ML20154D493

Safety Evaluation Supporting Amend 142 to License NPF-1

ML20154D493
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	05/11/1988
From:	Office of Nuclear Reactor Regulation
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ML20154D473	List: ML20154D470 ML20154D484 ML20154D493
References
NUDOCS 8805190211
Download: ML20154D493 (3)

Text

. [ 'o UNITED STATES g

N E NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555

,o SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT N0.142 TO FACILITY OPERATING LICENSE NO. NPF-1 PORTLAND GENERAL ELECTRIC COMPANY THE CITY OF EUGENE, OREGON PACIFIC POWER AND LIGHT COMPANY TROJAN NUCLEAR PLtNT DOCKET NO. 50-344

1.0 INTRODUCTION

By letter dated August 16, 1985, Portland General Electric Company (PGE) requested changes to the Technical Specifications (TS) which would pennit relief from Limiting Condition for Operation (LCO) 3.0.4 for the following TS Sections:

3.2.4 -

Quadrant Power Tilt Ratio 3.3.3.5 -

Remote Shutdown Instrumentation (3 3.9.2 - Instrumentation (Refueling Operations)

(4 3.9.7 -

Crane Travel - Fuel Building (5 3.9.9 -

Containment Ventilation Isolation System (6 3.9.11 - Storage Pool Water Level (7) 3.4.6.1 - RCS Leakage (8) 3.6.4.1 -

Hydrogen Analyzers (9) 3.6.4.2 -

Electric Hydrogen Recombiners l (10)3.6.4.0 -

Hydrogen Vent System (11) 3.6.4.4 - Hydrogen Mixing System l By letter dated December 19, 1986, the request for Items 7 through 11  !

were withdrawn. By letter dated April 20, 1988, the request for Itesn 2 ,

was withdrawn. The April 20 letter did not affect the staff's initial l determination notice in the Federal Register on February 10, 1988 (53 FR 3958).

2.0 DISCUSSION AND EVALUATION LCO 3.0.4 prevents entry into an Operational Mode or other specified applicability condition unless the conditions of the Limiting Condition for Operation are met without reliance on provisions contained in the Action statements, unless othe M se excepted. This provision does not i prevent passage through Operational Modes as required to comply with Action statements.

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Specification 3.2.4 - Quadrant Power Tilt Ratio The proposed change to exempt TS 3.2.4 from the provisions of Specification 1

3.0.4 is consistent with the Westinghouse Standard Technical Specifications

(STS). In addition, the Quadrant Power Tilt Ratio is still subject to  ;

the same Action Statement as provided in TS 3.2.4 to ensure that the CNB and the linear heat generation limits are met during power operation at l

greater than 50% rated themal Power. Therefore, the proposed change does not affect the provisions and limitations of Specification 3.2.4 on Quadrant Power Tilt Ratio, and is acceptable. -

1 Specification 3.9.2 - Instrumentation (Refueling Operations) t The limiting condition for operation for Specification 3.9.2 requires a minimum of two source range (SR) neutron flux monitors to be in operation during any core alteration or positive reactivity changes. As it is presently written, Specification 3.9.2 does not allow detensioning of the reactor vessel head (entering Mode 6) with one source range monitor inoperable.

1 The intent of the TS is to enter core alterations with a redundant l j capability (two channels) of source range instruments. in the event one channel becomes inoperable, the other is still capable of providing ,

4 indication. Having only one source range instrument operable during i i "refueling mode" is permitted as long as core alterations or positive  !

a reactivity changes ceases to be performed. Entering Mode 6 with only  !

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one SR instrument is therefore considered to be acceptable since two SR channels are still required to be operable prior to resuming core alterations or positive reactivity changes.

Specification 3.9.7 - Crane Travel, Fuel Building u

The proposed change to exempt Specification 3.9.7 from the provisions of LCO 3.0.4 is acceptable since the control of loads over the spent fuel

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pool is irrelevant to plant operation and entry into operational modes.

Specification 3.9.9 - Containment Ventilation _ System The proposed change to exempt Specification 3.9.9 from the provision of I LC0 3.0.4 is acceptable since the containment ventilation penetrations will retain the capability of either being isolated automatically by the 3

Containment Ventilation Isolation (CVI) system, or by operator action.

Specification 3.9.11 - Storage Pool Water Level 1 1 The proposed change to exempt Specification 3.9.11 from the provisions of LCO 3.0.4 is acceptable since the minimum pool water level has not been altered, and that storage pool water level is irrelevant to Operational Modes.

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1 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 determinaticn of no significant hazards consideration. No coments were received.

4.0 ENVIRONMENTAL CONSIDERATION

I 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 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 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 the amendment.

5.0 ACKNOWLEDGEMENT OF PREAPPROVED CHANGES On January 5, 1987, the Commission amended its regulations that established the procedures for submitting correspondence, reports, applications, or other writter communications pertaining to the domestic licensing of production and utilization facilities. In part, the amendments indicated the correct mailing address for delivery of the comunications. As published in the Federal Register (51 FR 40303) November 6, 1986, licensee's whose Technical Specifications contained conflicting submittal directions were authori;;ed to delete the conflicting directions without formal applications, to amend their licenses to conform to the revised ccmunications procedures. PGE has implement changes, and the Comission acknowledges those changes.

6.0 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 proposed manner, and (2) such activities will be conducted in compliance with the Comission's regula-tions, and (3) the issuance of the amendment will not be inimical to the cornon defense and security or to the health and safety of the public.

Principal Contributors: C. Li L. Lois T. Chan Dated: May 11, 1988

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