Published January 1991 | Version v1
Report Restricted

Generic Issue 87: Flexible wedge gate valve test program

Description

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

Availability note (English)

MF available from INIS under the Report Number; OSTI as TI91007316;NTIS;INIS;GPO.

Files

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Additional details

Additional titles

Subtitle (English)
Phase 2, Results and analysis

Publishing Information

Imprint Pagination
79 p.
Report number
NUREG/CR--5558

Optional Information

Contract/Grant/Project number
Contract AC07-76ID01570
Secondary number(s)
EGG--2600.