[en] The paper outlines the main staffing requirements for the new generation power units with nuclear reactors. These requirements were developed taking into account IAEA recommendations. NPP staffing structure is described, including the main and auxiliary personnel. The main principles of personnel number determination are given. Special attention is taken to the issues of personnel skill and training, including both theoretical education and practical work on the power units in operation. The use of simulators, system of knowledge control and structure of training are considered. ''Shopless'' staffing structure approach is proposed for the NPP, assuming that the main scope of repair work is performed by the central repair organization, thus increasing the quality of repair and decreasing the number of personnel on the plant. Data are given on the personnel number for the WWER-640 and the BN-800 reactor designs. Specialists of the ''ATOMENERGOPROJECT'' Institute started their work on staffing on the early development stage of the basic design of WWER-640 reactor power unit which is the forerunner of the new generation reactors. This work was based on the approaches taken by the chief engineers of NPPs in operation during their meeting held in 1989 in Kalinin NPP. At this meeting definite decision was taken on changing over to involving manufacturer in the repair work of NPP components using manufacturer's technology. In 1992 the meeting of representatives of suppliers of the main components was held where representatives of ''ATOMENERGOREMONT'' and ''LENENERGOREMONT'' were present. The suppliers agreed on carrying out repair works on the components they produced. For this purpose special departments were set up having some experience. This repair work is already carried out by ''ATOMENERGOREMONT'' on some nuclear power plants. ''LENENERGOREMONT'' has gained considerable experience in this kind of repair work on the turbines of LO-1 and LO-2 NPP in Finland. Within the framework of agreement with SPB AEP, VNIIAES determined manpower (man-hours) of maintenance and repair works and gave recommendations on the structure of NPP management and number of repair personnel and personnel which should be involved for the repair of 3rd category components and comprehensive inspection of the reactor in case of total unloading of the core. Also, experience gained in designing of Loviisa-1 and Loviisa-2 NPP for Finland (in cooperation with IVO company) assuming shopless management structure and components repair made by the involved companies, was taken into account. As a result of these efforts, the concept of staffing of WWER-640 reactor NPP was developed and approved. This concept was based on the following points: repair of the 1st category components (routine repair) is carried out by the NPP repair personnel; - repair works on 2nd category (medium) and 3rd category (capital) components are carried out by the manufacturers under agreement with the NPP; - repair works mentioned in the previous point are fulfilled by ''ATOMENERGOREMONT'' (in the restricted access areas) or by ''ENERGOREMONT'' local company of the NPP region; - incoming inspection was adopted for the components delivered to the NPP. The suppliers are informed on their obligation to eliminate all defects revealed at the stage of the incoming inspection (either on the NPP site or in the manufacturer's). For instance, hydraulic lock of Loviisa NPP was returned to Leningrad hydromechanical works for repair; - applications for the component improvement to meet new safety standards include requirements on the components quality and provision of diagnostics means allowing repair works to be fulfilled with respect to the current component conditions; - according to the new General safety requirements OPB-88/97, components of safety related systems of 1H, 2H and 3H grades are monitored by the Atomic Safety Authority of Russia, quality assurance program being provided; - shopless management structure has been adopted eliminating duplication of some working posts; - requirements to the leaks in the valves and components have been increased allowing decrease of the liquid radioactive waste amount and hence decrease the number of personnel involved in its solidification procedure; - requirements on the components maintainability have been increased. (author)