ML20236A743

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Environ Assessment & Finding of No Significant Impact Supporting Util 860121 & 1021 Requests for Exemption from 10CFR50,App R,Section Iii.J Re Requirements for Emergency Lighting Units Covering Areas W/Safe Shutdown Equipment
ML20236A743
Person / Time
Site: Beaver Valley
Issue date: 07/20/1987
From: Stolz J
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20236A714 List:
References
NUDOCS 8707280200
Download: ML20236A743 (3)


Text

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l 7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION DUQUESNE LIGHT COMPANY l OHIO EDIS0N COMPANY l

PENNSYLVANIA POWER COMPANY j DOCKET NO. 50-334 ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT The U.S. Nuclear Regulatory Comission (the Commission) is considering issuance of an exemption from certain requirements of Appendix R to 10 CFR 50 I

, to Duquesne Light Company, Ohio Edison Company and Pennsylvania Power Company (the licensee), for the Beaver Valley Power Station, Unit No.1, located in Shippingport, Pennsylvania.

ENVIRONMENTAL ASSESSMENT Identification of Proposed Action: l

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The exemption would allow deviations from the requirements of Section III.J of Appendix R (Fire Protection) to 10 CFR 50 regarding requirements for emergency lighting units covering areas with safe shutdown equipment.

The requested exemption is responsive to Duquesne Light Company's application  ;

dated January 21, 1986 and supplemented by letter dated October 21, 1986.

The Need for the Proposed Action: l The proposed exemption is needed because special circumstances are present in that literal application of the regulation is not necessary to achieve the underlying purposes of the regulation; features comparable with the requirements i

8707280200 8701E20 i PDR ADOCK 05000334' i F PDR

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-P-of the regulation are available.

If the exemption is not granted, additional costs would be incurred by the licensee with no increase in the degree of sa .

Environmental Impacts of the Proposed Action:

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The proposed exemption will provide assurance of fire protection that is equivalent to that required by Appendix R such that there is no increase in the risk of fires at the facility.

I The probability of accidents has not been increased 6nd the post-accident radiological releases will not be greater than

  • previously determined, nor does the proposed exemption otherwise affect radiological plant effluents.

Therefore, the Comission concludes that there are no significant radiological environmental impacts associated with this proposed exemption.

With regard to potential nonradiological impacts, the proposed exemption involves features located entirely 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 Comission concludes that there are no significant nonradiological environmental impacts associated with the proposed exemption.

Alternative Use of Resources:

This action involves no use of resources not previously considered in the Final Environmental Statement (construction pennit and operating r license) f the Beaver Valley Power Station, Unit No.1.

Agencies and Persons Consulted:

i, The NRC staff reviewed the licensee's request and did not consult other agencies or persons.

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i FINDING OF NO SIGNIFICANT IMPACT Based upon the foregoing environmental assessment, the. Commission concludes l

l that the proposed action will not have a significant effect on the quality of the human environment. The Commission has, therefore, determined not to prepare an environmental impact statement for the proposed exemption.

For further details with respect to this action, see the application for the exemption dated January 21, 1986, as supplemented by letter dated October 21, 1986, which is available for public inspection at the Commission's Public

-l Document Room,1717 H Street, N.W., Washington, D.C., and at the B. F. Jones

. Memorial Library, 663 Franklin Avenue, Aliquippa, Pennsylvania 15001.

Dated at Bethesda, Maryland this 20th day, of July,1987.-

THE NUCLEAR GUL ORY C MMISSION

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J . Stolz, Director et Directorate I-4 sion of Reactor Pr ects I/II j

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