Generic Issue 87: Flexible wedge gate valve test program

Technical Report · Tue Jan 01 00:00:00 EST 1991

OSTI ID:6052350

Steele, R Jr; DeWall, K G; Watkins, J C ^[1]

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1. EG and G Idaho, Inc., Idaho Falls, ID (USA)

Qualification and flow isolation tests were conducted to analyze the ability of selected boiling water reactor process valves to perform their containment isolation functions at high energy pipe break conditions and other more normal flow conditions. Numerous parameters were measured to assess valve and motor-operator performance at various valve loadings and to assess industry practices for predicting valve and motor operator requirements. The valves tested were representative of those used in reactor water cleanup systems in boiling water reactors and those used in boiling water reactor high-pressure coolant injection (HPCI) steam lines. These tests will provide further information for the US Nuclear Regulatory Commission Generic Issue-87, Failure of the HPCI Steam Line Without Isolation,'' and Generic Letter 89--10, Safety-related Motor Operated Valve Testing and Surveillance.'' 6 refs., 54 figs., 4 tabs.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (USA). Div. of Engineering; EG and G Idaho, Inc., Idaho Falls, ID (USA)
• Sponsoring Organization: USNRC
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 6052350
• Report Number(s): NUREG/CR-5558; EGG-2600; ON: TI91007316; TRN: 91-004709
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
BWR TYPE REACTORS
VALVES
PERFORMANCE TESTING
CONTAINMENT
FAILURES
FLUID FLOW
HIGH PRESSURE COOLANT INJECTION
REACTOR SAFETY
CONTROL EQUIPMENT
ECCS
ENGINEERED SAFETY SYSTEMS
EQUIPMENT
FLOW REGULATORS
REACTOR PROTECTION SYSTEMS
REACTORS
SAFETY
TESTING
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
220900 - Nuclear Reactor Technology- Reactor Safety