ML20236X531

Safety Evaluation Supporting Amend 137 to License NPF-1

ML20236X531
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	12/01/1987
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20195G820	List: ML20195G811 ML20236X517 ML20236X531
References
NUDOCS 8712090265
Download: ML20236X531 (2)

Text

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$9 . . . . + ,d SAFETY EVALUATION E'Y THE OFFICE OF NUCLEAR PEACTOR REGULATION RELATED TO AMENDMENT NO.137TO FACILITY OPERATING L ICENSE NO. NFF-1 PORTLAND G_ENERAL ELECTRIC COMPANY THE CITY OF EUGENE, OREGON PACIFIC POWER AND LIGHT COMPAN_Y TROJAN NUCLEAR PLANT DOCKET NO. 50-344

1.0 INTRODUCTION

By letter dated June 22, 1987, Portland General Electric Company (PGE) requested changes to Technical Specification (TS) Table 3.3-1, " Reactor Trip System Instrumentation" and Table 4.3-1, " Reactor Trip System Instrumentation Surveillance Requirements," in accordance with Generic letter 85-09 regarding the operability requirements for the reactor trip breakers (RTDs) and the surveillance requirements for the manual reactor trip function, reactor trip breakers, and reactor trip bypass breakers.

This request is related to Item 4.3 of Generic letter 83-28.

2.0 DISCUSSION AND EVALUATION The proposed changes are as follows:

a. Table 3.3-1 will reference a new Action Statement 12 to Item 21 "Peactor Trip Breakers." The new Action Statement 12 will clarify the operability status of the RTBs with either the undervoltage or shunt trip attachment inoperable.

b. Table 4.3-1 will reference a new Note 13 to Item 1, " Manual Reactor Trip," and a new Note 14 to Item 21," Reactor Trip Breaker." A new Item 23, " Reactor Trip Bypass Breaker" will be added to the Table, arid will reference new Notes 15 and 16.

Notes 13 through 16 will prescribe requirements for the testing of the RTBs, bypass breakers, and manual reactor trip function.

The proposed revisions conform to the guidar.ce of Generic Letter 85-09, with one exception. In addition to testing the reactor trip bypass breakers within the periods specified by the Generic Letter, PGE proposed that the testing required for the reactor trip bypass breakers be performed on the same frequency as the reactor trip breakers, ie, each train tested every other month (Table 4.3-1, Note 7). Testing each train every 62 days on a staggered test basis would be consistent with reconcendations in the Westinghouse Standard Technical Specifications (W-STS) for reactor trip breaker testing.

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The proposed changes add new testino requirements which are intended to reduce the frequency of postulated Anticipated Transients Without Scram events. The staff has reviewed PGE's proposed changes to the Technical Specifications and finds them to be consistent with GL 85-09 and the b-STS. We further find the use of the staff guioance to be applicable to Trojan. As such, PGE's proposed changes are acceptable.

2.0 CONTACT WITH STATE OFFICIAL The NRC staff has rctified the Oregon Department of Energy of the proposed issuance of this amendment along with the proposed determination of no 4 significant hazards consideration. No comments were received.

3.0 ENVIRONMENTAL CONSIDERATION

This amendment involves a change in the installation or use of a facility "

conponent located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements. 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 i offsite, and that there is no significant increase 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 nc public comment on such 1 3

finding. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 551.22(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 the amend-ment.

4.0 CONCLUSION

l 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 operattun in the proposed manner, and (2) such activities will be conducteo in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical l to the common defense and security or to the health and safety of the public.

PRINCIPAL CONTRIBUTOR:

T. Chan Dated: December 1,1987

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