ML20141D446

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Safety Evaluation Supporting Amend 92 to License DPR-28
ML20141D446
Person / Time
Site: Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date: 03/27/1986
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20141D444 List:
References
NUDOCS 8604080082
Download: ML20141D446 (2)


Text

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT N0. 92 TO FACILITY OPERATING LICENSE NO. DPR-28 VERMONT YANKEE NUCLEAR POWER CORPORATION VERMONT YANKEE NUCLEAR POWER STATION DOCKET NO. 50-271

1.0 INTRODUCTION

By letter dated November 15, 1985, Vermont Yankee Nuclear Power Corporation (the licensee /VYNPC) proposed a change to Sections 3.6 and 4.6 of the Technical Specifications (TS) for the Vermont Yankee Nuclear Power Station. The proposed change would delete TS pertaining to the valves in the recirculation system equalizer lines. The Vermont Yankee plant is presently in a refueling outage which began September 21, 1985, and during which, recirculation system piping will be totally replaced. The replacement piping will not include equalizer lines between recirculation loops nor equalizer line valves. Therefore references to equalizer line valve position are no longer appropriate.

2.0 EVALUATION Presently TS require that equalizer valves be shut during both normal operation and single loop operation. These requirements were added to the TS in order to isolate the A and B recirculation loops, thereby achieving the piping configuration assured to exist in the currently applicable emergency core cooling system (ECCS) analysis. TS requiring these valves to be closed are necessary to assure the validity of the ECCS analysis.

During the present outage, the piping configuration will be changed so that the connecting lines between the A and B recirculation lines do not exist, thereby accomplishing the desired isolation in a more positive manner. Consequently, TS requiring that equalizer valves remain closed are no longer needed. There is no safety requirement that equalizer valves and lines remain. The proposed change is acceptable to the staff.

3.0 ENVIRONMENTAL CONSIDERATION

S This amendment changes a requirement with respect to installation or use of a facility component 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 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 8604080082 860327 PDR ADOCK 05000271 P

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.. 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 We have 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.

Principal Contributor:

V. Rooney Dated: March 27, 1986 s

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