Generic evaluation of small break loss-of-coolant accident behavior in Babcock & Wilcox design 177-FA operating plants
By: Bulletins and Orders Task Force, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission
Publisher: The Office; Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission; National Technical Information Service
Published: 1980
Place of publication: Washington, D.C; Springfield, Va
Language: eng
Number of pages: 128
Subjects: Pressurized water reactors -- Loss of coolant;  -- Nuclear power plants -- Accidents -- United States
Other titles: Babcock & Wilcox designed 177-FA operating plants
Notes: "Date published: January 1980."

"NUREG-0565."

Includes bibliographical references