ML20244B377

Proposed Tech Specs Re Early Shutdown of Plant

ML20244B377
Person / Time
Site:	Fort Saint Vrain
Issue date:	06/09/1989
From:	PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML20244B363	List: ML20244B361 ML20244B367 ML20244B377
References
NUDOCS 8906130086
Download: ML20244B377 (6)

Text

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TO P-89216 .J

SUMMARY

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PROPOSED CHANGE l

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. P-89216 Attachment 1 Page l'of 1 Summary of Proposed Change Section Description of Change Facility Operating. . Incorporates request in NRC License Letter, Heitner to Williams, dated 04/19/89-(G-89137), to amend the Facility Operating License to include a license condition on early shutdown.

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ATTACHMENT 2-TO P-89216-PROPOSED CHANGE l

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.I Fort St. Vrain Technical Specifications License Information Enclosure (1) to AEC~

Letter dated 12/21/73 Amendment No.

'Page 5 of 5 l (4) Early Shutdown l The licensee is not authorized to operate the reactor I (above 2 percent 1 of full . power) for electric power i production after June 30, 1990.

E. This license.~1s subject to all' Federal, State, and local standards imposed pursuant to the requirements of the Federal Water Pollution Control Act of 1972.

3. This license is effective as of the date of issuance and shall-expire at midnight, September 17, 2008.

FOR THE ATOMIC ENERGY COMMISSION "0RIGINAL' SIGNED BY:"

A. Giambusso, Deputy Director for Reactor Projects Directorate of Licensing Attachments:

Appendices A and B - Technical Specifications Date of Issuance: December 21, 1973 1

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ATTACHMENT 3 TO F-89216 NO SIGNIFICANT HAZARDS CONSIDERATION ANALYSIS

, . :,5 P-89216 Attachment 3 Page 1 of 1 NO SIGNIFICANT HAZARDS CONSIDERATION ANALYSIS Description of Amendment Request:

This amendment request is prompted. by NRC letter, Heitner to~

Williams, dated 04/19/89 (G-89137). That letter advised PSC of the need for an amendment to Facility Operating License No. DPR-34; to wit: "The licensee is not authorized to operate the reactor (above 5 percent of full power) for electric power production after June. 30, 1990." PSC preposes a modification to the NRC's suggested amendment statement to reflect a more conservative 2?; power restriction after shutdown.

Basis for no Significant Hazards Determination:

The -proposed change does not involve. a significant- hazards consideration because operation of FSV in accordance with this change would not:

1. involve a significant increase in the probability or consequences of an accident previously evaluated. The early shutdown of Fort St. Vrain will not adversely affect any plant system design or function, nor will it adversely affect safety.

2. create the possibility of a new or different - kind of accident from any accident previously evaluated. The early -;

shutdown of Fort St. Vrain will not result in any new  ;

failure modes.

3. involve a significant reduction in a margin of safety. The early shutdown of Fort St. Vrain will .have no- adverse effects on any margin of safety. Inclusion of this amendment .l in the license is based on an NRC request.

l Additionally, the restriction included in this proposed change prohibiting operation above 274 of full power further avoids any- '

i significant hazards consideration. Although PSC does not intend to l take the reactor critical after final shutdown, any unforeseen  ;

i circumstances requiring criticality would be accommodated by the 2?s ,

I power level restriction. Long term operation at 27; power or any- '!

(' other power level is not being proposed. Remaining below 2?; avoids

-any.significant heat being added to the core.

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