Risk Importance Measures in the Design and Operation of Nuclear Power Plants

Vrbanić, Ivan; Samanta, Pranab; Bašić, Ivica

doi:10.1115/1.861394

Cited by 8 publications

(3 citation statements)

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“…Components with a RAW value equal to or greater than 2, CCF RAW value equal to or greater than 20, or FV equal to or greater than 0.005 were considered to be of significant risk [5].…”

Section: Methodsmentioning

confidence: 99%

Development of the Reliability Assurance Program in a Brazilian nuclear power plant subsidized by a Reliability, Availability and Maintainability Model

Gomes,

Neto,

Maturana

et al. 2023

Braz. J. Rad. Sci.

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The main objective of this work is to present a methodology for the development of a Reliability Assurance Program (RAP) specific to a PWR experimental nuclear installation, through the analysis of the installation and the development of a preliminary RAP subsidized by a Reliability, Availability and Maintainability (RAM) model. The study of an evaluation was carried out in the long-term decay heat removal of the studied experimental plant, whose data were used for application of the RAP. The necessary steps for applying the developed RAP are followed, using the data from the assessment of the studied plant, resulting in a list of components of significant risk for the Program, and in the following steps of sending the list to the experts panel, ranking of SSCs by the panel and development of the final list of significant risk SSCs for using the list in the optimization of the plant. The RAP subsidized by a RAM model will be able to work with the logical relationships between each component of the plant for their effects on energy generation and with the quantitative prediction of the magnitude of each contributor to the occurrence of high-level events, and the developed methodology can be applicable throughout the experimental plant. In this way, it will be possible to implement the RAP in the plant, which will provide a structured way to meet the regulatory requirements for its licensing. Also, it will be possible to complement the plant safety analysis report, which must contain the RAP.

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“…Components with a RAW value equal to or greater than 2, CCF RAW value equal to or greater than 20, or FV equal to or greater than 0.005 were considered to be of significant risk [5].…”

Section: Methodsmentioning

confidence: 99%

Development of the Reliability Assurance Program in a Brazilian nuclear power plant subsidized by a Reliability, Availability and Maintainability Model

Gomes,

Neto,

Maturana

et al. 2023

Braz. J. Rad. Sci.

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show abstract

“…This cycle is relatively convoluted, is dependent upon interpretation, and now and again requires extra assessments. Accessibility of measures that can be straightforwardly associated with a segment of a safety system, "component level" significance measures, can work on the utilization of these actions in numerous applications [13].…”

Section: Author Detailsmentioning

confidence: 99%

Introductory Chapter: An Overview of Reliability and Risk Analysis

Zubair¹,

Ahmed²

2021

Practical Applications in Reliability Engineering

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“…The above relation was discussed, e.g., in [8] which also provides its demonstration by calculations based on a PSA model. Thus, the importance measures RAW and RRW for particular failure event are related to each other, with probability of considered failure event as a parameter.…”

mentioning

confidence: 95%

Basic Relation between RAW and RRW and Some of Its Implications on Risk Reduction Strategies

Vrbanić¹,

Bašić²,

Samanta³

2022

joe

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In using risk-informed approaches for ensuring safety of operating nuclear power plants (NPPs), risk importance measures obtained from probabilistic safety assessments (PSAs) of the plants are integral elements of consideration in many cases. In PSA models and applications associated with NPPs the risk importance of a particular feature (e.g. function, system, component, failure mode or operator action) can be, most generally, divided into two categories: importance with respect to risk increase potential and importance with respect to risk decrease potential. The representative of the first category, as used for practical purposes, is Risk Achievement Worth (RAW). Representative of the second category, as mentioned in consideration of risk importance, is Risk Reduction Worth (RRW). It can be shown that the two risk importance measures, RAW and RRW, are dependent on each other. The only parameter in this mutual dependency is probability of failure of the considered feature. The paper discusses the relation between RAW and RRW and some of its implications, including those on the general strategies for the reduction of risk imposed for the operation of the considered facility. Two general risk reduction strategies which are considered in the discussion are: a) risk reduction by decreasing the failure probability of the considered feature; and b) risk reduction while keeping the failure probability of the considered feature at the same level. Simple examples are provided to illustrate the differences between two strategies and point to main issues and conclusions.

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Risk Importance Measures in the Design and Operation of Nuclear Power Plants

Cited by 8 publications

References 0 publications

Development of the Reliability Assurance Program in a Brazilian nuclear power plant subsidized by a Reliability, Availability and Maintainability Model

Development of the Reliability Assurance Program in a Brazilian nuclear power plant subsidized by a Reliability, Availability and Maintainability Model

Introductory Chapter: An Overview of Reliability and Risk Analysis

Basic Relation between RAW and RRW and Some of Its Implications on Risk Reduction Strategies

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