ML20206M731

Safety Evaluation Supporting Amend 97 to License DPR-3

ML20206M731
Person / Time
Site:	Yankee Rowe
Issue date:	06/17/1986
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20206M703	List: ML20206M698 ML20206M718 ML20206M731
References
NUDOCS 8607010272
Download: ML20206M731 (3)

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 97 TO FACILITY OPERATING LICENSE N0. DPR-3 YANKEE ATOMIC ELECTRIC COMPANY YANKEE NUCLEAR POWER STATION DOCKET NO.50-029

1.0 INTRODUCTION

By letter dated October 15, 1985, the Yankee Atomic Electric Company (YAEC) submitted a request for changes to the Yankee Nuclear Power Station Technical Specifications (TS).

The amendment modifies the TS to add containment isolation valves for the containment breathing air system.

2.0 EVALUATION The licensee installed a containment breathing air system inside the vapor container during the 1985 refueling outage. The system includes two manual isolation valves that are normally locked closed.

The staff has evaluated the installation and associated proposed TS.

. The installation contains one locked closed valve inside containment and one locked closed valve outside containment, as required by 10 CFR Part 50, Appendix A, Criterion 56. In addition, the valves are designed with test fittings to allow type C testing in accordance with 10 CFR Part l 50, Appendix J.

The proposed change implements this modification in the TS, and the proposed change meets all applicable requirements. The staff finds, therefore, that the TS 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 area as defined in 10 CFR Part 20. The staff has determined that the amendment involves no significant increase in the am'ounts, 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 cumula-tive 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 ccncluded, based on the considerations discussed above, that:

(1) there is reasonable assurance that the health and safety of the will not be endangered by operation in the proposed manner; and such(2) public 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 Principal Contributor: J. W. Clifford

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Dated: June 17, 1986 9

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