Development of Human Factors Validation System for the Advanced Control Room of APR1400

LEE, Myeong Soo; Hong, Jin; Suh, Jeong Kwan; Lee, Seung Ho; Hwang, Do Hyun

doi:10.3327/jnst.46.90

Cited by 3 publications

(1 citation statement)

References 2 publications

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“…We pieced together the development of the detailed hardware architecture from multiple documentation and published sources on the APR1400 [4,[19][20][21][22][23][24][25], as an exact and verified diagram is proprietary. Therefore, the constructed diagrams included in this paper are approximate or fictious representations based on the described connections and functionality.…”

Section: Assumption 2: Internal Architecture Is Approximatedmentioning

confidence: 99%

Systems-Theoretic Hazard Analysis of Digital Human-System Interface Relevant to Reactor Trip

Chen¹,

Dinh²,

Han³

et al. 2021

12th Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies (NPIC&HMIT 2021)

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Human-system interface is one of the key advanced design features applied to modern digital instrumentation and control systems of nuclear power plants. The conventional design is based on a compact workstation-based system within the control room. The compact workstation provides both a strategic operating environment while also a convenient display for plant status information necessary to the operator. The control environment is further enhanced through display panels, visual and auditory alarms, and procedure systems. However, just like the legacy control, the HSI should incorporate diversity to demonstrate sufficient defense-in-depth protection against common cause failures of the safety system. Furthermore, the vulnerability of the HSI is affected by a plethora of factors, such as human error, cyberattacks, software common cause failures, etc., that complicate the design and analysis. Therefore, this work aims to identify and evaluate existing system vulnerabilities to support the licensing, deployment, and operation of HSI designs, especially the functions that are relevant to a reactor trip. We performed a systematic hazard analysis to investigate potential vulnerabilities within the HSI design using the novel redundancy-guided systems-theoretic hazard analysis. This method was developed and demonstrated by Idaho National Laboratory under a project initiated by the Risk-Informed Systems Analysis Pathway of the U.S. Department of Energy's Light Water Reactor Sustainability Program. The goal of the project is to develop a strong technical basis for risk assessment strategies to support effective, reliable, and licensable digital instrumentation and control technologies.

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Section: Assumption 2: Internal Architecture Is Approximatedmentioning

confidence: 99%

Systems-Theoretic Hazard Analysis of Digital Human-System Interface Relevant to Reactor Trip

Chen¹,

Dinh²,

Han³

et al. 2021

12th Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies (NPIC&HMIT 2021)

View full text Add to dashboard Cite

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Human Error Mode Identification for NPP Main Control Room Operations Using Soft Controls

LEE

KIM

Jang

2011

J. Nucl. Sci. Technol.

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The operation environment of main control rooms (MCRs) in modern nuclear power plants (NPPs) has considerably changed over the years. Advanced MCRs, which have been designed by adapting digital and computer technologies, have simpler interfaces using large display panels, computerized displays, soft controls, computerized procedure systems, and so on. The actions for the NPP operations are performed using soft controls in advanced MCRs. Soft controls have different features from conventional controls. Operators need to navigate the screens to find indicators and controls and manipulate controls using a mouse, touch screens, and so on. Due to these different interfaces, different human errors should be considered in the human reliability analysis (HRA) for advanced MCRs. In this work, human errors that could occur during operation executions using soft controls were analyzed. This work classified the human errors in soft controls into six types, and the reasons that affect the occurrence of the human errors were also analyzed.

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Technical Review on the Localized Digital Instrumentation and Control Systems

Kwon¹,

Lee²

2009

Nuclear Engineering and Technology

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Development of Human Factors Validation System for the Advanced Control Room of APR1400

Cited by 3 publications

References 2 publications

Systems-Theoretic Hazard Analysis of Digital Human-System Interface Relevant to Reactor Trip

Systems-Theoretic Hazard Analysis of Digital Human-System Interface Relevant to Reactor Trip

Human Error Mode Identification for NPP Main Control Room Operations Using Soft Controls

Technical Review on the Localized Digital Instrumentation and Control Systems

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