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Site Evaluation for Nuclear Installations, Safety Requirements
This Safety Requirements publication was prepared under the IAEA programme on Safety Standards for Nuclear Installations. It establishes requirements and provides criteria for ensuring safety in site evaluation for nuclear installations. The Safety Guides on site evaluation listed in the references section provide recommendations on how to meet the requirements established in this Safety Requir…
The Role of Probabilistic Safety Assessment and Probabilistic Safety Criteria…
This book consist : Introduction; The role in PSA; PSA management, methodology and documentation; and Development of PSA. (Jml)
Use of Probabilistic Safety Assessment for Operational Safety PSA'91: Proceed…
Proceedings contains material Opening remarks and invited papers; Methodology (Session 2A); Regulatory applications (Session 2B); PSA use and applications – part I (Session 3A); Applications to process facilities (Session 3B(1) and International activities (Session 3B(2)); Operating experience and ageing (Session 4A); PSA use and applications – Part II (Session 4B); PSA results and insights…
Probabilistic Safety Assessment, Safety Reports
This book consist : Introduction; Capabilities and limitatin of the methodology of PSA; Further development of methodology; Guidelines for presentation and interpretation of PSA results; How should PSA be used in the future?; and Conclusions. (Jml)
Procedures for Conducting Probabilistic Safety Assessments of Nuclear Power P…
This safety practice report provides guidance on conducting a Level 1 PSA for internal events in nuclear power plants. The main emphasis is on the procedural steps of the PSA rather than the details of the corresponding methods. The report is intended to assist technical persons managing or performing PSAs. A particular aim is to promote a standardized framework, terminology and form of documen…
Quality Assurance for Safety in Nuclear Power Plants and Other Nuclear Instal…
The revised Safety Code and its corresponding Safety Guides replace Safety Series No. 50-C-QA (Rev. 1), Code on the Safety of Nuclear Power Plants: Quality Assurance, and Safety Series Nos 50-SG-QA1 to 50-SG-QA11, and present new simplified basic requirements and implementation methods for quality assurance in a nuclear context. They provide recommendations to regulatory bodies in establishing …
Understanding and Mitigating Ageing in Nuclear Power Plants: Materials and Op…
Plant life management (PLiM) is a methodology focused on the safety-first management of nuclear power plants over their entire lifetime. It incorporates and builds upon the usual periodic safety reviews and license renewals as part of an overall framework designed to assist plant operators and regulators in assessing the operating conditions of a nuclear power plant, and establishing the techni…
Design of Nuclear Installations Against External Events Excluding Earthquakes…
The status of the IAEA safety standards derives from the IAEA’s Statute, which authorizes the IAEA to establish or adopt, in consultation and, where appropriate, in collaboration with the competent organs of the United Nations and with the specialized agencies concerned, standards of safety for protection of health and minimization of danger to life and property, and to provide for their appl…
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