RC-93-0069, Application for Amend to License NPF-12 Consisting of TS Change TSP 930019,replacing SGs Utilized Engineered Safeguards Design Rating of Core power.Non-proprietary Rev 1 to WCAP-13481 & Proprietary Rev 1 to WCAP-13480 Repts Encl

Application for Amend to License NPF-12 Consisting of TS Change TSP 930019,replacing SGs Utilized Engineered Safeguards Design Rating of Core power.Non-proprietary Rev 1 to WCAP-13481 & Proprietary Rev 1 to WCAP-13480 Repts Encl

ML20064H437
Person / Time
Site:	Summer
Issue date:	03/11/1994
From:	Skolds J SOUTH CAROLINA ELECTRIC & GAS CO.
To:	George Wunder NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML19304B842	List: ML20064H450 ML20064H455 ML20064H464 ML20064H470 RC-93-0069, Application for Amend to License NPF-12 Consisting of TS Change TSP 930019,replacing SGs Utilized Engineered Safeguards Design Rating of Core power.Non-proprietary Rev 1 to WCAP-13481 & Proprietary Rev 1 to WCAP-13480 Repts Encl
References
RC-93-0069, RC-93-69, NUDOCS 9403170301
Download: ML20064H437 (4)

Text

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South Cuo inz Elsetric & G:2 Cornpiny J hn ko a enk nsv SC 29065 Nuclear Operatie is SCE&G

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March 11,1994 Refer to: RC-94-0069 Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555 Attention: Mr. G. F. Wunder Gentlemen:

Subject:

VIRGIL C. SUMMER NUCLEAR STATION DOCKET N0. 50/395 OPERATING LICENSE NO. NPF-12 STEAM GENERATOR REPLACEMENT TECHNICAL SPECIFICATION CHANGE REQUEST (REM 6000-10 TSP 930019)

On January 9, 1992, South Carolina Electric & Gas Company (SCE&G) met with NRC representatives to discuss the Virgil C. Summer Nuclear Station (VCSNS)

Steam Generator Replacement (SGR) Project. In this meeting, it was agreed that early submittal of discrete packages of analyses would aid NRC review and approval of the analyses and associated Technical Specification changes [

to support SCE&G's September 1994 SGR outage. Where possible, analyses and evaluations performed to support the Replacement Steam Generators (RSGs) utilized the Engineered Safeguards Ussign Rating (" stretch" power rating) of 2900 MWt core power. This conservatively wnds the current licensed core power of 2775 MWt and minimizes future reana;ys cffort for a potential stretch power application. However, it should be eghasized that approval is not being sought at this time for stretch power operation.

To date, four submittals (dated September 3, 1992, March 12, 1993, April 30, 1993, and October 29,1993) have been provided to support SGR. This submittal provides the final safety analysis results for Small Break Loss of Coolant Accidents and a related Technical Specification change. In order to provide one complete document for the licensing submittal, this final submittal is provided as revised replacement pages to the October 29, 1993 letter.

The topics addressed in this subaittal include revised pages for:

The Table of Contents The List of Tables (page v only)

The Executive Summary Section 1.0 - Introduction - Description of License Amendment I

Request Section 3.1 - Loss of Coolant Accident Analyses Section 3.11 - Summary of Technical Specification Changes 6 [,[dk 170- D b DbOk 05000$95 8/f 2 'g"ijg

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- Section 4.0 - Conclusions

- Appendix 1 - Assessment of Unreviewed Safety Questions (10CFR50.59)

Appendix 2 - No Significant Hazards Determination (10CFR50.92)

- Appendix 3 - Proposed Technical Specification Changes

- Appendix 4 - WCAP-13480, " Westinghouse Delta 75 Steam Generator Design and Fabrication Information for Virgil C. Summer Nuclear Station"

- Appendix 6 - VCSNS FSAR Chapter 15 Write-Ups

- Appendix 7 - VCSNS SI Pump Test Report Also attached is a copy of the revised Technical Specification page (page 3/4 5-6) for NRC issuance.

The Executive Summary provides the results of the analyses and evaluations contained in the Licensing submittal. In all cases, acceptable results have been obtained for the revised operating conditions associated with the RSGs.

SCE&G plans to start the SGR outage in early September 1994. Therefore, NRC review and approval of the enclosed Technical Specification change is requested by August 31, 1994. An implementation period of three months is requested to allow for plant documentation revisions to support the approved Technical Specification change.

Please note that WCAP-13480 has been revised to reflect the latest design information for the Delta 75 steam generator.

Enclosed are:

1. WCAP-13480, Revision 1, " Westinghouse Delta 75 Steam Generator Design and Fabrication Information for Virgil C. Summer Nuclear Station" (Proprietary).

2. WCAP-13481, Revision 1, " Westinghouse Delta 75 Steam Generator Design and Fabrication Information by Virgil C. Summer Nuclear Station" (Non-Proprietary).

Also enclosed are a Westinghouse authorization letter, CAW-93-545, accompanying affidavit, Proprietary Information Notice, and Copyright Notice.

As Item 1 contains information proprietary to Westinghouse Electric Corporation, it is supported by an affidavit signed by Westinghouse, the owner of the information. The affidavit sets forth the basis on which the information may be withheld from public disclosure by the Commission and addresses with specificity the considerations listed in paragraph (b)(4) of Section 2.790 of the Commission's regulations.

Document Control Desk TSP 930019 Page 3 of 3 Accordingly, it is respectfully requested that the information which is proprietary to Westinghouse be withheld from public disclosure in accordance with 10 CFR Section 2.790 of the Commission's regulations.

Correspondence with respect to the copyright or proprietary aspects of'the items listed above or the supporting Westinghouse Affidavit should reference CAW-93-545 and should be addressed to Nicholas J. Liparulo, Manager of Nuclear Safety and Regulatory Activities, Westinghouse Electric Corporation, P. O. Box 355, Pittsburgh, Pennsylvania 15230-0355.

This Technical Specification has been reviewed and approved by the PSRC and the NSRC. 1 declare that the statements and matters set forth herein are true and correct to the best of my knowledge, information, and belief.

SCE&G appreciates NRC's efforts to support the SGR schedule. If you have any questions, please contact April Rice at (803) 345-4232.

Very truly yours, hh John L. Skolds ARR/JLS/nkk Attachments c: 0. W. Dixon L. R. Cartin R. R. Mahan (w/o attachments) R. B. Clary R. J. White NSRC S. D. Ebneter Central File System NRC Resident Inspector RTS (TSP 930019, REM 6000-10)

J. B. Knotts Jr. File (810.39,813.20)

A. A. Craft NUCLEAR EXCELLENCE - A SUfMER TRADITION!

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CAW-93-545 AFFIDAVIT COMMONWEALTH OF PENNSYLVANIA:

ss COUNTY OF ALLEGHENY:

Before me, the undersigned authority, personally appeared Henry A. Sepp, who, being by me duly sworn according to law, deposes and says that he is authorized to execute this Affidavit on behalf of Westinghouse Electric Corporation (" Westinghouse") and that the averments of fact set forth in this Affidavit are true and correct to the best of his knowledge, information, and belief:

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( IM Henry A. Sepp, M(anager Strategic Licensing Issues Sworn to and subscribed

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