ML19345C925

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Forwards IE Info Notice 80-41, Failure of Swing Check Valve in Decay Heat Removal Sys at Davis Besse Unit 1. No Response Required
ML19345C925
Person / Time
Site: Trojan File:Portland General Electric icon.png
Issue date: 11/10/1980
From: Engelken R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To: Withers B
PORTLAND GENERAL ELECTRIC CO.
References
NUDOCS 8012080625
Download: ML19345C925 (1)


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UNITED STATES NUCLEAR REGULATORY COMMISSION g

t REGION V

.o 1990 N. CALIFORNLA BOULEVARD

,e SUITE 202. WALNUT CREEK PLAZA o,,,e WALNUT CREEK CALIFORfv1A 94006 Novemoer 10, 1980 n

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Portland General Electric Company

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121 S. W. Salmon Street

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Portland, Oregon 97204

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Attention: Mr. Bart D. Withers C

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Vice President iluclear Gentlemen:

This Information riotice is provided as an early notification of a possibly significant matter.

It is expected tnat recipients will review the information for possible. applicability to their facilities. No specific action or response is requested at this time.

If further NRC evaluations so indicate, an IE Circular or Bulletin will be issued to recocrend or request specific licensee actions.

If you have questions regarding tnis matter, please contact the.0irector of tne appropriate NRC Regional Office.

Si cerely, f

irector

Enclosures:

1.

IE Information Notice do. 80-41 2.

Recently issued IE Information ilotices cc w/ enclosures:

C. P. Yundt, PGE J. W. Durham, Esq., POE I

8 012 0 8 0 LZ^f Q

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sj SSINS No.: 6835 Accession No.:

8008220260 UNITED STATES IN 80-41 NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT b

WASHINGTON, D.C.

20555 November 10, 1980

/

IE Informatien Notice No. 80-41: FAILURE OF SWItiG CHECK VALVE IN THE DECAY HEAT REMOVAL SYSTEM AT DAVIS-BESSE UNIT tl0. 1 Descr'etion of Circumstances:

On October 9,1980 the resident inscector at the Davis-Besse facility was infon::ed that the licensee nad perfonned leak rate tests and identified exces-sive leakage through Cecay Heat Removal System cneck valve CF-30. Valve CF-30 is the' inboard one of two in-series check valves that is used to isolate the reactor coolant system from the low pressure decay heat removal sy tem. On further investigation the licensee found that t'le talve disc and arm nad separated from the valve body ana was lodged jb. under the valve cover plate.

The two 2 5/8 x 5/8 inch bolts and locking mechanism for the bolts that holds the arm to the valve body were missing and have not been located. The CF-30 valve is a 14-inch swing check valve manufactured by Velan Valve Corporation.

The cause of the failure has not been identified.

The test that was in progress

  • nen the failure was identified was being con-ducted in resconse to a lett;. f cm Darrell G. Eisenhut. Office of Nuclear Reactor Regulations to all Ligh. Water Reactor Licensees, LWR Primarv Coolant System Pressure Isolation Valves, February 23, 1980.

This IE Information Notice is provided as an early notification of a possibly significant matter that is still under review by the NRC staff.

It is expected that recipients will review the information for possible applicability to their facilities. No specific action or response is requested at this time.

If flRC evaluations so indicate, further licensee actions may be requested or required.

No written response to this IE Information Notice is required.

If you have any questions regarding this matter, please contact the Director of the appropriate NRC Regional Office.

IN 80-41 November 10, 1980 RECEilTLY ISSUED IE INF0FFATION NOTICES Infomation Cate of Notice No.

Subject Itsue Issued to 80 40 Failure Of Swing Check 11/10/80 All power facilities Valve In The Decay Heat with and OL or CP Removal System At Davis-Besse Unit No.1 80-39 Malfunctions Of Solenoid 10/31/80 All light water reactor Valves Manufactured By facilities holding Valcor Engineering Corporation power reactor OLs or cps 80-38' Cracking In Charging Pump 10/30/80 All PWR facilities Casing Cladding with an OL or CP 80-37 Containment cooler leaks 10/24/80 All nuclear pcwer and reactor cavity facilities holding flooding at Indian Point power reactor OLs Unit 2 or cps 80-26 Failure of Steam 10/10/80 All nuclear power Generator Support Bolting reactor facilities holding power reector OLs or cps 80-35 Leaking and dislodged 10/10/80 All categories G and Iodine-124 implant seeds G1 medical licensees 80-34 Baron dilution of reactor 9/26/80 All pressurized water ecolant during steam reactor facilities generator decontamination holding power reactor OLs 80-33 Determination of teletherapy 9/15/80 All teletherapy timer ac uracy (G3) licensees 80-32 Clarification of certain 8/12/80 All NRC and agreement requirements for Exclu-state licensees sive-use shipments of radioactive materials 80-31 I4aloperation of Gould-8/27/80 All light water reactor Brown Boveri Type 480 facilities holding OLs volt type K-6005 and_

or cps K-00N 600S circuit breakers

  • Operating Licenses or Construction Pemits