ML20141P247

Safety Evaluation Supporting Amend 111 to License NPF-1

ML20141P247
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	03/04/1986
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20141P100	List: ML20141P099 ML20141P101 ML20141P247
References
NUDOCS 8603190185
Download: ML20141P247 (2)

Text

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT' NO.111 TO FACILITY OPERATING LICENSE N0. NPF-1 PODTLAND GENERAL ELECTRIC COMPANY THE CITY OF EUGENE, OREGON PACIFIC POWER AND LIGHT COMPANY TROJAN NUCLEAR PLANT DOCKET N0. 50-344 Introduction By letter dated October II, 1985, Portland General Electric (the licensee) requested an amendment to the Technical Specifications, Appendix A, Facility Operating License No. NPF-1 for the Trojan Nuclear Plant. The application requests a change to the Technical Specifications to clarify the licensee requirements for the Containment Ventilation Isolation System (Section 4.9.9) by specifying which monitoring channels must be included in the system operability test.

Discussion and Evaluation The Trojan Technical Specification 4.9.9, which is the surveillance requirements for the Containment Ventilation Isolation System during refueling operations, currently implies that all radiation monitoring instrumentation channels must be demonstrated to initiate containment ventilation isolation on a high radiation signal. The licensee's containment monitoring system consists of four normal range channels and one accident range effluent monitoring channel. Since the accident range subsystem does not provide, nor is intended to provide, a containment isolation signal on high radiation, it is unnecessary to demonstrate its operability under Technical Specification 4.9.9.

The licensee has therefore proposed a clarification to Technical Specification 4.9.9 which specifies which monitoring channels must be included in the system oparability test. The staff has reviewed this reauest. This changed in considered a clarification of an existing Technical Specification and is, there#0re, acceptable.

Environmental Consideration This amendment involves a chance in surveillance requirements. Tbe staff has determined that the amendment involves no significant increase in the amounts B603190185 860314 fDR ADOCK 05000344 PDR

and no significant changes 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 consider-ations 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.

Conclusion We nave ccncluded, 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.

Date: March 4, 1986 Principal Contributor:

H. Gilpin l

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