Materials code case acceptability ASME Section 3 Division 1

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

OSTI ID:6345309

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. This regulatory guide lists those Section III ASME Code Cases oriented to materials and testing 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: 6345309
• Report Number(s): REG/G-1.85-Rev.27; ON: TI91004617
• Country of Publication: United States
• Language: English

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