BWR reactor water cleanup system flexible wedge gate isolation value qualification and high energy flow interruption test
By: prepared by K.G. Dewall, R. Steele, Jr.
Contributors: Steele, Robert.; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering.; U.S. Nuclear Regulatory Commission. Division of Safety Issue Resolution.; Idaho National Engineering Laboratory.
Publisher: Division of Engineering; Division of Safety Issue Resolution, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
Published: 1989
Place of publication: Washington, DC
Language: eng
Subjects: Boiling water reactors -- Safety measures.; Nuclear power plants -- Piping -- Valves -- Testing.; Valves -- Testing.
Notes: "Idaho National Engineering Laboratory."

Distributed to depository libraries in microfiche.

Vols. 1-3 no longer available for sale by the Supt. of Docs.

"Date published: October 1989."

"NUREG/CR-5406."

"EGG-2569."

Includes bibliographical references.

Technical.

A6857 and B5529.
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