[Federal Register Volume 63, Number 23 (Wednesday, February 4, 1998)]
[Notices]
[Pages 5821-5822]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 98-2684]
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NUCLEAR REGULATORY COMMISSION
[Docket No. 50-285]
Omaha Public Power District (Fort Calhoun Station, Unit No. 1);
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-40 issued to Omaha
Public Power District, for operation of the Fort Calhoun Station, Unit
No. 1 located in Washington County, Nebraska.
Environmental Assessment
Identification of Proposed Action
The proposed action would exempt Omaha Public Power District from
the requirements of 10 CFR 70.24, which requires in each area in which
special nuclear material is handled, used, or stored, a monitoring
system that will energize clear audible alarms if accidental
criticality occurs. The proposed action would also exempt the licensee
from the requirements of 10 CFR 70.24(a)(3) 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 August 29, 1997, as supplemented by
letter dated October 23, 1997.
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 onsite in any given location 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 there is no significant environmental impact if the
exemption is granted. Inadvertent or accidental criticality will be
precluded through compliance with the Fort Calhoun Station, Unit No. 1
Technical Specifications, the design of the fuel storage racks
providing geometric spacing of fuel assemblies in their storage
locations, and administrative controls imposed on fuel handling
procedures. Technical Specifications requirements specify reactivity
limits for the fuel storage racks and minimum spacing between the fuel
assemblies in the storage racks.
Appendix A of 10 CFR Part 50, ``General Design Criteria for Nuclear
Power Plants,'' Criterion 62, requires the criticality in the fuel
storage and handling system shall be prevented by physical systems or
processes, preferably by use of geometrically-safe configurations. This
is met at Fort Calhoun Station Unit No. 1, as identified in the
Technical Specifications and the Updated Safety Analysis Report (USAR).
The basis for the exemption is that inadvertent or
[[Page 5822]]
accidental criticality will be precluded through compliance with the
Fort Calhoun Station, Unit No. 1 Technical Specifications Sections 2.8,
2.10.1, 2.10.2, 4.4, and 4.4.1; the geometric spacing of fuel
assemblies in the new fuel storage racks and spent fuel storage pool;
and administrative controls, USAR Sections 9.5, 11.2.3, and Appendix G,
which are imposed on fuel handling procedures.
The proposed exemption would not result in any significant
radiological impacts. The proposed exemption would not affect
radiological plant effluents nor cause any significant occupational
exposures since the Technical Specifications, design controls including
geometric spacing of fuel assembly storage spaces, and administrative
controls preclude inadvertent criticality. The amount of radioactive
waste would not be changed by the proposed exemption.
The proposed exemption does not result in any significant
nonradiological environmental impacts. The proposed exemption involves
features located entirely within the restricted area as defined in 10
CFR Part 20. It does not affect non-radiological plant effluents and
has no other environmental impact. Accordingly, the Commission
concludes that there are no significant non-radiological environmental
impacts associated with the proposed action.
Alternatives to the Proposed Action
Since the Commission has concluded that there is no measurable
environmental impact associated with the proposed action, any
alternatives with equal or greater environmental impact need not be
evaluated. As an alternative to the proposed exemption, the staff
considered denial of the requested exemption. 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.
Alternative Use of Resources
This action does not involve the use of any resources not
previously considered in the Final Environmental Statement (FES) for
the Fort Calhoun Station, Unit No. 1, dated August 1972.
Agencies and Persons Consulted
In accordance with its stated policy, on January 29, 1998, the
staff consulted with the Nebraska State official, Ms. Cheryl Rodgers of
the Department of Health, regarding the environmental impact of the
proposed action. The State official had no comments.
Finding of No Significant Impact
Based upon 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 August 29, 1997, and supplemental letter dated
October 23, 1997, which is available for public inspection at the
Commission's Public Document Room, which is located at The Gelman 5
Building, 2120 L Street, NW., Washington, D. C., and at the local
public document room located at the W. Dale Clark Library, 215 South
15th Street, Omaha, Nebraska 68102.
Dated at Rockville, Maryland, this 29th day of January 1998.
For the Nuclear Regulatory Commission.
L. Raynard Wharton,
Project Manager, Project Directorate IV-2, Division of Reactor Projects
III/IV, Office of Nuclear Reactor Regulation.
[FR Doc. 98-2684 Filed 2-3-98; 8:45 am]
BILLING CODE 7590-01-P
