Nondestructive examination (NDE) reliability for inservice inspection of light water reactors

Technical Report · Fri May 01 00:00:00 EDT 1992

OSTI ID:5282161

Doctor, S R; Good, M S; Heasler, P G; Hockey, R L; Simonen, F A; Spanner, J C; Taylor, T T; Vo, T V ^[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 11 of the ASME Code. This is a progress report covering the programmatic work from October 1989 through September 1990.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (United States). Div. of Engineering; Pacific Northwest Lab., Richland, WA (United States)
• Sponsoring Organization: USNRC; Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 5282161
• Report Number(s): NUREG/CR-4469-Vol.12; PNL-5711-Vol.12; ON: TI92013739
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
IN-SERVICE INSPECTION
RELIABILITY
PWR TYPE REACTORS
PIPES
PROGRESS REPORT
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTOR VESSELS
CONTAINERS
COOLING SYSTEMS
DOCUMENT TYPES
ENRICHED URANIUM REACTORS
INSPECTION
POWER REACTORS
REACTORS
SAFETY
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210700 - Nuclear Power Plants- Regulation & Licensing
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled