[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