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| {{#Wiki_filter:/IREGULA'1RYINFORMATION DISTRIBUTIOh 8YSTEM(RIDS)ACCESSION NBR:9812070079 DOC.DATE: | | {{#Wiki_filter:/I REGULA'1 RY INFORMATION DISTRIBUTIOh 8YSTEM (RIDS)ACCESSION NBR:9812070079 DOC.DATE: 98/11/24 NOTARIZED: |
| 98/11/24NOTARIZED: | | YES FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C. |
| YESFACIL:50-244 RobertEmmetGinnaNuclearPlant,Unit1,Rochester GAUTH.NAMEAUTHORAFFILIATION MECREDY,R.C.
| | Rochester Gas S Electric Corp.RECIP.NAME RECIPIENT AFFILIATION VISSING,G.S. |
| Rochester GasSElectricCorp.RECIP.NAME RECIPIENT AFFILIATION VISSING,G.S. | | DOCKET¹05000244 |
| DOCKET¹05000244 | |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Forwardsapplication foramendtolicenseDPR-18,revising ImprovedTechSpecdescription offuelcladdingmatl(4.2.1)&updatinglistofreferences providedinTS5.6.5forCOLR.DISTRIBUTION CODE:AOOIDCOPIESRECEIVED:LTR LENCLLSIZE:C2TITLE:ORSubmittal:
| | Forwards application for amend to license DPR-18,revising Improved Tech Spec description of fuel cladding matl (4.2.1)&updating list of references provided in TS 5.6.5 for COLR.DISTRIBUTION CODE: AOOID COPIES RECEIVED:LTR L ENCL L SIZE: C2 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) |
| .05000244INTERNAL: | | .05000244 INTERNAL: RECIPIENT ID CODE/NAME PD1-1 LA VISSING,G. |
| RECIPIENT IDCODE/NAME PD1-1LAVISSING,G. | | CENTE MCB NRR/DSSA/SPLB NUDOCS-ABSTRACT COPIES LTTR ENCL 1'1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME PD1-1 PD NRR/DE/ECGB/A NRR/DRCH/HICB NRR/DSSA/SRXB OGC/HDS3 COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 0 EXTERNAL: NOAC 1 1 NRC PDR D N NOTE TO ALL NRIDS" RECIPIENTS: |
| CENTEMCBNRR/DSSA/SPLB NUDOCS-ABSTRACT COPIESLTTRENCL1'1111111111RECIPIENT IDCODE/NAME PD1-1PDNRR/DE/ECGB/A NRR/DRCH/HICB NRR/DSSA/SRXB OGC/HDS3COPIESLTTRENCL1111111110EXTERNAL:
| | PLEASE HELP US TO REDUCE WASTE.TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DZSTRZBUTZON LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)ON EXTENSION 415-2083 I TOTAL NUMBER OF COPIES REQUIRED: LTTR 13 ENCL 12 T f I J ROCHESTER GAS AND ELECTRIC CORPORATION.69EASTAVENIIE, ROCHESTER, N Y.14649-0001 AREA CODE 7I6-546-2700 ROBERT C.MECREDY Vice President Nvcfeor Operotions November 24, 1998 U.S.Nuclear Regulatory Commission Document Control Desk Attn: Guy S.Vissing Project Directorate I-1 Washington, D.C.20555 |
| NOAC11NRCPDRDNNOTETOALLNRIDS"RECIPIENTS:
| |
| PLEASEHELPUSTOREDUCEWASTE.TOHAVEYOURNAMEORORGANIZATION REMOVEDFROMDZSTRZBUTZON LISTSORREDUCETHENUMBEROFCOPIESRECEIVEDBYYOUORYOURORGANIZATION, CONTACTTHEDOCUMENTCONTROLDESK(DCD)ONEXTENSION 415-2083ITOTALNUMBEROFCOPIESREQUIRED:
| |
| LTTR13ENCL12 TfIJ ROCHESTER GASANDELECTRICCORPORATION.69EASTAVENIIE, ROCHESTER, NY.14649-0001 AREACODE7I6-546-2700 ROBERTC.MECREDYVicePresident NvcfeorOperotions November24,1998U.S.NuclearRegulatory Commission DocumentControlDeskAttn:GuyS.VissingProjectDirectorate I-1Washington, D.C.20555
| |
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| ==Subject:== | | ==Subject:== |
| Application forAmendment toFacilityOperating LicenseFuelAssemblyMaterialChangeRochester GasandElectricCorporation R.E.GinnaNuclearPowerPlantDocketNo.50-244 | | Application for Amendment to Facility Operating License Fuel Assembly Material Change Rochester Gas and Electric Corporation R.E.Ginna Nuclear Power Plant Docket No.50-244 |
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| ==DearMr.Vissing:== | | ==Dear Mr.Vissing:== |
| TheenclosedLicenseAmendment Request(LAR)proposestorevisetheGinnaStationImprovedTechnical Specifications description ofthefuelcladdingmaterial(TS4.2.1)andtoupdatethelistofreferences providedinSpecification 5.6.5fortheCoreOperating LimitsReport.TheLARisbeingproposedsinceRochester GasandElectric(RG&E)planstobegininserting Westinghouse fuelassemblies containing fuelrodsfabricated withthezirconium alloymaterialZIRLOintotheR.E.GinnaNuclearPowerPlantCycle28coreandbeyond.Thesefuelassemblies willbefabricated withZIRLOalloytoobtainadditional operational benefitfromthealloy'simprovedcorrosion resistance anddimensional stability underirradiation.
| | The enclosed License Amendment Request (LAR)proposes to revise the Ginna Station Improved Technical Specifications description of the fuel cladding material (TS 4.2.1)and to update the list of references provided in Specification 5.6.5 for the Core Operating Limits Report.The LAR is being proposed since Rochester Gas and Electric (RG&E)plans to begin inserting Westinghouse fuel assemblies containing fuel rods fabricated with the zirconium alloy material ZIRLO into the R.E.Ginna Nuclear Power Plant Cycle 28 core and beyond.These fuel assemblies will be fabricated with ZIRLO alloy to obtain additional operational benefit from the alloy's improved corrosion resistance and dimensional stability under irradiation. |
| Evaluations andanalyseshavebeenperformed toshowthatthecurrentdesignbasisandlimitsremainvalidasdescribed withintheattachedLAR.Sincethematerialdescription changeisrequiredforloadingthenewfuelintothereactorvesselduringthe1999Refueling Outage,RG&Edesirestomakethechangeassoonaspracticable. | | Evaluations and analyses have been performed to show that the current design basis and limits remain valid as described within the attached LAR.Since the material description change is required for loading the new fuel into the reactor vessel during the 1999 Refueling Outage, RG&E desires to make the change as soon as practicable. |
| Therefore, werequestNRCconsideration ofthisLARinordertosupportaplannedfuelloadingstartdateofMarch24,1999.RG&Ealsorequestsa14dayimplementation periodfollowing NRCapproval(i.e.,RG&EmustreceiveNRCacceptance ofthisLARbyMarch10,1999topreventimpacting theoutagecriticalpath).Veulyyours,'3'7WSXa070079 eSZaa4PDRADOCK05000244PPDR'obertC.Mecr | | Therefore, we request NRC consideration of this LAR in order to support a planned fuel loading start date of March 24, 1999.RG&E also requests a 14 day implementation period following NRC approval (i.e., RG&E must receive NRC acceptance of this LAR by March 10, 1999 to prevent impacting the outage critical path).Ve uly yours,'3'7 WSXa070079 eSZaa4 PDR ADOCK 05000244 P PDR'obert C.Mecr |
| 'ih Attachments xc:Mr.GuyS.Vissing(MailStop14B2)ProjectDirectorate I-1DivisionofReactorProjects-I/IIOfficeofNuclearReactorRegulation U.S.NuclearRegulatory Commission Washington, D.C.20555RegionalAdministrator, Region1U.S.NuclearRegulatory Commission 475Allendale RoadKingofPrussia,PA19406U,S.NRCGinnaSeniorResidentInspector Mr.F.WilliamValentino, President NewYorkStateEnergy,Research, andDevelopment Authority Corporate PlazaWest286Washington AvenueExtension Albany,NY12203-6399 | | 'i h Attachments xc: Mr.Guy S.Vissing (Mail Stop 14B2)Project Directorate I-1 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation U.S.Nuclear Regulatory Commission Washington, D.C.20555 Regional Administrator, Region 1 U.S.Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 U,S.NRC Ginna Senior Resident Inspector Mr.F.William Valentino, President New York State Energy, Research, and Development Authority Corporate Plaza West 286 Washington Avenue Extension Albany, NY 12203-6399 |
| ~'}} | | ~'}} |
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Forwards Revised Emergency Operating Procedures for Re Ginna NPP
ML17265A5131999-01-12012 January 1999
Forwards Revised Cover Page for Ginna Station Technical Requirements Manual (Trm), Rev 7,correcting Error in Effective Date
ML17265A5111999-01-11011 January 1999
Requests Relief Per 10CFR50.55a(a)(3)(ii) from Certain Requirements of Section XI of ASME Bp&V Code for ISI Program.Relief Requests 37,38 & 39 Encl
ML17265A5101999-01-11011 January 1999
Requests Relief Per to 10CFR50.55a(a)(3)(ii) from Certain Requirements of Section XI of ASME B&PV Code for ISI Program.Relief Request 40 Encl
1999-09-30
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/I REGULA'1 RY INFORMATION DISTRIBUTIOh 8YSTEM (RIDS)ACCESSION NBR:9812070079 DOC.DATE: 98/11/24 NOTARIZED:
YES FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.
Rochester Gas S Electric Corp.RECIP.NAME RECIPIENT AFFILIATION VISSING,G.S.
DOCKET¹05000244
SUBJECT:
Forwards application for amend to license DPR-18,revising Improved Tech Spec description of fuel cladding matl (4.2.1)&updating list of references provided in TS 5.6.5 for COLR.DISTRIBUTION CODE: AOOID COPIES RECEIVED:LTR L ENCL L SIZE: C2 TITLE: OR Submittal:
General Distribution NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72)
.05000244 INTERNAL: RECIPIENT ID CODE/NAME PD1-1 LA VISSING,G.
CENTE MCB NRR/DSSA/SPLB NUDOCS-ABSTRACT COPIES LTTR ENCL 1'1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME PD1-1 PD NRR/DE/ECGB/A NRR/DRCH/HICB NRR/DSSA/SRXB OGC/HDS3 COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 0 EXTERNAL: NOAC 1 1 NRC PDR D N NOTE TO ALL NRIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE.TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DZSTRZBUTZON LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)ON EXTENSION 415-2083 I TOTAL NUMBER OF COPIES REQUIRED: LTTR 13 ENCL 12 T f I J ROCHESTER GAS AND ELECTRIC CORPORATION.69EASTAVENIIE, ROCHESTER, N Y.14649-0001 AREA CODE 7I6-546-2700 ROBERT C.MECREDY Vice President Nvcfeor Operotions November 24, 1998 U.S.Nuclear Regulatory Commission Document Control Desk Attn: Guy S.Vissing Project Directorate I-1 Washington, D.C.20555
Subject:
Application for Amendment to Facility Operating License Fuel Assembly Material Change Rochester Gas and Electric Corporation R.E.Ginna Nuclear Power Plant Docket No.50-244
Dear Mr.Vissing:
The enclosed License Amendment Request (LAR)proposes to revise the Ginna Station Improved Technical Specifications description of the fuel cladding material (TS 4.2.1)and to update the list of references provided in Specification 5.6.5 for the Core Operating Limits Report.The LAR is being proposed since Rochester Gas and Electric (RG&E)plans to begin inserting Westinghouse fuel assemblies containing fuel rods fabricated with the zirconium alloy material ZIRLO into the R.E.Ginna Nuclear Power Plant Cycle 28 core and beyond.These fuel assemblies will be fabricated with ZIRLO alloy to obtain additional operational benefit from the alloy's improved corrosion resistance and dimensional stability under irradiation.
Evaluations and analyses have been performed to show that the current design basis and limits remain valid as described within the attached LAR.Since the material description change is required for loading the new fuel into the reactor vessel during the 1999 Refueling Outage, RG&E desires to make the change as soon as practicable.
Therefore, we request NRC consideration of this LAR in order to support a planned fuel loading start date of March 24, 1999.RG&E also requests a 14 day implementation period following NRC approval (i.e., RG&E must receive NRC acceptance of this LAR by March 10, 1999 to prevent impacting the outage critical path).Ve uly yours,'3'7 WSXa070079 eSZaa4 PDR ADOCK 05000244 P PDR'obert C.Mecr
'i h Attachments xc: Mr.Guy S.Vissing (Mail Stop 14B2)Project Directorate I-1 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation U.S.Nuclear Regulatory Commission Washington, D.C.20555 Regional Administrator, Region 1 U.S.Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 U,S.NRC Ginna Senior Resident Inspector Mr.F.William Valentino, President New York State Energy, Research, and Development Authority Corporate Plaza West 286 Washington Avenue Extension Albany, NY 12203-6399
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