalyses. | | We request that NRC approval of this LAR be provided by November 20, 1995.This approval date is required to support an implementation date in February 1996 since included within this LAR is a change in the allowed fuel enrichment limit.This enrichment limit is being changed to support conversion to 18 month refueling cycles with the new fuel scheduled to be shipped by Westinghouse beginning in February 1996.The technical evaluation of this change in enrichment was previously submitted to the NRC by Reference (g).With an implementation date in February 1996, all surveillances as proposed in Attachment C will be current with the following exceptions: |
| Thechangesarediscussed indetaili'nAttachment A.Revision0ofNUREG-1431 wasusedforthepreparation ofthisLARsinceRevision1hasonlyrecentlybeenissued.However,allapprovedTravellers whichwereusedtogenerateRevision1areaddressed inthissubmittal.
| | a~b.SR 3.6.6.13-This requires a verification every 5 years of the spray additive flow rate through each eductor path.The current Ginna Station TS do not contain this requirement. |
| Theonlyexception isTraveller BWR-26,C.1relatedtoLCO3.0.4.ThisTraveller hasnotbeengenerically evaluated fortheWestinghouse plantsasrequiredbytheReviewer's NoteaddedaspartofthisapprovedTraveller.
| | However, recirculation flow from the RWST through the eductors is performed monthly.In addition, sample lines associated with the spray additive tank have not previously demonstrated blockage.A review'of industry events related to the spray additive tank also did not reveal any concerns with respect to blockage.SR 3.7.3.1-This requires a verification every 24 months that each main feedwater pump discharge valve (HFPDV)can close within 80 seconds following receipt of an actual or simulated signal.The current Ginna Station TS do not contain this requirement. |
| Therefore, RG&Ehaselectedtodeferimplementation ofthisTraveller untilafterthisevaluation hasbeenperformed. | | However, the HFPDVs were last tested on April 14, 1992 with one valve closing in 73.1 seconds and the second valve closing in 75.9 seconds.These values are within the 80 second limit and provide assurance of the HFPDVs OPERABILITY. |
| WerequestthatNRCapprovalofthisLARbeprovidedbyNovember20,1995.Thisapprovaldateisrequiredtosupportanimplementation dateinFebruary1996sinceincludedwithinthisLARisachangeintheallowedfuelenrichment limit.Thisenrichment limitisbeingchangedtosupportconversion to18monthrefueling cycleswiththenewfuelscheduled tobeshippedbyWestinghouse beginning inFebruary1996.Thetechnical evaluation ofthischangeinenrichment waspreviously submitted totheNRCbyReference (g).Withanimplementation dateinFebruary1996,allsurveillances asproposedinAttachment Cwillbecurrentwiththefollowing exceptions:
| | Based on the above information, RG&E requests that these SRs be deferred until the refueling outage scheduled to begin by April 1, 1996.RG&E would like to note that we have requested an exemption to 10 CFR 50, Appendix K, Sections I.D.3 and I.D.5 with respect to upper plenum injection issues (Ref.(h))which, when approved, would result in a change to the Ginna Station license.This change is not addressed, or otherwise included within this LAR.The final implementation date will be coordinated with the NRC following final approval of this LAR.Any questions related to this LAR should be directed to Hark Flaherty at (716)724-8512.Very truly yours, Robert C.Hecre y MDFX612 Attachments |
| a~b.SR3.6.6.13-Thisrequiresaverification every5yearsofthesprayadditiveflowratethrougheacheductorpath.ThecurrentGinnaStationTSdonotcontainthisrequirement. | |
| However,recirculation flowfromtheRWSTthroughtheeductorsisperformed monthly.Inaddition, samplelinesassociated withthesprayadditivetankhavenotpreviously demonstrated blockage. | |
| Areview'of industryeventsrelatedtothesprayadditivetankalsodidnotrevealanyconcernswithrespecttoblockage.
| |
| SR3.7.3.1-Thisrequiresaverification every24monthsthateachmainfeedwater pumpdischarge valve(HFPDV)canclosewithin80secondsfollowing receiptofanactualorsimulated signal.ThecurrentGinnaStationTSdonotcontainthisrequirement.
| |
| However,theHFPDVswerelasttestedonApril14,1992withonevalveclosingin73.1secondsandthesecondvalveclosingin75.9seconds.Thesevaluesarewithinthe80secondlimitandprovideassurance oftheHFPDVsOPERABILITY. | |
| Basedontheaboveinformation, RG&ErequeststhattheseSRsbedeferreduntiltherefueling outagescheduled tobeginbyApril1,1996.RG&Ewouldliketonotethatwehaverequested anexemption to10CFR50,AppendixK,SectionsI.D.3andI.D.5withrespecttoupperplenuminjection issues(Ref.(h))which,whenapproved, wouldresultinachangetotheGinnaStationlicense.Thischangeisnotaddressed, orotherwise includedwithinthisLAR.Thefinalimplementation datewillbecoordinated withtheNRCfollowing finalapprovalofthisLAR.Anyquestions relatedtothisLARshouldbedirectedtoHarkFlahertyat(716)724-8512.
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| Verytrulyyours,RobertC.HecreyMDFX612Attachments
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| ==References:== | | ==References:== |
| | | (a)Letter from R.C.Hecredy, RG&E, to A.R.Johnson, NRC, |
| (a)LetterfromR.C.Hecredy,RG&E,toA.R.Johnson,NRC, | |
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| ==Subject:== | | ==Subject:== |
| Conversion toImprovedTechnical Specifications, datedFebruary28,1994.(b)LetterfromR.C.Hecredy,RG&E,toA.R.Johnson,NRC, | | Conversion to Improved Technical Specifications, dated February 28, 1994.(b)Letter from R.C.Hecredy, RG&E, to A.R.Johnson, NRC, |
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| ==Subject:== | | ==Subject:== |
| LicenseAmendment Application
| | License Amendment Application Requests, dated April 26, 1995.(c)Letter from R.C.Mecredy, RG&E, to A.R.Johnson, NRC, |
| : Requests, datedApril26,1995.(c)LetterfromR.C.Mecredy,RG&E,toA.R.Johnson,NRC,
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| ==Subject:== | | ==Subject:== |
| Application forAmendment toOperating LicenseReactorCoolantActivityTechnical Specifications, datedHay23,1994.(d)NUREG-1431, StandardTechnical Specifications, westinghouse Plants,Revision0,September 1993.(e)GenericLetter91-04,ChangesinTechnical Specification Surveillance Intervals toAccommodate a24-NonthFuelCycle,datedApril2,1991.(f)NRC,FinalPolicyStatement onTechnical Specifications Improvements forNuclearPowerReactors, datedJuly21,1993.(g)LetterfromR.C.Mecredy,RG&E,toA.R.Johnson,NRC, | | Application for Amendment to Operating License Reactor Coolant Activity Technical Specifications, dated Hay 23, 1994.(d)NUREG-1431, Standard Technical Specifications, westinghouse Plants, Revision 0, September 1993.(e)Generic Letter 91-04, Changes in Technical Specification Surveillance Intervals to Accommodate a 24-Nonth Fuel Cycle, dated April 2, 1991.(f)NRC, Final Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 21, 1993.(g)Letter from R.C.Mecredy, RG&E, to A.R.Johnson, NRC, |
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| ==Subject:== | | ==Subject:== |
| Technical Specification Improvement Program,datedHay5,1995.(h)LetterfromR.C.Mecredy,RG&E,toA.R.Johnson,NRC, | | Technical Specification Improvement Program, dated Hay 5, 1995.(h)Letter from R.C.Mecredy, RG&E, to A.R.Johnson, NRC, |
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| ==Subject:== | | ==Subject:== |
| RequestforExemption toSelected10CFRPart50,AppendixKRequirements, datedNovember5,1992.
| | Request for Exemption to Selected 10 CFR Part 50, Appendix K Requirements, dated November 5, 1992. |
| xc:U.S.NuclearRegulatory Commission Mr.AllenR.Johnson(MailStop14B2)PWRProjectDirectorate I-1Washington, D.C.20555U.S.NuclearRegulatory Commission (2copies)Mr.CarlSchultenOfficeofTechnical Specifications Branch(MailStop011E22)Washington, D.C.20555U.S.NuclearRegulatory Commission RegionI475Allendale RoadKingofPrussia,PA19406Hr.GerryL.JonesINELLockeedIdahoHailStop38702525FreemontAvenueIdahoFalls,ID83415-3870 Hr.ClydeMortonPQP301HartzAvenueSuite206Danville, CA94526-3328 Ms.DonnaRossNewYorkStateEnergyOfficeGinnaSeniorResidentInspector Hr.JimAndrachek Westinghouse ElectricCompanyEnergyCenterEast4-14350NorthernPikeHonroeville, PA15146-2886 Hr.DonaldHoffmanEXCELServicesCorporation 11921Rockville PikeSuite100Rockville, HD20852Hr.GeneEckholt(copyofAttachment C,F,andGonly)NorthernStatesPowerCompanyPrairieIslandNuclearGenerating PlantRoute2Welch,HN55089Mr.ThomasMalanowski (copyofAttachments C,F,andGonly)Wisconsin ElectricPower231WestMichiganMilwaukee, WI53201 Nr.RickPulec(copyofAttachments C,F,andGonly)Wisconsin PublicServiceP.O.Box19002700NorthAdamsGreenBay,WI54307-9002 UNITEDSTATESOFAMERICANUCLEARREGULATORY COMMISSION IntheHatterof))Rochester GasandElectricCorporation | | 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 (2 copies)Mr.Carl Schulten Office of Technical Specifications Branch (Mail Stop 011E22)Washington, D.C.20555 U.S.Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Hr.Gerry L.Jones INEL Lockeed Idaho Hail Stop 3870 2525 Freemont Avenue Idaho Falls, ID 83415-3870 Hr.Clyde Morton PQP 301 Hartz Avenue Suite 206 Danville, CA 94526-3328 Ms.Donna Ross New York State Energy Office Ginna Senior Resident Inspector Hr.Jim Andrachek Westinghouse Electric Company Energy Center East 4-1 4350 Northern Pike Honroeville, PA 15146-2886 Hr.Donald Hoffman EXCEL Services Corporation 11921 Rockville Pike Suite 100 Rockville, HD 20852 Hr.Gene Eckholt (copy of Attachment C, F, and G only)Northern States Power Company Prairie Island Nuclear Generating Plant Route 2 Welch, HN 55089 Mr.Thomas Malanowski (copy of Attachments C, F, and G only)Wisconsin Electric Power 231 West Michigan Milwaukee, WI 53201 Nr.Rick Pulec (copy of Attachments C, F, and G only)Wisconsin Public Service P.O.Box 19002 700 North Adams Green Bay, WI 54307-9002 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Hatter of))Rochester Gas and Electric Corporation |
| )(R.E.GinnaNuclearPowerPlant)DocketNo.50-244APPLICATION FORAMENDMENT TOOPERATING LICENSEPursuanttoSection50.90oftheregulations oftheU.S.NuclearRegulatory Commission (NRC),Rochester GasandElectricCorporation (RG&E),holderofFacilityOperating LicenseNo.DPR-18,herebyrequeststhatthelicenseandtheTechnical Specifications setforthinAppendixAtothatlicensebeamended.ThisrequestforchangeistoconverttheentireTechnical Specifications toImprovedTechnical Specifications format.Severalrequirements arealsorelocated tootherprogramsanddocuments inaccordance withthecriteriacontained intheNRCFinalPolicyStatement onTechnical Specifications Improvements forNuclearPowerReactors. | | )(R.E.Ginna Nuclear Power Plant)Docket No.50-244 APPLICATION FOR AMENDMENT TO OPERATING LICENSE Pursuant to Section 50.90 of the regulations of the U.S.Nuclear Regulatory Commission (NRC), Rochester Gas and Electric Corporation (RG&E), holder of Facility Operating License No.DPR-18, hereby requests that the license and the Technical Specifications set forth in Appendix A to that license be amended.This request for change is to convert the entire Technical Specifications to Improved Technical Specifications format.Several requirements are also relocated to other programs and documents in accordance with the criteria contained in the NRC Final Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors.A description of the amendment request, necessary background information, justification of the requested change, and no significant hazards and environmental considerations are provided in Attachment A.This evaluation demonstrates that the proposed changes do not involve a significant change in the types or a significant increase in the amounts of effluents or any change in the authorized power level of the facility.The proposed changes also do not involve a significant hazards consideration. |
| Adescription oftheamendment request,necessary background information, justification oftherequested change,andnosignificant hazardsandenvironmental considerations areprovidedinAttachment A.Thisevaluation demonstrates thattheproposedchangesdonotinvolveasignificant changeinthetypesorasignificant increaseintheamountsofeffluents oranychangeintheauthorized powerlevelofthefacility.
| | I (}} |
| Theproposedchangesalsodonotinvolveasignificant hazardsconsideration.
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| I(}} | |
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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
IR 05000244/19992011999-09-24024 September 1999
Forwards Insp Rept 50-244/99-201 (Operational Safeguards Response Evaluation) on 990621-24.No Violations Noted. Primary Purpose of Osre to Assess Licensee Ability to Respond to External Threat.Insp Rept Withheld
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
ML17265A7451999-08-23023 August 1999
Forwards fitness-for-duty Performance Data Rept for Six Months Ending 990630,per 10CFR26.71(d)
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
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
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
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
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
1999-09-30
[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
[Table view] |
Text
g'O'RIDRITY 1 ACCELERATED Rl DS P l<OCESSli G)I REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)~CCESSION NBR:9506080198 DOC.DATE:-95/05/26 NOTARIZED:
YES'FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G AUTH.NAME AUTHOR.AFFILIATION MECREDY,R.C.
Rochester Gas&Electric Corp.RECIP.NAME RECIPIENT AFFILIATION JOHNSON A.R.Pro'ect Directorate I-1 PD1-1 Post 941001 DOCKET 05000244 W~p I 3 ()()
SUBJECT:
Forwards application for amend to license DPR-18,revising TSs in entirety by converting to improved TSs.~: fo+>7oD TITLE: OR Submittal:
General Distribution NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
05000244 RECIPIENT ID CODE/NAME PD1-1 LA JOHNSON,A INTERNA IBE CENT 0 B NRR/DSSA/SRXB OGC/HDS3 EXTERNAL: NOAC COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 0 1 1 RECIPIENT ID CODE/NAME PD1-1 PD NRR/DE/EMCB NRR/DS SA/S PLB NUDOCS-ABSTRACT NRC PDR COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 D 0 C u N YOTE TO ALL"RIDS" RECIPIEYTS:
PLEASE HELP US TO REDUCE lVKSTE!COYTAC'f'I'I IE DOCL'IIEET CONTROL DESK, ROOKI Pl-37 (EXT.504-~083)TO ELI XIIX.ATE YOI.'R%ANIL FROW!DIS f Rl 8UTIOY LIS'I'S I'OR DOCI.5,1I.'X'I'S 0'Ol.'ON'"I'L'I'.
D!TOTAL NUMBER OF COPIES REQUIRED: LTTR 12 ENCL 11 AND ROCHESTER GAS AND EIECTRIC CORPORATION
~89 FASTAtrrENUE, ROCHESTER, N.Y Id&f9-0001 ARFA CODE716 56-2700 ROBERT C.MECREDY Vice President Nucteor Operations Hay 26, 1995 U.S.Nuclear Regulatory Commission Document Control Desk Attn: Allen R.Johnson Project Directorate I-1 Washington, D.C.20555
Subject:
Application for Amendment to Facility Operating License Conversion to Improved Technical Specifications Rochester Gas&Electric Corporation R.E.Ginna Nuclear Power Plant Docket No.50-244
Dear Hr.Johnson,
The enclosed License Amendment Request (LAR)proposes to revise the Ginna Station Technical Specifications in its entirety by converting to Improved Technical Specifications (ITS).This LAR also proposes to revise the Ginna Station Operating License.The proposed application is consistent with the original purpose of the Technical Specification Improvement Program as outlined in Reference (a).The technical specification changes withdrawn by Reference (b)are also addressed in this LAR.In addition, the changes requested by Reference (c)are included within this submittal (i.e., this LAR does not supersede Reference (c)but is consistent with the changes being requested).
The proposed ITS contained in this LAR are based on the current Ginna Station Technical Specifications (through Amendment No.59), NUREG-1431 (Ref.(d)), and other documents.
The proposed ITS Limiting Conditions for Operations (LCO)or Surveillance Requirements (SRs)which are less restrictive than the current Ginna Station Technical Specifications (TS)and which are not consistent with NUREG-1431 are listed below (LCOs and SRs are those listed in Attachment C to this letter): a~b.c~All refueling interval surveillances were changed from 18 months to 24 months consistent with the guidance of Generic Letter 91-04 (Ref.(e)).Allow both post-accident charcoal filters to be removed from service at the same time provided that both containment spray trains are OPERABLE (LCO 3.6.6 and current Ginna Station TS 3.3.2.2).Only require one component cooling water heat exchanger to be OPERABLE when the system is required to be OPERABLE (LCO 3.7.7 and current Ginna Station TS 3.3.3.1).('st50b080 i'st8'st5052b, PDR ADOCK 05000244 P','DR o pV' 0'I rI I W N S/~t~J t t 1, Allow both motor driven auxiliary feedwater (AFW)pumps to be removed from service for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> (LCO 3.7.5 and current Ginna Station TS 3.4.2.1.b).
Increase the allowed outage times for certain reactor trip system and engineered safety feature actuation system functions up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> (LCO 3.3.1, LCO 3.3.2, and current Ginna Station TS 3.5.1 and 3.5.2).Allow an additional 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> to restore an inoperable reactor trip breaker or Automatic Trip Logic train in HODES 3, 4, and 5 after exiting HODE 2 with this condition (LCO 3.3.1 and current Ginna Station TS 3.5.1).Allow the use of a closed system to isolate a containment penetration with a failed containment isolation valve (LCO 3.6.3 and current Ginna Station TS 3.6.3).Only require one offsite power source to be OPERABLE during HODE changes (LCO 3.8.1 and current Ginna Station TS 3.7.2.l.b.2, 3.7.2.2.a, and 3.7.2.2.b).
Allow 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to reduce the Power Range Neutron Flux trip Function setpoint when Fo or F~is not within limits (LCO 3.2.1, LCO 3.2.2, and current Ginna Station TS 3.10.2.2).Remove the requirement to test certain reactor coolant system pressure isolation valves when the plant has been in cold shutdown for>7 days (SR 3.4.14.1 and current Ginna Station TS 4.3.3.1).Remove the requirement to test the motor driven AFW pump cross-over motor operated isolation valves (LCO 3.7.5 and current Ginna Station TS 4.8.3).Remove the requirement to verify that the AFW pumps and valves can actuate within 10 minutes (LCO 3.7.5 and current Ginna Station TS 4.8.10).Increase the allowed tolerances for the pressurizer safety valves setpoint (LCO 3.4.10 and current Ginna Station TS 3.3.1.3.a).Increase the allowed fuel enrichment limit from 4.25 weight percent to 5.05 weight percent (Specification 4.3.l.I.a and current Ginna Station TS 5.3.1.b).Relocate the following parameters and setpoints to the Core Operating Limits Report: Overpower~T and Overtemperature
~T parameters (LCO 3.3.1 and current Ginna Station TS 2.3.1.2.d and 2.3.1.2.e).
Refueling water storage tank (RWST)boron concentration (LCO 3.5.4 and current Ginna Station TS 3.3.l.l.a and 3.3.1.2).Accumulator boron concentration (LCO 3.5.1 and current Ginna Station TS 3.3.1.l.b and 3.3.1.3). iv.SHUTDOWN MARGIN (LCO 3.1.1 and current Ginna Station TS 3.10.1.1 and Figure 3.10-2).p.Relocate the containment integrity requirements during refueling (i.e., NODE 6)from the technical specifications (current Ginna Station TS 3.5.2, 3.5.5, and 3.8.l.a).q.Relocate the Reactor Coolant Pump Underfrequency trip Function from technical specifications (current Ginna Station TS 2.3.1.2.g and 3.5.1).r.Relocate the AFW and Standby AFW system manual initiation functions from technical specifications (current Ginna Station TS 3.5.2).The above changes, while different from NUREG-1431 and the current Ginna Station TS, are consistent with the Final Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors (Ref.(f))and the accident analyses.The changes are discussed in detail i'n Attachment A.Revision 0 of NUREG-1431 was used for the preparation of this LAR since Revision 1 has only recently been issued.However, all approved Travellers which were used to generate Revision 1 are addressed in this submittal.
The only exception is Traveller BWR-26, C.1 related to LCO 3.0.4.This Traveller has not been generically evaluated for the Westinghouse plants as required by the Reviewer's Note added as part of this approved Traveller.
Therefore, RG&E has elected to defer implementation of this Traveller until after this evaluation has been performed.
We request that NRC approval of this LAR be provided by November 20, 1995.This approval date is required to support an implementation date in February 1996 since included within this LAR is a change in the allowed fuel enrichment limit.This enrichment limit is being changed to support conversion to 18 month refueling cycles with the new fuel scheduled to be shipped by Westinghouse beginning in February 1996.The technical evaluation of this change in enrichment was previously submitted to the NRC by Reference (g).With an implementation date in February 1996, all surveillances as proposed in Attachment C will be current with the following exceptions:
a~b.SR 3.6.6.13-This requires a verification every 5 years of the spray additive flow rate through each eductor path.The current Ginna Station TS do not contain this requirement.
However, recirculation flow from the RWST through the eductors is performed monthly.In addition, sample lines associated with the spray additive tank have not previously demonstrated blockage.A review'of industry events related to the spray additive tank also did not reveal any concerns with respect to blockage.SR 3.7.3.1-This requires a verification every 24 months that each main feedwater pump discharge valve (HFPDV)can close within 80 seconds following receipt of an actual or simulated signal.The current Ginna Station TS do not contain this requirement.
However, the HFPDVs were last tested on April 14, 1992 with one valve closing in 73.1 seconds and the second valve closing in 75.9 seconds.These values are within the 80 second limit and provide assurance of the HFPDVs OPERABILITY.
Based on the above information, RG&E requests that these SRs be deferred until the refueling outage scheduled to begin by April 1, 1996.RG&E would like to note that we have requested an exemption to 10 CFR 50, Appendix K, Sections I.D.3 and I.D.5 with respect to upper plenum injection issues (Ref.(h))which, when approved, would result in a change to the Ginna Station license.This change is not addressed, or otherwise included within this LAR.The final implementation date will be coordinated with the NRC following final approval of this LAR.Any questions related to this LAR should be directed to Hark Flaherty at (716)724-8512.Very truly yours, Robert C.Hecre y MDFX612 Attachments
References:
(a)Letter from R.C.Hecredy, RG&E, to A.R.Johnson, NRC,
Subject:
Conversion to Improved Technical Specifications, dated February 28, 1994.(b)Letter from R.C.Hecredy, RG&E, to A.R.Johnson, NRC,
Subject:
License Amendment Application Requests, dated April 26, 1995.(c)Letter from R.C.Mecredy, RG&E, to A.R.Johnson, NRC,
Subject:
Application for Amendment to Operating License Reactor Coolant Activity Technical Specifications, dated Hay 23, 1994.(d)NUREG-1431, Standard Technical Specifications, westinghouse Plants, Revision 0, September 1993.(e)Generic Letter 91-04, Changes in Technical Specification Surveillance Intervals to Accommodate a 24-Nonth Fuel Cycle, dated April 2, 1991.(f)NRC, Final Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 21, 1993.(g)Letter from R.C.Mecredy, RG&E, to A.R.Johnson, NRC,
Subject:
Technical Specification Improvement Program, dated Hay 5, 1995.(h)Letter from R.C.Mecredy, RG&E, to A.R.Johnson, NRC,
Subject:
Request for Exemption to Selected 10 CFR Part 50, Appendix K Requirements, dated November 5, 1992.
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 (2 copies)Mr.Carl Schulten Office of Technical Specifications Branch (Mail Stop 011E22)Washington, D.C.20555 U.S.Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Hr.Gerry L.Jones INEL Lockeed Idaho Hail Stop 3870 2525 Freemont Avenue Idaho Falls, ID 83415-3870 Hr.Clyde Morton PQP 301 Hartz Avenue Suite 206 Danville, CA 94526-3328 Ms.Donna Ross New York State Energy Office Ginna Senior Resident Inspector Hr.Jim Andrachek Westinghouse Electric Company Energy Center East 4-1 4350 Northern Pike Honroeville, PA 15146-2886 Hr.Donald Hoffman EXCEL Services Corporation 11921 Rockville Pike Suite 100 Rockville, HD 20852 Hr.Gene Eckholt (copy of Attachment C, F, and G only)Northern States Power Company Prairie Island Nuclear Generating Plant Route 2 Welch, HN 55089 Mr.Thomas Malanowski (copy of Attachments C, F, and G only)Wisconsin Electric Power 231 West Michigan Milwaukee, WI 53201 Nr.Rick Pulec (copy of Attachments C, F, and G only)Wisconsin Public Service P.O.Box 19002 700 North Adams Green Bay, WI 54307-9002 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Hatter of))Rochester Gas and Electric Corporation
)(R.E.Ginna Nuclear Power Plant)Docket No.50-244 APPLICATION FOR AMENDMENT TO OPERATING LICENSE Pursuant to Section 50.90 of the regulations of the U.S.Nuclear Regulatory Commission (NRC), Rochester Gas and Electric Corporation (RG&E), holder of Facility Operating License No.DPR-18, hereby requests that the license and the Technical Specifications set forth in Appendix A to that license be amended.This request for change is to convert the entire Technical Specifications to Improved Technical Specifications format.Several requirements are also relocated to other programs and documents in accordance with the criteria contained in the NRC Final Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors.A description of the amendment request, necessary background information, justification of the requested change, and no significant hazards and environmental considerations are provided in Attachment A.This evaluation demonstrates that the proposed changes do not involve a significant change in the types or a significant increase in the amounts of effluents or any change in the authorized power level of the facility.The proposed changes also do not involve a significant hazards consideration.
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