ML20154J511

Application for Amend to License NPF-12,revising Tech Specs Supporting Refueling & Operation of Plant W/Vantage 5 Improved Fuel Design.Proprietary WCAP-11656,nonproprietary WCAP-11657 & Westinghouse Safety Evaluation Encl

ML20154J511
Person / Time
Site:	Summer
Issue date:	05/20/1988
From:	Nauman D SOUTH CAROLINA ELECTRIC & GAS CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML19292H836	List: ML20154J511 ML20154J517 ML20154J520 ML20154J525
References
NUDOCS 8805270023
Download: ML20154J511 (3)

Text

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C r fins Electric & Gas Oomp:my D A. P n Jenkinsville. SC 29065 Nuclear CSM inns SCE&G ""

A BCNNtl 'Asigy May 20, 1988 Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

Virgil C. Summer Nuclear Station Docket No. 50/395 Operating License No. NPF-12 Technical Specification Change Vantage 5 Reload Gentlemen:

South Carolina Electric & Gas Company (SCE&G) hereby requests a revision to the Technical Specifications for the Virgil C. Summer Nuclear Station. This proposed change revises numerous Technical Specifications in support of refueling and operating the Virgil C. Summer plant with Vantage 5 (V-5) improved fuel design. Currently, the V. C. Summer plant is operating in Cycle 4 with a Westinghouse 17 x 17 low parasitic fueled core.

Attachments 1 through 7 to this letter constitute a partial licensing submittal for the transition to the Westinghouse Vantage 5 fuel. Attachment 1 provides the safety evaluation for Vantage 5 fuel which includes the mechanical, nuclear, thermal and hydraulic, and accident evaluations. In addition, Section 7.0 of this attachment provides a summary of the Technical Specifications Sections being changed. Attachment 2 provides the marked-up pages to those Technical Specifications being revised. Attachments 3 and 4 forward the Non-Loss-of-Coolant (LOCA) and LOCA accident analyses,

' respectively. Attachment 5 provides the thimble plug removal evaluation.

The significant hazards evaluation pursuant to 10CFR50.92 is included as Attachment 6. Lastly, the radiological impact assessment is forwarded as Attachment 7.

As previously stated, these attachments are a partial submittal for the V-5 Technical Specifications changes. One of the assumptions used in the supporting analyses was a Tave reduction to 585.5'F from 587.4'F. This reduction would have resulted in a 3 megawatt electrical output penalty to the plant. SCE&G will recover the megawatt reduction by restoring Tave to 587.4'F; however, these analyses have not been completed. SCE&G will forward an addendum to Attachment 1 and the affected Technical Specification marked-up pages from Attachment 2. In addition, there may be changes to the non-LOCA accident analysis in Attachment 3, but has not been confirmed as of this time.

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Document Control Desk May 20, 1988 Page 2 The Technical Specifications which will be provided by June 17, 1988 are:

Pace Section Description of Chance 2-2 Figure 2.1-1 Core Limits 2-5 Table 2.2-1 OPAT and 0 TAT Trip Setpoints 3/4 2-10 Figure 3.2-3 Total Reactor Coolant System Flow Rate Requirements 3/4 2-16 Table 3.2-1 Tave

-Also provided are Westinghouse WCAP-11656 (Proprietary Class 2) and WCAP-116E7 (Non-Proprietary), "Westinghouse Improved Thermal Design Procedurc Instrument Uncertainty Methodology" and Westinghouse Letter "Application for Withivilding Frc7rietary Information from Public Disclosure" (CAW-87-125) with Affidavit AW-i6-060.

As WCAP-11656 cnntains information proprietary to Westinghouse Electric Corooration, 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 consijerations listed in paragraph (b)(4) of Section 2.790 of the Commission's regulations.

Accordingly, it is respectfully requested that the information which is proprietary to Westinghouse be withheld from public disclosure in accordance with 10CFR2.790 of thc Commission's regulations. Corre;pondence with respect to the proprietary aspects of the Application f6r Withholding or the supporting Westinghouse affidavit should reference CAW-87-125 and should be addressed to R. W. Wiesemann, Manager Regulatory and Legislative Affairs, Westinghouse Electric Corporation, P. O. Box 355, Pittsburgh, Pennsylvania 15230.

The enclosed prooosed Technical Specification amendment has been reviewed and approved by both the Plant Safety Review Committee and the Nuclear Safety Review Co.nmittee. The application fee of $150 is enclosed.

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Document Control Desk May 20, 1988 Page 3 Should you have any questions concerning this Technical Specifications amendment request, please call at your convenience.

Very truly yours, 1 *J

0. A. Nauman MDB/ DAN: led Attachments pc: (w/o Attachments)

J. G. Connelly, Jr./0. W. Dixon, Jr./T. C. Nichols, Jr.

E. C. Roberts W. A. Williams, Jr.

• J. N. Grace J. J. Hayes, Jr.

General Managers

• C. A. Price

• R. B. Clary

• R. M. Campbell, Jr.

• K. E. Hodland G. O. Percival R. L. Prevatte (w/ Attachments)

J. B. Knotts, Jr.

H. G. Shealy w/ Attachments M. D. Blue w/ Attachments L. R. Cartin w/ Attachments NSRC RTS (TSP 880013)

NPCF File (813.20) (w/Attc:hments)

• Copy being routed

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