An Investigation of Fire Human Reliability Analysis (HRA) Factors for Quantification of Post-fire Operator Manual Actions (OMA) 


Vol. 38,  No. 6, pp. 72-78, Dec.  2023
10.14346/JKOSOS.2023.38.6.72


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  Abstract

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.

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  Cite this article

[IEEE Style]

최선영, 강대일, 정용훈, "An Investigation of Fire Human Reliability Analysis (HRA) Factors for Quantification of Post-fire Operator Manual Actions (OMA)," Journal of the Korean Society of Safety, vol. 38, no. 6, pp. 72-78, 2023. DOI: 10.14346/JKOSOS.2023.38.6.72.

[ACM Style]

최선영, 강대일, and 정용훈. 2023. An Investigation of Fire Human Reliability Analysis (HRA) Factors for Quantification of Post-fire Operator Manual Actions (OMA). Journal of the Korean Society of Safety, 38, 6, (2023), 72-78. DOI: 10.14346/JKOSOS.2023.38.6.72.

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