Canada Deuterium Uranium Updated Fire Probabilistic Risk Assessment Model for Canadian Nuclear Plants
The Canadian Nuclear Power Plants (NPPs) use some portions of NUREG/CR-6850 in carrying out Fire Probabilistic Risk Assessment (PRA). An assessment for the applicability of NUREG/CR-6850 to CANDU reactors was performed and a CANDU Fire PRA was introduced. There are 19 operating CANDU reactors in Canada at five sites (Bruce A, Bruce B, Darlington, Pickering and Point Lepreau). A fire load density survey was done for all Fire Safe Shutdown Analysis (FSSA) fire zones in all CANDU sites in Canada. National Fire Protection Association (NFPA) Standard 557 proposes that a fire load survey must be conducted by either the weighing method or the inventory method or a combination of both. The combination method results in the most accurate values for fire loads. An updated CANDU Fire PRA model is demonstrated in this paper that includes the fuel survey in all Canadian CANDU stations. A qualitative screening step for the CANDU fire PRA is illustrated in this paper to include any fire events that can damage any part of the emergency power supply in addition to FSSA cables.
[1] U.S. Nuclear Regulatory Commission and Electric Power Research Institute, “EPRI/NRC-RES Fire PRA Methodology for Nuclear Power Facilities, Volume 2: Detailed Methodology”, NUREG/CR-6850 Supplement 1, EPRI 1008239, Technical Report, October 2004.
[2] Hossam Shalabi & George Hadjisophocleous, 2018 “CANDU Fire Database”, CNL Nuclear Review, 18 December 2018.
[3] Hossam Shalabi, 2016 “Fire Probabilistic Risk Assessment of Nuclear Reactors” Fire Engineering Page 80-86, 1 January 2016.
[4] Hossam Shalabi & George Hadjisophocleous, 2018 “CANDU Fire Probabilistic Risk Assessment (PRA) Model”, CNL Nuclear Review, 18 December 2018.
[5] CSA standard N293-95 “Fire Protection for CANDU Nuclear Power Plants”, February 1997.
[6] Hossam Shalabi & George Hadjisophocleous, 2019 “CANDU Fire Load Densities in Canadian Nuclear Plants paper”, CNL Nuclear Review, Accepted to be published.
[7] CSA standard N293-12 “Fire Protection for CANDU Nuclear Power Plants”, November 2017.
[8] NFPA (2016), ‘NFPA 557, Standard for Determination of Fire Load for Use in Structural Fire Protection Design’, National Fire Protection Association, Quincy MA.
[9] Thauvoye, C., Zhao, B., Klein, J., Fontana, M. (2009), ‘Fire Load Survey and Statistical Analysis’, Fire Safety Science, Vol. 9, pp 991-1002.
[10] Anon, P, (1942). ‘Building Materials and Science structures – Fire Resistance Classification of Building Construction’, Report of Subcommittee on Fire Resistance Classification of Central Housing Committee on Research, Design and Construction, Report BMS92, National Bureau of Standards, Washington.
[11] Green, M., (1977). ‘A Survey of Fire Loads in Modern Office Building – Some Preliminary Results’, Fire Technology, vol. 13(1), pp 42 – 52.
[12] Barnett, C. R., (1984). ‘‘Pilot Fire Load Survey,’’ Project Report No 3580, New Zealand Fire Protection Association. MacDonald Barnett Partners, Auckland.
[13] Yii, H. W., (2000). ‘Effects of Surface Area and Thickness on Fire Loads’, Fire Engineering Research report, No. 2000/13 University of Canterbury, Christchurch, New Zealand.
[14] NBCC. 2015. National Building Code of Canada 2015. National Research Council of Canada, Ottawa, Ontario.
[15] Hossam Shalabi & George Hadjisophocleous, 2019 “CANDU Fire PRA Qualitative Analysis Screening Step”, CNL Nuclear Review, Under Consideration
[16] Probabilistic set of filter criteria in the frame of Fire PSA, Florian Berchtold, Burkhard Forell, Ulrich Krause (2015) International Workshop on Fire Probabilistic Risk Assessment (PRA)
[17] Facharbeitskreis (FAK PSA) (2005a). Probabilistic Safety Analysis for Nuclear Power Plants: Methods for Probabilistic Safety Analysis for Nuclear Power Plants, Status: August 2005, BfS-SCHR-37/05, Salzgitter, October 2005.
[18] Verification and Validation of Selected Fire Models for Nuclear Power Plant Applications Volume 7: Fire Dynamics Simulator (FDS), April 2007.
[19] IEEE 383-2015 - IEEE Standard for Qualifying Electric Cables and Splices for Nuclear Facilities.
[20] Inspection Manual Chapter 0609, Appendix F, “Fire Protection Significant Determination Process,” USNRC, February 2005 (available through the USNRC public website).
[1] U.S. Nuclear Regulatory Commission and Electric Power Research Institute, “EPRI/NRC-RES Fire PRA Methodology for Nuclear Power Facilities, Volume 2: Detailed Methodology”, NUREG/CR-6850 Supplement 1, EPRI 1008239, Technical Report, October 2004.
[2] Hossam Shalabi & George Hadjisophocleous, 2018 “CANDU Fire Database”, CNL Nuclear Review, 18 December 2018.
[3] Hossam Shalabi, 2016 “Fire Probabilistic Risk Assessment of Nuclear Reactors” Fire Engineering Page 80-86, 1 January 2016.
[4] Hossam Shalabi & George Hadjisophocleous, 2018 “CANDU Fire Probabilistic Risk Assessment (PRA) Model”, CNL Nuclear Review, 18 December 2018.
[5] CSA standard N293-95 “Fire Protection for CANDU Nuclear Power Plants”, February 1997.
[6] Hossam Shalabi & George Hadjisophocleous, 2019 “CANDU Fire Load Densities in Canadian Nuclear Plants paper”, CNL Nuclear Review, Accepted to be published.
[7] CSA standard N293-12 “Fire Protection for CANDU Nuclear Power Plants”, November 2017.
[8] NFPA (2016), ‘NFPA 557, Standard for Determination of Fire Load for Use in Structural Fire Protection Design’, National Fire Protection Association, Quincy MA.
[9] Thauvoye, C., Zhao, B., Klein, J., Fontana, M. (2009), ‘Fire Load Survey and Statistical Analysis’, Fire Safety Science, Vol. 9, pp 991-1002.
[10] Anon, P, (1942). ‘Building Materials and Science structures – Fire Resistance Classification of Building Construction’, Report of Subcommittee on Fire Resistance Classification of Central Housing Committee on Research, Design and Construction, Report BMS92, National Bureau of Standards, Washington.
[11] Green, M., (1977). ‘A Survey of Fire Loads in Modern Office Building – Some Preliminary Results’, Fire Technology, vol. 13(1), pp 42 – 52.
[12] Barnett, C. R., (1984). ‘‘Pilot Fire Load Survey,’’ Project Report No 3580, New Zealand Fire Protection Association. MacDonald Barnett Partners, Auckland.
[13] Yii, H. W., (2000). ‘Effects of Surface Area and Thickness on Fire Loads’, Fire Engineering Research report, No. 2000/13 University of Canterbury, Christchurch, New Zealand.
[14] NBCC. 2015. National Building Code of Canada 2015. National Research Council of Canada, Ottawa, Ontario.
[15] Hossam Shalabi & George Hadjisophocleous, 2019 “CANDU Fire PRA Qualitative Analysis Screening Step”, CNL Nuclear Review, Under Consideration
[16] Probabilistic set of filter criteria in the frame of Fire PSA, Florian Berchtold, Burkhard Forell, Ulrich Krause (2015) International Workshop on Fire Probabilistic Risk Assessment (PRA)
[17] Facharbeitskreis (FAK PSA) (2005a). Probabilistic Safety Analysis for Nuclear Power Plants: Methods for Probabilistic Safety Analysis for Nuclear Power Plants, Status: August 2005, BfS-SCHR-37/05, Salzgitter, October 2005.
[18] Verification and Validation of Selected Fire Models for Nuclear Power Plant Applications Volume 7: Fire Dynamics Simulator (FDS), April 2007.
[19] IEEE 383-2015 - IEEE Standard for Qualifying Electric Cables and Splices for Nuclear Facilities.
[20] Inspection Manual Chapter 0609, Appendix F, “Fire Protection Significant Determination Process,” USNRC, February 2005 (available through the USNRC public website).
@article{"International Journal of Chemical, Materials and Biomolecular Sciences:79213", author = "Hossam Shalabi and George Hadjisophocleous", title = "Canada Deuterium Uranium Updated Fire Probabilistic Risk Assessment Model for Canadian Nuclear Plants", abstract = "The Canadian Nuclear Power Plants (NPPs) use some portions of NUREG/CR-6850 in carrying out Fire Probabilistic Risk Assessment (PRA). An assessment for the applicability of NUREG/CR-6850 to CANDU reactors was performed and a CANDU Fire PRA was introduced. There are 19 operating CANDU reactors in Canada at five sites (Bruce A, Bruce B, Darlington, Pickering and Point Lepreau). A fire load density survey was done for all Fire Safe Shutdown Analysis (FSSA) fire zones in all CANDU sites in Canada. National Fire Protection Association (NFPA) Standard 557 proposes that a fire load survey must be conducted by either the weighing method or the inventory method or a combination of both. The combination method results in the most accurate values for fire loads. An updated CANDU Fire PRA model is demonstrated in this paper that includes the fuel survey in all Canadian CANDU stations. A qualitative screening step for the CANDU fire PRA is illustrated in this paper to include any fire events that can damage any part of the emergency power supply in addition to FSSA cables.
", keywords = "Fire safety, CANDU, nuclear, fuel densities, FDS, qualitative analysis, fire probabilistic risk assessment.", volume = "13", number = "10", pages = "480-5", }
