ML17264A250
| ML17264A250 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 11/27/1995 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Russell W NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML17264A251 | List: |
| References | |
| NUDOCS 9511290177 | |
| Download: ML17264A250 (6) | |
Text
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,ACCELERATED RIDS PROCESSING REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9511290177 DOC-DATE: 95/11/27 NOTARIZED: YES DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
05000244 AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.
Rochester Gas 6 Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION RUSSELL,W.T.
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05000244 R
SUBJECT:
Forwards application for amend to license DPR-18,revising TS to implement 10CFR50,App J,Option B.
DISTRIBUTION CODE:
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General Distribution NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
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NOTE TO ALL"RIDS" RECIPIENTS:
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AND ROCHESTER GASANDEIECTRIC CORN)RATION ~ 89 EASTAVGVUE, ROCHESTER, N.Y. Id&f9-0001 AREA CODE716 54'6-2700 ROBERT C. MECREDY Vice President Hucteor operations November 27, 1995 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
WilliamT. Russell Director, Office ofNuclear Reactor Regulation Washington, D.C. 20555
Subject:
Application for Amendment to Facility Operating License Implementation of 10 CFR 50, Appendix J, Option B Rochester Gas &Electric Corporation R.E. Ginna Nuclear Power Plant Docket No. 50-244
References:
(a)
Federal Register, Volume 60, Number 186, pages 49495 - 49505.
(b)
Letter from R.C. Mecredy, RG&E, to A.R. Johnson, NRC,
Subject:
Applicationfor Amendment to Facility Operating License, Conversion to Improved Technical Specifications, dated May 26, 1995.
Dear Mr. Russell,
The enclosed License Amendment Request (LAR)proposes to revise the Ginna Station Technical Specifications and license to implement 10 CFR 50, Appendix J, Option B. The Federal Register notice of the final Option B rule contains five requirements with respect to implementation (Ref.
(a)). These five requirements are discussed below:
Specific exemptions to Option A ofthis apperrdix that have been formallyapproved by the AIrC or NRC according to 10 CFR 50.12, are stillapplicable to Option B ofthis appendix ifnecessary, unless specifically revoked by the NRC.
The current Ginna Station license has four exemptions with respect to 10 CFR 50, Appendix J, Option A, which are proposed to be removed as part ofthis LAR.
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A licensee or applicant for an operating license may adopt Option B, orparts thereof, as specifiedin Section VAofthis Appendix, by submittingitsimplementation plan and request for revision to technical specifications (see paragraph B.3 below) to the Director ofthe Office oflAiclearRegulation.
This letter serves as the request to change the Ginna Station Technical Specifications to implement Option B. RGB'lans to implement Option B as part ofthe implementation of the improved standard technical specifications (ISTS) which are currently undergoing NRC staff review (Ref. (b)). This implementation is anticipated to occur in February 1996.
The regulatory guide or other implementation document used by a licensee, or applicant for an operating license, to develop a performance-based leakage-testing program must be included, by general reference, in the plant specifications.
The submittal for technical specification revisions must containjustification, including supporting analyses, ifthe licensee chooses to deviate from methods approved by the Conmussion and endorsedin a regulatory guide.
This LARproposes to add a specific reference to Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program" in the Administrative Controls section ofthe Ginna Station Technical Specifications. No exceptions to the regulatory guide, nor the documents which are endorsed by the regulatory guide, are being requested.
Therefore, RG&E does not propose to "deviate from methods approved by the Commission and endorsed in a regulatory guide."
The detailed licensee programs for conducting testing under Option B must be available at the plant siteforNRC inspection.
The detailed performance-based leakage-test program willbe available for NRC inspection upon implementation ofthe ISTS for Ginna Station as discussed in the response to item ¹2 above.
Since the implementation of Option B is being requested to occur at the same time as implementation ofthe ISTS for Ginna Station, the review ofthis submittal should be coordinated with the overall NRC review ofthe May 26, 1995 submittal.
Very truly yours, Robert C. Mecredy
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) MDF<782 Attachments 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 Mr. Carl Schulten Technical Specifications Branch (Mail Stop 011E22)
Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King ofPrussia, PA 19406 Ginna Senior Resident Inspector Mr. Donald Hoffman EXCEL Services Corporation 11921 Rockville Pike Suite 100 Rockville, MD 20852