TY - JOUR
T1 - Methodological and Practical Comparison of Integrated Probabilistic Risk Assessment (I-PRA) with the Existing Fire PRA of Nuclear Power Plants
AU - Sakurahara, Tatsuya
AU - Mohaghegh, Zahra
AU - Reihani, Seyed
AU - Kee, Ernie
N1 - Funding Information:
The authors wish to acknowledge the South Texas Project Nuclear Operating Company (STPNOC) for sharing plant data and information. The authors thank Fatma Yilmaz (STPNOC) for providing a critical review of this paper and for invaluable feedback from the nuclear industry perspective. This work made use of the Illinois Campus Cluster, a computing resource that is operated by the Illinois Campus Cluster Program in conjunction with the National Center for Supercomputing Applications and is supported by funds from the University of Illinois at Urbana-Champaign. The PRA model was developed and quantified using the commercial PRA software RISKMAN, developed by ABS Consulting Inc. The authors would like to thank all members of the Socio-Technical Risk Analysis Laboratory (http://soteria.npre.illinois.edu/) for their feedback and especially appreciate the reviews by Pegah Farshadmanesh, Sai Zhang, Justin Pence, and Ha Bui.
Publisher Copyright:
© 2018, © 2018 American Nuclear Society.
PY - 2018/12/2
Y1 - 2018/12/2
N2 - Nearly half of the U.S. nuclear power plants (NPPs) are in the process of transitioning, or have already transitioned, to a risk-informed, performance-based fire protection program. For this transition, Fire Probabilistic Risk Assessment (Fire PRA) is used as a foundation for fire risk evaluation. To increase realism in Fire PRA by reducing conservative bias, the authors have developed an Integrated Probabilistic Risk Assessment (I-PRA) methodological framework that does not require major changes to the existing plant Probabilistic Risk Assessments (PRAs). The underlying failure mechanism models associated with fire events are developed in a separate module, which can be interfaced and connected to the existing plant PRA. This paper explains the areas of methodological advancements in I-PRA, comparing them with the existing Fire PRA of NPPs. This comparison is further demonstrated in a realistic case study that applies the I-PRA framework to a critical fire-induced scenario at an NPP. The core damage frequency (CDF) for the selected scenario, computed by the I-PRA framework, is compared with the results of the Full Compartment Burn screening method and the existing Fire PRA methodology. Using the I-PRA framework, the CDF for the selected scenario has decreased by a factor of 20 compared with the Full Compartment Burn screening approach and by a factor of 2 compared to the existing Fire PRA methodology based on NUREG/CR-6850 and the subsequent NUREGs that have updated the data and methods for individual steps.
AB - Nearly half of the U.S. nuclear power plants (NPPs) are in the process of transitioning, or have already transitioned, to a risk-informed, performance-based fire protection program. For this transition, Fire Probabilistic Risk Assessment (Fire PRA) is used as a foundation for fire risk evaluation. To increase realism in Fire PRA by reducing conservative bias, the authors have developed an Integrated Probabilistic Risk Assessment (I-PRA) methodological framework that does not require major changes to the existing plant Probabilistic Risk Assessments (PRAs). The underlying failure mechanism models associated with fire events are developed in a separate module, which can be interfaced and connected to the existing plant PRA. This paper explains the areas of methodological advancements in I-PRA, comparing them with the existing Fire PRA of NPPs. This comparison is further demonstrated in a realistic case study that applies the I-PRA framework to a critical fire-induced scenario at an NPP. The core damage frequency (CDF) for the selected scenario, computed by the I-PRA framework, is compared with the results of the Full Compartment Burn screening method and the existing Fire PRA methodology. Using the I-PRA framework, the CDF for the selected scenario has decreased by a factor of 20 compared with the Full Compartment Burn screening approach and by a factor of 2 compared to the existing Fire PRA methodology based on NUREG/CR-6850 and the subsequent NUREGs that have updated the data and methods for individual steps.
KW - Fire Probabilistic Risk Assessment
KW - Integrated Probabilistic Risk Assessment framework
KW - NUREG/CR-6850
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U2 - 10.1080/00295450.2018.1486159
DO - 10.1080/00295450.2018.1486159
M3 - Article
AN - SCOPUS:85049945195
SN - 0029-5450
VL - 204
SP - 354
EP - 377
JO - Nuclear Technology
JF - Nuclear Technology
IS - 3
ER -