ML20066D350
| ML20066D350 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 01/08/1991 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20066D352 | List: |
| References | |
| NUDOCS 9101140344 | |
| Download: ML20066D350 (4) | |
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q 7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION NORTHEAST NUCLEAR ENERGY COMPANY MILLSTONE NUCLEAR POWER STATION UNIT NO. 2 DOCKET NO. 50-336 ENVIRONMENTAL A_SS_ESSMENT AND FINDING OF NO SIGNIFICA_NT IMPACT The U. S. Nuclear Regulatory Comission (the Commission) is considering issuance of an exemption from the requirements of Appendix J to 10 CFR Part 50 to hortheast Nuclear Energy Company, et al. (the licensee) for the Millstone Nuclear Power Station, Unit No. 2 located at the licensee's site in New London County, Connecticut.
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ENVIRONMENTAL ASSESSMENT Identif_ication of Proposed Action:
The licensee in a letter dated June 8,1990, requested an exemption from the requirements of 10 CFR 50, Section III.A and Section III.C of Appendix J to the extent that it requires Type C (local leak rate) testing of containment isolationvalvesinthereactorbuildingclosedcoolingwater(RBCCW) system.
One of the conditions of all operating licenses for water-cooled power reactors as specified in 10 CFR 50.54(o) is that primary reactor containments shall meet the containment leakage test requirements set forth in 10 CFR 50, i
l Appendix J.
Section III of Appendix J contains three subsections, lettered A through C, each of which _ specifies requirerr.ents for a particular aspect of
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containment leak testing. Sections III. A and III.C are the subjects of the proposed exemption request.
Specifically,Section III.A identifies certain components subject to the requirements of Section III.C and Section III C of 9101140344 910108
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, Appendix J identifies leakage testing requirements (Type C Tests) for containment isolation valves that can provide a direct connection between the inside and outside atmospheres of the primary reactor containment under nonnal operating conditions.
The licensee has stated that the exemption would not present an undue risk to the public health and safety.
The_ Need for the Proposed Action:
The exemption is needed to relieve the licensee of the requirement to provide Type C testing of the 12 containment isolation valves of the RBCCW system at Unit No. 2 of the Millstone Nuclear Power Station.
Enviornmental Impacts of the Proposed Action:
The proposed exemption from the requirements of Appendix J To 10 CFR-r i
Part 50 Sections III.A and III.C involves no changes in plant operation or any accident and thus involves no changes in plant effluents or any changes in the use of resources.
The valves in question are required to be opened-in case of an accident and thus their leak tight integrity is irrelevant. Since the minimum design pressure of the RBCCW system is 60 psig and since the maximum design pressure of the containment during an accident is 54.psig, in the event a break of the RBCCW inside the containment, the leakage through the closed isolation valves would be inside the containment and thus provide no eau.pe to the enviruinent.
If during an accident no RBCCW system were i
cperhtional, a minimum pressure of 42 psig would be maintained.
It h unlikely that the containment pressure would be maintained above 42 psig very long-and, therefore, leakage from the containment into the RBCCW would be minimal and escape would be into the enclosure building where it would be collected. Accordingly, the Consnission concludes that the proposea action would have no inpact on the environment.
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. Alternatives to the Proposed Action:
The only alternative to the proposed action would be to implement the modifications to assure leak-tight integrity of the RBCCW containment isolation valves in the closed position within the acceptance criteria specified in Appendix J.
As discussed above, since there are no environment impacts associated with the proposed action utilizing the only alternative would save any environmental costs.
_ Alternative use of Resources:
This action does not involve the use of any resources different from or beyono the scope of resources used during plant operation, which were assessed in the Final Environmental Statement relating to plant operation, dated June 1973 r
Agencies and Persons Consulted:
The Comission's staff reviewed the licensee's request that supports the proposed exemption. The staff did not consult other agencies or persons.
FINDING OF NO SIGN _IFICANT IMPACT:
Based upon the foregoing environmental assessment, the Comission 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 oroposed exemption.
For further details with respect to this action, see the request for exemption dated June 8, 1990. A copy is available for public inspection at the Comission's Public Document Room, the Gelman Building, 2120 L Street, NW, 1
, Washington, D.C. 20555, and at the local public document room located at the Learning Resources Center, Thames Valley State Technical College, 574 New London Turnpike, Norwich, Connecticut 06360.
Dated at Rockvlie, Maryland this 8th day of January,
- 1991, FOR THE Nt! CLEAR REGULATORY COMMISSION g.'A Jo TT. Stolz, Direc P ject Directorate I-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation e
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