Example value-impact analysis of non-destructive examination methods used for inservice inspection of BWR piping

Conference · Sun Dec 01 00:00:00 EST 1985

OSTI ID:5467072

Tabatabai, A S; Simonen, F A

This paper describes work recently completed at Pacific Northwest Laboratory (PNL) to use value-impact (V/I) analysis methods to help guide research to improve the effectiveness of inservice inspection (ISI) procedures at nuclear power plants. The example developed at PNL uses the results of probabilistic fracture mechanics and probabilistic risk analysis (PRA) studies to compare three generic categories of non-destructive examination (NDE) methods. These NDE methods are used to detect possible pipe cracks such as those induced by intergranular stress corrosion (IGSCC). The results of the analysis of this example include (1) quantification of the effectiveness of ISI in increasing plant safety in terms of reduction in core-melt frequency, (2) estimates of the industry cost of performing ISI, (3) estimates of radiation exposures to plant personnel as a result of performing ISI, and (4) potential areas of improvement in the NDE and ISI process.

• Research Organization: Pacific Northwest Lab., Richland, WA (USA)
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 5467072
• Report Number(s): PNL-SA-13451; CONF-860722-17; ON: TI86013597
• Resource Relation: Conference: ASME pressure vessel and piping conference and exhibit, Chicago, IL, USA, 20 Jul 1986
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
PIPES
IN-SERVICE INSPECTION
NONDESTRUCTIVE TESTING
CRACKS
FRACTURE MECHANICS
IMPACT TESTS
NUCLEAR POWER PLANTS
PROBABILISTIC ESTIMATION
RISK ASSESSMENT
INSPECTION
MATERIALS TESTING
MECHANICAL TESTS
MECHANICS
NUCLEAR FACILITIES
POWER PLANTS
REACTORS
TESTING
THERMAL POWER PLANTS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled