Safety-related operator actions: methodology for developing criteria
Description
This report presents a methodology for developing criteria for design evaluation of safety-related actions by nuclear power plant reactor operators, and identifies a supporting data base. It is the eleventh and final NUREG/CR Report on the Safety-Related Operator Actions Program, conducted by Oak Ridge National Laboratory for the US Nuclear Regulatory Commission. The operator performance data were developed from training simulator experiments involving operator responses to simulated scenarios of plant disturbances; from field data on events with similar scenarios; and from task analytic data. A conceptual model to integrate the data was developed and a computer simulation of the model was run, using the SAINT modeling language. Proposed is a quantitative predictive model of operator performance, the Operator Personnel Performance Simulation (OPPS) Model, driven by task requirements, information presentation, and system dynamics. The model output, a probability distribution of predicted time to correctly complete safety-related operator actions, provides data for objective evaluation of quantitative design criteria
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A08/MF A01; 1 as DE84008552.
Files
Additional details
Publishing Information
- Imprint Pagination
- 154 p.
- Report number
- NUREG/CR--3515
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 16006970
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BWR TYPE REACTORS; CONTROL ROOMS; ENGINEERING; FAILURES; FAULT TREE ANALYSIS; HUMAN FACTORS; MATHEMATICAL MODELS; NUCLEAR POWER PLANTS; PERFORMANCE; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR OPERATORS; REACTOR SAFETY; RELIABILITY
- Descriptors DEC
- ENRICHED URANIUM REACTORS; NUCLEAR FACILITIES; PERSONNEL; POWER PLANTS; POWER REACTORS; REACTORS; SAFETY; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- ORNL/TM--8942.