Inservice inspection Code Case acceptability: ASME Section XI, Division 1

Technical Report · Sat Jul 01 00:00:00 EDT 1989

OSTI ID:5781956

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
• OSTI ID: 5781956
• Report Number(s): REG/G-1.147-Rev.7; ON: TI89016460
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
BWR TYPE REACTORS
IN-SERVICE INSPECTION
REGULATORY GUIDES
PWR TYPE REACTORS
PRESSURE VESSELS
REACTOR COMPONENTS
REACTOR SAFETY
REGULATIONS
STANDARDS DOCUMENT
ULTRASONIC TESTING
ACOUSTIC TESTING
CONTAINERS
DOCUMENT TYPES
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MATERIALS TESTING
NONDESTRUCTIVE TESTING
REACTORS
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WATER COOLED REACTORS
WATER MODERATED REACTORS
210700* - Nuclear Power Plants- Regulation & Licensing
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