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A Safety Assessment Methodology for a Digital Reactor Protection System  

Lee Dong-Young (Instrumentation & Control-Human Factors Div., Korea Atomic Energy Research Institute)
Choi Jong-Gyun (Instrumentation & Control-Human Factors Div., Korea Atomic Energy Research Institute)
Lyou Joon (Dept. of Electrical and Computer Engineering, Chungnam National University)
Publication Information
International Journal of Control, Automation, and Systems / v.4, no.1, 2006 , pp. 105-112 More about this Journal
Abstract
The main function of a reactor protection system is to maintain the reactor core integrity and the reactor coolant system pressure boundary. Generally, the reactor protection system adopts the 2-out-of-m redundant architecture to assure a reliable operation. This paper describes the safety assessment of a digital reactor protection system using the fault tree analysis technique. The fault tree technique can be expressed in terms of combinations of the basic event failures such as the random hardware failures, common cause failures, operator errors, and the fault tolerance mechanisms implemented in the reactor protection system. In this paper, a prediction method of the hardware failure rate is suggested for a digital reactor protection system, and applied to the reactor protection system being developed in Korea to identify design weak points from a safety point of view.
Keywords
Failure rate; fault tree analysis; failure mode effect analysis; reliability; safety;
Citations & Related Records

Times Cited By Web Of Science : 1  (Related Records In Web of Science)
Times Cited By SCOPUS : 5
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1 Krishna B. Misra, Reliability Analysis and Prediction, Elsevier, 1992
2 MIL-HDBK-217F, Reliability Prediction of Electric Equipment, 1991
3 KAERI/TR-2164/2002, Reliability Study: KSNPP Reactor Protection System, Korea Atomic Energy Research Institute, 2002
4 NUREG/CR-4780, Volume 1, Procedures for Treating Common Cause Failures in Safety and Reliability Studies: Procedural Framework and Examples, NRC, 1988
5 Computer Program, Version 10.0 by ISOGRAPH, Reliability Workbench for Windows 95/98/NT/2000/ Me, 2002
6 D. Y. Lee, J. B. Han, and J. Lyou, 'Reliability analysis of the reactor protection system with fault diagnosis,' Key Engineering Materials, Advances in Nondestructive Evaluation, Part 2, pp. 1749-1754, November 2003
7 KNICS-RPS-AR103, Rev.00, Unavailability Analysis for Reactor Protection System, Korea Atomic Energy Research Institute, 2003
8 NUREG/CR-1278, Handbook of Human Reliability Analysis with Emphasis on Nuclear Power Plant Application, NRC, 1983
9 ANSI/IEEE Std. 352, IEEE Guide for General Principles of Reliability Analysis of Nuclear Power Generating Station Safety Systems, 1987
10 IEEE Std. 603, IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations, 1998