ML20138B783
| ML20138B783 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 03/20/1986 |
| From: | Gridley R TENNESSEE VALLEY AUTHORITY |
| To: | Youngblood B Office of Nuclear Reactor Regulation |
| References | |
| GL-83-28, NUDOCS 8603250160 | |
| Download: ML20138B783 (2) | |
Text
o TENNESSEE VALLEY AUTHORITY SN 157B Lookout Place March 20, 1986 Director of Nuclear Reactor Regulation Attention:
Mr. B. Youngblood, Project Director PWR Project Directorate No. 4 Division of Pressurized Water Reactors (PWR)
Licensing A U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Youngblood:
In the Matter of
)
Docket Nos. 50-327 Tennessee Valley Authority
)
50-328 By the November 7, 1983 letter from L. M. Mills to E. Adensam, we provided a response for our Sequoyah Nuclear Plant (SQN) to each of the items in Generic Letter 83-28.
In response to your letter dated December 19, 1985 and a November 19, 1985 letter from T. Novak, enclosed is a revised response to item 3.2.3 of Generic Letter 83-28 for our SQN.
If you have any questions, please call Jerry Wills at FTS 858-2683.
Very truly yours.
[
TENNESSEE VALLEY AUTHORITY j
R.
ridley Manager of icensing Enclosure cc (Enclosure):
U.S. Nuclear Regulatory Comission Region II Attn:
Dr. J. Nelson Grace, Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. Carl Stahle Sequoyah Project Manager U.S. Nuclear Regulatory Comission 7920 Norfolk Avenue Bethesda, Maryland 20814 8603250160 860320 DR p
ADOCM 05000327 k
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An Equal Opportunity Employer
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ENCLOSURE REVISED RESPONSE TO ITEM 3.2.3 OF GENERIC LETTER 83-28 SEQUOYAH NUCLEAR PLANT ITEM 3.2.3 OF GENERIC LETTER 83-28 Licensees and applicants shall identify, if applicable, any post-maintenance test requirements in existing technical specifications which are perceived to degrade rather than enhance safety. Appropriate changes to thesa test requirements, with supporting justification, shall be submitted for staff approval.
TVA REVISED RESPONSE A review was made of existing technical specification surveillances, and none of the technical specifications were perceived to degrade rather than enhance safety except for the diesel generator requirement. A proposed revision to this technical specification was submitted to NRC for approval by J. A. Domer's letter dated February 1,1985 to E. Adensam which requested approval of a proposed license amendment (SQN TVA TS 57).
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