Risk-based in-service inspection of steam generator tubes
Conference
·
· Transactions of the American Nuclear Society; (United States)
OSTI ID:7056189
- Public Service Electric and Gas Co., Hancocks Bridge, NJ (United States)
During a normal refueling outage in a pressurized water reactor, nondestructive inspection of steam generator tubes is used extensively to maximize plant safety and to maximize its generating production capacity during the next fuel cycle. The problem is to identify and implement the most cost-effective in-service inspection (ISI) policy at as low as reasonably achievable radiation exposure. This paper presents a new methodology to develop plant-specific sampling strategies and acceptance criteria for ISI of steam generator tubes using a risk assessment approach. Based on plant-specific data augmented by industry data, the methodology is currently being applied to Salem units 1 and 2 steam generator tube inspections during refueling outages IRF10 and 2RF6.
- OSTI ID:
- 7056189
- Report Number(s):
- CONF-920606--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 65
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
BOILERS
CHEMICAL REACTIONS
CORROSION
DECISION MAKING
EDDY CURRENT TESTING
ELECTROMAGNETIC TESTING
ENRICHED URANIUM REACTORS
FUEL CYCLE
FUEL MANAGEMENT
IMPLEMENTATION
IN-SERVICE INSPECTION
INSPECTION
INTERGRANULAR CORROSION
MATERIALS TESTING
NONDESTRUCTIVE TESTING
OCCUPATIONAL EXPOSURE
POWER REACTORS
PWR TYPE REACTORS
RADIATION PROTECTION
REACTOR FUELING
REACTOR SAFETY
REACTORS
SAFETY
SALEM-1 REACTOR
SALEM-2 REACTOR
STEAM GENERATORS
TESTING
THERMAL REACTORS
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
BOILERS
CHEMICAL REACTIONS
CORROSION
DECISION MAKING
EDDY CURRENT TESTING
ELECTROMAGNETIC TESTING
ENRICHED URANIUM REACTORS
FUEL CYCLE
FUEL MANAGEMENT
IMPLEMENTATION
IN-SERVICE INSPECTION
INSPECTION
INTERGRANULAR CORROSION
MATERIALS TESTING
NONDESTRUCTIVE TESTING
OCCUPATIONAL EXPOSURE
POWER REACTORS
PWR TYPE REACTORS
RADIATION PROTECTION
REACTOR FUELING
REACTOR SAFETY
REACTORS
SAFETY
SALEM-1 REACTOR
SALEM-2 REACTOR
STEAM GENERATORS
TESTING
THERMAL REACTORS
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS