ML20151S113

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Environ Assessment & Finding of No Significant Impact Re Exemption from Requirements of 10CFR50,App R Concerning Separation of Auxiliary Feedwater Isolation Valves,Per 880229 Request
ML20151S113
Person / Time
Site: Millstone 
Issue date: 04/08/1988
From: Stolz J
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20151S118 List:
References
NUDOCS 8804280194
Download: ML20151S113 (3)


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7590-01 UNITED STATES NUCLEAR REGttLATORY COMMISSION NORTHEAST NUCLEAR ENERGY COMPANY, ET AL.

MILLSTONE NUCLEAR POWER STATION, UNIT NO. 2 DOCKET NO. 50-336 ENVIRONMENTAL ASSESSMENT AND FINDING OF N0 SIGNIFICANT IMPACT The U. S. Nuclear Regulatory Comission (the Comission) is considering issuance of an exemption from the requirements of Appendix R to 10 CFR Part 50 to Northeast Nuclear Energy Company, et al. (the licensee), for the Millstone Nuclear Power Station, Unit No. 2, located in New London County, Connecticut.

ENVIRONMENTAL ASSESSMENT Identificetion of proposed Action:

The exemption would grant relief from the requirements of Appendix R,Section III.G.(2)(b) as these requirements relate to the separation of Auxiliary Feedwater Isolation Valves 2-FW-43A and B.

Section III.G(2)(b) of Appendix R would require the subject valves to be separated by 20 feet, free of intervening combustibles, since these valves are in redundant trains of equipment required for post-fire, safe shutdown, of the I

reactor.

The exemption is responsive to the licensee's application for exemption dated February 79, 1988.

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The Need for the Proposed Action:

The proposed exemption is needed because the features described in the licensee's reauest regarding the existing and proposed fire protection at the plant for this item are the most practical method for meeting the intent of Appendiy R and literal compliance would not significantly enhance the fire protection capability, l

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Environnental inpa,c,t,s,pf.,t,he,P,rppp, sed _ Action: The proposed exemption will provide a degree of fire protectiori such that there is no increase in the risk of fires at this facility. Consequently, the probability of fires has not been increased and the potential post-fire radiological releases will not be greater than previcusly determined nor does the proposed exeniption otherwise affect radiological plant effluents. Therefore, the Concissic.r. concludes that there are no significant radiological environnental impacts asscciated with the proposed exenption.

With regard to potential nonradiological impacts, the proposed exen.ption involves features located entirely within the restricted area as defined in 1C CFR Part 20.

It does not affect nonradiological plant effluents and has no other environnental impact. Therefore, the Conenission concludes that there are no significant nonradiological environmental impacts associated with the proposed exemption.

Alternativ_e_totheProposedAction:

It has been concluded that there is no reasurable impact associated with the proposed exemption and associated license arendnent; ar.y alternatives to the exer.ption will have either no environmental inipact or greater environmental impact.

Alternative Use of Resources:

This action involves no use of resources not previously considered in the Final Environmental Statenents for the Millstone Nuclear Power Station, Unit No. 2.

Acencies and Persons Consulted: The NRC staff reviewed the licensee's request and did not consult other agencies or persons.

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3-FINDING OF NO SIGNIFICANT IMPACT The Connission has deterndned not to prepare an environn. ental in'pect statenent for the proposed exemption.

Based upon the foregoing environn, ental assessnent, we conclude that the proposed action will not have a significant effect on the quality o' the hun.an envirornent.

For further details with respect to this action, see the application for an. ens 34til dated February 29, 1988 which is available for public inspection at the Corrission's Public Document Room,1717 H Street, N.W., Washington, D.C.

and at the Waterford Public Library, 49 Pope Ferry Road, Waterford, Connecticut 06385.

I Dated at Rockville, Maryland, this 8th day of April 1980-FOR THE NUCLEAR REGULATORY COMMISSION h

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l iac 7 W Johd F. Stolz, Director Frp3ectDirectorateI-4 i

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Of fice of Nuclear Reactor Regulation l

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