ML20209F423

Forwards Application for Amend to License DPR-34,revising Tech Specs Re Limiting Conditions for Operation of Protective Sys Instrument Setpoints & Allowable Values

ML20209F423
Person / Time
Site:	Fort Saint Vrain
Issue date:	06/21/1985
From:	Lee O PUBLIC SERVICE CO. OF COLORADO
To:	Johnson E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20209F429	List: ML20209F423 ML20209F440 ML20209F446
References
P-85214, TAC-47416, NUDOCS 8507120466
Download: ML20209F423 (3)

Text

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P.O. Box 840 Denver, CO 80201 0840 OSCAR R. LEE VICE PRESIDENT June 21, 1985 Fort St. Vrain Unit No. 1 P-85214 Regional Administrator Region IV E ([,

j ij M Nuclear Regulatory Commission

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611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 M 4885 5

M Attn: Mr. Eric H. Johnson e

t g DOCKET N0. 50-267

SUBJECT:

Proposed Changes to Sections 2.1, 3.3, 4.0, 5.0, LC0 4.4.1, and SR 5.4.1 of the Fort St.

Vrain Technical Specifications

Dear Mr. Johnson:

At the request of the Nuclear Regulatory Commission Staff (The Commission) and as committed to by Public Service Company (PSC) in reference 5, a proposed revision to Sections 2.1, 3.3, 4.0, 5.0, LC0 4.4.1, and SR 5.4.1 of the Fort St. Vrain (FSV)

Technical Specifications is hereby submitted for approval.

This submittal incorporates standard Commission guidance for Plant Protective System (PPS) Instrument Setpoints and Allowable Values.

The revisions were made using the model Westinghouse Standard Technical Specifications Format as a guide. Only the lines that are changed by this amendment are noted with a vertical bar in the left margin.

.A review of Analysis Values for the PPS was performed by GA Technologies.

Detailed calculations to determine the Trip Setpoints and Allowable Values were performed for Public Service Company by Sargent and Lundy Engineers.

These calculations are available for review by the Commission in PSC's offices.

I I, 8507120466 050621 PDR ADOCK 05000267 q. 5-e von

(&yoY 4

r P-85214 Page 2 In the process of compiling the setpoint changes, a circulator trip has been identified which is included in the PPS, but has never been included in the FSV Technical Specifications.

PSC is in the process of analyzing Programmed Feedwater Flow-Low, a function of circulator speed, using methodology consistent with the other PPS parameters.

However, due to the recent discovery of this omission (January,1985)

PSC cannot complete the analysis for inclusion in this submittal.

PSC does commit to submit the revised Programmed Feedwater Flow Low Circulator Trip Allowable Values and Trip Setpoints on or before October 1, 1985.

In the interim, PSC has incorporated the existing trip setpoint into this submittal. This trip setpoint which is not associated with a Safety Limit will continue to provide equipment protection until the analyzed trip setpoint is approved by the Commission.

The following attachments are included: : Summary of Proposed Changes referenced to the FSV Technical Specifications. : The Proposed Changes to Sections 2.1, 3.3, 4.0, and LC0 4.4.1 of the FSV Technical Specifications. : A Significant Hazards Considerations Analysis. : The results of the Analysis Values review. : The Detector Decalibration Curves and Calibration instructions of High Neutron Flux Scram and Rod Withdrawal Prohibit Setpoints and Allowable Values approved b St. Vrain Nuclear Facility Safety Committee (NFSC)y the Fort for the current cycle, Fuel Cycle 4. : Summary of Proposed Changes to Section 5.0, SR 5.4.1, and to related definitions included in Section 2.1. : The Proposed Changes to Sections 2.1 and 5.0 and SR 5.4.1 of the FSV Technical Specifications. : Significant Hazards Considerations Analysis for SR 5.4.1.

In accordance with the provisions of 10CFR170, an application fee of

$150.00 is enclosed.

A 180 day period after approval of these revisions by the Commission is requested before the revised sections are incorporated into the FSV Technical Specifications. The 180 day period is required by PSC to revise the System Operating Procedures, computer software, Plant Protective System daily log sheets, the Surveillance Procedures, the Emergency Procedures, the Technical Specification Compliance Log, and

F P-85214 Page 3 the Overall Plant Operating Procedures. This time is also required to retrain all licensed personnel.

If you have any questions regarding this submittal, please contact Mr. M. H. Holmes at (303) 571-8409.

Very truly yours, N

0.R. Lee, Vice President Electric Production ORL/JW:pa Attachments - Summary of Proposed Changes - Proposed Changes to LSSS 3.3 and LC0 4.4.1 - Significant Hazards Considerations Analysis - Analysis Values - Detector Decalibration Curves - Summary of Proposed Changes - Proposed Changes to SR 5.4.1 - Significant Hazards Considerations Analysis

REFERENCES:

1) P-80340, Lee to Miller dated October 1, 1980

2) G-83255, Madsen to Lee dated July 11, 1983

3) G-83409, Wagner to Johnson dated November 3, 1983

4) P-83415, Lee to Collins dated December 30, 1983

5) P-84078, Warembourg to Collins, dated March 9, 1984 6)G-84137,Johnsonto Lee dated April 24, 1984

7) P-84155, Warembourg to Johnson dated May 25, 1984 cc: A.J. Hazie - Colorado Department of Health