Remaining and emerging issues pertaining to the human reliability analysis of domestic nuclear power plants |
Park, Jinkyun
(Korea Atomic Energy Research Institute)
Jeon, Hojun (Korea Hydro and Nuclear Power) Kim, Jaewhan (Korea Atomic Energy Research Institute) Kim, Namcheol (Korea Electric Power Corporation, Engineering and Construction) Park, Seong Kyu (Atomic Creative Technology, Co. Ltd) Lee, Seungwoo (Korea Institute of Nuclear Safety) Lee, Yong Suk (Future and Challenge, Co. Ltd) |
1 | U.S Nuclear Regulatory Commission (NRC), An approach for determining the technical adequacy of probabilistic risk assessment results for risk-informed activities, in: Regulatory Guide 1.200, 2009. Part 3. |
2 | American Society of, American Society of Mechanical Engineering (ASME) and American Nuclear Society (ANS), Standard for Level 1/large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant Applications, Addenda to ASME/ANS RA-S-2008, 2013. RA-Sb. |
3 | J.M. O'Hara, J.C. Higgins, J.J. Persensky, P. Lewis, J. Bongarra, Human Factors Engineering Pro, 2004. |
4 | S. Kim, K. Oh, Application of HuRECA analysis method to APR-1400 HRA, in:Transactions of the Korean Nuclear Society Spring Meeting, May 18-19, Jeju, Republic of Korea, 2017. |
5 | S.W. Lee, J.S. Ha, P.H. Seong, J.H. Park, J.K. Kim, Development of a HRA method based on human factor issues for advanced NPP, in: Transactions of the Korean Nuclear Society Spring Meeting, May 27-28, Pyeongchang, Republic of Korea, 2010. |
6 | Y.J. Chang, J. Xing, S. Peters, Human reliability analysis method development in the U.S Nuclear Regulatory Commission, in: 13th International Conference on Probabilistic Safety Assessment and Management (PSAM 13), October 2-7, Seoul, Republic of Korea, 2016. |
7 | Electric Power Research Institute, SHARP1 - A Revised Systematic Human Action Reliability Procedure, 1992. EPRI-TR-101711. |
8 | D. Gertman, H. Blackman, J. Marble, J. Byers, C. Smith, The SPAR-H Human Reliability Method, NUREG/CR-6883, Idaho National Laboratory, 2005. |
9 | A. Kolaczkowski, J. Forester, E. Lois, S. Cooper, Good practices for implementing human reliability analysis, NUREG-1792, in: U.S. Nuclear Regulatory Commission, 2005. |
10 | U.S Nuclear Regulatory Commission (NRC) and Electric Power Research Institute (EPRI), EPRI/NRC-RES Fire Human Reliability Analysis Guidelines, 2009. NUREG-1921. |
11 | A.D. Swain, Accident Sequence Evaluation Program Human Reliability Analysis Procedure, NUREG/CR-4772, Sandia National Laboratories, 1987. |
12 | A.D. Swain, H.E. Guttmann, Handbook of Human Reliability Analysis with Emphasis on Nuclear Power Plant Applications, NUREG/CR-1278, Sandia National Laboratories, 1983. |
13 | I.S. Kim, B.G. Kim, D.I. Choi, E. Lee, Incorporating MACST mitigation strategy into PSA models: HRA and data issues, in: Transactions of the Korean Nuclear Society Autumn Meeting, October 25-27, Gyeongju, Republic of Korea, 2017. |
14 | J. Park, Y. Kim, W. Jung, J. Kim, J.H. Park, S.C. Jang, A Study on the Application of a Novel Seismic HRA Method to Nuclear Power Plants, KAERI/TR-5643/2014, Daejeon, Republic of Korea, 2014. |
15 | J.M. O'Hara, J.C. Higgins, W.F. Stubler, J. Krame, Computer-based Procedure Systems: Technical Basis and Human Factors Review Guidance, NUREG/CR-6634, Brookhaven National Laboratory, New York, 2000. BNL-NUREG-55264. |
16 | J.M. O'Hara, W.S. Brown, The Effects of Interface Management Tasks on Crew Performance and Safety in Complex, Computer-Based Systems, 2002. NUREG/CR-6690, Washington, DC. |
17 | J.M. O'Hara, R.E. Hall, Advanced control rooms and crew performance issues:implications for human reliability, IEEE Trans. Nucl. Sci. 39 (4) (1992) 919-923. DOI |
18 | M. Porthin, M. Liinasuo, T. Kling, HRA of Digital Control Rooms: Literature Review, VTT-R-00434-16, VTT, Finland, 2015. |
19 | T. Zachariah, D. Vanover, J. Weglian, B. Webster, P. Tarpinian, R. Fine, D. Haessler, R. Davis-Zapata, M. Powell, R. Bunt, Y. Jo, Crediting Mitigating Strategies in Risk-Informed Decision Making, NEI 16-06/2016, Washington D.C., USA, August, 2016. |
20 | D.E. MacLeod, G.W. Parry, B.D. Sloane, P. Lawrence, E.M. Chan, A.V. Trifanov, Simplified Human Reliability Analysis Process for Emergency Mitigation Equipment (EME) Deployment, International Conference on Probabilistic Safety Assessment and Management (PSAM 12), Honolulu, Hawaii, June, 2014, 2014. |
21 | V. Fauchille, H. Bonneville, J.Y. Maguer, Experience Feedback from Fukushima towards Human Reliability Analysis for Level 2 Probabilistic Safety Assessments, International Conference on Probabilistic Safety Assessment and Management (PSAM 12), June, Honolulu, Hawaii, 2014. |
22 | S. St Germain, R. Boring, G. Banaseanu, Y. Akl, M. Xu, Modification of the SPAR-H method to support HRA for Level 2 PSA, in: 13th International Conference on Probabilistic Safety Assessment and Management, Seoul, South Korea October 2-7, 2016. |
23 | E.C. Susan, J. Xing, Y.J. Chang, What HRA needs to support site-wide, multi-hszard Level 2 PRA, in: International Topical Meeting on Probabilistic Safety Assessment and Analysis, Columbia, SC, September 22-26, 2013. |
24 | J. Ha, Y. Jin, K.S. Jung, M.J. Hwang, S.H. Han, D.I. Kang, Y.H. Lee, T.Y. Sung, J.E. Yang, H.D. Kim, S.Y. Park, J.H. Park, R.J. Park, S.D. Kim, M.K. Hwang, Development of Accident Management Guidance for Korean Standard Nuclear Power Plants, KAERI/RR-1939/98, Republic of Korea, Daejeon, 1998. |
25 | R.J. Park, D.H. Kim, Evaluation of Entry Condition for Severe Accident Management Guidance, IAEA Technical meeting on SAA and SAMG, Vienna, Austria, November, 2015. |
26 | S. Park, Y. Jin, S. Kim, Y. Song, Severe Accident Management Guidance for Pressurized Heavy Water Reactors, KAERI/TR-3283, Daejeon, Republic of Korea, 2006. |
27 | E.C. Sauvage, G. Dirksen, T.C. de Brunellis, Applicability of PSA Level 2 in the design of nuclear power plants, in: International Conference on Probabilistic Safety Assessment and Management (PSAM 12), Honolulu, Hawaii, June, 2014. |
28 | CNSC, Summary Report of the International Workshop on Multi-Unit Probabilistic Safety Assessment. Ottawa, Ontario, Canada, November 17-20, 2014. |
29 | J. Park, D.H. Ham, J. Kim, W.J. Jung, Characterizing Decision-Making Tasks Included in SAMGs, International Workshop on Status of Site Level PSA (Including Multi-Unit PSA) Development, Munich, Germany, 2018. |
30 | S.W. Jang, S.W. Lee, H.C. Ho, Improvement of diagnostic flow chart severe accident management guidance for nuclear power plants in Korea, in:Transactions of the Korean Nuclear Society Autumn Meeting Gyeongju, Korea, October, 2016. |
31 | M. Kim, S. Hong, K. Lee, C. Byun, Y. Jin, Development of severe accident management guidance for NPP in Korea, in: International Conference on Probabilistic Safety Assessment and Management (PSAM 6), San Juan, Puerto Rico, USA, June, 2002. |
32 | J. Park, W. Jung, S. Kim, S.Y. Choi, Y. Kim, S.J. Lee, J.E. Yang, V.N. Dang, A Guideline to Collect HRA Data in the Simulator of Nuclear Power Plants, KAERI/TR-5206/2013, Daejeon, Republic of Korea, 2013. |
33 | D.S. Kim, S.H. Han, J.H. Park, H.G. Lim, J.H. Kim, Multiunit Level 1 Probabilistic Safety Assessment: Approaches and Their Application to a Six-Unit Nuclear Power Plant Site, Nuclear Engineering and Technology, 2018 to be published in, https://doi.org/10.1016/j.net.2018.01.006. DOI |
34 | 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 |
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