• Journal of the Ergonomics Society of Korea
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• v.23 no.2
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• pp.13-24
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• 2004

Human error has brought about accidents more than 50% in system of a large size and complicated expecially in nuclear power plants(NPPs). The technology of Man Machine Interface(MMI) has been changed to the digitalized controls employing computer-based technology. According to this trend. the human factors guidelines are becoming main issue for reliable supports to digitalized information displays. However. the existing human factors guidelines is not enough for advanced information display on NPPs. The purpose of this research is to develop the reliable design and evaluation guidelines for advanced information display in main control room (MCR) of NPPs. In this study. the various general human factors guidelines concerning information display on CRT are integrated on data base management system. unified based on the integration rules. and applied in computer based procedures. The use of the integrated guidelines are expected to evaluate the existing information display on MCR in NPPs from the human factors point of view.

• Nuclear Engineering and Technology
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• v.41 no.3
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• pp.237-246
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• 2009

Digitalization of not only non-safety but also safety-grade I &C systems with full computerized Main Control Room (MCR) is the recent trend of I&C systems of nuclear power plants (NPP) around the world, while plant maintenance has been shifting from traditional time based maintenance to condition based maintenance. In order to cope with the new trend of operation and maintenance in NPP, a concept of online distributed diagnostic system for both plant operation and maintenance has been proposed in order to further improve both the plant efficiency and the work environment of plant operation staff members by organizational learning. In this respect, the research subjects of human machine interface (HMI) for the online distributed diagnostic system are also discussed for supporting the plant personnel at both MCR and local working places in the plant by the application of advanced ICT (Information and Communication Technologies).

• Nuclear Engineering and Technology
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• v.39 no.6
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• pp.703-716
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• 2007

As digital and computer technologies have grown, human-machine interfaces (HMIs) have evolved. In safety-critical systems, especially in nuclear power plants (NPPs), HMIs are important for reducing operational costs, the number of necessary operators, and the probability of accident occurrence. Efforts have been made to improve main control room (MCR) interface design and to develop automated or decision support systems to ensure convenient operation and maintenance. In this paper, an integrated decision support system to aid operator cognitive processes is proposed for advanced MCRs of future NPPs. This work suggests the design concept of a decision support system which accounts for an operator's cognitive processes. The proposed system supports not only a particular task, but also the entire operation process based on a human cognitive process model. In this paper, the operator's operation processes are analyzed according to a human cognitive process model and appropriate support systems that support each cognitive process activity are suggested.

• Journal of the Korean Society of Systems Engineering
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• v.5 no.1
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• pp.33-41
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• 2009

The analog or partly digital typed interface of main control room in nuclear power plant (NPP) is gradually being replaced to the totally digitalized interface suitable for the digital environment. SKN 3,4 Nuclear Power Plant is currently developed in such a way to employ advanced displays and controls such as computerized procedure system(CPS), large display panel(LDP), and Soft control. According to the developed design process, the main control room (MCR) of the SKN3,4 was aesthetically designed based on a design concept of the health and sustainability and technically evaluated with human factors guidelines, which somehow lack of the confidence on the evaluation for the rapidly changing digital environment. The suitable review guideline for the digitalized interface and the environment was developed such as the guideline for CPS with information displays on VDU. For the guideline development, tremendous guidelines and technical papers related to evaluation issues of digital environment has been collected, analyzed and transformed to electric database forms and then built on database management system, called Design Review Supporting System to retrieve the appropriate issues for the practical usage of evaluators-in-field.

• Nuclear Engineering and Technology
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• v.51 no.6
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• pp.1554-1560
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• 2019

Development of digital main control rooms (MCRs) has greatly changed operating environments by altering operator tasks, and thus the unique characteristics of digital MCRs should be considered in terms of human reliability analysis. Digital MCR tasks can be divided into primary tasks that directly supply control input to the plant equipment, and secondary tasks that include interface management conducted via soft controls (SCs). Operator performance regarding these secondary tasks must be evaluated since such tasks did not exist in previous analog systems. In this paper, we analyzed SC-related tasks based on simulation data, and classified the error modes of the SCs following analysis of all operational tasks. Then, we defined the factors to be considered in human reliability analysis methods regarding the SCs; such factors are mainly related to interface management and computerized operator support systems. As these support systems function to reduce the number of secondary tasks required for SC, we conducted an assessment to evaluate the efficiency of one such support system. The results of this study may facilitate the development of training programs as well as help to optimize interface design to better reflect the interface management task characteristics of digitalized MCRs.

• Proceedings of the KIEE Conference
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• 1999.07b
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• pp.686-689
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• 1999

발전소 운전원 훈련용 시뮬레이터는 중앙제어실(MCR:Main Control Room) 운전원의 운전결과가 실시간 운영체계하에 발전소 프로세스 모델 및 컴퓨터 시스템과 통합되어 실제 발전소와 같은 반응을 운전원에게 제공하여야 한다. 따라서 시뮬레이터에는 프로세스의 동특성 이외에도 제어시스템의 모델링 및 운전원과 인터페이스되는 제어기들이 실제적으로 구성되어야하며, 이들 제어기와 컴퓨터시스템간 다양한 입력간의 통신 및 동기(Synchronization)가 중요하다. 본 논문에서는 원자력 발전소 시뮬레이터에서 쓰이는 지능형 계기(Intelligent Type Instrument)로 분류된 기기를 살펴보고 시뮬레이션을 위해 개발 구현된 방법들을 기술하고자한다.

• Nuclear Engineering and Technology
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• v.52 no.6
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• pp.1180-1187
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• 2020

A team of operators is required for nuclear power plant operation, and communication between the operators is an important aspect of the team's ability to successfully carry out tasks. It has been difficult to evaluate the quality of this communication though, and as the relationship between communication quality and team performance has yet to be clarified, it has not been applied to most human reliability analysis (HRA) methodologies. This study investigates the relationship between the quality of communication and team performance using data from a full-scope training simulator of a digital main control room (MCR). Two important characteristics of communication were considered to determine quality: each operator's ability to self-confirm the status of a given task in a digital MCR, and the type of communication, as divided into 1-way, 2-way, and 3-way between operators. To measure team performance, the concept of an unsafe act was employed, which is defined as a human error that has the potential to negatively affect plant safety. Analysis results showed that the communication quality and team performance were related to each other. With this more clearly defined relationship, the results of this study can be applied to related performance shaping factors to improve HRA.

• Proceedings of the KIEE Conference
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• 2000.07d
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• pp.2831-2833
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• 2000

Since the access to Station Control Computers(DCCs) is restricted to the main control room(MCR). the operating data of power plants can't be easily analyzed and effectively managed. It is possible to reduce waste of time and human energy by means of building the Remote Monitoring Network of DCCs connected to Local Area Network. automatizing collection and analysis of DCC data. gathering the operating state of power plants. and managing systematically. Furthermore. this system help preventing trip by means of analyzing the data promptly and watching main system continuously.

• Journal of the Korean Society of Safety
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• v.38 no.6
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• pp.72-78
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• 2023

The purpose of this paper is to derive a quantified approach for Operator Manual Actions (OMAs) based on the existing fire Human Reliability Analysis (HRA) methodology developed by the Korea Atomic Energy Research Institute (KAERI). The existing fire HRA method was reviewed, and supplementary considerations for OMA quantification were established through a comparative analysis with NUREG-1852 criteria and the review of the existing literature. The OMA quantification approach involves a timeline that considers the occurrence of Multiple Spurious Operations (MSOs) during a Main Control Room Abandonment (MCRA) determination and movement towards the Remote Shutdown Panel (RSP) in the event of a Main Control Room (MCR) fire. The derived failure probability of an OMA from the approach proposed in this paper is expected to enhance the understanding of its reliability. Therefore, it allows moving beyond the deterministic classification of "reliable" or "unreliable" in NUREG-1852. Also, in the event of a nuclear power plant fire where multiple OMAs are required within a critical time range, it is anticipated that the OMA failure probability could serve as a criterion for prioritizing OMAs and determining their order of importance.

• Proceedings of the Earthquake Engineering Society of Korea Conference
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• 2002.09a
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• pp.341-348
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• 2002

In these days, The base isolation system is often used to improve the seismic capacity of the structures instead of conventional techniques of strengthening the structural members. The purpose of this study is to evaluate dynamic property evaluation of control equipment using lead Lead Rubber Bearing. In this study, a base isolation test of seismic monitoring control cabinet with LRB(lead rubber bearing) was performed. The cabinet will be installed on access floor in MCR(main control room) of nuclear power plant. Details and dynamic characteristics of the access floor were considered in the construction of testing specimen. N-S component of El Centre earthquake was used as seismic input motion. Acceleration response spectrums in the top of cabinets showed that the first mode frequency of cabinet with LRB(lead rubber bearing) was shifted to 7.5 Hz in compared with 18Hz of cabinet without LRB and the maximum peak acceleration was reduced in a degree of22 percent from 2.35 g to 1.84 g