ML20082J422

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Environ Assesment & Finding of No Significant Impact Re Amend Change to Tech Spec 4.6.1.3a to Be Consistent W/Std Tech Specs & Allow Continuous Pressure Testing of Containment Air Lock Door Seal Gaskets
ML20082J422
Person / Time
Site: Byron, Braidwood  Constellation icon.png
Issue date: 08/15/1991
From: Barrett R
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20082J425 List:
References
NUDOCS 9108280077
Download: ML20082J422 (3)


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UNITED STATES NUCLEAR REGULATORY COMMISSION COMMONWEALTH EDIS0N COMPANY BYRON STATION, UNIT NOS.-1 AND 2 BRAIDWOOD STATION, UNIT NOS. I AND 2 ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT The U. S. Nuclear Regulatory Commission (the Commission) is considering issuance of amendments to ility Operating License Nos. NPF-37, NPF-66, NPF-72, r

and NPF-77, issued to commonwealth Edison Company (Ceco, the licensee), for operation of the Byron Station, Unit Nos. I and 2, and Braidwood Station, Unit Nos. 1 and 2, located in Ogle County and Will County, Illinois, respectively.

ENVIRONMENTAL ASSESSMENT Identification of Proposed Action The proposed amendment would revise the provisions in the Technical Specifications (TS) relating to TS 4.6.1.3a to reflect the option of pressure testing the containment air lock gaskets with a permanently installed continuous pressurization and leakage monitoring system, or manually with precision flow measurements.

The proposed action is in accordance with the licensee's application for amendment dated October 4, 1988. That application was supplemented by letters dated August 14, 1989, March 20 and Aptil 8, 1991, which provided additional details but did not change the substance of the requested amendment.

The Need for the Proposed Action The propcv d change to the TS is required in order to provide the licensee an optio1 to use a continuous pressure testing method of the containment air lock door seal gaskets in lieu of manual testing which 9108280077 910815 PDR~ ADOCK 05000454 p

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_ reflects the NRC staff's positim regarding the 72-hour air lock oNrability test in NUREG-0452, Revision 4a, " Standard Technical Specifications for Westinghouse Pressurized Water Reactors."

Environmental Impacts of the Proposed Action The Commission has completed its evaluation of the proposed revision to the TS and concludes that use of a permanently installed continuous pressuri-zation and leakage monitoring system would not increase the probability or consequences of accidents, 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 non-radiological impacts, the proposed change to the TS involves systems located within the restricted area as defined in 10 CFR Part 20.

It does not affect non-radiological plant effluents and has no other environmental impact. Therefore, the Commission concludes that there are no significant non-radiological environmental impacts associated l

with the proposed amendment.

The Notice of Consideration of Issuance of Amendment and Opportunity for l

Hearing in connection with this action was published in the Federal Register I

on November 4, 1988 (53 FR 44685). No request for hearing or petition for leave to intervene was filed following this notice.

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 amendment. This would not reduce environmental impacts of plant operation and would result in reduced operational flexibility.

Alternative Use of Resources This action does not involve the use of any resources not previously considered in the Final Environmental Statements for the Byron Station and Braidwood Station, dated April 1982 and June 1984, respectively.

Agencies and Persons Consulted The NRC staff reviewed the licensee's request and did not consult other agencies or persons.

FINDING 0F NO SIGNIFICANT IMPACT 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.

Accordingly, the Commission has determined not to prepare an environmental impact statement for the proposed license amendment.

For further details with respect to this action, see the application for amendment dated October 4, 1988, as supplemented August 14, 1989, March 20 and~ April 8, 1991, which are available for public inspection at the Commission's Public Document Room, 2120 L Street, N.W., Washington, D.C. and 1

at the:

for Byron, the Byron Public Library,109 N. Franklin, P. O. Box 434, Byron, Illinois 61010; for Braidwood, the Wilmington Township Public Library, l

201 S. Kankakee Street, Wilmington, Illinois 60481.

Dated at Rockville, Maryland, this 15th day of August 1991.

i FOR THE NUCLEAP REGULATORY COMMISSION

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g Ric a J. Barrett, Director Project Directorate 111-2 Division of Reactor Projects - Ill/IV/V Office of Nuclear Reactor Regulation

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