Qualification of automated techniques for meeting ASME code and NRC requirements. [PWR; BWR]
Conference
·
OSTI ID:5933812
Nondestructive examinations for nuclear power plants must meet Volume 10, Part 50, Code of Federal Regulation requirements. For Inservice Inspection examinations, these regulations implement the rules of Section XI of the American Society for Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code). Since many of the ASME Code nondestructive examination rules were developed from manual examination practices, they may not apply to automated examinations. Alternate procedures are allowable through use of Code Cases, Nuclear Regulatory Commission Relief Requests, or ASME Code, Section XI, Paragraph IWA-2240 alternative examinations. Documentation of qualification test results for automated techniques is a necessary prerequisite for obtaining approval of alternate procedures. New Code rules are now being developed which will emphasize procedure qualification rather than detailed technique requirements. These qualification requirements should provide more incentive for adopting automated techniques with demonstrated procedure effectiveness.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 5933812
- Report Number(s):
- EGG-M-11983; CONF-830652-3; ON: DE83015441
- Country of Publication:
- United States
- Language:
- English
Similar Records
Analysis of preservice inspection relief requests and recommendations for ASME code changes
Inservice inspection Code Case acceptability: ASME Section XI, Division 1
Inservice inspection code case acceptability ASME Section 11 Division 1
Technical Report
·
Wed May 01 00:00:00 EDT 1985
·
OSTI ID:5698841
Inservice inspection Code Case acceptability: ASME Section XI, Division 1
Technical Report
·
Sat Jul 01 00:00:00 EDT 1989
·
OSTI ID:5781956
Inservice inspection code case acceptability ASME Section 11 Division 1
Technical Report
·
Wed Oct 31 23:00:00 EST 1990
·
OSTI ID:6400593
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
BWR TYPE REACTORS
CONTAINERS
IN-SERVICE INSPECTION
INSPECTION
PRESSURE VESSELS
PWR TYPE REACTORS
REACTORS
STANDARDS
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
BWR TYPE REACTORS
CONTAINERS
IN-SERVICE INSPECTION
INSPECTION
PRESSURE VESSELS
PWR TYPE REACTORS
REACTORS
STANDARDS
WATER COOLED REACTORS
WATER MODERATED REACTORS