GO2-83-105, Responds to IE Bulletin 80-06, ESF Reset Controls. Preoperational Loss of Power Testing Identified Addl balance-of-plant Valves Not in Compliance W/Bulletin,Per .Reset Control Logic Will Be Modified

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Responds to IE Bulletin 80-06, ESF Reset Controls. Preoperational Loss of Power Testing Identified Addl balance-of-plant Valves Not in Compliance W/Bulletin,Per .Reset Control Logic Will Be Modified
ML20082D361
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 11/15/1983
From: Sorensen G
WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To: Schwencer A
Office of Nuclear Reactor Regulation
References
REF-SSINS-6820 GO2-83-1059, IEB-80-06, IEB-80-6, NUDOCS 8311220404
Download: ML20082D361 (1)


Text

Washington Public Power Supply System P.O. Box 968 3000GeorgeWashingtonWay Richland, Washington 99352 (509)372-5000 November 15, 1983 G02-83-1059 Docket No. 50-397 Director of Nuclear Reactor Regulation Attention: Mr. A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Mr. Schwencer:

Subject:

NUCLEAR PROJECT N0. 2 ENGINEERED SAFETY FEATURES (ESF)

RESET CONTROL, IE BULLETIN 80-06 (Q 031.136)

Reference:

Letter, F)2-82-445, G. D. Bouchey (SS) to A.

Schwencer (NRC), " Safety Evaluation Report, NUREG-0692, Outstanding Issue 1.7(11),

Engineered Safety Features (ESF) Reset Control, dated May-14, 1982 The reference provided the Supply System response to IEB 80-06, Engineered Safety Features (ESF) Reset Control. Subsequent preoperational loss of power testing identified additional balance of plant valves as not complying with IEB 80-062 Directions have been implemented to modify the reset control logic of those valves in noncompliance and initiate a review to determine the extent and correct any further balance of plant component noncompliance.

Upon completion of this effort, a summary response to IEB 80-06 will be provided identifyi.ng those components requiring modification Jur to this effort and confirming final Supply System conformance. This effort is to be complete prior to fuel load.

Should you have any questions, please contact Mr. P. L. Powell, Manager, WNP-2 Licensing.

Very truly yours, I wm G. C. Sorensen, Manager Regulatory Programs PLP/ tmh cc: R Auluck - NRC WS Chin - BPA AD Toth - NRC Site g 8311220404 831115 PDR ADOCK 05000397 G PDR

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