ML20213C933

Responds to Generic Ltr 83-28, Required Actions Based on Generic Implications of Salem ATWS Events. Procedures P-7 & P-12 Used for Identification of Reactor Trip Sys Components. Item 2.1 Complete

ML20213C933
Person / Time
Site:	Fort Saint Vrain
Issue date:	10/31/1986
From:	Gahm J PUBLIC SERVICE CO. OF COLORADO
To:	Berkow H Office of Nuclear Reactor Regulation
References
GL-83-28, P-86610, TAC-52840, NUDOCS 8611100361
Download: ML20213C933 (2)

Text

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0 Public Service- .. .

Company of Colorado 16805 WCR 19 1/2, Platteville, Colorado 80651 October 31, 1986 Fort St. Vrain  ;

Unit No. 1 l P-86610 Director of Nuclear Reactor Regulation U. S. Nuclear Regylatory Commission Washington, D.C. 20555 Attention: Mr..H. N. Berkow, Director Standardization and Special Projects Directorate Docket No. 50-267

SUBJECT:

Generic Letter 83-28, Action Item 2.1

REFERENCE:

(1) NRC letter, Eisenhut to All Licensees dated July 8, 1983 (G-83256)

(2) PSC letter, Lee to Eisenhut dated November 4, 1983 (P-83359)

(3) PSC letter, Gahm to Johnson dated June 14, 1985 (P-85204)

Dear Mr. Berkow:

In response to Generic Letter 83-28 (Reference 1) " Required Actions Based on Generic Implications of the Salem ATWS Events," PSC submitted information (Reference 2) related to PSC's identification of Reactor Trip Systems (RTS) components. In Reference 3 PSC indicated that the identification of all RTS components as safety related would be accomplished as part of the maintenance procedure rewrite program. This rewrite effort is part of PSC's Performance Enhancement Program.

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P-86610 Page 2 October 31, 1986 In recent telephone conversations with Mr. Ken Heitner of your office, PSC has indicated that PSC has approached the resolution of Item 2.1 of Generic Letter 83-28 in a manner somewhat different than described in letter P-85204. _Through the use of administrative controls, specifically Procedure P-7 " Station Service Request Processing" and Procedure P-12 " Plant Maintenance", PSC has established the method for the identification of RTS components.

Procedure P-7 is used for corrective and preventative maintenance activities. Procedure P-12 is used to perform all maintenance activities under the control of the Superintendent of Maintenance and Superintendent of Betterment Engineering and must. be used -in conjunction with P-7.

The use of either Results (Betterment Engineering) or Maintenance 2

procedures is authorized when any equipment-specific Station Service Request (SSR) is initiated. Each SSR has a field where the safety related status of the subject equipment must be identified before maintenance activities can begin. This-determination, therefore, would identify RTS components or any FSV equipment which is safety related. The administrative controls represented by the SSR process and the use of maintenance procedures assure that any component is properly identified as safety related before maintenance activities can begin. PSC believes that this process meets the intent of Item 2.1 of Generic Letter 83-28 and that this item chould be considered complete.

Should you have any questions concerning this letter, please do not hesitate to contact Mr. M, Holmes at (303) 480-6960 for further information.

Sincerely,

/k J. W. Gahm Manager, Nuclear Production Fort St. Vrain Nuclear Generating Station JWG/DCG:pw cc: J.E. Gagliardo

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