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U.S. Department of Energy
Office of Scientific and Technical Information

Inservice inspection code case acceptability ASME Section 11 Division 1

Technical Report ·
OSTI ID:6400593
Section 50.55a, Codes and Standards,'' of 10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities,'' requires, in part, that each operating license for a boiling or pressurized water-cooled nuclear power facility and each construction permit for a utilization facility be subject to the conditions in paragraph (g), Inservice Inspection Requirements,'' of {section}50.55a. Paragraph (g) requires, in part, that Classes 1, 2, and 3 components and their supports meet the requirements of Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components,'' of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code or equivalent quality standards. Paragraph 50.55a (b), in part, references the latest editions and addenda in effect of Section XI of the Code and any supplementary requirements to that section of the Code. This regulatory guide lists those Section XI ASME Code Cases that are generally acceptable to the NRC staff for implementation in the inservice inspection 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:
6400593
Report Number(s):
REG/G-1.147-Rev.8; ON: TI91004616
Country of Publication:
United States
Language:
English