TY - GEN
T1 - Simulation-based Recovery Action Analysis Using the EMRALD Dynamic Risk Assessment Tool
AU - Park, Jooyoung
AU - Pope, Chad
AU - Heo, Yunyeong
AU - Boring, Ronald
AU - Prescott, Steven
N1 - Funding Information:
This work was supported by the Risk-Informed System Analysis (RISA) Pathway of the U.S. Department of Energys’ Light aW ter Reactor Sustainability Program and the Laboratory Directed Research and Development funding of Idaho National Laboratory.
Funding Information:
This work was supported by the Risk-Informed System Analysis (RISA) Pathway of the U.S. Department of Energy’s Light Water Reactor Sustainability Program and the Laboratory Directed Research and Development funding of Idaho National Laboratory.
Publisher Copyright:
© 2023 American Nuclear Society, Incorporated.
PY - 2023
Y1 - 2023
N2 - A recovery action is defined as an action that prevents deviant conditions from producing unwanted effects. Recovery action evaluations are a critical part of human reliability analysis (HRA). However, limitations arise when treating recovery actions by using currently available HRA methods only. Representatively speaking, the existing recovery analysis methods do not explicitly consider the various recovery task types and recovery sequences that occur at actual NPPs. To handle challenges stemming from the existing recovery analysis methods, this study proposes a way to analyze recovery actions by employing the dynamic HRA method known as the Procedure-based Risk Investigation Method – HRA (PRIME-HRA). Through PRIME-HRA, dynamic simulation models can be developed using dynamic risk assessment tools such as Event Modeling Risk Assessment Using Linked Diagrams (EMRALD) [1] and the Human Unimodel for Nuclear Technology to Enhance Reliability (HUNTER) [2]. EMRALD and HUNTER are dynamic probabilistic risk assessment (PRA)/HRA tools developed at Idaho National Laboratory. This paper explores the differences between THERP, CBDT, and K-HRA in regard to recovery action analysis. It relates the challenges that stem from these approaches, and how we successfully developed PRIME-HRA. Finally, the proposed approach to analyzing recovery human actions within a dynamic context is touched upon, along with an example.
AB - A recovery action is defined as an action that prevents deviant conditions from producing unwanted effects. Recovery action evaluations are a critical part of human reliability analysis (HRA). However, limitations arise when treating recovery actions by using currently available HRA methods only. Representatively speaking, the existing recovery analysis methods do not explicitly consider the various recovery task types and recovery sequences that occur at actual NPPs. To handle challenges stemming from the existing recovery analysis methods, this study proposes a way to analyze recovery actions by employing the dynamic HRA method known as the Procedure-based Risk Investigation Method – HRA (PRIME-HRA). Through PRIME-HRA, dynamic simulation models can be developed using dynamic risk assessment tools such as Event Modeling Risk Assessment Using Linked Diagrams (EMRALD) [1] and the Human Unimodel for Nuclear Technology to Enhance Reliability (HUNTER) [2]. EMRALD and HUNTER are dynamic probabilistic risk assessment (PRA)/HRA tools developed at Idaho National Laboratory. This paper explores the differences between THERP, CBDT, and K-HRA in regard to recovery action analysis. It relates the challenges that stem from these approaches, and how we successfully developed PRIME-HRA. Finally, the proposed approach to analyzing recovery human actions within a dynamic context is touched upon, along with an example.
KW - Dynamic Risk Assessment
KW - Human Reliability Analysis
KW - Recovery Analysis
UR - http://www.scopus.com/inward/record.url?scp=85183327039&partnerID=8YFLogxK
U2 - 10.13182/NPICHMIT23-41090
DO - 10.13182/NPICHMIT23-41090
M3 - Conference contribution
AN - SCOPUS:85183327039
T3 - Proceedings of 13th Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies, NPIC and HMIT 2023
SP - 840
EP - 847
BT - Proceedings of 13th Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies, NPIC and HMIT 2023
PB - American Nuclear Society
T2 - 13th Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies, NPIC and HMIT 2023
Y2 - 15 July 2023 through 20 July 2023
ER -