05000265/LER-1981-012-03, /03L-0:on 810518,during Surveillance Testing,Valve MO-2-1001-7B Failed to Reopen.Caused by Failure of Auxiliary Contacts in Circuit Breakers to Disengage.Valve Manually Opened & Contacts Replaced

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/03L-0:on 810518,during Surveillance Testing,Valve MO-2-1001-7B Failed to Reopen.Caused by Failure of Auxiliary Contacts in Circuit Breakers to Disengage.Valve Manually Opened & Contacts Replaced
ML20009B603
Person / Time
Site: Quad Cities Constellation icon.png
Issue date: 06/10/1981
From: Kopacz J
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20009B601 List:
References
LER-81-012-03L-02, LER-81-12-3L-2, NUDOCS 8107160395
Download: ML20009B603 (2)


LER-1981-012, /03L-0:on 810518,during Surveillance Testing,Valve MO-2-1001-7B Failed to Reopen.Caused by Failure of Auxiliary Contacts in Circuit Breakers to Disengage.Valve Manually Opened & Contacts Replaced
Event date:
Report date:
2651981012R03 - NRC Website

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8 60 61 DOCKET NUMBER 68 69 EVENT DAT E 74 7b REPORT DATE 80 EVENT DESCRIPTl1N AND PROBAOLE CONSEQUENCES h lo ):l l At 0010 on May 18, 1981, while performing surveillance test QOS 1000-3, per I

Technical Specification 4.9.E., valve M0-2-1001-7B was closed but was unable to be l

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lt l+1l g, g,; l immediately manually open the velve.

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LER NUMBER:

LER/R0 81-12/03L-0 ll.

LICENSEE NAME: Commonwealth Edison Company Quad-Cities Nuclear Power Station Ill.

FACILITY NAME: Unit Two IV.

DOCKET NUMBER: 050-265 V.

EVENT DESCRIPTION

At 0010 on May 18, 1981, while performing surveillance testing, QOS 1000-3, for a U.it Two Diesel Generator outage, valve M0-2-1001-7B was closed but would not re-open from the Control Room. Af ter repeated attempts were made to open the valve frem the Control Room without success, the valve was manually opened.

VI.

PROBABLE CONSEQUENCES OF THE OCCURRENCE:

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The safety aspects of this event are mininal.

The failure of the M0 1001-7B valve to open prohibited the "B" RHRS pump to take its normal suction from the pressure suppression pool, thereby rendering the pump inoperable for use in the LPCI mode of RHRS.

However, the other three RHRS pumps were fully operable, hence the LPCI and containment cooling modes of the RHRS were still capable of performing their designed functions.

Vll. CAUSE:

The cause of the deviation was equipment failure. The auxiliary contacts in the circuit breaker failed to disengage. With the auxiliary contacts engaged, the opening coil was unable to energize, therefore disabling the valve.

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CORRECTIVE ACTION

The valve was immediately manually opened. Work Request Q12549 was initiated to investigate and correct the cause of the deviation. The auxiliary contacts in the circuit breaker were replaced like for like under this Work Request.

M0-2-1001-7B was tested satisfactorily at 3:05 p.m. on May 18, 1981.

No further corrective action was necessary.

On September 5,1979, the M0-2-1001-7C valve failed to close during testing due to faulty auxiliary contacts.

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