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http://dx.doi.org/10.1016/j.net.2018.01.006

Multi-unit Level 1 probabilistic safety assessment: Approaches and their application to a six-unit nuclear power plant site  

Kim, Dong-San (Korea Atomic Energy Research Institute)
Han, Sang Hoon (Korea Atomic Energy Research Institute)
Park, Jin Hee (Korea Atomic Energy Research Institute)
Lim, Ho-Gon (Korea Atomic Energy Research Institute)
Kim, Jung Han (Pusan National University)
Publication Information
Nuclear Engineering and Technology / v.50, no.8, 2018 , pp. 1217-1233 More about this Journal
Abstract
Following a surge of interest in multi-unit risk in the last few years, many recent studies have suggested methods for multi-unit probabilistic safety assessment (MUPSA) and addressed several related aspects. Most of the existing studies though focused on two-unit nuclear power plant (NPP) sites or used rather simplified probabilistic safety assessment (PSA) models to demonstrate the proposed approaches. When considering an NPP site with three or more units, some approaches are inapplicable or yield very conservative results. Since the number of such sites is increasing, there is a strong need to develop and validate practical approaches to the related MUPSA. This article provides several detailed approaches that are applicable to multi-unit Level 1 PSA for sites with up to six or more reactor units. To validate the approaches, a multi-unit Level 1 PSA model is developed and the site core damage frequency is estimated for each of four representative multi-unit initiators, as well as for the case of a simultaneous occurrence of independent single-unit initiators in multiple units. For this purpose, an NPP site with six identical OPR-1000 units is considered, with full-scale Level 1 PSA models for a specific OPR-1000 plant used as the base single-unit models.
Keywords
Inter-unit Dependency; Multi-unit Core Damage Frequency; Multi-unit Probabilistic Safety Assessment; Multi-unit Probabilistic Risk Assessment; Multi-unit Risk; Site Core Damage Frequency;
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  • Reference
1 U.S. Nuclear Regulatory Commission, Common-Cause Failure Database and Analysis Systems: Event Data Collection, Classification, and Coding (NUREG/CR-6268), Rev. 1, Washington, D.C, 2007.
2 K.N. Fleming, On the issues of integrated riskda PRA practitioners perspective, in: Proceedings of the ANS International Topical Meeting on Probabilistic Safety Analysis, San Francisco, CA, USA, 2005.
3 K.N. Fleming, On the risk significance of seismically induced multi-unit accidents, in: Proceedings of the ANS International Topical Meeting on Probabilistic Safety Assessment and Analysis, ID, USA, 2015.
4 M.A. Stutzke, Scoping estimates of multi-unit accident risk, in: Proceedings of Probabilistic Safety Assessment and Management (PSAM 12), Honolulu, Hawaii, 2014.
5 Pickard Lowe and Garrick, Inc, in: Seabrook Station Probabilistic Safety Assessment - Section 13.3 Risk of Two Unit Station, Prepared for Public Service Company of New Hampshire, PLG-0300, 1983.
6 S. Samaddar, K. Hibino, O. Coman, Technical approach for safety assessment of multi-unit NPP sites subject to external events, in: Proceedings of Probabilistic Safety Assessment and Management (PSAM 12), Honolulu, Hawaii, 2014.
7 K. Ebisawa, T. Teragaki, S. Nomura, H. Abe, M. Shigemori, M. Shimomoto, Concept and methodology for evaluating core damage frequency considering failure correlation at multi units and sites and its application, Nucl. Eng. Des. 288 (2015) 82-97.   DOI
8 C.S. Kumar, V. Hassija, K. Velusamy, V. Balasubramaniyan, Integrated risk assessment for multi-unit NPP sites - a comparison, Nucl. Eng. Des. 293 (2015) 53-62.   DOI
9 T.D. Le Duy, D. Vasseur, E. Serdet, Probabilistic safety assessment of twin-unit nuclear sites: methodological elements, Reliab. Eng. Syst. Saf. 145 (2016) 250-261.   DOI
10 S. Zhang, J. Tong, J. Zhao, An integrated modeling approach for event sequence development in multi-unit probabilistic risk assessment, Reliab. Eng. Syst. Saf. 155 (2016) 147-159.   DOI
11 S.H. Han, K. Oh, H.-G. Lim, J.-E. Yang, AIMS-MUPSA software package for multi-unit PSA, Nucl. Eng. Technol. 50 (2018) 1255-1265.   DOI
12 M. Modarres, T. Zhou, M. Massoud, Advances in multi-unit nuclear power plant probabilistic risk assessment, Reliab. Eng. Syst. Saf. 157 (2017) 87-100.   DOI
13 IAEA. Nuclear Power Reactors in the World, Reference Data Series No. 2, 2017 Edition, International Atomic Energy Agency, 2017.
14 H.-G. Lim, D.-S. Kim, S.H. Han, J.-E. Yang, Development of logical structure for multi-unit probabilistic safety assessment, Nucl. Eng. Technol. 50 (2018) 1210-1216.   DOI
15 J. Cho, S.H. Han, D.-S. Kim, H.-G. Lim, Multi-unit Level 2 probabilistic safety assessment: Approaches and their application to a six-unit nuclear power plant site, Nucl. Eng. Technol. 50 (2018) 1234-1245.
16 S.-Y. Kim, Y.H. Jung, S.H. Han, S.-J. Han, H.-G. Lim, Multi-unit Level 3 probabilistic safety assessment: Approaches and their application to a six-unit nuclear power plant site, Nucl. Eng. Technol. 50 (2018) 1246-1254.   DOI
17 D.S. Kim, J.H. Park, H.G. Lim, Multi-unit initiating event analysis for a singleunit internal events Level 1 PSA, in: Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, 2016.
18 S.H. Han, H.G. Lim, S.C. Jang, J.E. Yang, AIMS-PSA: a software for integrated PSA, in: Proceedings of the 13th International Conference on Probabilistic Safety Assessment and Management (PSAM 13), Seoul, Korea, 2016.
19 W.S. Jung, S.H. Han, J. Ha, A fast BDD algorithm for large coherent fault trees analysis, Reliab. Eng. Syst. Saf. 83 (2004) 369-374.   DOI
20 ASME/ANS, Addenda to ASME/ANS RA-S-2008, standard for level 1/large early release frequency probabilistic risk assessment for nuclear power plant applications, in: ASME/ANS RA-sb-2013, the American Society of Mechanical Engineers & American Nuclear Society, New York, U.S, 2013.
21 S.H. Han, H.G. Lim, Fault tree modeling of AAC power source in multi-unit nuclear power plant PSA, in: Transactions of the Korean Nuclear Society Fall Meeting, Gyeongju, Korea, 2015.
22 U.S. Nuclear Regulatory Commission, CCF Parameter Estimations (2007 Update), http://nrcoe.inl.gov/results/CCF/ParamEst2007/ccfparamest.htm, September 2008.
23 U.S. Nuclear Regulatory Commission, Guidelines on Modeling Common-Cause Failures in Probabilistic Safety Assessment (NUREG/CR-5485), Washington, D.C, 1998.
24 U.S. Nuclear Regulatory Commission, Reevaluation of Station Blackout Risk at Nuclear Power Plants - Analysis of Loss of Offsite Power Events: 1986-2004 (NUREG/CR-6890), 1, 2005. Washington, D.C.
25 U.S. Nuclear Regulatory Commission, CCF Parameter Estimations (2012 Update), http://nrcoe.inl.gov/results/CCF/ParamEst2012/ccfparamest.htm, November 2013.
26 KAERI, Development of Site Risk Assessment and Management Technology Including Extreme External Events, KAERI/RR-4225/2016, Korea Atomic Energy Research Institute, 2017.
27 IAEA, Attributes of Full Scope Level 1 Probabilistic Safety Assessment (PSA) for Applications in Nuclear Power Plants, IAEA-TECDOC-1804, International Atomic Energy Agency, Vienna, 2016.
28 EPRI, Seismic Probabilistic Risk Assessment Implementation Guide, Electric Power Research Institute, Palo Alto, CA, 2013, 3002000709.
29 J.H. Kim, I.K. Choi, Evaluation of failure probability considering seismic correlation for probabilistic safety assessment, in: Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, 2012.