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
Similar Records
Inservice inspection Code Case acceptability: ASME Section XI, Division 1
Optimizing an inservice inspection program plan
Design and fabrication Code Case acceptability ASME Section III Division 1
Technical Report
·
Sat Jul 01 00:00:00 EDT 1989
·
OSTI ID:5781956
Optimizing an inservice inspection program plan
Conference
·
Fri Dec 31 23:00:00 EST 1982
· Proc. Am. Power Conf.; (United States)
·
OSTI ID:6687706
Design and fabrication Code Case acceptability ASME Section III Division 1
Technical Report
·
Wed Oct 31 23:00:00 EST 1990
·
OSTI ID:6398229
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
210700* -- Nuclear Power Plants-- Regulation & Licensing
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900 -- Nuclear Reactor Technology-- Reactor Safety
ACOUSTIC TESTING
BWR TYPE REACTORS
CONTAINERS
DOCUMENT TYPES
IN-SERVICE INSPECTION
INSPECTION
LICENSING
MATERIALS TESTING
NATIONAL ORGANIZATIONS
NONDESTRUCTIVE TESTING
NUCLEAR FACILITIES
PRESSURE VESSELS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR LICENSING
REACTOR SAFETY
REACTORS
REGULATIONS
REGULATORY GUIDES
SAFETY
STANDARDS DOCUMENT
TESTING
ULTRASONIC TESTING
US NRC
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
210700* -- Nuclear Power Plants-- Regulation & Licensing
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900 -- Nuclear Reactor Technology-- Reactor Safety
ACOUSTIC TESTING
BWR TYPE REACTORS
CONTAINERS
DOCUMENT TYPES
IN-SERVICE INSPECTION
INSPECTION
LICENSING
MATERIALS TESTING
NATIONAL ORGANIZATIONS
NONDESTRUCTIVE TESTING
NUCLEAR FACILITIES
PRESSURE VESSELS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR LICENSING
REACTOR SAFETY
REACTORS
REGULATIONS
REGULATORY GUIDES
SAFETY
STANDARDS DOCUMENT
TESTING
ULTRASONIC TESTING
US NRC
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS