ML20063F378
| ML20063F378 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 02/08/1994 |
| From: | Blough A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20063F384 | List: |
| References | |
| NUDOCS 9402140284 | |
| Download: ML20063F378 (4) | |
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-7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION.
DETROIT EDISON COMPANY 1
FERMI 2 DOCKET NO. 50-341 ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT f
The U.S. Nuclear Regulatory Commission (the Commission) is considering issuance of an exemption from the requirement of 10 CFR Part 50, Appendix J, Paragraph III.A.6(b) to Detroit Edison Company (the licensee), for operation of the Fermi 2 Plant, located in Monroe County, Michigan.
ENVIRONMENTAL ASSESSMENT Identification of Proposed Action The proposed action would grant an exemption from the accelerated Type A integrated leak rate test frequency requirement of Appendix J, Paragraph III.A.6(b) of 10 CFR Part 50. On May 24, 1993, the licensee requested an exemption from paragraph III.A.6(b) which requires that if two consecutive Type A tests fail to meet the acceptance criteria,-a Type A. test.
shall be performed at each plant shutdown for refueling or approximately every 18 months, whichever o:: curs first, until two consecutive Type A tests meet the acceptance criteria. -The licensee identified the cause.of the' Type A failures-as Type C local leakage which has subsequently been corrected. The licenseeL
-referenced NRC Information Notice (IN) 85-71, " Containment Integrated Leak Rate Tests," for guidance concerning the requested exemption.
IN 85-71 states that "if Type B and C leakage rates constitute an identified contributor to this failure of the as-found condition for the CILRT [ Type A containment
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9402140284 940200 PDR ADOCK 05000341-P PDR
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integrated leak rate test), the general purpose of maintaining a high degree of containment integrity might be better served through an improved maintenance and testing program for containment penetration boundaries and isolation valves.
In this situation, the licensee may submit a Corrective Action Plan with an alternative leakage test program proposal as an exemption-request for NRC staff review."
If this submittal is approved, the licensee is-allowed to implement the corrective actions in lieu of the required increase in Type A test frequency.
The Need for the Proposed Action The proposed exemption is needed because compliance to paragraph III.A.6(b) of 10 CFR Part 50, Appendix J, would result in increased costs, extended outage time and additional personnel radiation exposure in order to comply with the increased Type A test frequency.
The establishment of a Corrective Action Plan meete-the underlying purpose of the regulations for maintaining overall containment integrity. This action is similar to that approved for several other facilities.
5 Environmental Impact of the Proposed Action The proposed exemption would allow the substitution of a Corrective Action Plan in lieu of an increased test frequency for containment Type A leakage tests. The purpose of Type A testing is to ensure that the leakage through the primary reactor containment would not exceed the maximum allowable leakage during a design basis accident.
It also provides assurance 'that the Local-Leak Rate Test (LLRT) Program adequately identifies and corrects containment penetrations requiring repair. The licensee has implemented a Corrective Action Plan to correct LLRT deficiencies which have been attributed as the cause for previous Type A failures which have led to the increased testing i
frequency.
The approved Corrective Action Plan.will provide equivalent assurance of containment integrity, and will not alter the method of operation of the facility.
The only change will be, on a one-time basis, the frequency for conducting the Type A CILRT. Therefore, post-accident radiological releases will not exceed previously determined values as a result of the proposed action.
--+her, the exemption is not expected to have an impact en plant radiological effluent releases. The proposed action does have the potential to reduce occupational exposure by reducing the amount of time personnel are required to spend in a radiologically restricted area.
With regard to potential non-radiological impacts, the proposed action and related change to the Technical Specifications involve a change in the surveillance requirements and will not affect non-radiological plant effluents nor does it have any other environmental impact.
Therefore, the Commission 3
concludes that there are no significant non-radiological environmental impacts associated with the proposed amendment.
Alternative to the Proposed Action Since the Commission concluded that there are no significant environmental effects that would result from the proposed action, any alternatives with i
equal or greater environmental impacts need not be evaluated.
The principal alternative would be to deny the requested exemption and amendment.
This would not reduce environmental impacts of plant operation and would result in reduced operational flexibility and greater occupational i
exposure to plant personnel.
Alternative Use of Resources This action does not involve the use of resources not previously considered j
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in connection with the Commission's Final Environmental Statement, dated 1
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August 1981, for Fermi 2.
Aaencies and Persons Consulted The staff consulted with the State of Michigan regardira tre environmental impact of the proposed action. The State had no comments.
FINDING OF NO SIGNIFICANT IMPACT The Commission has determined not to prepare an environmental impact statement for the proposed exemption.
Based upon the foregoing environmental assessment, the staff concludes that the proposed action will not have a significant effect on the quality of the human environment.
For further details with respect to this proposed action, see the licensee's application and request for exemption dated May 24, 1993.
This document is available for public inspection at the Commission's_ Public Document Room, 2120 L Street, N.W., Washington, DC 20555, and at the local public document room located at the Monroe County Library System, 3700 South Custer Road, Monroe, Michigan 48161.
Dated at Rockville, Maryland, this 8th day of February 1994.
FOR THE NUCLEAR REGULATORY COMMISSION A. Randolph Blough, Acting Director Project Directorate 111-1 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation