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.
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. Start Printed 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).Start Signature
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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