BWR feedwater nozzle and control rod drive return line nozzle cracking: resolution of generic technical activity A-10. Technical report

Technical Report · Sat Nov 01 04:00:00 EST 1980

OSTI ID:6070097

Snaider, R

This report summarizes work performed by the NRC staff in the resolution of Generic Technical Activity A-10, 'BWR Nozzle Cracking'. Generic Technical Activity A-10 is one of the generic technical subjects designated as 'unresolved safety issues' pursuant to Section 210 of the Energy Reorganization Act of 1974. The report describes the technical issues, the technical studies and analyses performed by the General Electric Company and the NRC staff, the staff's technical positions based on these studies, and the staff's plans for continued implementation of its technical positions. It also provides information for further work to resolve the non-destructive examination issue.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (USA). Office of Nuclear Reactor Regulation
• OSTI ID: 6070097
• Report Number(s): NUREG-0619-REV-1
• Country of Publication: United States
• Language: English

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