Criteria for safety-related nuclear power plant operator actions: initial pressurized water reactor (PWR) simulator exercises
Technical Report
·
OSTI ID:5320626
Nuclear plant control room simulator exercises for seven pressurized water reactor (PWR) events were conducted with ten control room teams. Operator performance was recorded by an automatic Performance Measurement System (PMS) and by subjective evaluation. Response times and error probabilities were estimated for selected actions. The effect of some experimental variables on operator performance is discussed. Application of the response time data to ANSI Standard N660 is included. The data collected will later be compared to field data being collected for similar events in order to provide a basis for extrapolation of simulator data to actual operating conditions. Ultimately, a base of human performance data will be developed from simulator experiments which can be used to establish criteria and standards, evaluate effects of key performance-shaping factors, and support safety/risk assessment analyses.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 5320626
- Report Number(s):
- NUREG/CR-1908; ORNL/NUREG/TM-434; ON: TI85015985
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ANALOG SYSTEMS
CONTROL ROOMS
ERRORS
FUNCTIONAL MODELS
HUMAN FACTORS
PERFORMANCE
PERSONNEL
PWR TYPE REACTORS
REACTOR OPERATORS
REACTOR SAFETY
REACTORS
SAFETY
SIMULATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ANALOG SYSTEMS
CONTROL ROOMS
ERRORS
FUNCTIONAL MODELS
HUMAN FACTORS
PERFORMANCE
PERSONNEL
PWR TYPE REACTORS
REACTOR OPERATORS
REACTOR SAFETY
REACTORS
SAFETY
SIMULATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS