ML19345A871

LER 80-025/03L-0:on 801007,while Performing Qos 1300-3, Reactor Core Isolation Cooling Motor Operated Valve Operability,Valve MO-2-1301-49 Could Not Be Fully Opened. Caused by Limit Switches Out of Position.Switches Adjusted

ML19345A871
Person / Time
Site:	Quad Cities
Issue date:	11/13/1980
From:	Tubbs R COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML19345A867	List: ML19345A866 ML19345A871
References
LER-80-025-03L-03, LER-80-25-3L-3, NUDOCS 8011250352
Download: ML19345A871 (2)

Text

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VRC FOPM 366 U. S. NUCLEAR KEGULATORY COMMISSloN 17 77)

LICENSEE EVENT REPORT (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

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REPORT OATE 80 1 8 60 61 OOCK ET NUMSER M 69 EVENT OATE 7%

EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h lo l2l l While performing QOS 1300-3, RCIC Motor Operated Valve Operability, RCIC pump l l 3 T31 1 discharge valve MO-2-1301-49 could not be fullf opened. The probable consequences l ml were minimal due to the fact that the HPCI system was fully operable. and the reactor l 101 s 1 I was in the process of being shutdown for a scheduled maintenance outage. l l

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J3 36 26 31 40 41 CAUSE DESCR.IPTION AND CORRECTIVE ACTIONS h 1 101 1 The cause of this occu,rrence is attributed to the limit switches on the valve I li li i l operator were out of position. The limit switches were adjusted and the valve was I i,i,i l tested satisfactorily on October 20, 1980, before unit startup. I I

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l. LER NUMBER: 80-25/03L ll. LICENSEE NAME: Commonwealth Edison Company Quad-Cities Nuclear Power Station 111. FACILITY NAME: Unit Two IV. DOCKET NUMBER: 050-265 V. EVENT DESCRIPTION:

On October 17, 1980, the unit was being shutdown in preparation for a scheduled maintenance outage. At 1800, during the routine monthly performance of QOS 1300-3, "RCIC Motor Operated Valve Operability Test",

as required by Technical Specifications 4.5.E.1. and 4.5.A.I.d., it was discovered that M0-2-1301-49 (RCIC Discharge Isolation to the Reactor Feedwater system) could not be fully opened. Occurrences of RCIC valves not being fully functional have been previously documented, but in these cases, the valve would not close, but had backup Isolation, leaving the RCIC systems in an operable mode.

VI. PROBABLE CONSEQUENCES OF THE CCCURRENCE:

Per Technical Specification 3.5.E.2. continued reactor operation is allowed for 7 days, if all active components of the HPCI are operable.

I f this cannot be met per Technical Specification 3.5.E.3. the reactor must be shutdown and reactor pressure reduced to less than 90 psig.

At the time of occurrence, the HPCI system was operable and the unit was being shutdown; thus, all Technical Specification requirements were fulfilled. Due to the availability of the backup system and the pro-gression to reactor shutdown, there were no adverse safety implications.

Vll. CAUSE:

Upon examination of the valve and its motor operator, it was discovered that the limit switches on the limitorque valve operator were out of position. The valve is a 4 inch Gate valve supplied by Crane Company, and i ts operator is a Limitorque model SMB-000.

Vill. CORRECTIVE ACTION:

The limit switches on the limitorque operator were adjusted to their proper position, and operability of the valve was demonstrated by completely cycling the valve three times on October 20, 1980.

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