ML20135J100
| ML20135J100 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 09/20/1985 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20135J101 | List: |
| References | |
| NUDOCS 8509250235 | |
| Download: ML20135J100 (3) | |
Text
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7590-01
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UNITFP STATES HUCLEAR REGULATORY C0FNISSION b.
COMMONWEALTH EDTSON COMPANY DOCKET NO. 50-249 ENVIRONMENTAL ASSESSMENT AND FIMDitt 0F N0 SIGNIFICANT IMPACT The U.S. Nuclear Regulatory Commission (the Commission) is considering issuance of an exemption from certain testing requirements of Appendix J to 10 CFR Part 50 to the Commonwealth Edison Company (Ceco) (the licensee) for Dresden Nuclear Power Station, Unit No. 3 located at the licensee's site in Grundy County, Illinois.
ENVIRONMENTAL ASSESSME.iT Identification of Proposed Action:
The proposed action would grant an exemption from certain requirements of Appendix J to 10 CFR Part 50 for type B and C testing of certein valves, vents, drains, sumps and penetrations which maintain containment integrity at design bases accident conditions. The. exemption is strictly schedular ir that it would allow a 30-day extensicn of the 2-year test interval for the above components required by Appendix 0.
The Need for the Proposed Action:
The licensee shut down for its Cycle 9 refueling outage on September 30, 1983 and was scheduled to shut down for its Cycle 10 refueling outage in the Spring of 1985. However, because of an unanticipated 4-month outage extension in 1984, the shutdown for refuelino and other modifications has been extended to October 26, 1985. This will cause CECO to exceed the 2-year test interval required by Appendix J for type B and C testing of certain 050 250235 050920 DR ADOCK O 29
7590-01
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Environmental Impact of -the Proposed Action:
The proposed exemption affects only the interval between the test of certain components required te essure containment integrity. Because the operational period of these components will be shortened oue to the aforenentioned 4-month Cycle 9 refueling outage extension, the operational challenge to these components has been less than usually occurs in the 2-year test interval. Thus, post-accident radiological releases will not differ from those determined previously and the proposed exemption does not otherwise affect facility radiological effluent or occupational exposures.
With regard to potential nonradiological irpacts, the proposed exemption does not affect plant nonradiological effluents and has no other environmental irpect. Therefore, the Commission concludes there are no measurable radiological or nonradiological environmental impacts associated with the proposed exemption.
Alternatives to the Proposed Action:
Since the Commission has concluded there is no measurable environmentel impact associated with the proposed exemption, any alternatives with equal or greater environmental inpact need not be evaluated. The principal alternative to the exemption would be to require rigid compliance with 'the Appendix J requirements. Such action would not enhance the protection of the environment and would result in unjustified costs.
Alternative Use of Resources:
This action does not involve the use of resources not considered previously in the Final Environmental Statement for Dresden Unit 3.
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. Acencies and Persons Consulted:
The NRC staff reviewed the licensee's request and did not consult other agencies or persons.
FINDING OF NO SIGNIFICANT IMPACT The Commission has determined not to prepare an environmental impact statement for the proposed exemption.
Based upon the environmental assessment, the NRC staff concludes that the proposed action will not have a significant effect on the quality of the hu' man environment.
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For further details with respect to this proposed action, see the
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licensee's letter dated August 26, 1985. This letter is available for public inspection at the Commission's Public Document Room,1717 H Street, N.W., Washington, D.C. and at the Morris Public Library, 604 Liberty Street, Morris, Illinois 60451.
Dated at Bethesda, Maryland this 20 day of September 1985.
FOR THE NUCLEAR REGULATORY COMMISSION f
Dennis M. Crutc t e d, ssistant Director for Safety Assessment Division of Licensing L
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