ML20203M910

Safety Evaluation Supporting Amend 75 to License DPR-61

ML20203M910
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	04/29/1986
From:	Office of Nuclear Reactor Regulation
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Shared Package
ML20203M906	List: ML20203M905 ML20203M908 ML20203M910
References
NUDOCS 8605020136
Download: ML20203M910 (2)

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 75 TO FACILITY OPERATING LICENSE NO. DPR-61 CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT DOCKET NO. 50-213

1.0 INTRODUCTION

By letter dated February 21, 1986, the Connecticut Yankee Atomic Power Company (CYAPC0) submitted a request for changes to the Haddam Neck Plant technical specifications.

The amendment incorporates three new fire protection systems, which are required to protect safe shutdown equipment, into the Haddam Neck Plant technical specifications. These fire protection systems include the directional spray water suppression system in the cable-spreading area hallway, the water curtain-type spray system in the area of the service water pumps and two early warning fire detectors in the auxiliary feedwater pump room.

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 March 26, 1986 (51 FR 10455). No comments or requests for hearing were received.

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2.0 EVALUATION In submittals dated July 16, and December 15, 1982, the licensee committed to install additional fire prJtection systems to support the licensee's pending exemption requests. The staff evaluated the adequacy of the ,

proposed modifications and reported its conclusions in the exemption issued on November 14, 1984. By letter dated February 21, 1986, the licensee informed NRC that the installation of the additional fire protection systems was completed as of August 1985, and proposed to add these new fire protection features to the existing inventory of detection and suppression systems covered by the technical specification surveillance requirements. This conforms with the guidelines in the Standard Technical Specifications.

Based on our evaluation of the licensee's proposed changes to the plant

technical specifications, as delineated in the February 21, 1986 letter, I we conclude that the proposed technical specifications provide an

[ improved level of fire protection by providing additional assurance that l appropriate fire protection systems will be operable. Therefore, we l conclude that the proposed changes are acceptable.

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3.0 ENVIRONMENTAL CONSIDERATION

This amendment involves a change to a requirement with respect to the installation or use of facility components located within the restricted l area as defined in 10 CFR Part 20 and changes to the surveillance l requirements. The staff has determined that the amendment involves i 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 l 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 eli set forth in 10 CFR 51.22(c)gibility (9). Pursuant criteria forCFR to 10 categorical 51.22(b) exclusion 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 Safety Evaluation has been prepared by D. Kubicki and F. Akstulewicz.

l Dated: April 29,1986 I l

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