Following the Fukushima accident, research of accident tolerant fuel (ATF) and cladding materials began in order to improve the nuclear power plant safety following a Beyond Design Basis Accident (BDBA). National laboratories, industry, and universities are involved in this activity. Researchers at the University of Wisconsin are simulating BDBA’s to examine the effect of ATF cladding material using MELCOR. Use of alternate cladding materials (FeCrAl) and potential operator recovery actions have been previously studied. In this work, we examine the effect of FeCrAl coating on Zircaloy using a special version of MELCOR-1.8.6 (YU) developed by Idaho National Laboratory. This MELCOR version allows one to examine the effect of cladding coatings (Cr, FeCrAl) assuming appropriate thermo-physical data are available. FeCrAl is used as a first application of this modeling approach for clad coatings. Using a Short- Term Station Blackout (STSBO accident sequence shows that overall accident progression is quite similar to events without a coating, except for the start rapid core heatup, degradation and significant hydrogen generation. These events are delayed for more than an hour compared to nominal conditions.