Evaluation of Generic issue 125.II.7, reevaluate provision to automatically isolate feedwater from steam generator during a line break
By: prepared by S.J. Bruske ... [et al.].
Contributors: Bruske, S. J.; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Reactor and Plant Systems.; EG & G Idaho.
Publisher: Division of Reactor and Plant Systems, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
Published: 1988
Place of publication: Washington, DC
Language: eng
Number of pages: 48
Subjects: Steam-boilers -- Pipelines -- Failures.; Feed-water -- Safety measures.; Nuclear power plants -- United States -- Safety measures.
Notes: "EG&G Idaho, Inc."

Distributed to depository libraries in microfiche.

"Date published: July 1988."

"NUREG/CR-5178."

"EGG-2544."

Includes bibliographical references.

Final.

A6881.