[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]
BILLING CODE 7590-01-P
