[Federal Register Volume 59, Number 30 (Monday, February 14, 1994)]
[Unknown Section]
[Page 0]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 94-3378]


[[Page Unknown]]

[Federal Register: February 14, 1994]


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NUCLEAR REGULATORY COMMISSION
[Docket No. 50-341; FERMI 2]

 

Detroit Edison Co.; Environmental Assessment and Finding of No 
Significant Impact

    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 occurs 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 licensee reference 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 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 
increased 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 meets the underlying purpose 
of the regulations for maintaining overall containment integrity. This 
action is similar to that approved for several other facilities.

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 
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. Further, the exemption is 
not expected to have an impact on 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 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 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 exposure to plant personnel.

Alternative Use of Resources

    This action does not involve the use of resources not previously 
considered in connection with the Commission's Final Environmental 
Statement, dated August 1981, for Fermi 2.

Agencies and Persons Consulted

    The staff consulted with the State of Michigan regarding the 
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, NW., 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 III-1, Division of Reactor 
Projects--III/IV/V, Office of Nuclear Reactor Regulation.
[FR Doc. 94-3378 Filed 2-11-94; 8:45 am]
BILLING CODE 7590-01-M