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| | number = ML17265A462 | | | number = ML17265A462 |
| | issue date = 11/24/1998 | | | issue date = 11/24/1998 |
| | title = 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 | | | title = 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 |
| | author name = MECREDY R C | | | author name = Mecredy R |
| | author affiliation = ROCHESTER GAS & ELECTRIC CORP. | | | author affiliation = ROCHESTER GAS & ELECTRIC CORP. |
| | addressee name = VISSING G S | | | addressee name = Vissing G |
| | addressee affiliation = NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) | | | addressee affiliation = NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| | docket = 05000244 | | | docket = 05000244 |
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| | document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE | | | document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE |
| | page count = 6 | | | page count = 6 |
| | | project = |
| | | stage = Request |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:/I REGULA'1 RY INFORMATION DISTRIBUTIOh 8YSTEM (RIDS)ACCESSION NBR:9812070079 DOC.DATE: 98/11/24 NOTARIZED: | | {{#Wiki_filter:/ |
| YES FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C. | | I REGULA'1 RY INFORMATION DISTRIBUTIOh 8YSTEM (RIDS) |
| Rochester Gas S Electric Corp.RECIP.NAME RECIPIENT AFFILIATION VISSING,G.S. | | ACCESSION NBR:9812070079 DOC.DATE: 98/11/24 NOTARIZED: YES DOCKET ¹ FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas S Electric Corp. |
| DOCKET¹05000244
| | RECIP.NAME RECIPIENT AFFILIATION VISSING,G.S. |
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| |
|
| ==SUBJECT:== | | ==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: | | Forwards application for amend to license DPR-18,revising Improved Tech Spec description of fuel cladding matl (4.2.1) |
| General Distribution NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72)
| | & updating list of references provided in TS 5.6.5 for COLR. |
| .05000244 INTERNAL: RECIPIENT ID CODE/NAME PD1-1 LA VISSING,G. | | DISTRIBUTION CODE: AOOID TITLE: OR COPIES RECEIVED:LTR Submittal: General Distribution L ENCL L SIZE: C2 NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72) . 05000244 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR' ENCL ID CODE/NAME LTTR ENCL PD1-1 LA 1 PD1-1 PD 1 1 VISSING,G. 1 1 INTERNAL: CENTE 1 1 NRR/DE/ECGB/A 1 1 MCB 1 1 NRR/DRCH/HICB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS3 1 0 EXTERNAL: NOAC 1 1 NRC PDR D |
| 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:
| | 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 | | 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 I |
| | J f |
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| | ROCHESTER GAS AND ELECTRIC CORPORATION.69EASTAVENIIE, ROCHESTER, N Y. 14649-0001 AREA CODE 7I6-546-2700 ROBERT C. MECREDY November 24, 1998 Vice President Nvcfeor Operotions U.S. Nuclear Regulatory Commission Document Control Desk Attn: Guy S. Vissing Project Directorate I-1 Washington, D.C. 20555 |
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| |
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| ==Subject:== | | ==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 | | 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, WSXa070079 eSZaa4 PDR P |
| | ADOCK 05000244 PDR |
| | 'obert |
| | '3'7 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 |
|
| |
|
| ==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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Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(ii)(B) & 10CFR21.Addl Analyses Are Being Performed to Support Future Cycle Operation & Supplemental LER Is Scheduled to Be Submitted by 990618
ML17265A5641999-03-0101 March 1999
Forwards Response to NRC 990217 RAI Concerning Changes to QA Program for Re Ginna Station Operation.Rg&E Is Modifying Changes Requested in 981221 Submittal.Modified QA Program,Encl
ML17265A5671999-03-0101 March 1999
Forwards Application for Amend to License DPR-18,to Revise TSs Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6).Supporting Tss,Encl
ML17265A5551999-02-25025 February 1999
Informs That Util Is in Process of Revising fitness-for-duty Program,Developed in Accordance with 10CFR26.Util Will Continue to Use Dept of Health & Human Svcs Certified Test Facility for Majority of Tests During Yr
ML17265A5561999-02-22022 February 1999
Forwards FFD Performance Data Rept for Six Months Ending 981231,per 10CFR26.71(d)
ML17265A5451999-02-12012 February 1999
Forwards Simulator Four Year Certification Rept,Per 10CFR55.45(b)(5)(ii)
ML17309A6491999-02-12012 February 1999
Forwards Ginna Station EOPs
ML17265A5431999-02-0909 February 1999
Supplements 980806 Relief Request with Attached Table.Util Third 10-Yr ISI of Reactor Vessel Being Performed During 1999 Refueling Outage,Beginning on 990301
ML17265A5361999-02-0202 February 1999
Forwards Response to NRC 981203 RAI Re Resolution of Unresolved Safety Issue USI A-46.Util Does Not Agree with NRCs Interpretation.Detailed Bases,Encl
ML17311A0691999-01-25025 January 1999
Forwards Revs to Ginna Station Emergency Plan Implementing Procedures (Epips).Previous Rev Had Incorrect Effective Date
ML17311A0671999-01-14014 January 1999
Forwards Revised Emergency Operating Procedures for Re Ginna NPP
ML17265A5131999-01-12012 January 1999
Forwards Revised Cover Page for Ginna Station Technical Requirements Manual (Trm), Rev 7,correcting Error in Effective Date
ML17265A5111999-01-11011 January 1999
Requests Relief Per 10CFR50.55a(a)(3)(ii) from Certain Requirements of Section XI of ASME Bp&V Code for ISI Program.Relief Requests 37,38 & 39 Encl
ML17265A5101999-01-11011 January 1999
Requests Relief Per to 10CFR50.55a(a)(3)(ii) from Certain Requirements of Section XI of ASME B&PV Code for ISI Program.Relief Request 40 Encl
1999-09-30
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I REGULA'1 RY INFORMATION DISTRIBUTIOh 8YSTEM (RIDS)
ACCESSION NBR:9812070079 DOC.DATE: 98/11/24 NOTARIZED: YES DOCKET ¹ FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas S Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION VISSING,G.S.
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 TITLE: OR COPIES RECEIVED:LTR Submittal: General Distribution L ENCL L SIZE: C2 NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72) . 05000244 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR' ENCL ID CODE/NAME LTTR ENCL PD1-1 LA 1 PD1-1 PD 1 1 VISSING,G. 1 1 INTERNAL: CENTE 1 1 NRR/DE/ECGB/A 1 1 MCB 1 1 NRR/DRCH/HICB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS3 1 0 EXTERNAL: NOAC 1 1 NRC PDR 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 I
J f
ROCHESTER GAS AND ELECTRIC CORPORATION.69EASTAVENIIE, ROCHESTER, N Y. 14649-0001 AREA CODE 7I6-546-2700 ROBERT C. MECREDY November 24, 1998 Vice President Nvcfeor Operotions 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, WSXa070079 eSZaa4 PDR P
ADOCK 05000244 PDR
'obert
'3'7 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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