[Federal Register Volume 63, Number 237 (Thursday, December 10, 1998)]
[Notices]
[Pages 68315-68316]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 98-32945]
=======================================================================
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket No. 50-286]
Power Authority of the State of New York; Indian Point Nuclear
Generating Unit No. 3; Environmental Assessment and Finding of No
Significant Impact
The U.S. Nuclear Regulatory Commission (the Commission) is
considering issuance of an exemption from certain requirements of its
regulations for Facility Operating License No. DPR-64, issued to the
Power Authority of the State of New York (the licensee), for operation
of the Indian Point Nuclear Generating Unit No. 3, located in
Westchester County, New York.
Environmental Assessment
Identification of Proposed Action
The proposed action would exempt the licensee from the requirements
of 10 CFR 70.24, which requires a monitoring system that will energize
clear audible alarms if accidental criticality occurs in each area in
which special nuclear material is handled, used, or stored. The
proposed action would also exempt the licensee from the requirements to
maintain emergency procedures for each area in which this licensed
special nuclear material is handled, used, or stored to ensure that all
personnel withdraw to an area of safety upon the sounding of the alarm,
to familiarize personnel with the evacuation plan, and to designate
responsible individuals for determining the cause of the alarm, and to
place radiation survey instruments in accessible locations for use in
such an emergency.
The proposed action is in accordance with the licensee's
application for exemption dated September 24, 1998.
The Need for the Proposed Action
The purpose of 10 CFR 70.24 is to ensure that if a criticality were
to occur during the handling of special nuclear material, personnel
would be alerted to that fact and would take appropriate action. At a
commercial nuclear power plant the inadvertent criticality with which
10 CFR 70.24 is concerned could occur during fuel handling operations.
The special nuclear material that could be assembled into a critical
mass at a commercial nuclear power plant is in the form of nuclear
fuel; the quantity of other forms of special nuclear material that is
stored on site is small enough to preclude achieving a critical mass.
Because the fuel is not enriched beyond 5.0 weight percent Uranium-235
and because commercial nuclear plant licensees have procedures and
design features that prevent inadvertent criticality, the staff has
determined that it is unlikely that an inadvertent criticality could
occur due to the handling of special nuclear material at a commercial
power reactor. The requirements of 10 CFR 70.24, therefore, are not
necessary to ensure the safety of personnel during the handling of
special nuclear materials at commercial power reactors.
Environmental Impacts of the Proposed Action
The Commission has completed its evaluation of the proposed action
and concludes that inadvertent or accidental criticality will be
precluded through compliance with the Indian Point Unit No. 3 Technical
Specifications, through the design of the fuel storage racks, and
through administrative controls imposed on fuel handling procedures.
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 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 exemption.
With regard to potential non-radiological impacts, the proposed
action does not involve any historic sites. It does not affect
nonradiological plant effluents and has no other nonradiological
environmental impact. Therefore, there are no significant non-
radiological 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 exemption, the staff considered
denial of the proposed action (i.e., the no action alternative). Denial
of the request would result in no change in current environmental
impacts. The environmental impacts of the proposed action and the
alternative action are similar.
[[Page 68316]]
Alternative Use of Resources
This action does not involve the use of any resources not
previously considered in the Final Environmental Statement related to
the Indian Point Unit 3, dated February 1975.
Agencies and Persons Consulted
In accordance with its stated policy, on October 28, 1998, the
staff consulted with the New York State Official, Jack 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 Commission
concludes that the proposed action 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 letter dated September 24, 1998, which is available for
public inspection at the Commission's Public Document Room, which is
located at The Gelman Building, 2120 L Street, NW., Washington, DC, and
at the local public document room located at the 100 Martine Avenue,
White Plains Public Library, White Plains, New York, 10601.
Dated at Rockville, Maryland, this 8th day of December, 1998.
For the Nuclear Regulatory Commission.
Alexander W. Dromerick,
Acting Director, Project Directorate I-1, Division of Reactor
Projects--I/II, Office of Nuclear Reactor Regulation.
[FR Doc. 98-32945 Filed 12-9-98; 8:45 am]
BILLING CODE 7590-01-P
