ML19341B521

LER 80-035/03L-0:on 801228,after Pumping Drywell Equipment Drain Sump,Outboard Isolation Valve AO-2-2001-16 Required Approx 15 Minutes to Give Closed Indication.Caused by Maladjusted Position Indication Limit Switch

ML19341B521
Person / Time
Site:	Quad Cities
Issue date:	01/16/1981
From:	Tubbs R COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML19341B517	List: ML19341B516 ML19341B521
References
LER-80-035-03L-02, LER-80-35-3L-2, NUDOCS 8102020445
Download: ML19341B521 (2)

Text

Nr.c FORM 355 U. S. NUCLEAR REGULATORY COYM!SSION (7 77)

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7 8 60 61 DOCK ET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT OESCRIPTION AND PROB ASLE CONSEQUENCES h10 l o t 21 l Af ter pumping the Drywell Equipment Drain Sump, outboard isolation valve A0-2-2001-169

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required approximately 15 minutes to give closed indication. Technical ,

,o,,,; Speci fications require a closure time of less than or equal to 20 seconds. The ,

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redundant Isolation valve A0-2-2001-15 was placed in the closed position.

solation Capability of the Equipment Orain Sump was always intact.

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o I. LER NUMBER: .ER/R0 80-35/03L

11. LICENSEE NAME: Commonwealth Edison Company quad-Cities Nuclear Power Station lil. FACILITY NAME: Unit Two IV. DOCKET NUMBER: 050-265 V. EVENT DESCRIPTION:

On December 28,1980, at 1600, the Drywell Equipment Drain Sump was undergoing routine pump down. Upon conclusion of the evolution it was noted that the outboard Isolation valve, A0-2001-16, had an excessive closure time of approximately 15 minutes. Technical Specification Table 3.7-1, requires that the closure time shall be less than or equal to 20 seconds. Attempts were made to open the valve with no apparent success.

Personnel were sent to the location of the valve and another attempt was made. It was reported that there was not enough travel to actuate the limit switches. There are no recorded instances of this valve failing in this mode.

VI. PROBABLE CONSEQUENCES OF THE OCCURRENCE:

Per Technical Specification 3.7.D.2. , continued reactor operation is allowed, provided that at least one valve in that line is closed. The redundant outboard isolation valve, A0-2-2001-15, was closed. At all times the reactor was operated within the requirements of the Technical Specification.

Impact upon the system was also minimal. The recirculation through the Drywell Equipment Drain Sump coolers was in no way impaired, and the sump had been pumped down immediately prior to the occurrence. Coolant leakeges were within Technical Specif' ation limits.

Vll. CAUSE:

Failure of the valve to close within the required time was due to a-limit switch and the length of valve stem travel. that were out of adjustment.

The valve is a 3 Inch 150 Cast Steel Gate valve manufactured by Crane Company.

Vill. CORRECTIVE ACTION:

The Drywell Equipment Drain Sump pumps were out of service'during the repai r and the following items were performed. The stroke of.the valve stem was lengthened, packing was adjusted, and _ both the open and shut limit switches were reset. At 2200 the valve A0-2-2001-16 was cycled three times. satisfactorily with a closure-time'of 4.2 seconds.

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