ML17263A792
| ML17263A792 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 09/27/1994 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Andrea Johnson NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17263A793 | List: |
| References | |
| NUDOCS 9410040089 | |
| Download: ML17263A792 (4) | |
Text
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9410040089 DOC.DATE: 94/09/27 NOTARIZED: NO FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Roch ster G
AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.
Rochester Gas 6 Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R.
Project Directorate I-3
SUBJECT:
Forwards 51-1224912-01, "Safety Evaluation of Ginna SG Replacement."
DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR Submittal:
General Distribution NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
DOCKET 05000244 05000244 INTERNAL:
RECIPIENT ID CODE/NAME PDl-3 LA JOHNSON,A ER 01 N
/DRCH/HICB NRR/DSSA/SPLB NUDOCS-ABSTRACT OGC/HDS3 COPIES LTTR ENCL 1
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0 RECIPIENT ID CODE/NAME PD1-3 PD NRR/DE/EELB NRR/DRPW NRR/DSSA/SRXB OC/LFDCB COPIES LTTR ENCL 1
1 1
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0 EXTERNAL: NOAC 1
1 NRC PDR 1
1 NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE iVASTE!CONTACTTHE DOCUMENTCONTROL DESK. ROOM P1.-37 (EXT. 504-2083 ) TO EL IifINATE YOUR. JAifE FROif DISTRIBUTIONLISTS I:OR DOCI..'MENTS YOU DON"I'EED!
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 14 ENCL 12
ANn ROBERT C. MECREDY Vice Prerident Cinna Nuclear Produciion U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Allen R. Johnson Project Directorate I-3 Washington, D.C.
20555 September 27, 1994 ROCHESTER GAS ANDELECTRIC CORPORATION + 89EASTAVFNUE, ROCHESTER, N.Y. 14649-000I AREA CODE7I6 546-2700
Subject:
Preliminary Safety Evaluation of Replacement Steam Generators R.E.
Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Johnson:
Rochester Gas and Electric has completed a preliminary safety evaluation of the BWI Replacement Steam Generators (RSGs).
RG&E intends to install the RSGs in the Ginna Plant in the spring of 1996.
The results of the safety evaluation show that operation of Ginna with the replacement steam generators does not involve any unreviewed safety questions, nor will it require any Technical Specification changes.
Consequently, the preliminary safety evaluation indicates that the replacement may be performed under the provisions of 10CFR50.59 without prior NRC approval.
RG&E is providing a copy of this safety evaluation in order to keep the NRC informed of the ongoing status of this project.
RG&E is not requesting NRC review and approval of this document.
The final safety evaluation will be forwarded for your information when completed.
Very truly yours, Robert C.
Me edy BJFE347 Attachment xc:
Mr. Allen R. Johnson (Mail Stop 14D1)
Project, Directorate I-3 Washington, D.C.
20555 fl U.S. Nuclear. Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector 941004008'P 940927 PDR ADOCK 05000244 P
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Rochester Gas 8c Electric Corporation Interoffice Correspondence September 22, 1994 TQ:
File EWR 10034
Subject:
Approval of Vendor Technical Documents BWNT Document ¹51-1224912-01, "Evaluation of Ginna SG Replacement" In accordance with Engineering Procedure QE-704 Rev. 3, effective 5/11/92, the purpose ofthis memorandum is to identify that the subject document has been reviewed and accepted for use by Rochester Gas and Electric Corporation.
The results of the evaluation are applicable to R.E. Ginna. The evaluation is preliminary, and requires that the conclusions of several sections be verified by detailed analysis.
These sections are adequately identified in the body of the evaluation, and are summarized in Section 6, pp 64-
- 65. The evaluation willbe revised to include the results of these analyses.
Prepared by:
Nuclear Engine, SGRP Date:
NS&L Review:
NS&L Engineer Date:
Reviewed &
Approved Manager NS&L BJF:tad RGE 94-077