[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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