Probabilistic safety assessment of the Dukovany NPP - a tentative study. Appendix A. Methodology and supplementary analyses

The nomenclature used throughout the study, the method of analysis of failures with a common cause, and the way of including the human factor are outlined. Computer codes REPA 1D, D4, SLAP 3, and RISK SPECTRUM PSA are described. The theoretical principles are outlined of the sensitivity analysis, the significance analysis, and the uncertainty analysis employed in the detailed quantitative failure analysis. The possibility of clogging of the TQ cooling system at the Dukovany nuclear power plant is briefly assessed. The reliability of the human factor in complex systems is discussed, and a categorization system is proposed for the influence of the human factor on the NPP safety. 4 figs., 32 refs