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Environmental Assessment and Finding of No Significant Impac

 

Environmental Assessment and Finding of No Significant Impac



[Federal Register: May 22, 1995 (Volume 60, Number 98)]
[Notices]               

[Page 27140-27141]

>From the Federal Register Online via GPO Access [wais.access.gpo.gov]









NUCLEAR REGULATORY COMMISSION



[Docket No. 50-267]

 


Environmental Assessment and Finding of No Significant Impact; 
Public Service Company of Colorado Fort St. Vrain Nuclear Generating 
Station



    The Nuclear Regulatory Commission (the NRC) is considering the 
issuance of an exemption from the requirements of 10 CFR 50.54(w) to 
maintain onsite property insurance to the Public Service Company of 
Colorado (PSC or the licensee) for the Fort St. Vrain Nuclear 
Generating Station (FSV) pursuant to the requirements of 10 CFR 50.12.



Environmental assessment



Identification of Proposed Action



    The exemption will delete the requirements of 10 CFR 50.54(w) for 
the licensee to maintain onsite property insurance. FSV is permanently 
shut down and all the fuel assemblies are currently stored in an 
independent spent fuel storage installation (ISFSI), and the ISFSI is 
licensed under 10 CFR Part 72. In addition, decommissioning of FSV is 
approximately 65 percent complete, and PSC estimates that the facility 
license will be terminated and the facility released for unrestricted 
use in 1996.



The Need for the Proposed Action



    The exemption is needed to eliminate the requirements of 10 CFR 
50.54(w), which are appropriate for an operating plant but are not 
needed at the shutdown FSV. Granting the proposed exemption would 
reduce unnecessary costs for PSC.



Environmental Impact of the Proposed Action



    The proposed action to eliminate the requirements for the licensee 
to have in effect and to continue to maintain onsite property insurance 
will have no environmental impact because FSV is permanently shut down, 
defueled, and 65 percent decommissioned. Thus, the risk of an accident 
requiring reactor stabilization or extensive decontamination does not 
exist at FSV. In addition, for the worst-case accident at FSV, the 
radiological release from the accident is a whole-body dose to an 
individual of 8.30 mrem. This dose is considerably less than 1 percent 
of the U.S. Environmental Protection Agency's ``Protective Action 
Guidelines'' dose of 1000 mrem that requires protective action.
    The requested exemption would not authorize construction or 
operation, would not authorize a change in licensed activities, and 
would not effect changes in the permitted types or amounts of 
radiological effluent. With regard to potential nonradiological 
impacts, the NRC concludes that no measurable radiological or 
nonradiological impacts are associated with the exemption.



Alternatives to the Proposed Action



    Because the NRC concluded that there are no significant 
environmental effects [[Page 27141]] that would result from the 
proposed action, alternatives need not be evaluated.



Alternative Use of Resources



    This action does not involve the use of any resources not 
previously considered in the Final Environmental Statement for FSV.



Agencies and Persons Consulted



    The license initiated this exemption, and the NRC staff is 
reviewing its request. The State of Colorado was notified of the 
proposed exemption. State Officials had no comments on the exemption.



Finding of No Significant Impact



    NRC has determined not to prepare an environmental impact statement 
for the proposed exemption.

    Based on this environmental assessment, the staff concludes that 
the proposed action will not have a significant effect on the quality 
of the human environment.

    For further details on this action, see the licensee's application 
dated February 16, 1995, which is available for public inspection at 
the NRC's Public Document Room, 2120 L Street, NW, Washington, DC 
20037, and at the local public document room at the Weld Library 
District.--Downtown Branch, 919 7th Street, Greeley, CO 80631.



    For the Nuclear Regulatory Commission.



    Dated at Rockville, Maryland, this 12th day of May, 1995.



Michael F. Weber,

Chief, Low-Level Waste and Decommissioning Projects Branch, Division of 
Waste Management, Office of Nuclear material Safety and Safeguards.
[FR Doc. 95-12471 Filed 5-19-95; 8:45 am]
BILLING CODE 7590-01-M

 
 

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