Parameters affecting MOV performance

Technical Report · Thu Dec 31 04:00:00 EST 1992

DOI:https://doi.org/10.2172/10114652· OSTI ID:10114652

Watkins, J C; DeWall, K G; Steele, R Jr

This paper presents the background status and current research on the motor-operated valve (MOV) disc and stem factor loads. Generic Safety Issue (GSI)-87 ``Failure of HPCI Steam Line Without Isolation`` and Generic Letter (GL) 89-10 ``Safety-Related Motor-Operated Valve Testing and Surveillance`` have initiated a great deal of research on MOVs in a relatively short time. Most of this research has concentrated on the motor-operated, rising, stem, wedge gate valve, which is the predominant valve in the GSI-87 applications and is widely used in the systems covered by GL 89-10. The Idaho National Engineering Laboratory (INEL), sponsored by the US Nuclear Regulatory Commission (USNRC), is performing research to assist in the resolution of GSI-87 and the implementation of GL 89-10. This work has identified two friction loads that were not well understood and that have a significant influence on the force required to operate a valve under load. The lack of understanding of one of the friction loads has led to questions about the diagnostic testing performed on MOVs over the last few years. It is also not known how aging (time) will affect these friction loads. This is also a subject of ongoing research.

• Research Organization: EG and G Idaho, Inc., Idaho Falls, ID (United States)
• Sponsoring Organization: Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 10114652
• Report Number(s): EGG-M--92475; ON: DE93005194
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220900
42 ENGINEERING
420200
AGING
FACILITIES, EQUIPMENT, AND TECHNIQUES
FRICTION
PRESSURE EFFECTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
RELIABILITY
SERVICE LIFE
TESTING
VALVES