This book consist of Introduction; Responsibilities and Functions of Regulatory Body; Personnel Requirements and Qualifications; Training Programme; Training Schedules and Implementation; and Conclusion. (Jml)
NUREG-1022, “Event Reporting Guidelines: 10 CFR 50.72 and 50.73,” contains guidelines that the staff of the U.S. Nuclear Regulatory Commission (NRC) considers acceptable for use in meeting the requirements of Title 10 of the Code of Federal Regulations (10 CFR) 50.72 and 50.73. Several identified reporting issues could not be quickly resolved given certain ambiguities in NUREG-1022, Revisio…
This Safety Guide recommends actions, conditions and procedures in relation to external human induced events and provides guidance for fulfilling the requirements of Safety Standards Series No. NS-R-3, Site Evaluation for Nuclear Installations, when conducting a site evaluation for a nuclear power plant.
This document is about the technical study of Nuclear Power Plant Vol.1, namely the feasibility study of the first power plant in Indonesia between the Indonesian government represented by BATAN and PLN and the Italian government represented by Nira and ENEL. This study is an important document and becomes a part of Indonesian history related to PLTN in 1980. Volume one is divided into 4 sections.
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 practic…
Accident analysis, i.e. deterministic safety analysis, is an important tool for confirming the adequacy and efficiency of provisions within the defence in depth concept for the safety of nuclear power plants (NPPs). An analysis that lacks consistency or quality, or is incomplete, represents a safety issue for a given NPP. The purpose of the report is therefore to provide the necessary practical…
This Guide describes the first stage of the siting process for nuclear power plants — the site survey, which involves the study and investigation of a large region to select one or more preferred candidate sites. Its purpose is to recommend procedures and provide information for use in implementing a part of the Code of Practice on Safety in Nuclear Power Plant Siting (IAEA Safety Series No. …
This book consist : Introduction; Basic principles for structuring, staffing and documenting the organization for quality assurance; Organizational structure of the responsible organization; Organization of the plant disgners; Organization of manufacturers and constructors; and Record. (Jml)
This report provides practical guidance on the methods available for verification of the software and validation of computer based systems in nuclear power plants, and on how and when these methods can be effectively applied. It will be of particular interest to all those involved in the development, implementation, maintenance and use of software and computer based instrumentation and control …
Deterministic safety analysis (henceforth referred to as accident analysis) is an important tool for confirming the adequacy and efficiency of provisions within the defence in depth concept for the safety of nuclear power plants (NPPs). Due to the close interrelation between accident analysis and safety, an analysis that lacks consistency, is incomplete or of poor quality is considered a safety…