Study on a new framework of Human Reliability Analysis to evaluate soft control execution error in advanced MCRs of NPPs

Since the Three Mile Island (TMI)-2 accident, human error has been recognized as one of the main causes of Nuclear Power Plant (NPP) accidents, and numerous studies related to Human Reliability Analysis (HRA) have been carried out. Most of these methods were developed considering the conventional type of Main Control Rooms (MCRs). However, the operating environment of MCR5 in NPPs has changed with the adoption of new Human-System Interfaces (HSIs) that are based on computer-based technologies. The MCRs that include these digital technologies, such as large display panels, computerized procedures, and soft controls, are called advanced MCRs. Among the many features of advanced MCRs, soft controls are a particularly important feature because operating actions in NPP advanced MCRs are performed by soft control. Due to the differences in interfaces between soft control and hardwired conventional type control, different Human Error Probabilities (HEPs) and a new HRA framework should be considered in the HRA for advanced MCRs. To this end, a new framework of a HRA method for evaluating soft control execution human error is suggested by performing a soft control task analysis and the literature regarding widely accepted human error taxonomies is reviewed. Moreover, since most current HRA databases deal with operation in conventional MCRs and are not explicitly designed to deal with digital HSIs, empirical analysis of human error and error recovery considering soft controls under an advanced MCR mockup are carried out to collect human error data, which is essential to estimate the final HEP using the proposed framework of the HRA method. Finally, final HEPs in advanced MCRs are estimated by integrating the suggested HRA framework, and a nominal HEP and recovery failure probability database developed from empirical studies.
Publisher
PERGAMON-ELSEVIER SCIENCE LTD
Issue Date
2016-05
Language
ENG
Keywords

MAIN CONTROL; PROBABILITIES; IDENTIFICATION; HRA

Citation

ANNALS OF NUCLEAR ENERGY, v.91, pp.92 - 104

ISSN
0306-4549
DOI
10.1016/j.anucene.2016.01.007
URI
http://hdl.handle.net/10203/208465
Appears in Collection
NE-Journal Papers(저널논문)
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