ML20196C157

Safety Evaluation Supporting Amend 144 to License NPF-1

ML20196C157
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	06/22/1988
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20196C108	List: ML20196C105 ML20196C131 ML20196C157
References
NUDOCS 8807010017
Download: ML20196C157 (2)

Text

1. UNITED STATES

!" o*t NUCLEAR REGULATORY COMMISSION

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.144 TO FACILITY OPERATING LICENSE N0. NPF-1 PORTLAND GENERAL ELECTRIC COMPANY THE CITY OF EUGENE, OREGON PACIFIC _ POWER AND LIGHT COMPANY TROJAN NUCLEAR PLANT DOCKET N0. 50-344

1.0 INTRODUCTION

By letter dated April 12, 1966, Portland General Electric Company (PGE) proposed changes to the Trojan Technical Specifications (TS) that would rename the hot shutdown panel from "C-160 panel" to "Remote Shutdown .

Station," and would also delete its referenced location.

The existing C-160 panel on the 45-foot elevation of the Turbine Building is being redesigned and replacea in accordance with the requirements of 10 CFR 50.59. The objective of the replacement and relocation is to resolve a nunter of technical problems, including human engineering discrepancies and maintenance problems due to equipment accessibility and space limitations with the current panel in its present location.

This evaluation addresses only the proposed name change of the C-160 panel and the deletion of its referenced location, and does not evaluate the functional adequacy of the redesigned and relocated remote shutdown station.

2.0 Discussion and Evaluation The design function of the current C-160 panel and the new remote shutdown station is to be capable of achieving and maintaining the plant in its safe shutdown conditions from outside the control room. Various instru-ments and controls utilized during this evolution are located on these panels, among which are:

a) Auxiliary Feedwater Pump Start Controls, b) Reactor Coolant System Pressure Indication, c) Pressurizer Level Indication, d) Steam Generator Pressure and Level Indication, and e) Auxiliary Feedwater Flow Controls.

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, . Item (a) above is listed in TS Table 3.3-3, "Engineered Safety Features Actuation System Instrumentation," and Items (b), (c), (d) and (e) are listed in TS Table 3.3-9, "Remote Shutdown Monitoring Instrumentation."

The location of each of these Items as referenced by the TS is the current C-160 panel which is located on the 45 foot elevation of the Turbine Building.

Since the C-160 panel is being renamed "Remote Shutdown Station", and is also being relocated to the 45 foot elevation of the Control Building, any reference to its fomer name and location must be accordingly revised.

Based on the above, we find the proposed TS changes to be administrative in nature, and acceptable.

3.0 . CONTACT WITH STATE OFFICIAL The NRC staff has notified the Oregon Department of Energy of the proposed issuance of this amendment along with the proposed detemination of no significant hazards consideration. No coments were received.

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4.0 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 that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Comission l has previously published a proposed finding that the amendment involves l no significant hazards consideration and there has been no public coment l on such finding. Accordingly, the 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 assess-mer.t need be prepared in connection with the issuance of the amendment.

5.0 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 pro)osed manner, and (2) such activities will be conducted in compliance wit 1 the Comission's regul-attons, and (3) the issuance of the amendment will not be inimical to the comon defense and security or to the health and safety of the public.

PRINCIPAL CONTRIBUTOR:

T. Chan 1

Dated: June 22, 1988 l

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