ML20207Q534

Application to Amend License NPF-1,incorporating License Change Application 150 to Revise Surveillance Requirements for Safety Injection Sys Accumulator Isolation Valves. Description of Change Encl

ML20207Q534
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	01/20/1987
From:	Lindblad W PORTLAND GENERAL ELECTRIC CO.
To:
Shared Package
ML20207Q530	List: ML20207Q529 ML20207Q534 ML20207Q537
References
TAC-64533, NUDOCS 8701270491
Download: ML20207Q534 (3)

Text

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4 PORTLAND GENERAL ELECTRIC COMPANY EUGENE WATER & ELECTRIC BOARD AND PACIFIC POWER & LIGHT COMPANY Operating License NPF-1 Docket 50-344 License Change Application 150 This License Change Application requests modifications to Operating License NPF-1 for the Trojan Nuclear Plant to revise surveillance requirements for safety injection system accumulator isolation valves.

PORTLAND GENERAL ELECTRIC COMPANY u.a . uuataa

. C&e A?Y d President i

Subscribed and sworn to before me this 20th day of January 1987.

24, _

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' Notary Public of Oregopf My Commission Expires:

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8701270491 870120 PDR ADOCK 05000344 P PDR l

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LCA 150 Page 1 of 2 Description of Change Delete the words "... by removal of the breaker from the circuit" from Technical Specification 4.5.1.c.

Reason for Change Surveillance Technical Specification 4.5.1.c for accumulator isolation valven MO8808A, B, C and D requires disconnecting power from the valve operators by removal of the breaker from the circuit whenever RCS pres-sure exceeds 2000 psis. This results in loss of valve position indica-tion (VPI) in the control room and necessitates racking in the breaker to regain remote operation capability. The requirement to remove the breaker is unnecessarily restrictive and inconsistent with other Technical Specifications. With the installation of a lockout feature on the accumulator isolation valve control room switches, control power to the valve operators could be disconnected remotely while retaining VPI.

A change to the Technical Specification is necessary to allow use of this preferred method to satisfy the surveillance requirement.

Sjanificant Hazards Consideration Determination In accordance with the requirements of 10 CFR 50.92, this license change request is judged to involve no significant hazards based upon the fol-lowing information:

1. Does the proposed license change involve a significant increase in the probability or consequences of an accident?

Since the surveillance requirement for the accumulator isolation

valves remains, there is no significant increase in the proba-bility or consequences of an accident. This change merely allows use of the added lockout feature rather than ramoval of the breaker.

2. Does the proposed license change create the possibility of a new or different kind of accident from any acc!. dent previously evaluated?

Changing this surveillance requirement for accumulator isolation valves to allow use of the lockout feature does not create the possibility of a new or different kind of accident. Demonstra-tion of operability for each accumulator remains a requirement.

o LCA 150 Page 2 of 2

3. Does the proposed amendment involve a significant reduction in a margin of safety?

Sincu the requirement to demonstrate operability of each accu-mulator remains, there is no significant reduction in the margin of safety. Use of the lockout feature may actually increase the margin of safety since VPI is retained and remote valve control can be returned more expeditiously.

In the April 6, 1983 Federal Register, the NRC published a list of examples of amendments that are not likely to involve a significant hazards concern. Example No. 1 of that list applies to this change and states:

"A purely administrative change to technical specifications, eg, a change to achieve. consistency throughout the technical specifica-tions, correction of an error, or a chenge in nomenclature."

SAFETY / ENVIRONMENTAL EVALUATION Safety and environmental evaluations were performed as required by 10 CFR 50 and the Trojan Technical Specifications. This review deter-mined that an unroviewed safety question does not exist since Plant operations remain consistent with the Updated FSAR, adequate surveillance is maintained, and there is no conceivable impact upon the environment.

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