ML17325A497

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Notice of Issuance of Environ Assessment & Finding of No Significant Impact Re Issuance of Amend to License DPR-74 to Permit Replacement of Four Steam Generators in Order to Restore Plant to Original Operating Condition
ML17325A497
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 11/23/1987
From: Wigginton D
Office of Nuclear Reactor Regulation
To:
Shared Package
ML17325A495 List:
References
NUDOCS 8712040215
Download: ML17325A497 (4)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION INDIANA AND MICHIGAN POMER COMPANY L

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2 7590-01 NOTICE OF ISSUANCE OF ENVIRONMENTAL ASSESSMENT The U. S. Nuclear Regulatory Commission (NRC) is considering issuance of a license amendment to Facility Operating License No. DPR-74 issued to Indiana and Michigan Power Company (the licensee) for operation of the Donald C.

Cook Nuclear Plant, Unit No. 2, located in Berrien County, Michigan.

Identification of Pro osed Action The license amendment would permit the licensee to replace major components of the four steam generators in Cook Unit 2 in order to restore the plant to its original operating condition.

The amendment would revise the Technical Specifications in response to the licensee's application dated March 12, 1987, as supported by the Steam Generator Repair Report submitted November 7, 1986 and revised March 30 and July 24,

1987, as may be further revised based on the NRC staff's continuing review.

The NRC staff has prepared an environmental assessment of the proposed

action, "Environmental Assessment by the Office of Nuclear Reactor Regulation Related to the Repair of Steam Generators, Indiana and Michigan Electric
Company, Donald C.

Cook Nuclear Plant, Unit No. 2, Docket No. 50-316,"

dated November 23, 198?.

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Radiolo ical Im acts The licensee has taken appropriate steps to ensure that occupational doses to the work force and population will be within the limits of 10 CFR Part 20 and are below the annual dose design objectives of 10 CFR Part 50, Appendix I.

Therefore, the radiological impact of the repair project to the public and the work force will not significantly affect the human environment.

Nonradiolo ical Im acts With regard to potential nonradiological impacts, the proposed license amendment involves features located entirely within the restricted area as defined in 10 CFR Part 20. It does not affect nonradiological plant effluents.

Any such effluents will be controlled by the licensee under existing plans to:

prevent or mitigate the impact of such effluents.

The licensee will control noisy operations of construction machinery and will restore any area inadvert-ently disturbed.

Therefore, the Commission concludes that there are no signifi-cant nonradiological environmental impacts associated with the proposed license amendment.

FINDING OF NO SIGNIFICANT IMPACT The staff has reviewed the proposed steam generator repair program and the proposed amendment relative to the requirements set forth in 10 CFR Part 51.

Based upon the environmental assessment, the staff concluded that there are no significant radiological or nonradiological impacts associated with the

4-proposed action and that the proposed action will not have a significant effect on the quality of the human environment.

Therefore, the Commission has determined, pursuant to 10 CFR 51.31, not to prepare an environmental impact statement for the proposed amendment.

For further details with respect to this action, see (1) the Environmental Assessment dated November 23, 1987; and (2) the application for amendment dated March 12, 1987 as supported by an earlier transmittal dated November 7, 1986 with the Steam Generator Repair Report that was later revised on March 30 and July 24, 1987.

These documents are available for public inspection at the Commission's Public Document

Room, 1717 H Street, NW.,

Washington, DC, and at the Maude Preston Palenske Memorial Library, 500 Market Street, St. Joseph, Michigan 49085.

Dated at Bethesda, Maryland, this 23rd day of November 1987.

FOR THE NUCLEAR REGULATORY COMMISSION David L. Wiggin o

, Acting Director Project Directorate III-3 Division of Reactor Projects