ML20098A938
| ML20098A938 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 09/18/1984 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | Adensam E Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8409250324 | |
| Download: ML20098A938 (2) | |
Text
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4 TENNESSEE VALLEY AUTHORITY
' CHATTANOOGA. TENNESSEE 37401
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'0, z.400 Ciestnut Street Tower II
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c iSeptember 18, 1984-v s
l Director of. Nuclear Reactor Regulation -
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' Attention:
4 Ms.;E. Adansas, Chief
. Licensing Branch No. 4.
- Division ofz Licensing.
! < - ;; ;J U.32 Nuclear Regulatory Commission
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2T Washington, D.C.~.20555-4 s
Dear Ms'.i Adensaa:
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- bi In the Matter of-
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Docket Nos. 328
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= Tennessee Valley Authority
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L Unit 2 'of the Sequoyah Nuclear Plant -is presently scheduled to complete
. cycle 2 ' operations and enter the next refuelOg outage on September 21,
= 196.4. This letter is to notify you = of our pland for the unit 2, cycle-3
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reload. oore. The c/cle' 3 reload core design was analyzed in accordance
~ with tho' methodology documented in. the.WCAP-9273 dated March 1978,
. Westinghouse Reload Safety. Evaluation Methodology." The results of this f analysis and review are documented'in "Sequoyah Nuclear Plant Unit 2 Reload Safety Evaluation'(RSE):for Cycle.3' operation." Only those incidents s
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! analyzed and reported in the Sequoyah Final Safety Analysis Report _(FSAR)-
have been reviewed for the oyole 3. design.. The results of the analysis y
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- demonstrate that the ' core reload will--not adversely affect the safety.of the plant and~thit the cycle 3. core design'does not cause the previously
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acceptable safety limits for any incident to be exceeded.- Also, the analysis has shown that the ourrent Technical Specifications, as. approved 7-L through Amendment 27 to Operating License DPR-79,: are applicable and-that 7
no changes are necessary.
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.. A detailed myiew of the Westinghouse methodology,' analysis techniques and results has been performed by,the cochnical staff within TVA. The RSE has.
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.also been reviewed by the Sequoyah Plant Operations Review Committee (PORC)
.and,the Nuclear Safety Review Board (NRSB). 'The unit 2, cycle-3 reload j
oore.has.been evalaataxi pursuant to 10 CFR 50.59 and a determination has D-been made that. no unreviewed safety questions exist. Accordingly, no I
review of the RSE - for unit 2 cycle 3. operations is :being mquested.
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e An Equal Opportunity Employer
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. Director of Nuclear Reactor, Regulation September 18, 1984
.. If you have any questions concerning this matter, please get in touch with Jerry Wills at FTS 858-2683.,
Very truly yours, TENNESSEE VALLEY AUTHORITY
\\
L. M. Mills, Manager Nuclear Licensing Sworn to subscri %d efore me th
' day of 2 1984 No Public f,
- My asion Expires f/ #
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ec:.U.S. Nuclear Regulatory Commission Region II
' Attn:
Mr. James P. O'Reilly Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 i
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