[Federal Register Volume 68, Number 231 (Tuesday, December 2, 2003)]
[Notices]
[Pages 67490-67491]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 03-29901]


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NUCLEAR REGULATORY COMMISSION

[Docket No. 50-286]


Energy Nuclear Operations, Inc., Indian Point Nuclear Generating 
Unit No. 3, Environmental Assessment and Finding of No Significant 
Impact

    The U.S. Nuclear Regulatory Commission (NRC) is considering 
issuance of an exemption from Title 10 of the Code of Federal 
Regulations (10 CFR) part 50, section 50.60(a) for Facility Operating 
License No. DPR-64, issued to Entergy Nuclear Operations, Inc. (the 
licensee), for operation of the Indian Point Nuclear Generating Unit 
No. 3 (IP3), located in Westchester County, New York. Therefore, as 
required by 10 CFR 51.21, the NRC is issuing this environmental 
assessment and finding of no significant impact.

Environmental Assessment

Identification of the Proposed Action

    The proposed action would provide an exemption from the 
requirements of

[[Page 67491]]

10 CFR 50.60(a) to permit the use of the American Society of Mechanical 
Engineers Boiler and Pressure Vessel Code (ASME Code), Section XI, Code 
Case N-640, ``Alternative Requirement Fracture Toughness for 
Development of P-T [Pressure and Temperature] Limit Curves for ASME 
Section XI Division I,'' in lieu of 10 CFR part 50, appendix G, 
paragraph I.
    The proposed action is in accordance with the licensee's 
application dated May 28, 2003.

The Need for the Proposed Action

    The proposed action provides relief from the restriction of the P-T 
operating window defined by the P-T operating and test curves developed 
in accordance with ASME Code, Section XI, Appendix G procedure. ASME 
Code, Section XI, Appendix G procedure was conservatively developed 
based on the level of knowledge existing in 1974 concerning reactor 
pressure vessel materials and the estimated effects of operation. Since 
1974, the level of knowledge about these topics has been greatly 
expanded. This increased knowledge permits relaxation of the ASME Code, 
Section XI, Appendix G, requirements via application of ASME Code Case 
N-640 while maintaining the underlying purpose of the ASME Code, 
Section XI, Appendix G procedure. The restriction of the P-T operating 
and test curves developed in accordance with ASME Code, Section XI, 
Appendix G procedure would challenge the operations staff when 
operating at low temperatures.

Environmental Impacts of the Proposed Action

    The NRC has completed its evaluation of the proposed action and 
concludes as set forth below, there are no significant environmental 
impacts associated with the use of the alternative analysis methods to 
support the revision of the P-T curves.
    The proposed action will not significantly increase the probability 
or consequences of accidents, no changes are being made in the types of 
effluents that may be released off site, and there is no significant 
increase in occupational 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 have a potential to affect 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 NRC concludes that there are no significant 
environmental impacts associated with the proposed action.

Environmental Impacts of the 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

    The action does not involve the use of any different resource than 
those previously considered in the Final Environmental Statement for 
IP3, dated September 1972.

Agencies and Persons Consulted

    On November 20, 2003, the staff consulted with the New York State 
official, Mr. John Spath of the New York State Research and Development 
Authority, 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 May 28, 2003. Documents may be examined, and/or 
copied for a fee, at the NRC's Public Document Room (PDR), located at 
One White Flint North, Public File Area O1 F21, 11555 Rockville Pike 
(first floor), Rockville, Maryland. Publicly available records will be 
accessible electronically from the Agencywide Documents Access and 
Management System (ADAMS) Public Electronic Reading Room on the 
Internet at the NRC Web site, http://www.nrc.gov/reading-rm/adams.html. 
Persons who do not have access to ADAMS or who encounter problems in 
accessing the documents located in ADAMS, should contact the NRC PDR 
Reference staff by telephone at 1-800-397-4209 or 301-415-4737, or by 
e-mail to [email protected].

    Dated at Rockville, Maryland, this 24th day of November 2003.
    For the Nuclear Regulatory Commission.
Richard J. Laufer,
Chief, Section 1, Project Directorate I, Division of Licensing Project 
Management, Office of Nuclear Reactor Regulation.
[FR Doc. 03-29901 Filed 12-1-03; 8:45 am]
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