Main feedwater system degradation in safety-related ASME code class 2 piping inside the containment of a pressurized water reactor.

Bibliographic Details
Corporate Author: U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation
Format: Government Document eBook
Language:English
Published: Washington, DC : U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, [2001]
Series:NRC information notice ; 2001-09.
Subjects:
Online Access:https://purl.fdlp.gov/GPO/LPS126482
Description
Item Description:Title from HTML title screen (viewed on Sept. 30, 2010).
"June 12, 2001."
Electronic resource.
Physical Description:1 online resource.
Bibliography:Includes bibliographical references.