Nondestructive Examination (NDE) Reliability for Inservice Inspection of Light Water Reactors. Volume 15, Semiannual report: October 1991--March 1992

Technical Report · Wed Sep 01 00:00:00 EDT 1993

DOI:https://doi.org/10.2172/10186181· OSTI ID:10186181

Doctor, S R; Diaz, A A; Friley, J R ^[1]

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1. Pacific Northwest Lab., Richland, WA (United States)

The Evaluation and Improvement of NDE Reliability for Inservice Inspection of Light Water Reactors (NDE Reliability) Program at the Pacific Northwest Laboratory was established by the Nuclear Regulatory Commission to determine the reliability of current inservice inspection (ISI) techniques and to develop recommendations that will ensure a suitably high inspection reliability. The objectives of this program include determining the reliability of ISI performed on the primary systems of commercial light-water reactors (LWRs); using probabilistic fracture mechanics analysis to determine the impact of NDE unreliability on system safety; and evaluating reliability improvements that can be achieved with improved and advanced technology. A final objective is to formulate recommended revisions to ASME Code and Regulatory requirements, based on material properties, service conditions, and NDE uncertainties. The program scope is limited to ISI of the primary systems including the piping, vessel, and other components inspected in accordance with Section XI of the ASME Code. This is a progress report covering the programmatic work from October 1991 through March 1992.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (United States). Div. of Engineering; Pacific Northwest Lab., Richland, WA (United States)
• Sponsoring Organization: Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 10186181
• Report Number(s): NUREG/CR--4469-Vol.15; PNL--5711-Vol.15; ON: TI94001155
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100
210200
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900
BWR TYPE REACTORS
DEMONSTRATION PROGRAMS
FRACTURE MECHANICS
IN-SERVICE INSPECTION
NONDESTRUCTIVE TESTING
PERFORMANCE
PIPES
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
BOILING WATER COOLED
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
PROGRESS REPORT
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR SAFETY
REACTOR VESSELS
RECOMMENDATIONS
RELIABILITY
RISK ASSESSMENT
STAINLESS STEELS