DocumentCode :
3314153
Title :
Development of risk-based operation and maintenance management system for nuclear plants
Author :
Agarwal, Mayank ; Yarde, P.V.
Author_Institution :
Reactor Group, Bhabha Atomic Res. Centre, Mumbai, India
fYear :
2010
fDate :
14-16 Dec. 2010
Firstpage :
485
Lastpage :
488
Abstract :
Traditional approach in Decision-Making in nuclear plants & regulatory bodies is based on engineering judgment, O&M experience & technical specifications. However, this approach is conservative and at times tends to be arbitrary in nature. This is because these are prescript by the designers or regulators. So, no quantified inputs go to decision making criteria for plant management. The uncertainties associated with data or model is also not quantified. The state of art in “PSA-An analytical approach” enables to represent performance parameters in form of reliability and safety. This approach provides probabilistic, systematic, flexible and rational framework for optimization of parameters in decision making also gives integrated plant performance view for safety performance. The outcome of this approach is used for several applications in decision making. This paper discusses the development of risk-based operation and maintenance management system for nuclear plants / industries. This system is developed for the ease and effective decision making by the O&M agencies, considering risk contributed by each component and system. This tool is having user friendly GUI for plant operators with almost a all important elements for risk-based management such as CDF calculation, risk profile graph, system unavailability and IE contribution to CDF, importance analysis, uncertainty analysis, login sessions, compare risk-based surveillance test interval to traditional surveillance test interval, and scope for technical specifications, this system also facilitates the shutdown maintenance planning and scheduling. For validation and verification PSA model of research reactors is developed and system is implemented. And most of the results are comparable with professional software available in market. This paper underlies goal and acceptance criteria for judgment and correctness of data and model.
Keywords :
decision making; fission reactor safety; fission research reactors; graphical user interfaces; nuclear engineering computing; nuclear power stations; optimisation; risk management; surveillance; CDF calculation; GUI; IE contribution; O&M agencies; PSA model; PSA-an analytical approach; decision making criteria; engineering judgment; importance analysis; integrated plant performance; login sessions; maintenance management system; nuclear plants; optimization; plant management; plant operators; professional software; regulatory bodies; research reactors; risk profile graph; risk-based management; risk-based operation; risk-based surveillance test interval; safety performance; shutdown maintenance planning; shutdown maintenance scheduling; system unavailability; uncertainty analysis; Accidents; Inductors; Reliability engineering; Sensitivity; Core damage frequency; Probabilistic Safety Assessment; Risk management; component database; importance analysis; maintenance scheduling; surveillance test; uncertainty analysis;
fLanguage :
English
Publisher :
ieee
Conference_Titel :
Reliability, Safety and Hazard (ICRESH), 2010 2nd International Conference on
Conference_Location :
Mumbai
Print_ISBN :
978-1-4244-8344-0
Type :
conf
DOI :
10.1109/ICRESH.2010.5779598
Filename :
5779598
Link To Document :
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