RB 064-11

Provision on General Recommendations to the Development of Probabilistic Safety Analysis (Level 2 PSA) for NPPs with RBMK-type Reactors

Recommendations for registration of the changed in operating conditions of the systems and elements of the nuclear fuel cycle facility shutdown at determination of the pssibility to reduce the scope of maintenance and implementation of the corresponding changes to the maintenance documentation of the nuclear fuel cycle facility

Establishment and Monitoring Methods of Lifetime Performance Characteristics of NPP Valves. 

Establishment and Monitoring Methods of Lifetime Performance Characteristics of NPP Pressurized Equipment and Pipelines. 

Safety guide on nuclear energy use "Methodology of Assessment the Safety Culture Level at Nuclear Fuel Cycle Facilities"

Safety guide "General Recommendations for the Development of Probabilistic Safety Analysis (Level 1 PSA) in Case of Initiating Events at a Nuclear Unit Conditioned by On-site Fires and Flooding"