Analysis of corrective action data from trial program on programmatic performance indicators
The Nuclear Regulatory Commission (NRC) is considering the use of cause codes as performance indicators (PIs) to monitor licensee performance. In conjunction with the cause codes, corrective action codes are also under consideration to describe licensee corrective actions for problems as represented by the cause codes. The set of cause codes and corrective actions employed in a trial program to assess their usefulness included: (1) administrative error -- training; (2) design/installation -- procedure modification; (3) fabrication error -- discipline; (4) random equipment failure -- management change; (5) licensed operator error -- design modification; and (6) other personal error -- equipment replacement/adjustment. These causes were selected to represent a broad range of licensee programs, hence the designation of programmatic PIs, that could be monitored in a systematic manner to identify trends in performance. They should establish a basis and focus for further investigation of a particular programmatic area if undesirable trends are evidence. 2 figs.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- Sponsoring Organization:
- USNRC
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 6976001
- Report Number(s):
- CONF-890833-1; ON: DE90008886; TRN: 90-010333
- Resource Relation:
- Conference: 14. biennial conference on reactor operating experience: plant operations - the human element, Charlotte, NC (USA), 6-9 Aug 1989
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
NUCLEAR POWER PLANTS
REACTOR LICENSING
PERFORMANCE TESTING
COMPUTERIZED SIMULATION
DATA PROCESSING
DESIGN
FAILURE MODE ANALYSIS
FREQUENCY ANALYSIS
MODIFICATIONS
MONITORING
PROGRAM MANAGEMENT
REACTOR MAINTENANCE
REACTOR OPERATION
REACTOR OPERATORS
REACTOR SAFETY
TRAINING
US NRC
LICENSING
MAINTENANCE
MANAGEMENT
NATIONAL ORGANIZATIONS
NUCLEAR FACILITIES
OPERATION
PERSONNEL
POWER PLANTS
PROCESSING
SAFETY
SIMULATION
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
TESTING
THERMAL POWER PLANTS
US ORGANIZATIONS
220900* - Nuclear Reactor Technology- Reactor Safety
210700 - Nuclear Power Plants- Regulation & Licensing
990200 - Mathematics & Computers