Babcock and Wilcox Owners' Group program: Trip reduction and transient response improvement
In 1985, the average trip frequency for the industry was 4.3 trips per plant per year while Babcock Wilcox (B W)-designed plants had 4.5 trips. In early 1986, the B W Owners' Group (B WOG) established goals to reduce trip frequency and improve posttrip transient response. Through the recommendations of the B WOG Trip Reduction and Transient Response Improvement Program (TR/TRIP) and other utility initiatives, the trip frequency for the B WOG plants has been on a progressive downward trend and has been consistently below the industry average since 1986. The successful results in trip reduction for the B WOG plants are shown. The B WOG has implemented several programs that have resulted in fewer trips per plant. This success can be attributed to the following: (1) a comprehensive program to evaluate each trip and transient for root-cause determination, define corrective actions, share information, and peer reviews; (2) a broad program to review systems and components that contribute to trips and transients, identify specific recommendations to correct deficiencies, utility commitment to implementation, conduct internal monitoring and indirectly exert peer pressure; (3) an awareness of the goals at all levels in the organization coupled with strong executive-level involvement; and (4) timely implementation of recommendations.
- OSTI ID:
- 6923632
- Report Number(s):
- CONF-890604-; CODEN: TANSA; TRN: 90-023405
- Journal Information:
- Transactions of the American Nuclear Society; (USA), Vol. 59; Conference: Annual meeting of the American Nuclear Society, Atlanta, GA (USA), 4-8 Jun 1989; ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
Similar Records
The Joint Owners' Group Program on MOV Periodic Verification
A probabilistic evaluation of the safety of Babcock and Wilcox nuclear reactor power plants with emphasis on historically observed operational events
Related Subjects
BW STANDARD REACTOR
SCRAM
REACTOR OPERATION
OPTIMIZATION
DATA ANALYSIS
DATA BASE MANAGEMENT
ECCS
EMERGENCY PLANS
FEEDWATER
IMPLEMENTATION
PERFORMANCE
PRIMARY COOLANT CIRCUITS
PROBABILITY
PROGRAM MANAGEMENT
REACTOR CONTROL SYSTEMS
REACTOR INSTRUMENTATION
REACTOR MAINTENANCE
REACTOR SAFETY
RECOMMENDATIONS
RISK ASSESSMENT
SECONDARY COOLANT CIRCUITS
SENSITIVITY
STEAM GENERATORS
SYSTEM FAILURE ANALYSIS
TRANSIENTS
BOILERS
CONTROL SYSTEMS
COOLING SYSTEMS
ENERGY SYSTEMS
ENGINEERED SAFETY SYSTEMS
HYDROGEN COMPOUNDS
MAINTENANCE
MANAGEMENT
OPERATION
OXYGEN COMPOUNDS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR PROTECTION SYSTEMS
REACTOR SHUTDOWN
REACTORS
SAFETY
SHUTDOWNS
SYSTEMS ANALYSIS
VAPOR GENERATORS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200* - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled