Evaluation of corrective action data for reportable events at commercial nuclear power plants
805The Nuclear Regulatory Commission (NRC) approved the adoption of cause codes for reportable events as a new performance indicator (PI) in March 1989. Corrective action data associated with the causes of events were to be compiled also. The corrective action data was considered as supplemental information but not identified formally as a performance indicator. In support of NRC, the Nuclear Operations Analysis Center (NOAC) at the Oak Ridge National Laboratory (ORNL) has been routinely evaluating licensee event reports (LERs) for cause code and corrective action data since 1989. The compilation of corrective action data by NOAC represents the first systematic and comprehensive compilation of this type data. The thrust of analyzing the corrective action data was to identify areas where licensees allocated resources to solve problems and prevent the recurrence of personnel errors and equipment failures. The predominant areas of corrective action reported by licensees are to be evaluated by NRC to compare with NRC programs designed to improve plant performance. The set of corrective action codes used to correlate with individual cause codes and included in the analyses were: training, procedural modification, corrective discipline, management change, design modification, equipment replacement/adjustment, other, and unknown. 1 fig.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- Sponsoring Organization:
- USNRC; Nuclear Regulatory Commission, Washington, DC (USA)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 6076007
- Report Number(s):
- CONF-910603-2; ON: DE91007275; TRN: 91-010485
- Resource Relation:
- Conference: Annual meeting of the American Nuclear Society (ANS), Orlando, FL (USA), 2-6 Jun 1991
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
NUCLEAR POWER PLANTS
REACTOR ACCIDENTS
TRANSIENTS
REPORTING REQUIREMENTS
ADJUSTMENTS
ADMINISTRATIVE PROCEDURES
COMMUNICATIONS
DESIGN
ERRORS
FAILURES
HUMAN FACTORS
MANAGEMENT
OPTIMIZATION
ORNL
PERFORMANCE
REACTOR COMPONENTS
REACTOR CONTROL SYSTEMS
REACTOR INSTRUMENTATION
REACTOR MONITORING SYSTEMS
REMEDIAL ACTION
SPECIFICATIONS
TRAINING
US NRC
ACCIDENTS
CONTROL SYSTEMS
NATIONAL ORGANIZATIONS
NUCLEAR FACILITIES
POWER PLANTS
THERMAL POWER PLANTS
US AEC
US DOE
US ERDA
US ORGANIZATIONS
220900* - Nuclear Reactor Technology- Reactor Safety
210800 - Nuclear Power Plants- Economics