ML19326D734

Submits Addl Response to IE Bulletin 79-06C.Licensed Operator Assigned to Control Room Is Being Replaced by Unlicensed Operator Trained in Emergency Procedures Until Plant Is Returned to Operation After Spring 1980 Outage

ML19326D734
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	04/16/1980
From:	Broehl D PORTLAND GENERAL ELECTRIC CO.
To:	Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
IEB-79-06C, IEB-79-6C, NUDOCS 8007030233
Download: ML19326D734 (2)

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Portbnd Ge:1eral ElectricConpany Dona:d J. Broehl Assistant Vice President April 16, 1980 Trojan Nuclear Plant Docket 50-344 License NPF-1 Mr. R. H. Engelken, Director U. S. Nuclear Regulatory Commission Region V Suite 202, Walnut Creek Plaza 1990 N. California Blvd.

Walnut Creek, CA 94596

Dear Sir:

As emphasized in our response of August 29, 1979 to Short-Term Action Item 1.b of IE Bulletin 79-06C,

...the assignment of two licensed operators..." in the control room "...to ensure tripping of reactor coolant pumps...upon reactor trip and initiation of HPI caused by low Reactor Coolant System pressure" was considered

"...to be an interim measure." Therefore, due to other regulatory requirements regarding fire protection and radiation emergency planning, the second licensed operator assigned to the control room exclusively for tripping of reactor coolant pumps is being replaced by an unlicensed operator trained in the applicable emerhency procedures and actions.

The assignment of the ualicensed operator to the control room during Plant operation in Modes 1, 2, 3 and 4 to ensure tripping of reactor coolant pumps will be implemented when tl.e Trojan Nuclear Plant is returned to operation following the sprirg 1980 refueling shutdown. This action is considered to be temporary until such time that the long-term action required by IE Bulletin 79-06C (automatic tripping of RCPs upon reactor coolant trip

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!!r. R. H.-Engelken April 14, 1980

.Page 2-and initiation of 11PI caused by low Reactor Coolant System pressure) is 4

complete or the requirement is determined to no longer be necessary due

-to subsequent analyses.

Unless we hear otherwise, we assume this action satirfactorily complies with the intent of IE Bulletin 79-06C.

Sincerely, e

• l}'

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c: Mr.-Lynn Frank, Director State of Oregon Department of Energy Mr.11. ~ R. Denton, Director Office of Nuclear Reactor Regulation

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S. Nuclear Regulatory Comnission 4

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