ML17263A792

Forwards 51-1224912-01, Safety Evaluation of Ginna SG Replacement.

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: ML17263A792 ML17263A794
References
NUDOCS 9410040089
Download: ML17263A792 (4)

Text

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9410040089 DOC.DATE: 94/09/27 NOTARIZED: NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Roch ster G 05000244 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). 05000244 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PDl-3 LA 1 1 PD1-3 PD 1 1 JOHNSON,A 1 1 INTERNAL: ER 01 1 1 NRR/DE/EELB 1 1 N /DRCH/HICB 1 1 NRR/DRPW 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OC/LFDCB 1 0 OGC/HDS3 1 0 EXTERNAL: NOAC 1 1 NRC PDR 1 1 NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE iVASTE! CONTACT THE DOCUMENT CONTROL DESK. ROOM P1.-37 (EXT. 504-2083 ) TO EL I ifI NATE YOUR . JA ifE F ROif DISTRIBUTION LISTS I:OR DOCI..'MENTS YOU DON"I'EED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 14 ENCL 12

ANn ROCHESTER GAS AND ELECTRIC CORPORATION + 89EASTAVFNUE, ROCHESTER, N.Y. 14649-000I AREA CODE7I6 546-2700 ROBERT C. MECREDY Vice Prerident September 27, 1994 Cinna Nuclear Produciion U.S. Nuclear Regulatory Commission Document Control Desk Attn: Allen R. Johnson Project Directorate I-3 Washington, D.C. 20555

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 Specification changes.

it require any Technical 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

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l Rochester Gas 8c Interoffice Correspondence t!!

Electric Corporation 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 of this 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 will be revised to include the results of these analyses.

Prepared by: Date:

Nuclear Engine, SGRP NS&L Review: Date:

NS&L Engineer Reviewed &

Approved Manager NS&L BJF:tad RGE 94-077