Qualification methods for Class 1E vented lead acid batteries and racks to be used in nuclear power generating stations outside primary containment are described in this standard. Qualifications required by…
The criteria for the application and testing of diesel-generator units as Class 1E standby power supplies in nuclear power generating stations are described in this standard.
Established in this standard are criteria for variable selection, performance, design, and qualification of accident monitoring instrumentation for anticipated operational, design basis events and severe accidents.
Activities related to preferred power supply (PPS) reliability, including design considerations, analytical studies, operational and maintenance considerations, and interface agreements between a nuclear power generating station (NPGS) and its associated…
Practices are provided for establishing procedures that will yield data to demonstrate that the equipment can meet its performance requirements during and/or following one safe shutdown earthquake event preceded by…
Criteria for the design of an integrated security system for nuclear power generating stations are provided in this standard. Requirements are included for the overall system, interfaces, subsystems, and individual…
Common terminology and recommended practices for initiating and conducting event investigations, analyzing data, producing results, and identifying corrective actions associated with facility personnel, processes, equipment, and systems at nuclear facilities…
General reliability and availability analysis methods that can be applied to structures, systems, and components (SSCs) in nuclear power generating stations and other nuclear facilities are contained in this guide.
A structured framework for the incorporation of human reliability analysis (HRA) into probabilistic risk assessments (PRAs) is provided in this guide. To enhance the analysis of human/system interactions in PRAs,…
