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[en] The NRC Office of Nuclear Regulatory Research (RES) has been sponsoring an MOV testing program in support of the resolution of Generic Safety Issue 87 (GI-87), ''Failure of HPCI Steam Line Without Isolation.'' The initial scope of GI-87 involved the evaluation of the capability of certain motor-operated flexible wedge gate containment isolation valves to mitigate the loss of reactor coolant inventory in the event of a pipe break outside of the containment building at boiling-water-reactor (BWR) plants. The particular MOVs involved in the GI-87 program were those in the turbine steam supply lines for the high pressure coolant injection (HPCI) and reactor core isolation cooling (RCIC) systems, and in the supply line to the reactor water cleanup (RWCU) system. This information notice is intended addressees with specific information regarding the results of recent NRC-sponsored testing of motor-operated valves (MOVs) which was discussed at a public meeting on April 18, 1990
Source
Anon; 1360 p; ISBN 1-55937-206-0; 
; 1992; p. 6, Paper 127; IEEE Standards Press; Piscataway, NJ (United States); IEEE Standards Press, Institute of Electrical and Electronics Engineers, Inc., 445 Hoes Lane, Piscataway, NJ 08855-1331 (United States)
; 1992; p. 6, Paper 127; IEEE Standards Press; Piscataway, NJ (United States); IEEE Standards Press, Institute of Electrical and Electronics Engineers, Inc., 445 Hoes Lane, Piscataway, NJ 08855-1331 (United States)