ML20207J937

Safety Evaluation Supporting Amend 122 to License NPF-1

ML20207J937
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	12/16/1986
From:	Office of Nuclear Reactor Regulation
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ML20207J920	List: ML20207J917 ML20207J924 ML20207J937
References
NUDOCS 8701090037
Download: ML20207J937 (3)

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[ o UNITED STATES h  ; NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 4,

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_ SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REG RELATED TO AMENDMENT NO.122 TO FACILITY OPEPATING LICENS PORTLAND GENERAL ELECTRIC COMPANY THE CITY OF EUGENE, OREGON PACIFIC POWER AND LIGHT COMPANY TROJAN NUCLEAR PLANT DOCKET N0. 50-344 INTRODUCTION By letter dated December 27, 1985, Portland General Electric Company propose Technical Specification changes for the Trojan Nuclear Plant to resolve an in-The inconsistency involves the number of reactor coolant operating in MODE 3 (hot standby) and at low power during a postulated control rod bank withdrawal accident.

The Trojan FSAR Sections 15.4.1 and 15.4.2 describe a rod bank withdrawal a from a respectively.

Power, subcritical condition and at powers of 10%, 60%, and 100% Rated Thermal According to the current Trojan Technical Specifications, Section 3.4.1.1, operation with only two reactor coolant loops is permitted when the plant is operating below the P-7 setpoint (10% Rated Thermal Power). In addition, Section 3.4.1.2 permits two only loop actually in operation in MODE 3. reactor coolant loops to be operable with However, the rod bank withdrawal Thermal Power) in the FSAR assume that four coolant lo Thus, and there these is an analyses.

accident inconsistency between the Technical Specification requirements DISCllSSION AND EVALUATION To remedy this inconsistency, the licensee proposes to modify the Technical Specifications such that (1) all four coolant loops must be in operation when the plant is operating below the P-7 permissive, (2) all four coolant loops must be in operation in MODE 3 when any control rod drive mechanism (CRDM) is energized, and (3) all CRDMs must be immediately de-energized when there are less than four coolant loops in operation in MODE 3. The de-energizing of CROMs 10%h P

c' t may be accomplished by opening the reactor trip breakers or shutting down the rod drive motor / generator sets.

Section 3.4.1.1 page 3/4 4-2 under the heading "Below P-7:" is revised from requiring two reactor coolant loops to requiring four reactor coolant loops in operation. This revision is consistent with the FSAR assumption that four coolant loops are in operation during the rod bank withdrawal from low power accident. Therefore, we consider the change acceptable.

Section 3.4.1.2 under the heading " LIMITING CONDITION FOR OPERATION" is revised to reflect the new requirements that all four coolant loops must be operating in MODE 3 when any CRDM is energized, and all CRDMs must be immediately de-energized when there are less than four coolant loops in operation. By doing so the licensee removes the inconsistency between the Technical Specifications and the FSAR analyses. We consider these changes acceptable.

Section 4.4.1.2.1 under the heading " SURVEILLANCE REQUIREMENTS" is revised to show that all CRDMs should be verified de-energized if less than four coolant loops are in operation. This change is consistent with the ,

licensee's proposals. We thus consider this acceptable.

Section 3/4.4.1 under the heading " BASES" is revised to describe the consistency between the Technical Specification requirements and the accident analyses. We consider this change acceptable.

These changes make the Technical Specifications consistent with the accident analyses in MODE 3 and low power operation (less than P-7), as previously reviewed and approved by the staff. We therefore conclude that the Technical Specification changes for reactor coolant loop operability in MODE 3 and during low power operation are acceptable for Trojan.

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 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 $51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.

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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 reoulations, 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: December 22, 1986 PRINCIPAL CONTRIBUTORS:

S. L. Wu l

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