[Federal Register Volume 59, Number 178 (Thursday, September 15, 1994)]
[Unknown Section]
[Page 0]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 94-22869]
[[Page Unknown]]
[Federal Register: September 15, 1994]
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NUCLEAR REGULATORY COMMISSION
[Docket No. 50-440]
Cleveland Electric Illuminating Co., et al.; Perry Nuclear Power
Plant, 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 the requirements of 10 CFR
70.24 for Facility Operating License No. NPF-58 issued to the Cleveland
Electric Illuminating Company, Centerior Service Company, Duquesne
Light Company, Ohio Edison Company, Pennsylvania Power Company, and
Toledo Edison Company (the licensees) for operation of the Perry
Nuclear Power Plant (PNPP), Unit No. 1, located in Lake County, Ohio.
Environmental Assessment
Identification of Proposed Action
The proposed action would exempt PNPP from the requirements of 10
CFR 70.24(a)(1) to install a criticality monitoring system for the
handling, use, and storage of special nuclear material in the form of
unirradiated nuclear fuel assemblies and 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
and to conduct drills and designate responsible individuals for such
emergency procedures.
The proposed action is in accordance with the licensee's
application for exemption dated February 28, 1992.
The Need for the Proposed Action
Power reactor license applicants are evaluated for the safe
handling, use, and storage of special nuclear materials. The proposed
exemption from criticality accident requirements is based on the
original design for radiation monitoring at PNPP as discussed in a
Safety Evaluation Report, NUREG-0887. The exemption was granted with
the original Part 70 license but it expired with the issuance of the
Part 50 license when the exemption was inadvertently not included in
that license. Therefore, the exemption is needed to clearly define the
design of the plant as evaluated and approved for licensing.
Environmental Impact of the Proposed Action
The NRC staff 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 Perry Technical Specifications,
facility procedures, and compliance with the restrictions placed on the
exemption. The restrictions are: personnel involved in fuel handling
activities are trained in the radiological consequences of fuel
handling prior to participating in fuel handling activities; equipment
used in fuel handling activities is preoperationally tested;
criticality analyses are performed and maintained to ensure criticality
cannot result when stored fuel assemblies are optimally moderated; fuel
enrichments are less than 5 weight-percent U-235; a documented fuel
assembly storage plan is in effect allowing storage of fuel only in
authorized locations; fuel storage containers are stacked no more than
three high; reactor engineer or licensed reactor operator will verify
proper spacing of fuel assemblies during receipt, inspection, and
storage; and the minimum edge-to-edge distance between a group of three
fuel assemblies and all other fuel assemblies shall be 12 inches. Since
these measures provide assurance that criticality will not occur during
receipt, inspection, use, and handling and storage of fuel, this is an
acceptable alternative to a monitoring system. The exemption from 10
CFR 70.24(a)(3) does not preclude maintaining emergency procedures for
fuel handling accidents as discussed in Chapter 15 of the Safety
Analysis Report. Since the proposed exemption does not otherwise affect
radiological plant effluents nor cause any significant occupational
exposures, the NRC staff concludes that there are no radiological
environmental impacts associated with the proposed exemption.
With regard to potential nonradiological impacts, the proposed
exemption involves systems located within the restricted area as
defined in 10 CFR Part 20. It does not affect nonradiological plant
effluents and has no other environmental impact. Therefore, the NRC
staff concludes that there are no significant nonradiological
environmental impacts associated with the proposed amendment.
Alternative to the Proposed Action
Becuase the Commission's staff has concluded that there are no
significant environmental impacts associated with the proposed action,
any alternatives would have either no significantly different
environmental impact or greater environmental impact.
The principal alternative would be to deny the requested exemption.
This would not reduce environmental impacts as a result of plant
operations.
Alternative Use of Resources
This action does not involve the use of resources not previously
considered in the Final Environmental Statement related to operation of
the Perry Nuclear Power Plant, Units 1 and 2, dated August 1982.
Agencies and Persons Consulted
The NRC staff consulted with the Ohio State official regarding the
environmental impact of the proposed action. The state official had no
comments.
Finding of No Significant Impact
Based upon the foregoing environmental assessment, the NRC staff
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 exemption.
For further details with respect to the proposed action, see the
licensee's exemption request dated February 28, 1992, which is
available for public inspection at the Commission's Public Document
Room, Gelman Building, 2120 L Street, NW., Washington, DC 20555 and at
the local public document room at the Perry Public Library, 3753 Main
Street, Perry, Ohio 44081.
Dated at Rockville, Maryland, this 6th day of September 1994.
For the Nuclear Regulatory Commission.
John N. Hannon,
Director, Project Directorate III-3, Division of Reactor Project--III/
IV, Office of Nuclear Reactor Regulation.
[FR Doc. 94-22869 Filed 9-14-94; 8:45 am]
BILLING CODE 7590-01-M
