ML20042A578

LER 82-015/01T-0:on 820225,RHR Svc Water Valve MOV-1947 Failed to Close During Normal Operation.Caused by Wear of Valve Operator Stem Nut.Stem Nut MOV-1947 & Gaskets Replaced,Operator Lubricated & Limit Switches Reset

ML20042A578
Person / Time
Site:	Duane Arnold
Issue date:	03/11/1982
From:	Varner D IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20042A573	List: ML20042A572 ML20042A578
References
LER-82-015-01T, LER-82-15-1T, NUDOCS 8203230576
Download: ML20042A578 (2)

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7 0 Go GOCKET Ngues. es 08 GVE~T OATE 7. 75 ASPQafQ4TE avsur osscaierion 4No amosasta ccNsscusNCs3 h io t a i l During normal operation, RHR SW vaFve MOV-1947 f ailed to close. Valve is i g; used to maintain diff. press. between "B" RHR and "B" RHR SW systems du l to,.ii ring system operation. "B" RHR SW was declared inop., which compromised I tois; operability of "B" cont. spray sys. Because "A" RHR (LPCI mode) had prey I la le i l iously been declared inoo.(see LER 82-14), a 24-hour LC0 was entered and 1 Io i ri I a forced power reduction was begun as required by Tech. Spec. 3.5. A.6. I g a is i i 24-hour LCO became 7-day LCO when "A" RHR made coerable. Not rep. occur. I

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i ,o i ; The cause was attrib. to wear of valve op. stem nut. Stem nut on M0V-194  ;

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• J, DUANE ARN0LD ENERGY CENTER Iowa Electric Light and Power Company Licensee Event Report - Supplemental Data Docket No. 050-0331 Licensee Event Report Date: 3-11-82 Reportable Occurrence No: 82-015 Event

Description:

During normal operation while performing surveillance testing, residual heat removal service water (RHR SW) valve M0V-1947 f ailed to close. This valve is located on the service water discharge line from the "B" RHR heat exchanger and is used to maintain a differential pressure between the "B" RHR and the "B" RHR SW systems during system operation. The "B" RHR SW system was declared inoperable, which in turn compromised the operability of the "B" containment spray system. Because the "A" RHR system (LPCI mode) had previously been declared inoperable (see LER 82-014), a 24-hour limiting condition for operation (LCO) was entered and a forced power reduction was begun to take the reactor out of power operation as required by Technical Specification 3.5.A.6. The forced power reduction ended 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> into the 24-hour LC0 when the "A" RHR system was made operable. With the redundant RHR system now operable, the 24-hour LC0 was changed to a 7-day LC0 for the inoperable "B" RHR SW system. M0V-1947 was repaired 1.5 days af ter the "B" RHR SW system was declared inoperable, which ended the 7-day LC0. There have been no previous similar occurrences.

Caase

Description:

The cause was attributed to wear of the valve operator which resulted in the failure of the stem nut.

Corrective Action:

The stem nut on M0V-1947 was replaced. Gaskets were replaced and the operator was lubricated as required. The limit switches were reset and the motor operator was functionally tested satisfactorily. The valve operator MOV-2046 on the redundant system will be checked for similar stem nut wear.

MOV-1947 is a Model SMB-0 Limitorque valve operator. No further corrective action is planned.

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