ML20211D365

Safety Evaluation Supporting Amend 115 to License NPF-1

ML20211D365
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	05/29/1986
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20211D350	List: ML20211D345 ML20211D358 ML20211D365
References
NUDOCS 8606120829
Download: ML20211D365 (2)

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT N0.115 TO FACILITY OPERATING LICENSE NO. NPF-1 PORTLAND GENERAL ELECTRIC COMPANY THE CITY OF EUGENE, OREGON PACIFIC POWER AND LIGHT COMPANY TROJAN NUCLEAR PLANT DOCKET NO. 50-344

• - INTRODUCTION By letters dated November 1, 1985, as revised January 28, 1986, Portland General Electric (PGE) requested changes to the Trojan Technical Specification 3/4.1.3, " Movable Control Assemblies". The proposed changes include minor editorial changes and a slight format change as well as the major technical change which is a new ACTION 3.1.3.1C regarding electrical operability. .

DISCUSSION AND EVALUATION The proposed. Technical Specification change (ACTION 3.1.3.1C) would allow operation to continue for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for diagnosis and repair, for the case where one or more control rod assemblies are electrically inoperable. The existing Trojan Technical Specification requires the Plant to be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. A rod that is inoperable due to being untrippable is a more significant failure than a rod that cannot be moved due to an electrical failure but is still trippable. The change in ACTION distinguishes between these failures and requires the existing restrictive ACTION for the former while allowing more time for repair of the rod (s) that cannot be moved due to an electrical failure.

Based on our review, we find the proposed changes to the Trojan Technical Specification as requested by PGE, to be< acceptable.

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.

The staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents l

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that may be released offsite, and that there is no significant incr; case in individual or cumulative occupational radiation exposure. The Commission has previously published a proposed finding that the amendment involves no significant hazards consideration and there has been no public comment on such finding. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 951.22(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 be conducted in compliance with the Commission's regulations, and the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

Dated: May 29, 1986 PRINCIPAL CONTRIBUTOR:

M. Chatterton O

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