Abstract: Fire is analytically a significant contributor to nuclear power plant risk. In domestic nuclear safety license applications, internal fire probabilistic safety analysis（PSA） should be developed. The associated human reliability analysis（HRA） is the key technical element with certain difficulty. The US Nuclear Regulatory Commission（NRC） issued the guide NUREG-1921 specifically, to support NPP conducting a fire HRA. However, the domestic study on NUREG-1921 has not been thorough enough, and internal event HRA method and ideas applied in engineering projects. On the basis of studying the fire HRA methods provided by NUREG-1921, the fire response mechanism and fire human response characteristics of domestic NPPs were introduced into the performance forming factors（PSFs） of the fire HRA, which compared with the SPAR-H PSFs. Through optimization and improvement, a screening HRA decision tree and a scoping HRA decision tree of the main control room have been provided. Comparative analysis of the HRA of a fire in the electrical pannel area of the electrical building of a domestic pressurized water reactor NPP was implicated with the different methods of screening value HRA, scoping HRA and SPAR-H. This study provided references for the implementation of fire HRA in domestic nuclear power projects.