Initiating Event Frequencies for Internal Flooding and High-Energy Line Break PRAs

Utilities that operate nuclear power plants are increasingly using probabilistic risk assessments (PRAs) to make day-to-day decisions on design, operations, and maintenance and to support risk-informed applications. These applications require high-quality and complete PRAs to ensure that the decisions and proposed changes are technically well-founded. Such PRAs include the modeling and quantification of PRA models for accident sequences initiated by internal floods and high-energy line breaks. To support PRA updates and upgrades for such sequences, the Electric Power Research Institute (EPRI) has sponsored ongoing research to develop and refine guidance and generic data that can be used to estimate initiating event frequencies for internal flood- and high-energy line break-induced accident sequences. In 2023, EPRI published the fifth revision of a generic database for these initiating event frequencies. This revision produced advancements in the methodology for passive component reliability, including the quantification of aging effects on pipe rupture frequencies and the capability to adjust these frequencies to account for enhancements to integrity management strategies associated with leak inspections and non-destructive examinations. The purpose of this paper is to present these enhancements and illustrate their application with selected examples.

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Publication Details

Journal
Journal of Nuclear Engineering
Published
2025-09-16
DOI
https://doi.org/10.3390/jne6030037
Primary Topic
Risk and Safety Analysis
Type
article
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article

Initiating Event Frequencies for Internal Flooding and High-Energy Line Break PRAs

Mary Presley, Bengt Lydell, K.N. Fleming, Wadie Chalgham et al.
Journal of Nuclear Engineering
Risk and Safety Analysis
article

Initiating Event Frequencies for Internal Flooding and High-Energy Line Break PRAs

Mary Presley, Bengt Lydell, K.N. Fleming, Wadie Chalgham, Ali Mosleh
article en

Abstract

Utilities that operate nuclear power plants are increasingly using probabilistic risk assessments (PRAs) to make day-to-day decisions on design, operations, and maintenance and to support risk-informed applications. These applications require high-quality and complete PRAs to ensure that the decisions and proposed changes are technically well-founded. Such PRAs include the modeling and quantification of PRA models for accident sequences initiated by internal floods and high-energy line breaks. To support PRA updates and upgrades for such sequences, the Electric Power Research Institute (EPRI) has sponsored ongoing research to develop and refine guidance and generic data that can be used to estimate initiating event frequencies for internal flood- and high-energy line break-induced accident sequences. In 2023, EPRI published the fifth revision of a generic database for these initiating event frequencies. This revision produced advancements in the methodology for passive component reliability, including the quantification of aging effects on pipe rupture frequencies and the capability to adjust these frequencies to account for enhancements to integrity management strategies associated with leak inspections and non-destructive examinations. The purpose of this paper is to present these enhancements and illustrate their application with selected examples.

Journal of Nuclear EngineeringVol. 6(3)
Electric Power Research Institute (US), Orthopaedic Center of Vero Beach (US), Samueli Institute (US), ABS Consulting (United States) (US)
Openalex Percentile: Top 75%
Risk and Safety Analysis
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