Design and fabrication Code Case acceptability ASME Section III Division 1

Technical Report · Thu Nov 01 04:00:00 EST 1990

OSTI ID:6398229

Section 50.55a, Codes and Standards,'' of 10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities,'' requires, in part, that components of the reactor coolant pressure boundary be designed, fabricated, erected, and tested in accordance with the requirements for Class 1 components of Section III, Nuclear Power Plant Components,'' of the American Society of Mechanical Engineers (ASME) boiler and Pressure Vessel code or equivalent quality standards. Footnote 6 to {section} 50.55a states that the use of specific code Cases may be authorized by the Commission upon request pursuant to {section} 50.55a(a)(2)(ii), which requires that proposed alternatives to the described requirements or portions thereof provide an acceptable level of quality and safety. This regulatory guide lists those Section III ASME Code Cases oriented to design and fabrication that are generally acceptable to the NRC staff for implementation in the licensing of light-water-cooled nuclear power plants.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (USA). Office of Nuclear Regulatory Research
• Sponsoring Organization: NRC
• OSTI ID: 6398229
• Report Number(s): REG/G-1.84-Rev.27; ON: TI91004349
• Country of Publication: United States
• Language: English

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