[Federal Register Volume 64, Number 181 (Monday, September 20, 1999)]
[Notices]
[Pages 50839-50840]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 99-24381]


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NUCLEAR REGULATORY COMMISSION

[Docket Nos. 50-369 and 50-370]


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

    The U.S. Nuclear Regulatory Commission (the Commission) is 
considering issuance of exemptions from Facility Operating Licenses 
Nos. NPF-9 and NPF-17, issued to Duke Energy Corporation (the 
licensee), for operation of the McGuire Nuclear Station, Units 1 and 2, 
located in Mecklenberg County, North Carolina.

Environmental Assessment

Identification of Proposed Action

    The proposed action would exempt McGuire Nuclear Station, Units 1 
and 2, from certain requirements of Title 10 of the Code of Federal 
Regulations (10 CFR) Part 50, Appendix A, General Design Criterion 
(GDC) 57, regarding isolation of main steam branch lines penetrating 
the containment. The proposed action is in response to the licensee's 
application dated April 20, 1999.

The Need for the Proposed Action

    The licensee requested an exemption from GDC 57 for Containment 
Penetrations M261 and M393. GDC 57 imposes isolation requirements on 
lines that penetrate primary reactor containment and are neither part 
of the reactor coolant pressure boundary nor connected directly to the 
containment atmosphere. These are penetrations on main steam branch 
lines. These lines penetrate the containment and are not part of the 
reactor coolant pressure boundary or connected directly to the 
containment atmosphere. Outside of containment, these lines branch into 
various separate, individual lines before reaching the respective main 
steam isolation valves. From each of these main steam lines, one branch 
supplies main steam to the turbine-driven auxiliary feedwater (TDCA, 
using the licensee's abbreviation) pump.
    Valves SA-1, SA-2, SA-77, and SA-78 are locally operated, locked 
open, manual gate valves. Valves SA-5 and SA-6 are stop check valves. 
All of these valves are located in the branch lines that supply main 
steam to the TDCA. Valves SA-1, SA-2, SA-77, and SA-78 are required to 
be open, and SA-5 and SA-6 are required to be capable of opening for 
Engineered Safety Features (ESF) operations of the TDCA pump by 
Technical Specifications (TS). The TDCA is also part of the ESF. Valves 
SA-1, SA-2, SA-77, and SA-78 are not identified as Containment 
Isolation Valves in the TS or the Updated Final Safety Analysis Report, 
but perform that function. To comply literally with GDC 57, the 
licensee would have to add motor operators to valves SA-1, SA-2, SA-77, 
and SA-78, such that they become automatic or capable of remote 
operation. The licensee has requested an exemption from literal 
compliance with GDC 57. The licensee would rely instead on manual 
action to close the valves SA-1, SA-2, SA-77, and SA-78, or valves SA-
5, and SA-6. The time needed to do so has been factored into the 
accident analyses. Further, the applicable design-basis accident 
scenarios and consequences continue to be bounding.

Environmental Impacts of the Proposed Action

    The Commission has completed its evaluation of the proposed action 
and concludes that there is no significant environmental impact if the 
exemptions are granted. No changes will be made to the as-built design, 
and existing applicable procedures at the two units at the McGuire 
Nuclear Station will remain the same.
    The proposed action will not increase the probability or 
consequences of accidents, no changes are being made in the types of 
any effluents that may be released offsite, and there is no significant 
increase in the allowable individual or public radiation exposure. 
Therefore, there are no significant radiological environmental impacts 
associated with the proposed action.
    With regard to potential nonradiological 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.
    Accordingly, the Commission 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 Impact Statement 
related to the McGuire Nuclear Station.

Agencies and Persons Contacted

    In accordance with its stated policy, on September 13, 1999, the 
staff consulted with the North Carolina State official, Mr. John James, 
of the 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 Commission 
concludes that the proposed exemptions will not have a significant 
effect on the quality of the human environment. Accordingly, the 
Commission 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 request for the exemptions dated April 20, 1999, which is 
available for public inspection at the Commission's Public Document 
Room, The Gelman Building, 2120 L Street, NW., Washington DC, and at 
the local public document room located at the J. Murrey Atkins Library, 
University of North Carolina at Charlotte, 9201 University City 
Boulevard, Charlotte, North Carolina.


[[Page 50840]]


    Dated at Rockville, Maryland, this 14th day of September 1999.

    For the Nuclear Regulatory Commission.
Frank Rinaldi,
Project Manager, Section 1, Project Directorate II, Division of 
Licensing and Project Management, Office of Nuclear Reactor Regulation.
[FR Doc. 99-24381 Filed 9-17-99; 8:45 am]
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