ML20100F473
| ML20100F473 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 11/06/1984 |
| From: | Lainas G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20100F476 | List: |
| References | |
| TAC-53456, TAC-53457, NUDOCS 8412060599 | |
| Download: ML20100F473 (3) | |
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7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION NORTHERN STATES POWER COMPANY DOCKET N05. 50-282 AND 50-306 NOTICE OF ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT The U. S. Nuclear Regulatory Commission (the Commission) is considering the granting of relief from certain requirements of the ASME Code,Section XI, "R'ul'es for Inservice Inspection of Nuclear Power Plant Components" to the
' Northern States Power Company (the licensee), which would revise the first
. ten-year inservice inspection program for the Prairie Island Nuclear-Generating Plant, Unit Nos. 1 and 2.
The ASME Code requirements are incorporated by reference into the Commission's rules and regulations in 10 CFR Part 50.
ENVIRONMENTAL' ASSESSMENT Identification of Proposed Action: By letters dated December 22, 1983, March 9 and June 11, 1984, Northern States Power Company, the licensee, requested relief from the requirements set forth in the ASME Boiler and Pressure Vessel Code Section XI related to the Inservice Inspection (ISI) program and the Inservice Testing of Pumps and Valves (IST) covering the second ten-yeer I
interval. The licensee has determined that these requirements are impractical at the Prairie Island Nuclear Generating Plant Unit Nos. I and 2 for the second ten-year inspection program.
8412060599 841106 gDRADOCK05000g
. The Need for the Proposed Action:
If reliefs are not granted, the licensee will be subjected to unnecessary burdens serving no practical purposes and will be unable to utilize the latest version of the ASME code. As stated above, the licensee has determined that these requirements are impractical.
The NRC staff agrees with the licensee's findings.
' Environmental Impact of the Proposed Action:
Our evaluation of the proposed requests for relief from the ASME Code requirements indicates that the relief will not, in any way, reduce the integrity of safety systems.
Accordingly, post-accident radiological releases will not be greater than previously determined nor does the proposed relief otherwise affect radiological plant effluents, and there is no significant ircrease in occupational exposures. Therefore, the Commission concludes that there-are no significant radiological environmental impacts associated with this proposed relief.
With regard to potential non-radiological impacts, the proposed relief involves systems 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.
Therefore, the Commission concludes that there are no significant non-radiological environmental impacts associated with the proposed relief.
Alternative Use of Resources:
This action involves no use of resources not previously considered in the Final Environmental Statement (construction permit and operating license) for the Prairie Island Nuclear Generating Plant Unit Nos. I and 2.
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. 1 Acencies and Persons Consulted: The NRC staff reviewed the licensee's requests and did not consult other agencies or persons.
FINDING 0F NO SIGNIFICANT IMPACT The Commission has determined not to prepare an environmental impact statement for the proposed reliefs.
Based upon the foregoing environmental assessment, we conclude that the proposed action will not have a significant effect on the quality of the human environment.
For further details with respect to this action,;see the licensee's letters dated December 22, 1983 and March 9 and June 11, 1984, which are available for public inspection at the Commission's Public Document Room, 1717 H Street, N.W., Washington, D.C., and Environmental Conservation Library, Minneapolis Public Library, 300 Nicollet Mall, Minneapolis, Minnesota 55401.
Dated at Bethesda, Maryland this 6th day of November,1984..
FOR THE NUCLEAR REGULATORY COMMISSION LI M lGus C. Lainas, Assistant Director
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for Operating Reactors Division of Licensing Office of Nuclear Reactor Regulation
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