ML20082U923

Forwards Reload Safety Evaluation for Cycle 3 Operation

ML20082U923
Person / Time
Site:	Sequoyah
Issue date:	12/12/1983
From:	Mills L TENNESSEE VALLEY AUTHORITY
To:	Adensam E Office of Nuclear Reactor Regulation
Shared Package
ML20082U924	List: ML20082U923 ML20082U930
References
NUDOCS 8312190224
Download: ML20082U923 (2)

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TENNESSEE VALLEY AUTHORITY CH ATTANOOGA. TENNESSEE 374o1 400 Chestnut Street Tower II December 12, 1983 Director of Nuclear Reactor Regulation Attention: Ms. E. Adensam, Chief Licensing Branch No. 4 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Ms. Adensam:

In the Matter of ) Docket No. 50-327 Tennessee Valley Authority ) 50-328 Unit 1 of the Sequoyah Nuclear Plant is presently scheduled to complete cycle 2 operations and enter the next refueling outage in early 1984.

This letter is to notify you of our plans for the unit 1, cycle 3 reload core. The cycle 3 reload core design was analyzed in accordance with the methodology documented in the WCAP-9273 dated March 1978, " Westinghouse Reload Safety Evaluation Methodology." The results of this analysis and review are provided in the enclosure, "Sequoyah Nuclear Plant Unit 1 Reload Safety Evaluation (RSE) for Cycle 3 operation." Only those incidents analyzed and reported in the Scquoyah Final Safety Analysis Report (FSAR) have been reviewed for the cycle 3 design. The results of the analysis demonstrate that the core reload will not adversely affect the safety of the plard and that the cycle 3 core design does not cause the previously acceptable safety limits for any incident to be exceeded. Also, the analysis has shown that the current Technical Specifications, as approved through Amendment 32 to Operating License DPR-77, are applicable and that no changes are necessary.

A decalled review of the Westinghouse methodology, analysis techniques and results has been performed by the technical staff within TVA. The RSE has also been reviewed by the Sequoyah Plant Operations Review Committee (PORC) and the Nuclear Safety Review Board (NRSB). The unit 1, cycle 3 reload core has been evaluated pursuant to 10 CFR 50.59 and a determination has been mde that no unreviewed safety questions exist. Accordingly, no review of the RSE for unit 1 cycle 3 operations is being requested but is being provided for your information.

224 831212 h2hCK05000327 p

PDR 1983-TVA SOTH ANNIVERSARY

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Director of Nuclear Reactor Regulation December 12, 1983 If you have any questions, please call Jerry Wills at FTS 658-2683 Very truly yours, TENNESSEE VALLEY AUTHORITY L. M. Mills, Manager Nuclear Licensing Sworn t nd subscri before me ,,

this _ day of >< 1983 Notary Public Q

. My Commission Expires /' '

Enclosure cc: U.S. Nuclear Regulatory Commission (Enclosure)

Region II Attn: Mr. James P. O'Reilly Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30303 t

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