ML20209D415

Safety Evaluation Supporting Amend 129 to License NPF-1

ML20209D415
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	04/22/1987
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20209D382	List: ML20209D378 ML20209D398 ML20209D415
References
NUDOCS 8704290268
Download: ML20209D415 (2)

Text

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4 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR PEACTOR REGULATION RELATED TO AMENDMENT NO. 129 TO FACILITY OPERATING LICENSE NO. NPF-1 P_0RTLAND GENERAL ELECTRIC COMPANY THE CITY OF EUGENE, OREGON PACIFIC POWER AND LIGHT COMPANY I ' TROJAN NUCLEAR PLANT DOCKET N0. 50-344

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INTRODUCTION By letters dated October 17, 1986, and January 14, 1987, the Portland General Electric Company (the licensee) submitted License Change Application (LCA) 144 for Trojan Nuclear Plant, requesting a change to the plant Technical Specification (TS) Section 4.6.3.1.2.

Technical Specification 4.6.3.1.2 currently requires containment isolation l valves to be stroke-tested during cold shutdown or refueling (MODES 5 or 6).

The proposed change will allow such testing to be performed during any mode, rather than being restricted to the shutdown'or refueling modes.

The reason for the TS change is to make the testing requirements compatible with other ESF-related TS requirements which permit such testing in operating modes I through 4 DISCUSSION AND EVALUATION From the standpoint of valve operability testing, per se, the plant operating mode in which the testing is done is not important. Rather, it is more convenient to perform the valve test during the shutdown or refueling modes.

In reviewing the proposed TS 4.6.3.1.2, the staff finds that the important elements of the testing, namely, test frequency, which valves are to be tested, '

and test procedure, will remain the same. Furthermore, with redundant containment isolation valves, containment integrity can be maintained while

( one isolation valve of a penetration is being tested.

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! Since the proposed TS provides the same level of assurance of valve operability and containment integrity as the current TS, the staff finds the

, proposed TS change acceptable.

i ENVIRONMENTAL CONSIDERATION This amendment involves a change in the installation or use of a facility j component located within the restricted area as defired in 10 CFR Part 20.

! The staff has determined that the amendment involves no significant increase in the amounts, and no significant chance in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative cccupational radiation exposure. The Commission has previously

, published a proposed finding that the amendment involves a no significant hazards consideration and there has been no public concent on such finding. Accordingly,

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the amen'dment meets the eligibility criteria for categorical exclusion set forth in 10 CFP ?51.22(c)(9). Pursuant to 10 CFR 651.22(b), no environmental impact

statement or environmental assessment need be prepared in connection with the ,

issuance of the amendment.

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 j be conducted in compliance with the Commission's regulations, and the issuance 1 of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

l Dated: April 22, 1987 1

PPINCIPAL CONTRIBUTOR:

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