Criteria for safety-related nuclear-power-plant operator actions: initial boiling-water-reactor (BWR) simulator exercise
Technical Report
·
OSTI ID:6885453
Ten exercises were performed by 24 groups of operators from three utilities. Operator performance was recorded automatically by a program called the Performance Measurement System run on the simulator's computer. Data tapes were subsequently analyzed to extract operator response time (RT) and error rate information. In addition, demographic and subjective data were collected and analyzed in an attempt to identify and evaluate the possible effects of selected performance-shaping factors on operator performance. Operator RTs to the simulated events generally occurred within the intervals allowed in the draft ANSI-N660 design standard; however, they did not appear to be systematically related to the severity of the event, which was the basis for allocation of time margins in the standard. More collective experience in power plant operations was weakly correlated with faster responses. Limited data on omission errors yielded an error rate of greater than five percent.
- Research Organization:
- General Physics Corp., Chattanooga, TN (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 6885453
- Report Number(s):
- NUREG/CR-2534; ORNL/TM-8195; ON: DE83003185
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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22 GENERAL STUDIES OF NUCLEAR REACTORS
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ANALOG SYSTEMS
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210100 -- Power Reactors
Nonbreeding
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ANALOG SYSTEMS
BWR TYPE REACTORS
CONTROL ROOMS
ERRORS
FUNCTIONAL MODELS
HUMAN FACTORS
PERFORMANCE
PERSONNEL
REACTOR OPERATORS
REACTOR SAFETY
REACTOR SIMULATORS
REACTORS
SAFETY
SIMULATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS