ML20100H521

Forwards Draft Upgraded Tech Specs for Acceptance Review. Draft Specs Intended to Improve Accuracy,Completeness & Clarity of Facility Tech Specs Consistent W/Licensing Basis of Plant as Embodied in FSAR

ML20100H521
Person / Time
Site:	Fort Saint Vrain
Issue date:	04/01/1985
From:	Lee O PUBLIC SERVICE CO. OF COLORADO
To:	Johnson E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20100H524	List: ML20100H521 ML20100H525
References
P-85098, NUDOCS 8504090221
Download: ML20100H521 (2)

Text

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O';"L 0 Public Service ~ P.O. Box 840 Denver, CO 80201- 0840 OSCAR R. LEE VICE PRESIDENT April 1, 1985 Fort St. Vrain Unit No. 1 P-85098 4

Regional Administrator Region IV

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U.S. Nuclear Regulatory Commission M-2E 611 Ryan Plaza Drive, Suite 1000 -

Arlington, Texas 76011 ,

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Attention: Mr. Eric H. Johnson Docket No. 50-267

Subject:

Upgraded Technical Specifications for Acceptance Review

Reference:

1) PSC Letter, Lee to Johnson, dated 12/14/84 (P-84530)

Dear Mr. Johnson:

Enclosed for your review is one copy of the April 1,1985 draft of the Fort St. Vrain (FSV) Technical Specifications that Public Service Company (PSC) has developed as a result of the Technical Specification Upgrade Program. Five additional copies will be sent to Region IV and five to Bethesda when they become available. These draft specifications are intended to improve the accuracy, completeness, and clarity of the FSV Technical Specifications consistent with the licensing basis of the plant as embodied in the FSV Final Safety Analysis Report.

The draft specifications have been significantly reorganized. Many of the existing specifications have been either relocated, combined with others, or deleted. All deleted specifications are justified in a separate enclosure to this letter. Justification of other changes such as those concerning applicable modes is provided to the extent practicable in the basis of each specification. A more detailed explanation and justification will be provided when PSC submits the .

Technical Specifications for NRC approval.

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-As 'the upgrade effort proceeded, PSC determined that it would be beneficial ~to adopt the. basic format and number system of the Standard Technical. Specifications. A cross reference of the new

. numbering system to the existing number system is included .in this submittal.

PSC has completed an initial review of each of the draft specifications and has = incorporated comments resulting from that

, review. . A further review.-is in progress within PSC, which will proceed in parallel'with the NRC review- of these , April :1,' 1985 drafts.

LUpon receiving NRC , comments and prior to :;ubmitting the upgraded Technical Specifications for formal approval, it is proposed that an NRC-PSC meeting be held to -discuss and finalize the draft specifications. Subsequent to this meeting, a formal applio tion to amend the FSV Technical Specifications will be prepared and sub:'itted 4

to the Plant Operation Review Committee and the Nuclear Facility Safety Committee. The target date for submittal of the proposed amendment to the NRC is July 1, 1985 (Reference 1). This date is contingent upon completion of the NRC review and the PSC internal review and approval process.

Enclosure 1 provides the draft specifications for acceptance review.

, Enclosure. 2 identifies the deleted specifications and contains justification for the deletions.' Enclosure 3 contains the cross j reference list of the new numbering system to the existing numbering i system.

If you have any questions or comments about the enclosures, please=

contact Mr. M. H. Holmes at (303) 571-8409.

Very truly yours, (f)

0. R.

90 ee, Vice President Electric Production ORL/sem Enclosures cc: Tom King, NRC (with enclosures) i 4,--- , .m , _y ,, , . , . , . , , - - -r