Browse > Article
http://dx.doi.org/10.5516/NET.2009.41.6.849

AN OVERVIEW OF RISK QUANTIFICATION ISSUES FOR DIGITALIZED NUCLEAR POWER PLANTS USING A STATIC FAULT TREE  

Kang, Hyun-Gook (Korea Atomic Energy Research Institute)
Kim, Man-Cheol (Korea Atomic Energy Research Institute)
Lee, Seung-Jun (Korea Atomic Energy Research Institute)
Lee, Ho-Jung (Korea Atomic Energy Research Institute)
Eom, Heung-Seop (Korea Atomic Energy Research Institute)
Choi, Jong-Gyun (Korea Atomic Energy Research Institute)
Jang, Seung-Cheol (Korea Atomic Energy Research Institute)
Publication Information
Nuclear Engineering and Technology / v.41, no.6, 2009 , pp. 849-858 More about this Journal
Abstract
Risk caused by safety-critical instrumentation and control (I&C) systems considerably affects overall plant risk. As digitalization of safety-critical systems in nuclear power plants progresses, a risk model of a digitalized safety system is required and must be included in a plant safety model in order to assess this risk effect on the plant. Unique features of a digital system cause some challenges in risk modeling. This article aims at providing an overview of the issues related to the development of a static fault-tree-based risk model. We categorize the complicated issues of digital system probabilistic risk assessment (PRA) into four groups based on their characteristics: hardware module issues, software issues, system issues, and safety function issues. Quantification of the effect of these issues dominates the quality of a developed risk model. Recent research activities for addressing various issues, such as the modeling framework of a software-based system, the software failure probability and the fault coverage of a self monitoring mechanism, are discussed. Although these issues are interrelated and affect each other, the categorized and systematic approach suggested here will provide a proper insight for analyzing risk from a digital system.
Keywords
PRA; Risk; Fault Tree; Digital System; Safety-Critical; Digital;
Citations & Related Records
Times Cited By KSCI : 3  (Citation Analysis)
Times Cited By Web Of Science : 2  (Related Records In Web of Science)
Times Cited By SCOPUS : 9
연도 인용수 순위
1 Shin, H.G, Nam, S.G, Sohn, S.D and Chang, H.S, “Development of an advanced digital reactor protection system using diverse dual processors to prevent commonmode failure,” Nuclear Technology, Vol.141, 2003   DOI
2 Bellcore Technical Ref. TR-TSY-000332, Reliability prediction procedure for electronic equipment: issue 6, 1997
3 Kang, H.G, et al., Survey of the Advanced Designs of Safety-Critical Digital Systems from the PSA Viewpoint, Korea Atomic Energy Research Institute, KAERI/AR-00669/2003, 2003
4 Kang, H.G and Sung, T, “An analysis of safety-critical digital systems for risk-informed design,” Reliability Engineering and Systems Safety, Vol. 78, No. 3, 2002   DOI   ScienceOn
5 US MIL-HDBK-217, Reliability Prediction of Electronic Equipment, version F, DOD, USA, 1991
6 Fenton, N, Neil, M, David Marques, “Using Bayesian Networks to Predict Software Defects and Reliability,” 5th International Mathematical Methods in Reliability Conference (MMR 07), July 2007
7 IEEE, IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations, IEEE-7.4.3.2, 2003
8 Kahneman, D, Slovic, P, and Tversky, A, Judgment under uncertainty: Heuristics and biases, Cambridge University Press, 1982
9 DeLong, T, Smith, D, and Johnson, B, “Dependability Metrics to Assess Safety-Critical Systems,” IEEE Transactions on Reliability, Vol. 54, No. 3, 2005   DOI   ScienceOn
10 Forester, J, Bley, D, Cooper, S, Lois, E, Siu, N, Kolaczkowski, A, and Wreathall, J, “Expert elicitation approach for performing ATHEANA quantification,” Reliability Engineering and System Safety, Vol. 83, 2004
11 Dahll, G, The use of Bayesian Belief Nets in Safety Assessment of Software based System, HWP-527, Halden Project, 1998
12 US Nuclear Regulatory Commission (USNRC), Technical basis and implementation guidelines for a technique for human event analysis (ATHEANA), Washington, D.C., NUREG-1624 Rev. 1, 2000
13 Butler, R.W and Finelli, G.B, “Infeasibility of Quantifying the Reliability of Life-Critical Real-Time Software,” IEEE Transaction on Software Engineering, Vol.19, Issue 1, IEEE Press, 1993   DOI   ScienceOn
14 Eom, H.S, et al., Survey of Bayesian Belief Nets for Quantitative Reliability Assessment of Safety Critical Software Used in Nuclear Power Plants, Korea Atomic Energy Research Institute, KAERI/AR-594/2001, 2001
15 Seong, P.H, et al., Reliability and Risk Issues in Large Scale Safety-critical Digital Control Systems, Springer London, 2008
16 Lee, D.Y, Choi, J.G, and Lyou, Y, “A Safety Assessment Methodology for a Digital Reactor Protection System,” International Journal of Control, Automation, and Systems, Vol. 4, No. 1, 2006
17 Kaufman, L.M, Johnson, B.W, and Bechta Dugan, J, “Coverage Estimation Using Statistics of Extremes for When Testing Reveals No Failures”, IEEE Transactions on Computers, Vol. 51, No. 1, 2002   DOI   ScienceOn
18 Chu, T.L, Martinez-Guridi, Yue, M, Lehner, J, and Samanta, P, “Traditional Probabilistic Risk Assessment Methods for Digital Systems,” NUREG/CR-6962, October 2008
19 Kang, H.G and Jang, S.C, “Application of condition-based HRA method for a manual actuation of the safety features in a nuclear power plant,” Reliability Engineering & System Safety, Vol. 91, 2006   DOI   ScienceOn
20 Lee, J.S, Kim, M.C, Seong, P.H, Kang, H.G, and Jang, S.C, “Evaluation of error detection coverage and fault-tolerance of digital plant protection system in nuclear power plants,” Annals of Nuclear Energy, vol.33, pp.544-554, 2006   DOI   ScienceOn
21 Kim, M.C, Jang, S.C, and Ha, J, “Possibilities and limitations of applying software reliability growth models to safetycritical software,” Nuclear Engineering and Technology, vol.39, no.2, pp.145-148, 2007
22 Kim, S.J, Seong, P.H, Lee, J.S, Kim, M.C, Kang, H.G, and Jang, S.C, “A Method of Fault Coverage Evaluation for Digitalized Systems in Nuclear Power Plants using Simulated Fault Injection,” Reliability Engineering and System Safety, vol.91, pp.614-623, 2005   DOI   ScienceOn
23 ERPD-97, Electronic Parts Reliability Data, RAC, 1996
24 Parnas, D.L, Asmis, G.J.K, and Madey, J, “Assessment of Safety-critical Software in Nuclear Power Plants,” Nuclear Safety, Vol. 32, No. 2., 1991
25 Kang, H.G, Jang, S.C, and Lim, H.G, “ATWS Frequency Quantification Focusing on Digital I&C Failures,” Journal of Korea Nuclear Society, Vol. 36, 2004
26 Jung, H.S, Jang, S.C, Kim, M.C, Jun, S.T, “Analysis of Hardware Reliabilities for NPP Digital I&C Equipment Predicted by Various Methods,” International congress on advances in nuclear power plants; ICAPP '03, 2003
27 White, R.M and Boettcher, D.B, “Putting Sizewell B digital protection in context,” Nuclear Engineering International, pp. 41-43, 1994
28 Littlewood B, Wright D, “Some conservative stopping rules for the operational testing of safety-critical software,” IEEE Trans. Software Engineering, Vol. 23, No. 11, 1997, pp. 673-685   DOI   ScienceOn
29 HSE, The use of computers in safety-critical applications, London, HSE Books, 1998
30 INL, Technology Roadmap on Instrumentation, Control, and Human-Machine Interface to Support DOE Advanced Nuclear Energy Programs, INL/EXT-06-11862, Idaho National lab., March 2007
31 Uusitalo, L, "Advantages and challenges of Bayesian networks in environmental modeling," Ecological modeling, Vol. 203, pp.312-318, 2007   DOI   ScienceOn
32 Lu, L and Jiang, J, “Probabilistic Safety Assessment for Instrumentation and Control Systems in Nuclear Power Plants: An Overview,” Journal of Nuclear Science and Technology, Vol. 41, No.3, 2004   DOI   ScienceOn
33 OECD/NEA, Computer-Based Systems Important to Safety (COMPSIS) Project: 3 Years of Operation (2005-2007), Draft Report, NEA/CSNI/R(2008). 2008
34 Kang, H.G, Lim, H.G, Lee, H.J, Kim, M.C, and Jang, S.C, “A Test-Based Software Failure Probability Quantification Method for Safety-Critical Applications,” The 7th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety, Seoul, Korea, October 5-9, 2008
35 Kang, H.G, et al., The Common Cause Failure Probability Analysis on the Hardware of the Digital Protection System in Korean Standard Nuclear Power Plant, KAERI/TR-2908/2005, 2005