{"id":82324,"date":"2024-10-18T03:04:02","date_gmt":"2024-10-18T03:04:02","guid":{"rendered":"https:\/\/pdfstandards.shop\/product\/uncategorized\/ieee-379-1988\/"},"modified":"2024-10-24T19:49:49","modified_gmt":"2024-10-24T19:49:49","slug":"ieee-379-1988","status":"publish","type":"product","link":"https:\/\/pdfstandards.shop\/product\/publishers\/ieee\/ieee-379-1988\/","title":{"rendered":"IEEE 379 1988"},"content":{"rendered":"
New IEEE Standard – Inactive – Superseded. Superseded by 379-1994. The application of the single-failure criterion to the electrical power, instrumentation, and control portions of nuclear power generating station safety systems is covered. Conformance with the requirements of IEEE Std 603-1991 and the single-failure criterion as stated in that document is established. Interpretation and guidance in the application of the single-failure criterion, a discussion of the failures, and an acceptable method of single-failure analysis are presented.<\/p>\n
PDF Pages<\/th>\n | PDF Title<\/th>\n<\/tr>\n | ||||||
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9<\/td>\n | 2 Definitions <\/td>\n<\/tr>\n | ||||||
11<\/td>\n | 5.2 Nondetectable Failures 5.3 Cascaded Failures 5.4 Design Basis Events and Single Failures 5.5 Common-Cause Failures 5.6 Shared Systems <\/td>\n<\/tr>\n | ||||||
12<\/td>\n | 6 Design Analysis for Single Failure 6.1 Procedure 6.2 System Portions Analysis <\/td>\n<\/tr>\n | ||||||
13<\/td>\n | 6.3 Other Considerations <\/td>\n<\/tr>\n<\/table>\n","protected":false},"excerpt":{"rendered":" IEEE Standard Application of the Single-Failure Criterion to Nuclear Power Generating Station Safety Systems<\/b><\/p>\n |