Indiana Michigan Power Co., D.C. Cook, Unit No. 2, Environmental Assessment and Finding of No Significant Impact

NUCLEAR REGULATORY COMMISSION

[Docket No. 50-316]

Indiana Michigan Power Co., D.C. Cook, Unit No. 2, Environmental

Assessment and Finding of No Significant Impact

The U.S. Nuclear Regulatory Commission (the Commission) is

considering issuance of an exemption from the requirements of 10 CFR

part 50, appendix J, III.D.2.(a) and III.D.3., related to Type B and C

local leak rate testing of containment isolation valves, to the Indiana

Michigan Power Company (the licensee), for operation of the D.C. Cook

Nuclear Plant, Unit 2, located in Berrien County, Michigan.

Environmental Assessment

Identification of Proposed Action

The proposed action would grant a one-time schedular exemption from

the requirements of Appendix J, paragraphs III.D.2.(a) and III.D.3 of

10 CFR part 50 and approve an extension of the 2-year period between

the performance of Type B and C leak rate test by 150 days. Appendix J

to 10 CFR part 50, paragraph III.D.2.(a), states, in part, ``Type B

tests, except tests for air locks, shall be performed during reactor

shutdown for refueling, or other convenient intervals, but in no case

at intervals greater than 2 years.'' Paragraph III.D.3., states, ``Type

C tests shall be performed during each reactor shutdown for refueling

but in no case at intervals greater than 2 years.'' Taken together,

these sections require Type B and C containment leakage tests to be

performed at an interval not to exceed 2 years.

In a letter dated March 9, 1994, as supplemental April 13, 1994,

the licensee requested an exemption to 10 CFR part 50, Appendix J, to

allow the time between the performance of the required Type B and C

tests to exceed the 2-year maximum by up to 150 days.

The Need for the Proposed Action

The proposed exemption is needed because compliance with paragraphs

III.D.2(a) and III.D.3 of 10 CFR part 50, appendix J, would result in a

unit shutdown and additional personnel radiation exposure in order to

comply with the required Type B and C test frequency. The licensee last

conducted the required Type B and C leak rate tests during a refueling

outage in the spring of 1992. These previous leak rate tests will reach

the 2-year maximum test interval imposed by Appendix J starting on May

29, 1994. The licensee's next refueling outage is scheduled to begin in

August 1994. The extended interval between refueling outages is a

result of an equipment problem and scheduling to avoid coincident

refueling outages on both units. The exemption is requested to support

the current outage schedule and to avoid the potential for an earlier

reactor shutdown. If a forced outage is imposed to perform testing it

would present undue hardship and cost in the form of increased

radiological exposure. Furthermore, if a forced outage is imposed to

perform the required testing, an additional plant shutdown and startup

will be required. This action is similar to that approved for several

other facilities.

Environmental Impact of the Proposed Action

The proposed action includes exemptions from performing Type B and

C tests for a maximum period of 150 days beyond the required Appendix J

test intervals. As stated in 10 CFR part 50, appendix J, the purpose of

the primary containment leak rate testing requirements is to ensure

that leakage rates are maintained within the Technical Specification

requirements and to assure that proper maintenance and repair is

performed throughout the service life of the containment boundary

components. The requested exemption is consistent with the intent of 10

CFR 50.12(a), in that it represents a one-time only schedular extension

of short duration. The required leak tests will still be performed to

assess compliance with Technical Specification requirements, albeit

later, and to asure that any required maintenance or repair is

performed. As noted in paragraphs III.D.2.(a) and III.D.3 of Appendix

J, it was intended that the testing be performed during refueling

outages or other convenient intervals. Extending the Appendix J

intervals by a small amount to reach the next refueling outage will not

significantly impact the integrity of the containment boundary and,

therefore, will not significantly impact the consequences of an

accident or transient in the unlikely event of such an occurance during

the 150-day extended period.

Past Unit 2 local leak rate test data have demonstrated improving

leak rate test results. Although the As Found results for the 1989 and

1990 outages were 3.0 La and 0.74 La, respectively, which

exceeded the maximum limit of 0.6 La, the 1992 As Found was 0.18

La. The improved 1992 As Found result, which was a minor increase

from the 1990 As Left of 0.17 La, followed several corrective

actions by the licensee. The improving trend for the Type B and C

testing, well below the allowable limit, provides reasonable assurance

that the probability of exceeding the offsite dose rates established in

10 part 100 will not be increased by extending the current Type B and C

testing for a maximum of 150 days.

Thus, radiological releases will not differ from those determined

previously and the proposed exemption does not otherwise affect

facility radiological effluent or occupational exposures. The proposed

exemption will not increase the probability or consequences of any

reactor accidents. The proposed exemption does not affect plant

nonradiological effluents and has no other environmental impact.

Therefore, the Commission concludes that there are no measurable

radiological or nonradiological environmental impacts associated with

the proposed exemption.

Alternatives 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 and to require rigid compliance with the requirements of

paragraphs III.D.2.(a) and III.D.3 of appendix J to 10 CFR part 50.

Such action would not enhance the protection of the environment and

would result in unjustified burdens and costs for the licensee 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 for D.C. Cook, Units 1 and 2, dated August 1973.

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 March 9 and

April 13, 1994. 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 Maud

Preston Palenske Memorial Library, 500 Market Street, St. Joseph,

Michigan 49085.

Dated at Rockville, Maryland, this 22nd day of April 1994.

For the Nuclear Regulatory Commission.

John B. Hickman,

Acting Director, Project Directorate III-1, Division of Reactor

Projects--III/IV, Office of Nuclear Reactor Regulation.

[FR Doc. 94-10527 Filed 5-2-94; 8:45 am]

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