ML17319B626
| ML17319B626 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 09/09/1982 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17319B625 | List: |
| References | |
| NUDOCS 8211030264 | |
| Download: ML17319B626 (3) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.
60 TO FACILITY OPERATING LICENSE NO.
DPR-58 AND AMENDMENT NO.
43 TO FACILITY OPERATING LICENSE NO.
DPR-74 INDIANA AND MICHIGAN ELECTRIC COMPANY DONALD C.
COOK NUCLEAR PLANT UNIT NOS.
1 AND 2 DOCKET NOS.
50-315 AND 50-316 Introduction By letter dated August 20, 1982, the Indiana and Michigan Electric Company (the licensee) proposed changes to the Technical Specifications appended to Facility Operating License Nos.
DPR-58 and DPR-74 for the Donald C.
Cook Nuclear Plant Unit Nos.
1 and 2.
The proposed changes reflect the design of the new upper and lower containment volume radiation monitors.
The acceptability of these changes from a safety standpoint are discussed below.
Discussion and Evaluation The licensee has changed the design of the upper and lower containment Volume radiation monitors to minimize equipment failures of the type experienced with the original monitoring equipment.
The new design provides for Train A and Train 8 monitors,'ach train being capable of automatically isolating seven containment purge and exhaust valves.
Train A will be capable of isolating seven inboard purge and exhaust valves and Train B will be capable of isolating seven outboard valves, Each train consists of three channels and requires one channel to trip.
The licensee has proposed changes which are applicable to each train separately.
The proposed changes are similar to the present Technical Specifications and measurement ranges are consistent with the present Technical Specifications.
The lower containment monitors will also be used for leak detection functions 'during plant opera-tion and the Technical Specifications have been changed accordingly.
We conclude that the proposed Technical Specification changes are acceptable.
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2-Environmental Consideration We have determined that the amendments do not authorize a change in effluent types or total amounts nor an increase in power level and will not result in any significant envirormental impact.
Having made this determination, we have further concluded that the amendments involve an action which is insignificant fran the standpoint of environmental impact and, pursuant to 10 CFR f51.5(d)(4), that an environmental impact statement or negative declaration and environ-mental impact appraisal need not be prepared in connection with the issuance of these amendments.
Conclusion We have concluded, based on the considerations discussed above, that:
(1) because the amendments do not involve a significant increase in the probability or consequences of an accident previously evaluated, do not create the possibility of an accident of a type different from any evaluated previously, and do not involve a significant reduction in a margin of safety, the amendments do not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed
- manner, and (3) such activities will be conducted in compliance with the Commission's regulations and the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
Oated:
September 9,
1982 Principal Contributors:
R. Cilimberg C. Patel