{"id":112205,"date":"2024-10-18T16:23:14","date_gmt":"2024-10-18T16:23:14","guid":{"rendered":"https:\/\/pdfstandards.shop\/product\/uncategorized\/ieee-577-1976\/"},"modified":"2024-10-24T22:04:04","modified_gmt":"2024-10-24T22:04:04","slug":"ieee-577-1976","status":"publish","type":"product","link":"https:\/\/pdfstandards.shop\/product\/publishers\/ieee\/ieee-577-1976\/","title":{"rendered":"IEEE 577 1976"},"content":{"rendered":"
New IEEE Standard – Inactive – Superseded. Uniform minimum acceptable requirements for the performance of reliability analyses for safety-related systems found in nuclear power generating stations are provided. The requirements can be applied during design, fabrication, testing, maintenance, and repair of systems and components in nuclear power plants. The timing of the analysis depends upon the purpose for which it is performed.<\/p>\n
PDF Pages<\/th>\n | PDF Title<\/th>\n<\/tr>\n | ||||||
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1<\/td>\n | Title Page <\/td>\n<\/tr>\n | ||||||
2<\/td>\n | Foreword Participants <\/td>\n<\/tr>\n | ||||||
4<\/td>\n | CONTENTS <\/td>\n<\/tr>\n | ||||||
5<\/td>\n | 1. Purpose 2. Scope <\/td>\n<\/tr>\n | ||||||
6<\/td>\n | 3. Definitions 4. Requirements 4.1 General <\/td>\n<\/tr>\n | ||||||
7<\/td>\n | 4.2 Qualitative Analysis <\/td>\n<\/tr>\n | ||||||
8<\/td>\n | 4.3 Quantitative Analysis <\/td>\n<\/tr>\n | ||||||
9<\/td>\n | 4.4 Evaluation <\/td>\n<\/tr>\n<\/table>\n","protected":false},"excerpt":{"rendered":" IEEE Standard Requirements for Reliability Analysis in the Design and Operation of Safety Systems for Nuclear Power Generating Stations<\/b><\/p>\n |