Consumers Power Company Big Rock Point Plant; Environmental Assessment and Finding of No Significant Impact

Federal RegisterJan 5, 1996

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NUCLEAR REGULATORY COMMISSION

[Docket No. 50-155]

Consumers Power Company Big Rock Point Plant; Environmental

Assessment and Finding of No Significant Impact

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

considering issuance of an exemption from certain requirements of 10

CFR Part 50, Appendix J, Paragraph III.D.1.(a), Type A Tests, to the

Consumers Power Company (CPCo or the licensee), for operation of the

Big Rock Point Plant (BRP), located in Charlevoix County, Michigan.

Environmental Assessment

Identification of the Proposed Action

The proposed action would allow an exemption from the requirement

of 10 CFR Part 50, Appendix J, [Option A], Paragraph III.D.1.(a), for a

one-time schedular extension for the Type A test (containment

integrated leak rate test (ILRT)) of approximately 12 months, from the

1996 refueling outage to the 1997 refueling outage.

The proposed action is in accordance with the licensee's

application for exemption dated November 8, 1995.

The Need for the Proposed Action

The current ILRT requirements for Big Rock Point as set forth in

Appendix J, are that a set of three Type A tests must be performed at

approximately equal intervals during each 10-year period service

period. Also, the third test of each set shall be conducted when the

plant is shut down for the 10-year plant inservice inspections (ISI).

The previous Type A test was performed in Feburary 1992. The first of

the fourth 10-year period Type A tests is currently scheduled to be

performed in January 1996.

The licensee has requested a schedular exemption from the

requirement in 10 CFR Part 50, Appendix J, [Option A], Section

III.D.1.(a) to perform certain Type A tests at ``approximately equal

time intervals.'' Specifically, the proposed exemption would allow CPCo

to delay the Type A test until the January 1997 refueling outage. The

interval between the Type A tests would increase from 47 months to 59

months.

Environment Impacts of the Proposed Action

The Commission has completed its evaluation of the proposed action

and concludes that the proposed one-time exemption would not increase

the probability or consequences of accidents previously analyzed and

the proposed one-time exemption would not affect facility radiation

levels or facility radiological effluents. The licensee has analyzed

the results of previous Type A tests performed at the Big Rock Point

Plant to show adequate containment performance. The licensee will

continue to be required to conduct Type B and Type C local leak rate

tests which historically have been shown to be the principal means of

detecting containment leakage paths with the Type A tests confirming

the Type B and C tests results. It is also noted that the licensee

would perform a general inspection of accessible interior or exterior

surfaces of the containment structures and components although it is

only required by Appendix J to be conducted in conjunction with Type A

tests. The NRC staff considers that these inspections, though limited

in scope, provide an important added level of confidence in the

continued integrity of the containment boundary.

The change will not increase the probability or consequences of

accidents, no changes are being made in the types of any effluents that

may be released off site, and there is no significant increase in the

allowable individual or cumulative occupational radiation exposure.

Accordingly, the Commission concludes that there are no significant

radiological environmental impacts associated with the proposed

exemption.

With regard to potential nonradiological impacts, the proposed

exemption does involve features located entirely within the restricted

area as defined in 10 CFR Part 20. It does not affect nonradiological

plant effluents and has no other environmental impact. Accordingly, the

Commission concludes that there are no significant nonradiological

environmental impacts associated with the proposed exemption.

Alternatives to the Proposed Action

Since the Commission has concluded there is no measurable

environmental impact associated with the proposed action, any

alternatives with equal or greater environmental impact need not be

evaluated. As an alternative to the proposed action, the staff

considered denial of the proposed action. Denial of the application

would result in no change in current environmental impacts. The

environmental impacts of the proposed action and the alternative action

are similar.

Alternative Use of Resources

This action does not involve the use of any resources not

previously considered in the Final Environmental Statement Related to

the Operation of Big Rock Point Plant.

Agencies and Persons Consulted

In accordance with its stated policy, on November 20, 1995, the

staff consulted with the Michigan State official, Mr. Dennis Hahn of

the Nuclear Facilities and Environmental Monitoring Section, Office of

the Department of Public Health, regarding the environmental impact of

the proposed action. The State official had no comments.

Finding of No Significant Impact

Based upon the environmental assessment, the Commission 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

proposed action.

[[Page 423]]

For further details with respect to the proposed action, see the

licensee's letter dated November 8, 1995, which is available for public

inspection at the Commission's Public Document Room, The Gelman

Building, 2120 L Street, NW., Washington DC, and at the local public

document room located at the North Central Michigan College, 1515

Howard Street, Petoskey, MI 49770.

Dated at Rockville, Maryland, this 19th day of December 1995.

For the Nuclear Regulatory Commission.

Linh N. Tran,

Project Manager, Project Directorate III-I, Division of Reactor

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

[FR Doc. 96-145 Filed 1-4-96; 8:45 am]

BILLING CODE 7590-01-P

This is a copy of a public record, reproduced as it was published. It is not legal advice, and it may not be the version a court would rely on. Check the official source before you cite it.

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