The risk associated with the performance of alloy 22 waste package (WP) in the potential repository for high-level nuclear waste at Yucca Mountain (YM) was assessed using the Nuclear Regulatory Commission's Total-System Performance Assessment (TPA) Code. The high-temperature (above 100 °C) deliquescence relative humidity (RH) from mixed salt deposits on the WP surface was evaluated by lowering the critical RH (RH critical ) for aqueous corrosion to 35 to 60 pct. For the base case values of the critical potential for initiation of localized corrosion, the estimated dose increased from 0.05 to 1 mrem/year in 10,000 years by altering RH critical . For the modified case, by adding more data and refining the fitting, the estimated dose increased to 3.8 mrem/year at 10,000 years without lowering RH critical . Using the new repassivation potential with nitrate as an inhibitor without changes in RH critical , the estimated dose decreased to 0.03 mrem/year at 10,000 years. Taking credit for the remaining surface area of the WP after failure by localized corrosion reduces the estimated dose from 4 to 0.4 mrem/year. Anodic sulfur segregation at the interface of metal and passive film and subsequent spalling of passive film may enhance uniform corrosion. The cyclic process of fast active corrosion upon sulfur segregation followed by slow passive corrosion upon repassivation is unlikely to significantly reduce the WP lifetime.