• Proceedings of the Korean Institute of Industrial Safety Conference
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• 2002.11a
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• pp.245-248
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• 2002

시스템의 안전에 대한 인적오류(Human Error)의 영향은 심각하지만 구체적인 평가는 매우 어렵다. 주로 사용되는 인간신뢰도분석(HRA : Human Reliability Analysis)은 전체 시스템의 위험도에 대한 정량적 평가를 지원하는 데 집중되고 있고, 세부적인 평가는 개별적인 실험이나 사례에 의존하고 있다. 세부적인 평가나 설계 의사결정 과정을 지원하기가 어렵기 때문에, 종합적인 차원에서 인간공학적 확인 및 검증의 실무가 원활하지 않았다. 이러한 문제의 원인은 인적오류 평가에 활용된 HRA기법의 낙후성과 인적오류 평가가 MMI 설계과정과 잘 연결되지 않은 것이 주된 원인으로 보인다.(중략)

• Nuclear Engineering and Technology
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• v.52 no.1
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• pp.87-100
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• 2020

Performance shaping factors (PSFs) in a human reliability analysis (HRA) are one that may influence human performance in a task. Most currently applicable HRA methods for nuclear power plants (NPPs) use PSFs to highlight human error contributors and to adjust basic human error probabilities (HEPs) that assume nominal conditions of NPPs. Thus far, the effects of PSFs have been treated independently. However, many studies in the fields of psychology and human factors revealed that there may be relationships between PSFs. Therefore, the inter-relationships between PSFs need to be studied to better reflect their effects on operator errors. This study investigates these inter-relationships using two data sources and also suggests a context-based approach to treat the inter-relationships between PSFs. Correlation and factor analyses are performed to investigate the relationship between PSFs. The data sources are event reports of unexpected reactor trips in Korea and an experiment conducted in a simulator featuring a digital control room. Thereafter, context-based approaches based on the result of factor analysis are suggested and the feasibility of the grouped PSFs being treated as a new factor to estimate HEPs is examined using the experimental data.

• Proceedings of the Korean Institute of Industrial Safety Conference
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• 2003.10a
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• pp.225-230
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• 2003

원자력발전소의 안전성을 평가하는 확률론적 안전성평가(PSA) 기법 내에서 인간신뢰도분석(HRA： Human Reliability Analysis)은 파악된 사고경위 중 부적절한 인적행위사건에 대한 분석 및 평가를 담당하고 있다. 여러 HRA 전문가들이 제기하고 있는 기존 PSA HRA의 개선점 중 정성적 분석 관점에서 중요하게 고려되는 사항을 정리하면 다음과 같다. 첫째, 운전원의 진단 및 상황판단 또는 의사결정 단계에서의 특정한 오류 유발사항(error producing conditions or error forcing context)을 분석할 수 있는 방법이 필요하며, 둘째, 다양한 인적오류사건의 고려이다.(중략)

• Journal of the Korean Society of Safety
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• v.17 no.3
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• pp.123-130
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• 2002

This paper presents a new dynamic human reliability analysis method and its application for quantifying the human error probabilities in implementing accident management actions. The action associated with implementation of the cavity flooding during a station blackout sequence is considered for its application. This method is based on the concept of the quantified correlation between the performance requirement and performance achievement. For comparisons of current HRA methods with the new method, the characteristics of THERP, HCR, and SLIM-MAUD, which m most frequency used method in PSAs, are discussed. The MAAP code and Latin Hypercube sampling technique are used to determine the uncertainty of the performance achievement parameter. Meanwhile, the value of the performance requirement parameter is obtained from interviews. Based on these stochastic obtained, human error probabilities are calculated with respect to the various means and variances of the things. It is shown that this method is very flexible in that it can be applied to any kind of the operator actions, including the actions associated with the implementation of accident management strategies.

• Journal of the Korean Institute of Gas
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• v.6 no.4 s.18
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• pp.1-7
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• 2002

Human errors can take place in all levels that include the design, production, construction, operation and maintenance of plant facilities. It was found that the causes were concerned with the effects of human error. This study verified characteristics of the on-site operators and error mechanism, and used the classifying sheet to analyze human error that occurred in process. Also, by applying the ASEP(Accident Sequence Evaluation Program) HRA(Human Reliability Analysis) procedure, the algorithm to estimate the HEP and the ASEP HEP program to analyze human error in the plant were developed. If it is built in on-site, possible human error incident will be prevented and the systematic human error prevention strategy will be devised.

• Nuclear Engineering and Technology
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• v.51 no.1
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• pp.104-115
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• 2019

Since the Fukushima Daiichi accident, there has been an emphasis on the risk resulting from multi-unit accidents. Human reliability analysis (HRA) is one of the important issues in multi-unit probabilistic safety assessment (MUPSA). Hence, there is a need to properly identify all the human and organizational factors relevant to a multi-unit incident scenario in a nuclear power plant (NPP). This study identifies and categorizes the human and organizational factors relevant to a multi-unit incident scenario of NPPs based on a review of relevant literature. These factors are then analyzed to ascertain all possible unit-to-unit interactions that need to be considered in the multi-unit HRA and the pattern of interactions. The human and organizational factors are classified into five categories: organization, work device, task, performance shaping factors, and environmental factors. The identification and classification of these factors will significantly contribute to the development of adequate strategies and guidelines for managing multi-unit accidents. This study is a necessary initial step in developing an effective HRA method for multiple NPP units in a site.

• Proceedings of the ESK Conference
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• 1997.10a
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• pp.295-302
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• 1997

본 논문은 원자력발전소 사고관리 방안의 평가를 위하여인간 신뢰도 분석(Human Reliability Analysis: HRA)을 수행하고, 그 문제점을 보완하기 위하여 가능한 오류에 대한 정성적인 인적오류 분석(Human Error Analysis: HEA)과정을 추가하였다. 인적오류 분석의 기본 체계(framework)를 기법들을 검토하여 사고관리 방안 평가에서 인적오류의 가능성을 분석하는 절차와 대표적인 사례에 대한 분석 결과을 예시하였다.

• Nuclear Engineering and Technology
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• v.52 no.9
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• pp.1983-1989
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• 2020

The human reliability analysis is a method by which, in general terms, the human impact to the safety and risk of a nuclear power plant operation can be modelled, quantified and analysed. It is an indispensable element of the PSA process within the nuclear industry nowadays. The paper herein presents a sensitivity study of the human reliability analysis performed on a real nuclear power plant-specific probabilistic safety assessment model. The analysis is performed on a pre-selected set of post-initiator operator actions. The purpose of the study is to investigate the impact of these operator actions on the plant risk by altering their corresponding human error probabilities in a wide spectrum. The results direct the fact that the future effort should be focused on maintaining the current human reliability level, i.e. not letting it worsen, rather than improving it.

• Proceedings of the KSR Conference
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• 2010.06a
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• pp.2048-2051
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• 2010

Almost all companies have paid much attention to the safety management ranging from maintenance to operation even at the stage of designing in order to prevent accidents, but fatal accidents continue to increase throughout the world. In particular, it is essential to systematically prevent such fatal accidents as fire, explosion or leakage of toxic gas at factories in order to not only protect the workers and neighbors but also prevent economic losses and environmental pollution. In addition, HRA may be used to detect the human errors which may cause accidents or trace back to any mistake on the part of workers. Usually, HRA technique is used in association with other risk assessment techniques. Moreover, it can serve to enumerate the human errors which may occur during operation or down-time or correct the existing system to reduce the mistakes. This work focuses on the coincidence of human error and mechanical failure for management of human error, and on some important performance shaping factors to propose a method for improving safety effectively of the process industries.

• Nuclear Engineering and Technology
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• v.52 no.8
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• pp.1697-1705
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• 2020

To enhance the credibility of human reliability analysis, various kinds of data have been recently collected and analyzed. Although it is obvious that the quality of data is critical, the practices or considerations for securing data quality have not been sufficiently discussed. In this work, based on the experience of the recent human reliability data extraction projects, which produced more than fifty thousand data-points, we derive a number of issues to be considered for generating meaningful data. As a result, thirteen considerations are presented here as pertaining to the four different data extraction activities: preparation, collection, analysis, and application. Although the lessons were acquired from a single kind of data collection framework, it is believed that these results will guide researchers to consider important issues in the process of extracting data.