scholarly journals Development of a Leading Performance Indicator from Operational Experience and Resilience in a Nuclear Power Plant

2016 ◽  
Vol 48 (1) ◽  
pp. 114-128 ◽  
Author(s):  
Pamela F. Nelson ◽  
Cecilia Martin-Del-Campo ◽  
Bruce Hallbert ◽  
Ali Mosleh
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Performance Indicator ◽  
Operational Experience

How a Knowledge Data Base Assists the Process of Aging Management

2011 ◽  
Author(s):  
Horst Rothenho¨fer ◽  
Friedrich Scho¨ckle ◽  
Gu¨nter Ko¨nig
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Data Base ◽  
Nuclear Power ◽  
Collaborative Work ◽  
Operational Experience ◽  
Operational Parameters ◽  
Pdca Cycle ◽  
Definition Of ◽  
Status Analysis

The process of aging management in a nuclear power plant requires collaborative work of different departments. In this process information has to be gathered and evaluated systematically. At the beginning of the process it is important to classify all systems, structures and components (SSCs) into 3 categories of descending importance concerning safety where only the first two categories have to be considered for aging management. Basic information on the material and dimensions, operational parameters, quality status, analysis reports and relevant degradation mechanisms is stored in the data base for all SSCs of category 1 and 2. While a nuclear power plant is in service numerous events may occur which are related to aging and may have an influence on the quality of SSCs. Relevant events may be malfunction messages, maintenance results, operational experience, results of surveillance or events in external installations. It is important to evaluate these events concerning the aspect of aging and to decide which measures are required to prevent unexpected events of the same kind in the future. In some cases the new experience has to be assigned to comparable SSCs. These evaluations, the definition of measures and the tracking of their effectiveness have to be done by an aging management team that meets regularly every 3 months. The knowledge data base supports the application of the PDCA cycle and provides an overview and fast access to all quality documents related to each SSC including surveillance measures and results. It simplifies the generation of annual status reports which are valuable quality documents that reveal the effectiveness of aging management. Finally the procedure can be extended to SSCs which are important for the availability of the plant and thus take a step forward from aging management to plant life management.

scholarly journals Room Classification Based on EMC Conditions in Nuclear Power Plants

Energies ◽  
2020 ◽  
Vol 13 (2) ◽  
pp. 359 ◽  
Author(s):  
Hrvoje Grganić ◽  
Davor Grgić ◽  
Siniša Šadek
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Electromagnetic Compatibility ◽  
Numerical Calculations ◽  
Operational Experience ◽  
Systematic Classification

Electromagnetic compatibility (EMC) in nuclear power plants today mostly relies on the qualification tests of the new equipment and adhering to some good installation practices. Diversity of the electromagnetic environment and different susceptibility of the plant equipment calls for a systematic classification of the EMC zones in a nuclear power plant. The paper proposes a methodology that uses a combination of the qualification tests, in situ and bench immunity tests, site survey measurements, operational experience, and numerical calculations to divide a nuclear power plant into a reasonable number of EMC zones. This would primarily help to have a better overview of the current EMC level in the plant and to unify emission and susceptibility requirements for the new equipment. In this paper, special attention is given to the preparation and performance of the in situ tests, which present the most challenging step of the methodology. In addition, the paper proposes some of the possible applications of the numerical calculations and addresses their challenges and limitations. The novel classification methodology, inspired by the equipment qualification program, is illustrated with examples from Krško Nuclear Power Plant, which recently performed a comprehensive EMC assessment.

Research on Nuclear Power Plant Operational Safety Performance Based on Confidence Level and Fussy Evaluation Model

2013 ◽  
Vol 475-476 ◽  
pp. 1721-1724 ◽  
Author(s):  
Dong Xiao Niu ◽  
Zong Yun Song
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Performance Indicator ◽  
Evaluation Model ◽  
Indicator System ◽  
Safety Performance ◽  
Operational Safety ◽  
And Performance ◽  
Evaluation Matrix

Fussy evaluation model will be used in this article to evaluate the operational safety performance of nuclear power plant. Through the combination of the existing three indicator system, the article builds a safety performance indicator system and fatherly establishes evaluation matrix of the importance level and performance level,then gets the weigh and confidence of every indicator. Finally, the evaluation results of the operational safety performance of nuclear power plant can be obtained after analyzing the confidence and evaluation matrix.

Performance and Unavailability Analysis of RPS/ESFAS in Korea Standard Nuclear Power Plant (KSNPP)

2002 ◽  
Author(s):  
Seung-Cheol Jang ◽  
Kyung-Ran Min ◽  
Sang-Hoon Han
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Plant Protection ◽  
Technical Specification ◽  
Operating Experience ◽  
Protection System ◽  
Operational Experience ◽  
Actuation System ◽  
Safety Features

The safety-related performance analysis of plant protection system (PPS) comprising reactor protection system/engineered safety features actuation system (RPS/ESFAS) was performed from the operating experience of the Korean standard nuclear power plant (KSNPP). The PPS operational data was collected from the trouble reports (TR) to record details of test and maintenance activities at sites. The total operating experience of 8.63 commercial reactor years at four units during the period 1995 through 2000 was studied. The system unavailability analysis was also performed through the detailed fault tree models, using plant specific data based on observed operational experience. Estimated were the unavailabilities on 11 automatic trip parameters for the RPS and 6 signals for the ESFAS. Results of the data analysis and system unavailability were close to ones published for other CE-supplied plants, though this study included a lot of failures occurred in the beginning periods of commercial operation without percolation. This study was performed to provide technical basis for risk-informed applications like technical specification improvement.

scholarly journals Disturbances in the European Nuclear Power Plant Safety Related Electrical Systems

2011 ◽  
Vol 62 (3) ◽  
pp. 173-180
Author(s):  
Alexander Duchac ◽  
Marc Noël
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Research Centre ◽  
Operational Experience ◽  
Electrical Systems ◽  
Regulatory Authorities ◽  
Plant Safety ◽  
Nuclear Power Plant Safety ◽  
European Nuclear

Disturbances in the European Nuclear Power Plant Safety Related Electrical Systems This work is part of the European Clearinghouse on Nuclear Power Plant Operational Experience Feedback (NPP-OEF) activity carried out at the Joint Research Centre/Institute for Energy (JRC/IE) with the participation of ten EU Regulatory Authorities. It investigates the Forsmark-1 event of July 2006, as well as about 120 disturbances in the plant electrical systems that were reported to the Incident Reporting System (IRS) and US Licensee Event Reports (LER) in the period 1985-2008. The aim of the work was to provide important insights from the Forsmark event of July 2006 and illustrate some vulnerabilities of the plant electrical system to over voltage transients. It identified electrical equipment involved, failure modes, contributing factors, actual and potential consequences, and corrective actions. Initiating factors and associated root causes were also analysed. The analysis of International Operation Experience Feedback revealed number of events that involved disturbances in the plant electrical systems, and which may have features in common with the Forsmark-1 event. It underlines the importance of sharing lessons learned from design modifications made at another unit of similar design that if known, it could have identified susceptibility of emergency diesel generators to common mode failure before the event occurred. This paper also summarizes international projects that were initiated by Forsmark event, as well as important lessons that still can be learned from Forsmark event. This paper presents actions taken at nuclear power plants and regulatory authorities in different countries to prevent similar event to occur.

Fuzzy multi-objective decision making approach for nuclear power plant installation

2020 ◽  
Vol 39 (5) ◽  
pp. 6339-6350
Author(s):  
Esra Çakır ◽  
Ziya Ulukan
Keyword(s):  
Linear Programming ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Energy Supply ◽  
Energy Demand ◽  
Nuclear Power ◽  
Power Plants ◽  
Total Duration ◽  
Objective Functions ◽  
Multi Objective

Due to the increase in energy demand, many countries suffer from energy poverty because of insufficient and expensive energy supply. Plans to use alternative power like nuclear power for electricity generation are being revived among developing countries. Decisions for installation of power plants need to be based on careful assessment of future energy supply and demand, economic and financial implications and requirements for technology transfer. Since the problem involves many vague parameters, a fuzzy model should be an appropriate approach for dealing with this problem. This study develops a Fuzzy Multi-Objective Linear Programming (FMOLP) model for solving the nuclear power plant installation problem in fuzzy environment. FMOLP approach is recommended for cases where the objective functions are imprecise and can only be stated within a certain threshold level. The proposed model attempts to minimize total duration time, total cost and maximize the total crash time of the installation project. By using FMOLP, the weighted additive technique can also be applied in order to transform the model into Fuzzy Multiple Weighted-Objective Linear Programming (FMWOLP) to control the objective values such that all decision makers target on each criterion can be met. The optimum solution with the achievement level for both of the models (FMOLP and FMWOLP) are compared with each other. FMWOLP results in better performance as the overall degree of satisfaction depends on the weight given to the objective functions. A numerical example demonstrates the feasibility of applying the proposed models to nuclear power plant installation problem.

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