05000373/LER-1983-147, Updated LER 83-147/03X-1:on 831112,RHR B HX Outlet Valve 1E12-F003B Failed to Open Via Motor Operator or Manually. Caused by Water Trapped in Bonnet Cavity.Valve Limit Switches Temporarily changed.W/840320 Ltr

Updated LER 83-147/03X-1:on 831112,RHR B HX Outlet Valve 1E12-F003B Failed to Open Via Motor Operator or Manually. Caused by Water Trapped in Bonnet Cavity.Valve Limit Switches Temporarily changed.W/840320 Ltr

ML20087N237
Person / Time
Site:	LaSalle
Issue date:	02/23/1984
From:	Diederich G, Peters M COMMONWEALTH EDISON CO.
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
LER-83-147-03X, LER-83-147-3X, NUDOCS 8404030253
Download: ML20087N237 (4)

LER-2083-147, Updated LER 83-147/03X-1:on 831112,RHR B HX Outlet Valve 1E12-F003B Failed to Open Via Motor Operator or Manually. Caused by Water Trapped in Bonnet Cavity.Valve Limit Switches Temporarily changed.W/840320 Ltr

Event date:
Report date:
3732083147R00 - NRC Website

text

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fREPOR,TSUBMITTED 12/12/83" LICENSEE EVENT REPORT

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p 3 n.11-12-83 0 at 2215 with the unit in The inoperability l g ; valve (1E12-F003B) failed to open via the motor operator or manually.

g g gof this valve, while in the closed position, made B Shutdown Cooling and B The A Shutdown Cooling Loop was operable to control decay ,

gPool Cooling inoperative.

This second gheat. A second method of controlling decay heat was also available.

g Safe operation of the plant was mainta!ned. g goerj gmethod utilizes the RHR and RCIC systems.

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, g the closed pcsition. At the recommendation of Anchor Darling Valve Mfg., the valvethe wed g l limittion switches were temporarily changed such thatThis change should allow during and not by torque.

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" 815/357-6761 g PHONE:

NAME OP emEP ARER

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-l .: LER NUMBER: 83-14 7/03X-1 1 l' I . - LASALLE COUNTY. STATION: - Unit 1 111.- DOCKET-NUMBER: 050-373/374 .

IV. : EVENT. DESCRIPTION:

On 11-12-83 at 2215'with:the unit in Cold Shutdown, the B RHR Heat Exchanger outlet. valve (1E12-F0038) failed (to open via the motor operator or manually.

-The Inoperability of this valve, while in the _ closed position, made B Shut-3

'down' Cooling and B Suppression Pool Cooling inoperative.

V.n PROBA8LE: CONSEQUENCES-OF THE OCCURRENCE: -

The A Shutdown Cooling Loop was operable to control decay heat. A second method ~of controlling decay-heat was also available - LLP-83-29 which utilizes the. RHR and RCIC systems. By 0300 on 11-13-83, the A RHR Shutdown Cooling Loop-was in operation. A high temperature of'185 F on the reactor water cleanup. system bottom head drain was reached prior to A RHR Shutdown

' Cooling operation.- Safe operation.of the plant was' maintained.

VI. CAUSE:-

~

'1E12-F003B is a: flex-wedge gate valve manufactured by the Anchor Darling e ' Co .- Similar problems-with this valve have occurred previously. The correc-tive action in LER 83-117/03L-0 stated that the valve would be disassembled

-1 at the next planned. unit outage of4suf ficient duration an'd the valve internals

=inspacted Lfor any . potential . causes of inoperabili ty. A supplemental LER will '

-be issued-describing the" valve internals inspection. The 1E12-F003B valve was' disassembled via workLrequest L27760. The valve internals were inspected

.by. representatives of-Anchor Darling Co., Mark Controls Corp.,-and Ceco. The

' internals were evaluated as' extremely good. A wedge to seat rings contact

~ test (Blue -Test) Indicated approximately 100% contact. While performing

' Work Requesti . L29638, written to remove and ~ replace- the motor operator for the valve Internals 1 Inspection. the operator motor winding insulation was j: .foundL to be burnt. The valve was reassembled,! motor operator.-(with a new

' ;- ~ motor) was replaced, and the valve satisfactorily cycled. The valve subse-Lquently again became locked in the1 closed position while continuing to test.

ithe valve during various-conditions of B Shutdown Cooling, i t is believed

^

_ that the valve 'can become Inoperable in ~ the close posi tion due to water being

trapped in the' bonnet cavity. - Since the' bonnet cavity does not'have a'mecha-inism- toient of.f the entrapped water for valve opening, the wedge is hydrauli-E ically; locked..in the closed position.-

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.VII. " CORRECTIVE ~ ACTION:

- At'the' recommendation of Anchor Darling, the valve limit switches were tempo-rarily: changed;such that the wedge travel'is stopped by position and not by

- -torque. : This change would allow the water entrapped in the bonnet cavity to

;be; vented'through the' upper seat rings to wedge seat as the valve is opened.

A'temporaryLsystem! change' LAP 240-6 Att.'B 1-700-83 and work request L29978 L

' Ewere performed to accomplish the above recommendation. The valve has since L-

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$3 J' Pcge it ' LER NUMBER: 83-147/03X-1 Vll. CORRECTIVE ACTION (Cont'd):

been tested without failure several times under different conditions of B RHR Shutdown Cooling. A.I.R. 01-83-67128 has been issued to scrutinize the performance of_1E12-F003B over the next two excursions of the unit to cold shutdown. . If.the temporary system change to the valve resolves the valve becoming inoperative in the close position, a permanent modification will be made in accordance with Anchor Darling's recommendations.

- Prepared by: M. A. Peters l

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[D, Commonwe:lth Edison - O

' / LaSalle County Nuclear Station O

Rural Route #1, Box 220

( V 7 Marseilles, Illinois 61341

\ Telephone 815/357-6761 March 20, 1984 James G. Keppler Regional Administrator Region 111 U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137

Dear Si r:

Reportable Occurrence Report #83-147/03X-1 Docket #050-373 is being submitted to your office to supersede previously submitted Reportable Occurrence Report

1. 83-147/03L-0, in accordance with NUREG-0161, " Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File"; General instruction No. 3 G. J. Diede ich Superintendent LaSalle County Station GJD/GW/kg Enclosure CC: Director of Inspection & Enforcement Director of Management information & Program Control

- U.S. 'NRC Document Management Branch INP0-Records Center File /NRC ykR 2 O W e 74.72 'll