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This document provides guidelines for the definition of a reliability program at nuclear generating stations and other nuclear facilities. The document emphasizes reliability programs during the operating phase of such facilities; however, the general approach applies to all phases (e.g., design, construction, start-up, operating, and decommissioning) of the facility.

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This document provides guidelines for the definition of a reliability program at nuclear generating stations and other nuclear facilities. The document emphasizes reliability programs during the operating phase of such facilities; however, the general approach applies to all phases (e.g., design, construction, start-up, operating, and decommissioning) of the facility.

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This standard establishes criteria for qualification of safety-related actuators, and actuator components, in Nuclear Power Generating Stations and other Nuclear Facilities in order to demonstrate their ability to perform their intended safety functions.

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This document provides guidance for evaluating human-system performance related to systems, equipment, and facilities6 in nuclear power generating stations and other nuclear facilities. It summarizes specific evaluation techniques and presents rationale for their application within the integrated systems approach to plant design, operations, and maintenance described in IEEE Std 1023™.

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This document provides guidelines for the definition of a reliability program at nuclear generating stations and other nuclear facilities. The document emphasizes reliability programs during the operating phase of such facilities; however, the general approach applies to all phases (e.g., design, construction, start-up, operating, and decommissioning) of the facility.

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This guide contains 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.

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This Code provides requirements for the performance, design, fabrication, installation, inspection, acceptance testing, and quality assurance of equipment used in air and gas treatment systems in nuclear facilities. This Code also provides nonmandatory guidance for systems involving components covered by this Code.

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