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Current Status and Applications of Integrated Safety Assessment and Simulation Code System for ISA

  • Izquierdo, J.M. (Modeling and Simulation Area (MOSI), Nuclear Safety Council (CSN)) ;
  • Hortal, J. (Modeling and Simulation Area (MOSI), Nuclear Safety Council (CSN)) ;
  • Sanchez Perea, M. (Modeling and Simulation Area (MOSI), Nuclear Safety Council (CSN)) ;
  • Melendez, E. (Modeling and Simulation Area (MOSI), Nuclear Safety Council (CSN)) ;
  • Queral, C. (Energy and Fuels Department, Technical University of Madrid (UPM)) ;
  • Rivas-Lewicky, J. (Energy and Fuels Department, Technical University of Madrid (UPM))
  • Received : 2016.11.28
  • Accepted : 2017.01.13
  • Published : 2017.04.25

Abstract

This paper reviews current status of the unified approach known as integrated safety assessment (ISA), as well as the associated SCAIS (simulation codes system for ISA) computer platform. These constitute a proposal, which is the result of collaborative action among the Nuclear Safety Council (CSN), University of Madrid (UPM), and NFQ Solutions S.L, aiming to allow independent regulatory verification of industry quantitative risk assessments. The content elaborates on discussions of the classical treatment of time in conventional probabilistic safety assessment (PSA) sequences and states important conclusions that can be used to avoid systematic and unacceptable underestimation of the failure exceedance frequencies. The unified ISA method meets this challenge by coupling deterministic and probabilistic mutual influences. The feasibility of the approach is illustrated with some examples of its application to a real size plant.

Keywords

References

  1. ASME, Standard for Probabilistic Risk Assessment for Nuclear Power Plant Applications, ASME RA-S-2005, 2005. USA.
  2. USNRC, Regulatory Guide 1.70, Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants, November 1978. USA. AAN: ML011340072.
  3. T. Aldemir, A survey of dynamic methodologies for probabilistic safety assessment of nuclear power plants, Ann. Nucl. Energy 52 (2013) 113-124. https://doi.org/10.1016/j.anucene.2012.08.001
  4. E. Zio, Integrated deterministic and probabilistic safety assessment: concepts, challenges, research directions, Nucl. Eng. Des. 280 (2014) 413-419. https://doi.org/10.1016/j.nucengdes.2014.09.004
  5. Tunc Aldemir (Ed.), Advanced Concepts in Nuclear Energy Risk Assessment and Management, World Scientific Publishing Company Pte. Ltd, Singapore, 2017.
  6. J.M. Izquierdo, I. Canamon, TSD, a SCAIS Suitable Variant of the SDTPD. Presented at ESREL-2008 and 17th SRA Europe Annual Conference, Valencia (Spain), Sep 2008.
  7. J.M. Izquierdo, J. Hortal, M. Sanchez-Perea, E. Melendez, CSN Experience in the Development and Application of a Computer Platform to Verify Consistency of Deterministic and Probabilistic Licensing Safety Cases [Internet]. Vol I. General Approach and Deterministic Developments; CSN publication, Coleccion Otros Documentos, 40.2016 [cited March 2017]. Available from: https://www.csn.es/documents/10182/1012054/ODE-04.22+CSN+Experience+in+the+Development+and+Application+of+a+Computer+Platform+to+Verify+Consistency+of+Deterministic+and+Probabilistic+Licensing+Safety+Cases+Volume+I.+General+Approach+and+Deterministic+Developments.
  8. J.M. Izquierdo, J. Hortal, M. Sanchez-Perea, E. Melendez, Why sequence dynamics matters in PSA: checking consistency of probabilistic and deterministic analyses, in: T. Aldemir (Ed.), Advanced Concepts in Nuclear Energy Risk Assessment and Management, World Scientific Publishing Company Pte. Ltd, Singapore, 2017 (in press).
  9. R.H. Santos, A Standardized Methodology for the Linkage of Computer Codes, Application to RELAP5/Mod3.2. NUREG/IA- 0179, Office of Nuclear Regulatory Research, USNRC, USA, March 2000.
  10. J. Gil, I. Fernandez, S. Murcia, J. Gomez, H. Marrao, C. Queral, A. Exposito, G. Rodriguez, L. Ibanez, J. Hortal, J.M. Izquierdo, M. Sanchez, E. Melendez, A code for simulation of human failure events in nuclear power plants: SIMPROC, Nucl. Eng. and Des. 241 (2011) 1097-1107. https://doi.org/10.1016/j.nucengdes.2010.03.040
  11. J.M. Izquierdo, J. Hortal, M. Sanchez-Perea, E. Melendez. An Integrated PSA Approach to Independent Regulatory Evaluations of Nuclear Safety Assessments of Spanish Nuclear Power Stations [Internet]. CSN publication, Coleccion Otros Documentos, 28.2002 [cited March 2017]. Available from: https://www.csn.es/images/stories/english/publications/ode-04_18_psa.pdf.
  12. C. Queral, L. Mena-Rosell, G. Jimenez, M. Sanchez-Perea, J. Gomez-Magan, J. Hortal, Verification of SAMGs in SBO sequences with Seal LOCA. Multiple damage domains, Ann. Nucl. Energy 98 (2016) 90-111. https://doi.org/10.1016/j.anucene.2016.07.021
  13. E. Melendez, R. Munoz-Gomez, CSN activities in precursor analysis. NEA/CSNI/R(2003)11, in: Proceedings of the Workshop on Precursor Analysis, 28-30 March, 2001 at the Association Vincotte Nuclear (AVN), 2001. Brussels, Belgium.
  14. E. Melendez, R. Herrero, Use of PSA model XML Standard Formats for V&V. Presented at the 2015 International Topical Meeting on Probabilistic Safety Assessment and Analysis (PSA2015), Sun Valley (Idaho), Apr 26-30, 2015.
  15. C. Ibanez-Llano, A. Rauzy, E. Melendez, F. Nieto, Hybrid approach for the assessment of PSA models by means of binary decision diagrams, Reliab. Eng. Syst. Safe 95 (2010) 1076-1092, http://dx.doi.org/10.1016/j.ress.2010.04.016.
  16. E. Melendez, M. Sanchez-Perea, C. Queral, J. Mula, A. Hernandez, C. Paris. Standardized Probabilistic Safety Assessment Models: First Results and Conclusions of a Feasibility Study. Presented at the 13th International Conference on Probabilistic Safety Assessment and Management (PSAM 13), Seoul, Korea, 2-7 Oct, 2016.
  17. S.E. Galushin, J.M. Izquierdo, M. Sanchez-Perea, Transmission Functions and its application to the analysis of time uncertainties in Protection Engineering, Process Saf. Environ. Protect. 92 (2014) 625-636, http://dx.doi.org/10.1016/ j.psep.2013.07.004.
  18. United States Nuclear Regulatory Commission, Severe Accident Risks. An Assessment for Five US Nuclear Power Plants, NUREG 1150, 1989.
  19. D. Mandelli, A. Yilmaz, T. Aldemir, K. Metzroth, R. Denning, Scenario clustering and dynamic probabilistic risk assessment, Reliab. Eng. Syst. Safe. 115 (2013) 146-160. https://doi.org/10.1016/j.ress.2013.02.013
  20. L. Ibanez, J. Hortal, C. Queral, J. Gomez-Magan, M. Sanchez-Perea, I. Fernandez, E. Melendez, A. Exposito, J.M. Izquierdo, J. Gil, H. Marrao, E. Villalba-Jabonero, Application of the integrated safety assessment methodology to safety margins. Dynamic event trees, damage domains and risk assessment, Reliab. Eng. Syst. Safe. 147 (2016) 170-193. https://doi.org/10.1016/j.ress.2015.05.016
  21. J. Montero-Mayorga, C. Queral, J. Rivas-Lewicky, J. Gonzalez-Cadelo, Effects of RCP trip when recovering HPSI during LOCA in a Westinghouse PWR, Nucl. Eng. Des. 280 (2014) 389-403. https://doi.org/10.1016/j.nucengdes.2014.09.005
  22. M.J. Rebollo, C. Queral, G. Jimenez, J. Gomez-Magan, E. Melendez, M. Sanchez-Perea, Evaluation of the offsite dose contribution to the global risk in a Steam Generator Tube Rupture scenario, Reliab. Eng. Syst. Safe. 147 (2016) 32-48. https://doi.org/10.1016/j.ress.2015.10.016
  23. A. Flores, J.M. Izquierdo, K. Tucek, E. Gallego, Assessment of damage domains of the High-Temperature Engineering Test Reactor (HTTR), Ann. Nucl. Energy 72 (2014) 242-256. https://doi.org/10.1016/j.anucene.2014.05.008
  24. Nuclear Energy Agency, Informing Severe Accident Management Guidance and Actions through Analytical Simulations, Report of the Working Group on Analysis and Management of Accidents, Paris, France, 2017 (in press).

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