Provides guidance on the development, content and use of operational limits and conditions and operating procedures that affect them. This publication recommends how to meet the requirements established in Safety Standards Series No. NS-R-2, Safety of Nuclear Power Plants: Operation.

The recommendations provided in this Safety Guide are aimed primarily at operating organizations of nuclear power plants and regulatory bodies. It covers the concept of operational limits and conditions (OLCs), their content as applicable to nuclear power plants, and the responsibilities of the operating organization for their establishment, modification, compliance and documentation. Operating procedures (including emergency operating procedures and severe accident management guidelines) to support the implementation of the OLCs and to ensure their observance are also within the scope of this Safety Guide.

"The recommendations provided in this Safety Guide are aimed primarily at operating organizations of nuclear power plants and regulatory bodies. It covers the concept of operational limits and conditions (OLCs), their content as applicable to nuclear power plants, and the responsibilities of the operating organization for their establishment, modification, compliance and documentation. Operating procedures (including emergency operating procedures and severe accident management guidelines) to support the implementation of the OLCs and to ensure their observance are also within the scope of this Safety Guide."--Publisher's description.

The recommendations provided in this Safety Guide are aimed primarily at operating organizations of nuclear power plants and regulatory bodies. It covers the concept of operational limits and conditions (OLCs), their content as applicable to nuclear power plants, and the responsibilities of the operating organization for their establishment, modification, compliance and documentation. Operating procedures (including emergency operating procedures and severe accident management guidelines) to support the implementation of the OLCs and to ensure their observance are also within the scope of this Safety Guide.

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.

The present report is a revision of Safety Series No. 75-INSAG-3 (1988), updating the statements made on the objectives and principles of safe design and operation for electricity generating nuclear power plants. It includes the improvements made in the safety of operating nuclear power plants and identifies the principles underlying the best current safety policies to be applied in future plants. It presents INSAG's understanding of the principles underlying the best current safety policies and practices of the nuclear power industry.

This publication addresses the basics of the application of a graded approach in the regulatory oversight of nuclear installations, describes the approaches currently implemented by several regulatory bodies around the world and, based on these examples, proposes a generic methodology for application of a graded approach to regulation of nuclear installations. The publication provides practical examples and information on developing and implementing strategies and processes for all regulatory functions.

This publication deals with the latest nuclear power plant maintenance optimization programmes and provides key requirements and strategies for successful implementation. It documents shared proven maintenance optimization methods and techniques from Member States, including more detailed examples in the annexes of this publication.

The March 11, 2011, Great East Japan Earthquake and tsunami sparked a humanitarian disaster in northeastern Japan. They were responsible for more than 15,900 deaths and 2,600 missing persons as well as physical infrastructure damages exceeding $200 billion. The earthquake and tsunami also initiated a severe nuclear accident at the Fukushima Daiichi Nuclear Power Station. Three of the six reactors at the plant sustained severe core damage and released hydrogen and radioactive materials. Explosion of the released hydrogen damaged three reactor buildings and impeded onsite emergency response efforts. The accident prompted widespread evacuations of local populations, large economic losses, and the eventual shutdown of all nuclear power plants in Japan. "Lessons Learned from the Fukushima Nuclear Accident for Improving Safety and Security of U.S. Nuclear Plants" is a study of the Fukushima Daiichi accident. This report examines the causes of the crisis, the performance of safety systems at the plant, and the responses of its operators following the earthquake and tsunami. The report then considers the lessons that can be learned and their implications for U.S. safety and storage of spent nuclear fuel and high-level waste, commercial nuclear reactor safety and security regulations, and design improvements. "Lessons Learned" makes recommendations to improve plant systems, resources, and operator training to enable effective ad hoc responses to severe accidents. This report's recommendations to incorporate modern risk concepts into safety regulations and improve the nuclear safety culture will help the industry prepare for events that could challenge the design of plant structures and lead to a loss of critical safety functions. In providing a broad-scope, high-level examination of the accident, "Lessons Learned" is meant to complement earlier evaluations by industry and regulators. This in-depth review will be an essential resource for the nuclear power industry, policy makers, and anyone interested in the state of U.S. preparedness and response in the face of crisis situations.

Compares the requirements of IAEA Safety Series No. 50-C/SG-Q, Quality Assurance for Safety in Nuclear Power Plants and other Nuclear Installations with the ISO 9001:2000 standard issued by the International Organization for Standardization.