This report is based on information presented at two IAEA Technical Committee meetings held within the framework of the IAEA Project on Operational Safety Guidance in 1993 and 1994. The document was prepared to provide guidance to Member States in assessing the status of equipment qualification (EQ) in operational nuclear power plants and in preserving this status. It offers methods and practices for activities which are necessary for a successful implementation of periodical safety reviews. The report should be of value for all countries that are parties to the Convention on Nuclear Safety, which entered into force on 24 October 1996 and stipulates the review and, where necessary, the upgrading of the safety of existing nuclear installations.

This Safety Guide provides recommendations on a structured approach to the establishment and preservation of equipment qualification in nuclear installations, to confirm reliable performance of safety functions by such equipment during operational states and accident conditions, to avoid vulnerability due to common cause failure of the equipment. It applies primarily to equipment that performs one or more safety functions, but it may also be applied to items not important to safety, in accordance with national requirements. The qualification process covers electrical, instrumentation and control, and active mechanical equipment, and components associated with it, for example, seals, gaskets, lubricants, cables, connections, and mounting/anchoring structures. The qualification process for passive mechanical components for which the safety performance is assured by design in accordance with applicable codes, is outside the scope of this publication. The recommendations in this Safety Guide apply to new nuclear installations, and as far as is reasonably practicable to existing nuclear installations.

A compilation of currently available electronic versions of NRC regulatory guides.

Covers all aspects of electrical systems for nuclear power plants written by an authority in the field Based on author Omar Mazzoni's notes for a graduate level course he taught in Electrical Engineering, this book discusses all aspects of electrical systems for nuclear power plants, making reference to IEEE nuclear standards and regulatory documents. It covers such important topics as the requirements for equipment qualification, acceptance testing, periodic surveillance, and operational issues. It also provides excellent guidance for students in understanding the basis of nuclear plant electrical systems, the industry standards that are applicable, and the Nuclear Regulatory Commission's rules for designing and operating nuclear plants. Electrical Systems for Nuclear Power Plants offers in-depth chapters covering: elements of a power system; special regulations and requirements; unique requirements of a Class 1E power system; nuclear plants containment electrical penetration assemblies; on-site emergency AC sources; on-site emergency DC sources; protective relaying; interface of the nuclear plant with the grid; station blackout (SBO) issues and regulations; review of electric power calculations; equipment aging and decommissioning; and electrical and control systems inspections. This valuable resource: Evaluates industry standards and their relationship to federal regulations Discusses Class 1E equipment, emergency generation, the single failure criterion, plant life, and plant inspection Includes exercise problems for each chapter Electrical Systems for Nuclear Power Plants is an ideal text for instructors and students in electrical power courses, as well as for engineers active in operating nuclear power plants.

This publication provides recommendations and guidance for meeting Requirement 32 of IAEA Safety Standards Series No. SSR-2/1 (Rev. 1), Safety of Nuclear Power Plants: Design, for optimal operator performance involving systematic consideration of human factors, including the human machine interface (HMI). The Safety Guide provides a structured approach and guidance on application of human factors engineering (HFE) in the design of the HMI, which is the basis for human physical and cognitive processes in nuclear power plants. It applies to application of HFE in the design, operation and maintenance of the HMI for new plants, as well as for modifications of the HMI of existing plants.

"This Safety Guide provides recommendations on a structured approach to the establishment and preservation of equipment qualification in nuclear installations, to confirm reliable performance of safety functions by such equipment during operational states and accident conditions, to avoid vulnerability due to common cause failure of the equipment. It applies primarily to equipment that performs one or more safety functions, but it may also be applied to items not important to safety, in accordance with national requirements. The qualification process covers electrical, instrumentation and control, and active mechanical equipment, and components associated with it, for example, seals, gaskets, lubricants, cables, connections, and mounting/anchoring structures. The qualification process for passive mechanical components for which the safety performance is assured by design in accordance with applicable codes, is outside the scope of this publication. The recommendations in this Safety Guide apply to new nuclear installations, and as far as is reasonably practicable to existing nuclear installations."--Publisher's description.

On the basis of the principles included in the Fundamental Safety Principles, IAEA Safety Standards Series No. SF-1, this Safety Requirements publication establishes requirements applicable to the design of nuclear power plants. It covers the design phase and provides input for the safe operation of the power plant. It elaborates on the safety objective, safety principles and concepts that provide the basis for deriving the safety requirements that must be met for the design of a nuclear power plant. Contents: 1. Introduction; 2. Applying the safety principles and concepts; 3. Management of safety in design; 4. Principal technical requirements; 5. General plant design; 6. Design of specific plant systems.