The use of fully digitalized main control rooms (MCRs) in commercially operated nuclear power plants (NPPs) has commenced, but the search for a method to do comprehensive human reliability analyses (HRA) while operators use the digital MCRs is still ongoing. Task performance differs when systems are computer-based or in digital forms versus when in analog format. Most of the human reliability analysis methods in existence were developed primarily with the concept of how operators work in the analog MCRs. Some of the characteristics of these new digital MCRs provide opportunities for new types of operator errors, which may also affect operator response during time-critical tasks. This study describes the development of a method to solve this problem with a focus on the advanced power reactor-1400 (APR1400) NPP, which has a fully digitalized MCR. This study starts with identifying the specific features of the digital control room in the APR1400 NPP. The main issues when operators use digital MCRs are identified and the ways in which they impact human errors are determined. Then, how to analyze error modes and quantify human error probabilities are explored. Finally, based on the observed characteristics and distinguishing features of the APR1400 MCR, the cause based decision tree (CBDT), the integrated human event analysis system (IDHEAS), and the human reliability evaluator for computer-based control room actions (HuRECA) methods are suggested for modification to evaluate human reliability.