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

Technical Report · Sat Sep 01 00:00:00 EDT 1990

OSTI ID:6805054

Doctor, S R; Deffenbaugh, J D; Good, M S; Green, E R; Heasler, P G; Simonen, F A; Spanner, J C; Taylor, T T; Vo, T V ^[1]

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1. Pacific Northwest Lab., Richland, WA (USA)

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 1988 through March 1989. 8 refs., 15 figs., 19 tabs.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (USA). Div. of Engineering; Pacific Northwest Lab., Richland, WA (USA)
• Sponsoring Organization: NRC
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 6805054
• Report Number(s): NUREG/CR-4469-Vol.10; PNL--5711-Vol.10; ON: TI91000836
• Country of Publication: United States
• Language: English

Related Subjects

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Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
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Light-Water Moderated
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220900 -- Nuclear Reactor Technology-- Reactor Safety
BWR TYPE REACTORS
CHEMICAL ANALYSIS
CONTAINERS
COOLING SYSTEMS
DOCUMENT TYPES
ENERGY SYSTEMS
IN-SERVICE INSPECTION
INSPECTION
NONDESTRUCTIVE ANALYSIS
PIPES
PRESSURE VESSELS
PROGRESS REPORT
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
RELIABILITY
SAFETY
SURFACE PROPERTIES
WATER COOLED REACTORS
WATER MODERATED REACTORS