“…(Swain and Guttmann 1983). The NUREG/CR series, prepared by NRC contractors, provide analytical methods and technical information that have been incorporated into this guide and could be the source of additional information that supports the PSA.…”
Section: Handbook Of Human Reliability Analysis With Emphasis On Nuclmentioning
confidence: 99%
“…Early PRA studies during the 1970s (e.g., the Reactor Safety Study: An Assessment of Accident Risks in US Commercial Nuclear Power Plants (NRC 1975)) demonstrated the uses of ET and FT modeling of accident sequences for complex nuclear reactor power plants, and identified instances in which human interactions with the plant systems could hinder (exacerbate) or help (ameliorate) the initiation or propagation of event sequences. The Reactor Safety Study (NRC 1975) was supported by an early version of the Handbook of Human Reliability Analysis with Emphasis on Nuclear Power Plant Operations (Swain and Guttmann 1983). The early PRAs also served to identify areas where HRA methodology was weak and in need of improvement to adequately model the interactions and to quantify the probability of such actions.…”
“…(Swain and Guttmann 1983). The NUREG/CR series, prepared by NRC contractors, provide analytical methods and technical information that have been incorporated into this guide and could be the source of additional information that supports the PSA.…”
Section: Handbook Of Human Reliability Analysis With Emphasis On Nuclmentioning
confidence: 99%
“…Early PRA studies during the 1970s (e.g., the Reactor Safety Study: An Assessment of Accident Risks in US Commercial Nuclear Power Plants (NRC 1975)) demonstrated the uses of ET and FT modeling of accident sequences for complex nuclear reactor power plants, and identified instances in which human interactions with the plant systems could hinder (exacerbate) or help (ameliorate) the initiation or propagation of event sequences. The Reactor Safety Study (NRC 1975) was supported by an early version of the Handbook of Human Reliability Analysis with Emphasis on Nuclear Power Plant Operations (Swain and Guttmann 1983). The early PRAs also served to identify areas where HRA methodology was weak and in need of improvement to adequately model the interactions and to quantify the probability of such actions.…”
“…Human error probabilities for performing various tasks may be approximated from anticipated operator actions in the Handbook of Human Reliability Analysis with Emphasis on Nuclear Power Plant Applications Final Report (NUREGKR-1278) (Swain and Guttmann 1983). The use of NUREGKR-1278 is applicable to the Monitored Geologic Repository (MGR) since this will be a NRC regulated facility that will have equipment reliability and procedural requirements similar to those implemented at nuclear power plants.…”
“…As most individuals in the nuclear industry know, one of the most complete sources of procedural based information can be found in NUREG/CR-1278. (6) in this case, individual errors are recorded as derived from expert opinion based principally on military experience. In addition, the concept of expert opinion and the use of information from the expert opinion approach to develop generic data has been carried forward in two recent experiments.…”
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