ML16138A697

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Environ Assessment & Finding of No Significant Impact Re 880122 Application for Amend to Tech Specs to Increase Linear Heat Rate at 2-ft Core Elevation Level.Eis Unwarranted
ML16138A697
Person / Time
Site: Oconee  
Issue date: 04/25/1990
From: Hood D
Office of Nuclear Reactor Regulation
To:
Shared Package
ML16138A698 List:
References
NUDOCS 9005030118
Download: ML16138A697 (4)


Text

40 7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION DUKE POWER COMPANY DOCKETS NOS. 50-269, 50-270 AND 50-287 ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT The U. S. Nuclear Regulatory Commission (the Commission) is considering issuance of amendments to Facility Operating Licenses Nos. DPR-38, DPR-47, and DPR-55 issued to Duke Power Company (the licensee) for operation of the Oconee Nuclear Station, Units 1, 2 and 3, located in Oconee County, South Carolina.

ENVIRONMENTAL ASSESSMENT Identification of Proposed Action:

The proposed amendments would revise the provisions in the Technical Specifications (TSs) to allow an increase in the linear heat rate (LHR) at the 2-foot core elevation level.

TS Figure 3.5.2-16, LOCA-Limited Maximum Allowable Linear Heat, would be updated to reflect this change.

The proposed action is in accordance with the licensee's application for amendments dated January 22, 1988, as supplemented October 9, 1989.

The Need for the Proposed Action:

The proposed changes to the TSs are required to allow operation at the higher LHR.

Environmental Impacts of the Proposed Action:

The Commission has completed its evaluation of the proposed revision to the TSs. The proposed revision would allow the licensee to operate with a IRDC PD

2 higher LHR at the 2-foot core elevation for the first 1000 megawatt days per metric ton uranium (MWd/mtU) of fuel burnup. The limit would increase from 14.0 kw/ft to 14.5 kw/ft for this period of fuel burnup; the current 1000-2600 MWd/mtU burnup parameter would be deleted; and the current LHR limit for greater than 2600 MWd/mtU would apply after 1000 MWd/mtU. The limiting Final Safety Analysis Report (FSAR) accident analysis affected by this change is a large break loss of coolant accident (LOCA). Although the licensee's analysis shows an increase in peak fuel cladding temperatures as a result of this change, the maximum temperature (2028 degrees-F) remains below the maximum temperature allowed by 10 CFR 50.46(b)(1) of 2200 degrees-F. Therefore, the requested change is consistent with NRC requirements and criteria. No changes are being made in the types of any effluents that may be released offsite and there is no significant increase in the allowable individual or cumulative occupational radiation exposure. Accordingly, the Commission concludes that this proposed action would result in no significant radiological environmental impact.

With regard to potential nonradiological impacts, the proposed changes to the TSs involve systems located within the restricted area as defined in 10 CFR Part 20. These changes do not affect nonradiological plant effluents and have no other environmental impact. Therefore, the Commission concludes that there are no significant nonradiological environmental impacts associated with the proposed amendments.

Notices of Consideration of Issuance of Amendments and Opportunity for Hearing in connection with this action were published in the FEDERAL REGISTER on June 2, 1988 (53 FR 20196) and January 26, 1990 (55 FR 2720). No request

-3 for hearing or petition for leave to intervene was filed following these notices.

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 amendments. This would not reduce environmental impacts of plant operation and would prevent implementation of the modification which would provide increased operational flexibility.

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 Oconee Nuclear Station, Units 1, 2 and 3, dated March 1972.

Agencies and Persons Consulted:

The Commission's staff reviewed the licensee's request and did not consult other agencies or persons.

FINDING OF NO SIGNIFICANT IMPACT The Commission has determined not to prepare an environmental impact statement for the proposed license amendments.

Based upon the foregoing environmental assessment, we conclude that the proposed action will not have a significant effect on the quality of the human environment.

For further details with respect to this action, see the application for amendments dated January 22, 1988, as supplemented October 9, 1989, which is

-4 available for public inspection at the Commission's Public Document Room, 2120 L Street, NW., Washington, DC, and at the Oconee County Library, 501 West South Broad Street, Walhalla, South Carolina 29691.

Dated at Rockville, Maryland, this 25 day of April 1990.

FOR THE NUCLEAR REGULATORY COMMISSION Darl S. Hood, Acting Director Project Directorate 11-3 Division of Reactor Projects -

1/II Office of Nuclear Reactor Regulation