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RISS 인기검색어
- 검색키워드
- 저자 : Hallbert, Bruce P. (검색결과 4 건)
- 무료
- 기관 내 무료
- 유료
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HUMAN ERRORS DURING THE SIMULATIONS OF AN SGTR SCENARIO: APPLICATION OF THE HERA SYSTEM
WONDEA JUNG,APRIL M. WHALEY,BRUCE P. HALLBERT 한국원자력학회 2009 Nuclear Engineering and Technology Vol.41 No.10
Due to the need of data for a Human Reliability Analysis (HRA), a number of data collection efforts have been undertaken in several different organizations. As a part of this effort, a human error analysis that focused on a set of simulator records on a Steam Generator Tube Rupture (SGTR) scenario was performed by using the Human Event Repository and Analysis (HERA) system. This paper summarizes the process and results of the HERA analysis, including discussions about the usability of the HERA system for a human error analysis of simulator data. Five simulated records of an SGTR scenario were analyzed with the HERA analysis process in order to scrutinize the causes and mechanisms of the human related events. From this study, the authors confirmed that the HERA was a serviceable system that can analyze human performance qualitatively from simulator data. It was possible to identify the human related events in the simulator data that affected the system safety not only negatively but also positively. It was also possible to scrutinize the Performance Shaping Factors (PSFs) and the relevant contributory factors with regard to each identified human event.
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Nelson, Pamela F.,Martin-Del-Campo, Cecilia,Hallbert, Bruce,Mosleh, Ali Korean Nuclear Society 2016 Nuclear Engineering and Technology Vol.48 No.1
The development of operational performance indicators is of utmost importance for nuclear power plants, since they measure, track, and trend plant operation. Leading indicators are ideal for reducing the likelihood of consequential events. This paper describes the operational data analysis of the information contained in the Corrective Action Program. The methodology considers human error and organizational factors because of their large contribution to consequential events. The results include a tool developed from the data to be used for the identification, prediction, and reduction of the likelihood of significant consequential events. This tool is based on the resilience curve that was built from the plant's operational data. The stress is described by the number of unresolved condition reports. The strain is represented by the number of preventive maintenance tasks and other periodic work activities (i.e., baseline activities), as well as, closing open corrective actions assigned to different departments to resolve the condition reports (i.e., corrective action workload). Beyond the identified resilience threshold, the stress exceeds the station's ability to operate successfully and there is an increased likelihood that a consequential event will occur. A performance indicator is proposed to reduce the likelihood of consequential events at nuclear power plants.
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HUMAN ERRORS DURING THE SIMULATIONS OF AN SGTR SCENARIO: APPLICATION OF THE HERA SYSTEM
Jung, Won-Dea,Whaley, April M.,Hallbert, Bruce P. Korean Nuclear Society 2009 Nuclear Engineering and Technology Vol.41 No.10
Due to the need of data for a Human Reliability Analysis (HRA), a number of data collection efforts have been undertaken in several different organizations. As a part of this effort, a human error analysis that focused on a set of simulator records on a Steam Generator Tube Rupture (SGTR) scenario was performed by using the Human Event Repository and Analysis (HERA) system. This paper summarizes the process and results of the HERA analysis, including discussions about the usability of the HERA system for a human error analysis of simulator data. Five simulated records of an SGTR scenario were analyzed with the HERA analysis process in order to scrutinize the causes and mechanisms of the human related events. From this study, the authors confirmed that the HERA was a serviceable system that can analyze human performance qualitatively from simulator data. It was possible to identify the human related events in the simulator data that affected the system safety not only negatively but also positively. It was also possible to scrutinize the Performance Shaping Factors (PSFs) and the relevant contributory factors with regard to each identified human event.
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Pamela F. Nelson,Cecilia Martin-Del-Campo,Bruce Hallbert,Ali Mosleh 한국원자력학회 2016 Nuclear Engineering and Technology Vol.48 No.1
The development of operational performance indicators is of utmost importance for nuclearpower plants, since they measure, track, and trend plant operation. Leading indicatorsare ideal for reducing the likelihood of consequential events. This paper describesthe operational data analysis of the information contained in the Corrective Action Program. The methodology considers human error and organizational factors because of theirlarge contribution to consequential events. The results include a tool developed from thedata to be used for the identification, prediction, and reduction of the likelihood of significantconsequential events. This tool is based on the resilience curve that was built fromthe plant's operational data. The stress is described by the number of unresolved conditionreports. The strain is represented by the number of preventive maintenance tasks andother periodic work activities (i.e., baseline activities), as well as, closing open correctiveactions assigned to different departments to resolve the condition reports (i.e., correctiveaction workload). Beyond the identified resilience threshold, the stress exceeds the station'sability to operate successfully and there is an increased likelihood that a consequentialevent will occur. A performance indicator is proposed to reduce the likelihood ofconsequential events at nuclear power plants.
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