A benchmark system for comparing reliability modeling approaches for digital instrumentation and control systems

Nuclear Technology

Volumn 165, Issue 1, 2009, Pages 53-95

  Kirschenbaum, Jason ^a   Bucci, Paolo ^a   Stovsky, Michael ^b   Mandelli, Diego ^b   Aldemir, Tunc ^b   Yau, Michael ^c   Guarro, Sergio ^c   Ekici, Eylem ^a   Arndt, Steven A ^d  

^a Ohio State University   (United States)

^b OHIO STATE UNIVERSITY   (United States)

^c ASCA Inc   (United States)

^d U S NUCLEAR REGULATORY COMMISSION   (United States)

Author keywords

Dynamic flowgraph methodology; Dynamic PRA; Markov

Indexed keywords

GRAPHIC METHODS; NUCLEAR FUELS; NUCLEAR POWER PLANTS; PRESSURIZED WATER REACTORS; RELIABILITY; RISK ASSESSMENT; STEAM GENERATORS;

DIGITAL INSTRUMENTATION; DYNAMIC RELIABILITY; FEEDWATER CONTROL SYSTEM; INITIATING EVENTS; INSTRUMENTATION AND CONTROL SYSTEM; MAPPING TECHNIQUES; MARKOV; PROBABILISTIC RISK ASSESSMENT;

CONTROL SYSTEMS;

EID: 58649102076     PISSN: 00295450     EISSN: None     Source Type: Journal    
DOI: 10.13182/NT09-A4062     Document Type: Article

References (45)

1. "Use of Probabilistic Risk Assessment Methods in Nuclear Activities: Final Policy Statement," Federal Register, 60, 43622 (1995).
2. T. ALDEMIR, D. W. MILLER, M. STOVSKY, J. KIRSCHENBAUM, P. BUCCI, A. W. FENTIMAN, and L. M. MANGAN, "Current State of Reliability Modeling Methodologies for Digital Systems and Their Acceptance Criteria for Nuclear Power Plant Assessments," NUREG/CR-6901, U.S. Nuclear Regulatory Commission (2006).
3. J. KIRSCHENBAUM, M. STOVSKY, P. BUCCI, T. ALDEMIR, and S. A. ARNDT, "Benchmark Development for Comparing Digital Instrumentation and Control System Reliability Modeling Approaches," Proc. Int. Topl. Mtg. Probabilistic Safety Analysis (PSA '05), San Francisco, California, September 11-15, 2005, American Nuclear Society (2005) (CD-ROM).
4. H. KUMAMOTO and E. J. HENLEY, "Top-Down Algorithm for Obtaining Prime Implicant Set of Non-Coherent Fault Trees," IEEE Trans. Reliab., R-27, 242 (1977).
5. T. ALDEMIR and N. O. SIU, "Guest Editorial," Reliab. Eng. Syst. Safety, 52, 181 (1996).
6. D. JOHNSON, The Sampling Theorem; available on the Internet at http://cnx.org/content/m0050/2.18 (May 2007).
7. H. KANG and T. SUNG, "An Analysis of Safety-Critical Digital Systems for Risk-Informed Analysis," Reliab. Eng. Syst. Safety, 78, 307 (2002).
8. "Effects of Ethernet-Based, Non-Safety Related Controls on the Safe and Continued Operation of Nuclear Power Stations," Information Notice IN-2007-15, U.S. Nuclear Regulatory Commission (Apr. 17, 2007).
9. D. T. SMITH, T. A. DELONG, and B. W. JOHNSON, "A Safety Assessment Methodology for Complex Safety-Critical Hardware/Software Systems," Proc. Int. Topl. Mtg. Nuclear Plant Instrumentation, Controls, and Human-Machine Interface Technologies, Washington, D.C., November 13-16,2000, American Nuclear Society (2000) (CD-ROM).
10. M. SINGHAL and N. G. SHIVARATRI, Advanced Concepts in Operating Systems, p. 297, McGraw-Hill Book Company, New York (1994).
11. R. S. PRESSMAN, Software Engineering: A Practitioner's Approach, 6th Edition, McGraw-Hill Book Company, New York (2005).
12. N. F. SCHNEIDEWIND and T. W. KELLER, "Applying Reliability Models to the Space Shuttle," IEEE Scftware, 9, 4, 28(1992).
13. S. GUARRO, M. YAU, and M. MOTAMED, "Development of Tools for Safety Analysis of Control Software in Advanced Reactors," NUREG/CR-6465, U.S. Nuclear Regulatory Commission (1996).
14. J. DEVOOGHT and C. SMIDTS, "Probabilistic Reactor Dynamics - I: The Theory of Continuous Event Trees," Nucl. Sci. Eng., 111, 229 (1992).
15. T. ALDEMIR, "Utilization of the Cell-to-Cell Mapping Technique to Construct Markov Failure Models for Process Control Systems," Proc. Ist Int. Conf. Probabilistic Safety Assessment and Management (PSAM 1), p. 1431, G. APOSTO-LAKIS, Ed., Elsevier (1991).
16. T. ALDEMIR, "Quantifying Setpoint Drift Effects in the Failure Analysis of Process Control Systems," Reliab. Eng. Syst. Safety, 24, 33 (1989).
17. P. C. CACCIABUE, A. AMENDOLA, and G. COJAZZI, "Dynamic Logical Analytical Methodology Versus Fault Tree: The Case Study of the Auxiliary Feedwater System of a Nuclear Power Plant," Nucl. Technol., 74, 195 (1986).
18. C. ACOSTA and N. SIU, "Dynamic Event Trees in Accident Sequence Analysis: Application to Steam Generator Tube Rupture," Reliab. Eng. Syst. Safety, 41, 135 (1993).
19. M. HASSAN and T. ALDEMIR, "A Data Base Oriented Dynamic Methodology for the Failure Analysis of Closed Loop Control Systems in Process Plants," Reliab. Eng. Syst. Safety, 27, 275 (1990).
20. C. ELKS, Y. Y. YU, M. REYNOLDS, and B. W. JOHNSON, "Quantitative Dependability Assessment of a Digital Feed Water Control System: Preliminary Results," UVA-CCS-QDA-001, Version 7, University of Virginia (2006).
21. B. LI, M. LI, and C. SMIDTS, "Integrating Software into PRA: ATest-Based Approach," C. SPITZER, U. SCHMOKER, and V. N. DANG, Eds., Springer-Verlag, London, United Kingdom (2004).
22. Y, ZANG and M. M. GOLAY, "Development of a Method for Quantifying the Reliability of Nuclear Safety-Related Software," Proc. 6th Int. Conf. Probabilistic Safety Assessment and Management (PSAM 6), San Juan, Puerto Rico, June 20-23, 2002, Elsevier Science (2002) (CD-ROM).
23. M. MARSEGUERRA and E. ZIO, "Monte Carlo Approach to PSA for Dynamic Process Systems," Reliab. Eng. Syst. Safety, 52, 227 (1996).
24. L. LAMPORT, S. SHOSTAK, and P. PEASE, "The Byzantine Generals Problem," ACM Trans. Programming Languages and Systems, 4, 382 (1982).
25. J. KIRSCHENBAUM, M. STOVSKY, D. MANDELLI, P. BUCCI, T. ALDEMIR, D. W. MILLER, E. EKICI, and S. ARNDT, "A Benchmark System for the Assessment of Reliability Modeling Methods for Digital Instrumentation and Control Systems in Nuclear Plants," Proc. 5th Int. Topl. Mtg. Nuclear Plant Instrumentation, Controls, and Human Machine Interface Technology (NPIC&HMIT2006), Albuquerque, New Mexico, November 12-16, 2006, American Nuclear Society (2006).
26. M. HASSAN and T. ALDEMIR, "A Data Base Oriented Dynamic Methodology for the Failure Analysis of Closed Loop Control Systems in Process Plants," Reliab. Eng. Syst. Safety, 27, 275 (1990).
27. B. LEIMKUEHLER and S. V. SHERIKAR, "Getting Optimum Performance Through Feedwater Control Valve Modifications," presented at 6th Electric Power Research Institute Symp. Valve Technology, Portland, Maine, July 14-16, 1997.
28. Y.-S. HU and M. MODARRES, "Evaluating System Behavior Through Dynamic Master Logic Diagram (DMLD) Modeling," Reliab. Eng. Syst. Safety, 64, 241 (1999).
29. M. YAU, G. APOSTOLAKIS, and S. GUARRO, "The Use of Prime Implicants in Dependability Analysis of Software Controlled Systems," Reliab. Eng. Syst. Safety, 62, 23 (1998).
30. T. ALDEMIR, M. P. STOVSKY, J. KIRSCHENBAUM, D. MANDELLI, P. BUCCI, L. A. MANGAN, D. W. MILLER, X. SUN, E. EKICI, S. GUARRO, M. YAU, B. W. JOHNSON, C. ELKS, and S. A. ARNDT, "Dynamic Reliability Modeling of Digital Instrumentation and Control Systems for Nuclear Reactor Probabilistic Risk Assessments," NUREG/CR-6942, U.S. Nuclear Regulatory Commission (2007).
31. S. GUARRO and G. EWELL, "Integrating MEMS Quality and Reliability Goals with the Use of Multi-Valued Logic Analysis," Proc. 2nd Int. Conf. Integrated Micro/Nanotechnology for Space Applications (MNT99), Pasedena, California, April 11-15, 1999, Aerospace Corporation (1999).
32. M. YAU, M. MOTAMED, and S. GUARRO, "Nuclear Power Plant Digital System PRA Pilot Study with the Dynamic Flowgraph Methodology," Proc. 5th Int. Topl. Mtg. Nuclear Plant Instrumentation, Controls, and Human Machine Interface Technology (NPIC&HMIT2006), Albuquerque, New Mexico, November 12-16, 2006, American Nuclear Society (2006).
33. M. YAU, M. WETHERHOLT, and S. GUARRO, "Safety Analysis and Testing of Critical Space Systems Software," Proc. 4th Int. Conf. Probabilistic Safety Assessment and Management (PSAM4), New York, September 13-18, 1998, Springer Verlag (1999).
34. E. J. SHIELDS, G. APOSTOLAKIS, and S. B. GUARRO, "Detennining the Prime Implicants for Multi-State Embedded Systems," G. APOSTOLAKIS and J. S. WU, Eds., Proc. 2nd Int. Conf. Probabilistic Safety Assessment and Management (PSAM-II), San Diego, California, March 20-24, 1994, p. 7, International Association for Probabilistic Assessment and Management (1994).
35. K. RUSSELL, "Systems Analysis Programs for Hands-On Integrated Reliability Evaluations (SAPHIRE), Version 6.0: System Overview Manual," NUREG/CR-6532, U.S. Nuclear Regulatory Commission (1999).
36. "CAFTA for Windows, Version 3.0c," Science Applications International Corporation (1995).
37. "RISKMAN 7.1 for Windows," ABS Consulting (2003).
38. A. RAUZY, "New Algorithms for Fault Tree Analysis," Reliab. Eng. Syst Safety, 40, 203 (1993).
39. T. ALDEMIR, "Computer-Assisted Markov Failure Modeling of Process Control Systems," IEEE Trans. Reliab., R-36, 133 (1987).
40. L. DINCA and T. ALDEMIR, "Parameter Estimation Toward Fault Diagnosis in Nonlinear Systems Using a Markov Model of System Dynamics," Nucl. Sci. Eng, 127, 199 (1997).
41. P. BUCCI, L. A. MANGAN, J. KIRSCHENBAUM, D. MANDELLI, T. ALDEMIR, and S. ARNDT, "Incorporation of Markov Reliability Models for Digital Instrumentation and Control Systems into Existing PRAs," Proc. 5th Int. Topl. Mtg. Nuclear Plant Instrumentation, Controls, and Human Machine Interface Technology (NPIC&HMIT2006), Albuquerque, New Mexico, November 12-16, 2006, American Nuclear Society (2006).
42. P. BUCCI, J. KIRSCHENBAUM, L. A. MANGAN, T. ALDEMIR, C. SMITH, and T. S. WOOD, "Construction of Event-Tree/Fault-Tree Models from a Markov Approach to Dynamic System Reliability," Reliab. Eng. Syst. Safety, 93, 11, 1616 (2008).
43. S. RUSSELL and P. NORVIG, Artificial Intelligence: A Modern Approach, Prentice-Hall, New Jersey (2003).
44. N. E. TODREAS and M. S. KAZIMI, Nuclear Systems: Thermal Hydraulic Fundamentals, Hemisphere Publishing Corporation (1990).
45. C. E. SHANNON and W. WEAVER, The Mathematical Theory of Communication, University of Illinois Press, Urbana, Illinois (1964).