ML20056H141
| ML20056H141 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 08/18/1993 |
| From: | Bajwa S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20056H142 | List: |
| References | |
| NUDOCS 9309080285 | |
| Download: ML20056H141 (6) | |
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7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION BRUNSWICK STEAM ELECTRIC PLANT UNITS 1 AND 2 CAROLINA POWER & LIGHT COMPANY. ET AL.
DOCKET NOS. 50-325 AND 50-324 ENVIRONMENTAL ASSESSMENT AND FINDING 0F NO SIGNIFICANT IMPACT The U.S. Nuclear Regulatory Commission (the Commission) is considering issuance of amendments ta Facility Operating License Nos. DPR-71 and OPR-62 issued to Carolina Power & Light Company (CP&L or the licensee) for operation of the Brunswick Steam Electric Plant, Units 1 and 2 (BSEP),
located in Brunswick County, North Carolina.
ENVIRQNMENTAL ASSESSMENT Identification of the Proposed Action:
The proposed amendments would revise the Technical Specifications (TS) to reflect the replacement of existing Riley, GEMAC and Fenwal steam leak detection equipment with General Electric NUMAC leak detection equipment.
The proposed amendments would also revise surveillance requirements for the steam leak detection instrumentation associated with the reactor water cleanup system, the high pressure coolant injection system, and the reactor core isolation cooling system.
The Need for the ProDosed Action:
The proposed changes are needed so modifications can be made to upgrade the steam leak detection system prior to startup from the current outage.
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- l Environmental Impacts of the Proposed Action:
The staff has evaluated the proposed TS amendment and finds that the j
only line break for which the detection and/or mitigation action will be any different after the proposed modification is the reactor water cleanup (RWCU) cold leak, as mitigated by the differential flow instrumentation.
The isolation delay on this break will be increased from 45 seconds to 30 minutes.
The types of potential effluents remain unchanged.
The increased isolation time delay will result in a proportional increase in the amount of potential effluent.
General Electric has evaluated the consequences of a 300 gal / min RWCU systed cold water leak remaining unisolated for 30 minutes in its report GE-NE-770-14-0592, which was docketed by the licensee January 13, 1993.
The staff performed independent calculations, utilizing a reactor coolant concentration of 4 uCi/gm as the concentration for the release.
This value was chosen because the coolant concentration could be this high before technical specifications require the unit to be shut down.
Based upon this coolant concentration, a partition factor of 0.1 and a 300 gallon / min release rate for 30 minutes, doses were calculated.
Thyroid doses 11.9, 5.9, and 1.2 rem, were calculated for the control room operators, the members of the public at the site boundary, and tSe low population zone, respectively.
These doses are within the limits of 10 CFR Part 100 and are acceptable and demonstrate that changing the RWCU system isolation differential flow time delay trip setpoint and the allowable value from less than or equal to 45 seconds to less than or equal to 30 minutes is acceptable from a radiological dose aspect.
Therefore, there will not be a significant increase in the types or amounts of any effluent that may be released offsite.
and
. The proposed changes do not increase the probability or consequences of accidents.
The staff has determined that the proposed changes do not alter any initial condition assumed for the design basis accidents previously evaluated or change operation of safety systems utilized to mitigate the design basis accidents.
No changes are being made in the types of any effluents tnet may be released offsite, and there is no significant increase in che allowable individual or cumulative occupational radiation exposure.
Accordingly, the staff concludes that proposed action would result in no significant radiological environmental impact.
With regard to potential nonradiological impacts, the proposed changes to the TS involve components in the plant which are located within the restricted area as defined in 10 CFR Part 20.
It does not affect nonradiological plant effluents and has no other environmental impact.
Therefore, the staff concludes that there are no significant nonradiological environmental impacts associated with the proposed amendments.
Alternatives to the Prooosed Action:
Since the Commission has concluded that there are no significant environmental effects that would result from the proposed actions, any alternatives with equal or greater environmental impacts need not be evaluated.
The principal alternative would be to deny the licensee's 1
. request for amendments.
This would not reduce environmental impacts of plant operation.
Alternative Use of Resources:
This action does not involve the use of resources not previously considered in the Final Environmental Statement (FES) for the Brunswick Steam Electric Plant, Units 1 and 2, dated January 1974.
Acencies and Persons Consulted:
The NRC staff reviewed the licensee's request and did not consuit other agencies or persons.
The staff consulted with the State of North Carolina regarding the environmental inpact of the proposed action.
The State had no comments.
FINDING OF NO SIGNIFICANT IMPACT Based on the foregoing 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 license amendments.
For further details with respect to this action, see the epolication for amendment dated September 14, 1992, as supplemented January 13, January 25, February 8, May 11, May 16, May 21, June 18, July 8 and July 26, 1993, which is available for public inspection in the Commission's Public Document Room, the Gelman Building, 2120 L Street, NW., Washington, DC 20555, and the local public document room located at the University of North Carolina at Wilmington, William Madison Randall Library, 601 S.
College Road, Wilmington, North Carolina 28403-3297.
. Dated at Rockville, Maryland this 18th day of August 1993.
i FOR THE NUCLEAR REGULATORY COMMISSION q
Singh S. Bajwa, Acting Director Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation e
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