The digitalized Instrumentation and Control (I&C) system of Nuclear power plants can provide more powerful overall operation capability, and user friendly man-machine interface. The operator can obtain more information through digital I&C system. However, while I&C system being digitalized, three issues are encountered: 1) software common-cause failure, 2) the interaction failure between operator and digital instrumentation and control system interface, and 3) the non-detectability of software failure. These failures might defeat defense echelons, and make the Diversity and Defense-in-Depth (D3) analysis be more difficult. This work developed an integrated methodology to evaluate nuclear power plant safety effect by interactions between operator and digital I&C system, and then propose improvement recommendations. This integrated methodology includes component-level software fault tree, system-level sequence-tree method and nuclear power plant computer simulation analysis. Software fault tree can clarify the software failure structure in digital I&C systems. Sequence-tree method can identify the interaction process and relationship among operator and I&C systems in each D3 echelon in a design basis event. Nuclear power plant computer simulation analysis method can further analyze the available backup facilities and allowable manual action duration for the operator when the digital I&C fail to function. Applying this methodology to evaluate the performance of digital nuclear power plant D3 design, could promote the nuclear power plant operation safety. The operator can then trust the nuclear power plant than before, when operating the highly automatic digital I&C facilities.
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16th International Conference on Nuclear Engineering
May 11–15, 2008
Orlando, Florida, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-4817-5
PROCEEDINGS PAPER
Integrated Software Safety Analysis Method for Digital I&C Systems
Hui-Wen Huang,
Hui-Wen Huang
Institute of Nuclear Energy Research, Longtan, Taiwan
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Hung-Chih Hung,
Hung-Chih Hung
National Tsing Hua University, Hsinchu, Taiwan
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Chunkuan Shih,
Chunkuan Shih
National Tsing Hua University, Hsinchu, Taiwan
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Ming-Huei Chen,
Ming-Huei Chen
Institute of Nuclear Energy Research, Longtan, Taiwan
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Yuan-Chang Yu,
Yuan-Chang Yu
Institute of Nuclear Energy Research, Longtan, Taiwan
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Shu-Chuan Chen,
Shu-Chuan Chen
National Tsing Hua University, Hsinchu, Taiwan
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Wan-Tsz Tu,
Wan-Tsz Tu
National Tsing Hua University, Hsinchu, Taiwan
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Wei-Yi Yang
Wei-Yi Yang
National Tsing Hua University, Hsinchu, Taiwan
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Hui-Wen Huang
Institute of Nuclear Energy Research, Longtan, Taiwan
Hung-Chih Hung
National Tsing Hua University, Hsinchu, Taiwan
Chunkuan Shih
National Tsing Hua University, Hsinchu, Taiwan
Swu Yih
Ching Yun University, Taiwan
Ming-Huei Chen
Institute of Nuclear Energy Research, Longtan, Taiwan
Yuan-Chang Yu
Institute of Nuclear Energy Research, Longtan, Taiwan
Shu-Chuan Chen
National Tsing Hua University, Hsinchu, Taiwan
Wan-Tsz Tu
National Tsing Hua University, Hsinchu, Taiwan
Wei-Yi Yang
National Tsing Hua University, Hsinchu, Taiwan
Paper No:
ICONE16-48022, pp. 537-548; 12 pages
Published Online:
June 24, 2009
Citation
Huang, H, Hung, H, Shih, C, Yih, S, Chen, M, Yu, Y, Chen, S, Tu, W, & Yang, W. "Integrated Software Safety Analysis Method for Digital I&C Systems." Proceedings of the 16th International Conference on Nuclear Engineering. Volume 4: Structural Integrity; Next Generation Systems; Safety and Security; Low Level Waste Management and Decommissioning; Near Term Deployment: Plant Designs, Licensing, Construction, Workforce and Public Acceptance. Orlando, Florida, USA. May 11–15, 2008. pp. 537-548. ASME. https://doi.org/10.1115/ICONE16-48022
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