Status report: Intergranular stress corrosion cracking of BWR core shrouds and other internal components

Technical Report · Fri Mar 01 04:00:00 EST 1996

DOI:https://doi.org/10.2172/236061· OSTI ID:236061

On July 25, 1994, the US Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 94-03 to obtain information needed to assess compliance with regulatory requirements regarding the structural integrity of core shrouds in domestic boiling water reactors (BWRs). This report begins with a brief description of the safety significance of intergranular stress corrosion cracking (IGSCC) as it relates to the design and function of BWR core shrouds and other internal components. It then presents a brief history of shroud cracking events both in the US and abroad, followed by an indepth summary of the industry actions to address the issue of IGSCC in BWR core shrouds and other internal components. This report summarizes the staff`s basis for issuing GL 94-03, as well as the staff`s assessment of plant-specific responses to GL 94-03. The staff is continually evaluating the licensee inspection programs and the results from examinations of BWR core shrouds and other internal components. This report is representative of submittals to and evaluations by the staff as of September 30, 1995. An update of this report will be issued at a later date.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (United States). Div. of Engineering
• Sponsoring Organization: Nuclear Regulatory Commission, Washington, DC (United States)
• OSTI ID: 236061
• Report Number(s): NUREG--1544; ON: TI96007987
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
COMPLIANCE
CRACKS
INTERGRANULAR CORROSION
REACTOR COMPONENTS
REACTOR CORES
REGULATIONS
RELIABILITY
SHROUDS
STRESS CORROSION