[Federal Register Volume 65, Number 57 (Thursday, March 23, 2000)]
[Notices]
[Pages 15659-15660]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 00-7237]


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NUCLEAR REGULATORY COMMISSION

[DOCKET NOS. 50-269, 50-270, and 50-287]


Duke Energy Corporation; Oconee Nuclear Station, Units 1, 2, and 
3 Environmental Assessment and Finding of No Significant Impact

    The U.S. Nuclear Regulatory Commission (NRC) is considering 
issuance of an exemption from certain requirements of Title 10 of the 
Code of Federal Regulations (10 CFR) Section 50.44, 10 CFR 50.46, and 
10 CFR Part 50, Appendix K to the Duke Energy Corporation (the 
licensee/Duke) for operation of the Oconee Nuclear Station, Units 1, 2, 
and 3, Facility Operating License Nos. DPR-38, DPR-47, and DPR-55, 
respectively, located in Oconee County, Seneca, South Carolina.

Environmental Assessment

Identification of the Proposed Action

    The proposed action would exempt the licensee from certain 
requirements of 10 CFR 50.44, 10 CFR 50.46, and Appendix K of 10 CFR 
Part 50 to allow the use of Framatome Cogema Fuels (FCF) ``M5'' 
advanced alloy as a fuel rod cladding material.
    The proposed action is in accordance with the licensee's 
application for an exemption dated September 15, 1999.

The Need for the Proposed Action

    The proposed action is needed to allow the use of Framatome Cogema 
Fuels (FCF) ``M5'' advanced alloy as a fuel rod cladding material. The 
exemption is necessary since the chemical composition of M5 differs 
from the Zircaloy and ZIRLO cladding material specified in the 
regulations. The M5 alloy is a proprietary zirconium-based alloy, 
composed primarily of zirconium and niobium, that has demonstrated 
superior corrosion resistance and reduced irradiation growth relative 
to both standard and low-tin Zircaloy. Since the chemical composition 
of the M5 alloy differs from the specifications for Zircaloy or ZIRLO, 
an exemption is required for the use of the M5 alloy as a fuel cladding 
material at Oconee. The regulations set forth in 10 CFR 50.44, 10 CFR 
50.46 and Appendix K to 10 CFR Part 50 contain acceptance and 
analytical criteria regarding the light water nuclear reactor system 
performance during and following a postulated loss-of-coolant accident. 
These regulations specify the use of only two types of fuel cladding 
material, Zircaloy and ZIRLO.

Environmental Impacts of the Proposed Action

    The proposed action to implement the exemption described above is 
designed to enhance fuel rod performance characteristics over that of 
Zircaloy or ZIRLO clad fuel rods. The proposed action does not exempt 
the licensee from complying with the acceptance and analytical criteria 
of 10 CFR 50.44, 10 CFR 50.46 and Appendix K to 10 CFR Part 50 
applicable to the M5 alloy cladding. The exemption solely allows the 
criteria set forth in these regulations to apply to the M5 cladding 
material. The staff has concluded that the proposed action will not 
significantly increase the probability or consequences of accidents, 
there are no changes being made in the types of any effluents that may 
be released offsite, and there is no significant increase in 
occupational or public radiation exposure because this exemption will 
not change the criteria set forth in the present regulations, since the 
M5-clad fuel has been shown by the licensee to be capable of meeting 
this criteria. Therefore, the Commission concludes that there are no 
significant radiological environmental impacts associated with the 
proposed action.
    With regard to potential nonradiological environmental impacts, the 
proposed action does not involve any historic sites. It does not affect 
nonradiological plant effluents and has no other environmental impact. 
Therefore, there are no significant nonradiological environmental 
impacts associated with the proposed action.

[[Page 15660]]

    Accordingly, the NRC concludes that there are no significant 
environmental impacts associated with the proposed action.

Alternatives to the Proposed Action

    As an alternative to the proposed action, the staff considered 
denial of the proposed action (i.e., the ``no-action'' alternative). 
Denial of the application would result in no change in current 
environmental impacts. The environmental impacts of the proposed action 
and the alternative action are similar.

Alternative Use of Resources

    This action does not involve the use of any resources not 
previously considered in the Final Environmental Statement for the 
Oconee Nuclear Station, Units 1, 2, and 3.

Agencies and Persons Consulted

    In accordance with its stated policy, on March 14, 2000, the staff 
consulted with the South Carolina State official, Mr. Virgil L. Autry 
of the Division of Radiological Waste Management, Bureau of Land and 
Waste Management, Department of Health and Environmental Control, 
regarding the environmental impact of the proposed action. The State 
official had no comments.

Finding of No Significant Impact

    On the basis of the environmental assessment, the NRC concludes 
that the proposed action will not have a significant effect on the 
quality of the human environment. Accordingly, the NRC has determined 
not to prepare an environmental impact statement for the proposed 
action.
    For further details with respect to the proposed action, see the 
licensee's letter dated September 15, 1999, which is available for 
public inspection at the Commission's Public Document Room, The Gelman 
Building, 2120 L Street, NW., Washington, DC. Publically available 
records are accessible electronically from the ADAMS Public Library 
component on the NRC Web site, http://www.nrc.gov (the Electronic 
Reading Room).

    Dated at Rockville, Maryland, this 17th day of March 2000.

    For the Nuclear Regulatory Commission.
Richard L. Emch, Jr.,
Section Chief, Section 1, Project Directorate II, Division of Licensing 
Project Management, Office of Nuclear Reactor Regulation.
[FR Doc. 00-7237 Filed 3-22-00; 8:45 am]
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