ML20126E712

Safety Evaluation Supporting Amend 74 to License DPR-6

ML20126E712
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	06/07/1985
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20126E694	List: ML20126E691 ML20126E700 ML20126E712
References
NUDOCS 8506170190
Download: ML20126E712 (2)

Text

UNITED STATES of

! o NUCLEAR REGULATORY COMMISSION

$ j WASHINGTON, D. C. 20555

• %...../

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIOM SUPPORTING AMENDMENT NO. 74 TO FACILITY OPERATING LICENSE NO. DPR-6 CONSilMERS POWER COMPANY BIG ROCK POINT PLANT DOCKET NO. 50-155

1.0 INTRODUCTION

In an application dated November 14, 1984, Consumers Power Company (CPC)

= (the licensee) proposed to modify the Pig Pock Point Technical Specifications (TSs) to include the recently modified Reactor Enclosure Treated Waste Line

. Isolation Valve, CV-4049 as an automatic containment isolation valve, in the list of automatic containment isolation valves which are tested for operability and local leakage.

A Notice of Consideration of Issuance of Amendment to License and Proposed No Significant Hazards Consideration Determination and Opportunity for Hearing related to the requested action was published in the Federal Register on February ?7, 1985 (50 FR 7985). No public coments or requests for hearing were received.

2.0 EVALUATION The Reactor Enclosure Treated Waste Line Isolation Valve (CV-4049), was converted from a hand-switch operated valve to an automatic closure valve to resolve Systematic Evaluation Progran (SEP) Topic VI-4, Containment Isolation System concerns on local isolation of valves on non-safety systems.

CV-4049 was originally a normally closed valve inside containment which failed closed on loss of control air or electrical power and was remotely operable by a hand switch in the control room. A check valve inside containment was also in series with CV-4049. This arrangement did not meet General Design Criteria (GDC) 55 or 56 because CV-4049 was not an automatic isolation valve and because both valves were located inside containment. By letter dated February 2, 1984, CPC committed to install en automatic operator on CV-4049. In Section 4.20.4 of the Integrated Plant Safety Assessment for Big Rock Point (NUREG-0828), the NRC concluded that the relocation of CV-4049 outside containment to mcet GDC 55 and 56 would not significantly affect the penetration failure probability and was not required. Based upon the above discussion, the staff concludes that the licensee's proposed modification and associated operability and leak testing Technical Specifications are acceptable.

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3.0 ENVIRONMENTAL CONSIDERATION

This amendment involves a change in the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes to the surveillance requirements. The staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that this amendment involves no significant hazards consideration and there has been no public comment on such finding.

Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.

4.0 CONCLUSION

. The staff has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.

5.0 ACKNOWLEDGEMENT This evaluation was prepared by R. Dudley.

Dated: June 7, 1985.

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