ML20246J326

Safety Evaluation Supporting Amend 72 to License DPR-34

ML20246J326
Person / Time
Site:	Fort Saint Vrain
Issue date:	08/30/1989
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20246J294	List: ML20246J291 ML20246J309 ML20246J326
References
NUDOCS 8909050122
Download: ML20246J326 (2)

Text

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 72 TO FACILITY OPERATING LICENSE NO. DPR-34 PUBLIC SERVICE COMPANY OF COLORADO

- FORT ST. VRAIN NUCLEAR GENERATING STATION DOCKET NO. 50-267

1.0 INTRODUCTION AND BACKGROUND

By letter dated December 5, 1988, Public Service Company of Colorado (PSC) announced their plans to not operate the Fort St. Vrain Nuclear Generating Station (FSV) past June 30, 1990. By letter dated January 20, 1989, PSC requested relief from a number of commitments regarding FSV.

These requests are being considered in separate licensing actions. In a letter dated April 19, 1989, the NRC staff advised PSC to submit a license amendment concerning the proposed early shutdown of FSV. By letter dated June 9, 1989, PSC made the requested license amendment submittal.

2.0 EVALUATION The license amendment request effectively limits the reactor to low power af ter June 30, 1990. This effectively prohibits the reactor from operating in power production. With this severe limit on reactor power, it is difficult to exceed any reactor operating safety limits. Adequate decay heat removal can be achieved with only the liner cooling system (one loop). Long response times are available to deal with any operational problem.

Furthermore, it is the licensee's intent to maintain the reactor in the shutdown condition after June 1990 to allow for defueling. The provision of this amendment to allow up to 2% power operation will allow physics testing for unanticipated circumstances during defueling. However, this level of power operation adds only a small amount of heat to the core.

The staff has previously established that this low power limit is acceptable.

Thus, the staff concludes that the proposed license amendment is acceptable.

3.0 ENVIRONMENTAL CONSIDERATION

The amendment involves a change in the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20.

The staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure:. The Cc=ission l $[0$Nbfk P

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-SAFETY EVALUATION BY THE OFFICE-OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 72 TO FACILITY OPERATING LICENSE NO. DPR-34 PUBLIC SERVICE COMPANY OF COLORADO

- FORT ST. VRAIN NUCLEAR GENERATING STATION DOCKET NO. 50-267:

1.0 INTRODUCTION AND BACKGROUND

By letter dated December 5, 1988, Public Service Company of Colorado (PSC) announced their plans to not operate the Fort St. Vrain Nuclear GeneratingStation(FSV)pastJune 30, 1990. By letter dated -January 20, 1989, PSC requested relief.from a number of commitments regarding FSV.

These. requests are being considered-in separate licensing actions.- In -

a letter dated April 19, 1989, the NRC staff advised PSC to submit a license amendment concerning the proposed early shutdown of.FSV. . By letter dated" June 9, 1989, PSC made the requested. license amendment.

. submittal.

2.0 EVALUATION.

The license amendment request effectively limits the reactor to low power.

after June 30, 1990. This effectively prohibits the reactor from operating in power production. With this severe limit on reactor power, it is-i

-difficult to exceed any reactor operating safety limits. Adequate decay L heat removal can be achieved with only the liner cooling system (one i

loop). Long response times are available to deal with any operational problem.

Furthermore, it is the licensee's intent to maintain the reactor in the shutdown condition after June 1990 to allow for defueling. The provision of this atendment to allow up to 2% power operation will allow physics testing for unanticipated circumstances during defueling. However, this level of power operation adds only a small amount of heat to the core.

The staff has previously established that this low power limit is acceptable.

Thus, the staff concludes that the proposed license amendment'is acceptable.

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3.0 ENVIRONMENTAL CONSIDERATION

The amendment involves a change in the installation or use of a facility n component located within the restricted area as defined in 10 CFR Part 20.

l= The staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposures. The C0=.issicn P

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l has previously issued a proposed finding that the. amendment involves no 1 d

significant hazards consideration and there has been no public comment on such finding. Accordingly, the amendment meets the eligibilit criteria

1. forcategoricalexclusionsetforthin10CFRSection'51.22(c)9). Pursuant

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to10CFR51.22(b),noenvironmentalimpactstatementorenvironmental assessment need be prepared in connection with the issuance of the amendment. ,

CONCLUSION

'The staff has concluded, based on the considerations discussed above, that: (1) there is. reasonable assurance that the health and safety of the pub'lic will not be endangered by operation in the proposed manner, and-(2) such activities will be conducted in conspliance with the Commission's regulations,;and the issuance of the amendment will not be inimical to the common defense and-security or to the health and safety of the public.

Date: August 30, 1989 Principal Contributor: Kenneth L. Heitner l

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