ML20072S720
| ML20072S720 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 09/06/1994 |
| From: | Hannon J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20072S723 | List: |
| References | |
| NUDOCS 9409140210 | |
| Download: ML20072S720 (4) | |
Text
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7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION CLEVELAND ELECTRIC ILLUMINATING COMPANY. ET AL.
DOCKET N0.C$0-440 PERRY NUCLEAR POWER PLANT. UNIT NO. 1 ENVIRONMENTAL ASSESSMENT AND FINDING 0F 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 l
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 ProDosed 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.
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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 j
criticality accident requirements is based on the original design for radiation monitoring at PNPP as discussed in a Safety Evaiuation 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 I
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.
j 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 Because 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.
i 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.
Aaencies 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 environmentcl 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, D.C. 20555 and at the local public document room at the Perry Public Library, 3753 Mair. Street, Perry, Ohio 44081.
Dated at Rockville, Maryland, this 6th day of September 1994.
FOR THE NUCLEAR REGULATORY COMMISSION ORIGINAL SIGNED BY:
John N. Hannon, Director Project Directorate III-3 Division of Reactor Project - III/IV Office of Nuclear Reactor Regulation
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