{"id":110948,"date":"2024-10-18T16:03:37","date_gmt":"2024-10-18T16:03:37","guid":{"rendered":"https:\/\/pdfstandards.shop\/product\/uncategorized\/ieee-933-1999\/"},"modified":"2024-10-24T21:59:44","modified_gmt":"2024-10-24T21:59:44","slug":"ieee-933-1999","status":"publish","type":"product","link":"https:\/\/pdfstandards.shop\/product\/publishers\/ieee\/ieee-933-1999\/","title":{"rendered":"IEEE 933 1999"},"content":{"rendered":"
New IEEE Standard – Inactive – Superseded. Guidelines for the definition of a reliability program at nuclear power generating stations are developed. Reliability programs during the operating phase of such stations are emphasized; however, the general approach applies to all phases of the nuclear power generating station life cycle (e.g., design, construction, start-up, operating, and decommissioning).<\/p>\n
PDF Pages<\/th>\n | PDF Title<\/th>\n<\/tr>\n | ||||||
---|---|---|---|---|---|---|---|
1<\/td>\n | Title Page <\/td>\n<\/tr>\n | ||||||
3<\/td>\n | Introduction <\/td>\n<\/tr>\n | ||||||
4<\/td>\n | Participants <\/td>\n<\/tr>\n | ||||||
6<\/td>\n | CONTENTS <\/td>\n<\/tr>\n | ||||||
7<\/td>\n | 1. Overview <\/td>\n<\/tr>\n | ||||||
8<\/td>\n | 1.2 Purpose 2. References 3. Definitions and acronyms 3.1 Definitions <\/td>\n<\/tr>\n | ||||||
11<\/td>\n | 3.2 Acronyms <\/td>\n<\/tr>\n | ||||||
12<\/td>\n | 4. Program elements <\/td>\n<\/tr>\n | ||||||
13<\/td>\n | 4.1 Performance monitoring <\/td>\n<\/tr>\n | ||||||
15<\/td>\n | 4.2 Performance evaluation <\/td>\n<\/tr>\n | ||||||
20<\/td>\n | 4.3 Problem prioritization <\/td>\n<\/tr>\n | ||||||
22<\/td>\n | 4.4 Problem analysis and corrective action recommendation <\/td>\n<\/tr>\n | ||||||
26<\/td>\n | 4.5 Corrective action implementation and feedback <\/td>\n<\/tr>\n | ||||||
27<\/td>\n | 5. Major programmatic resources <\/td>\n<\/tr>\n | ||||||
28<\/td>\n | 5.1 Operations <\/td>\n<\/tr>\n | ||||||
29<\/td>\n | 5.2 Maintenance 5.3 Engineering <\/td>\n<\/tr>\n | ||||||
30<\/td>\n | 5.4 Safety <\/td>\n<\/tr>\n | ||||||
31<\/td>\n | 5.5 Licensing 5.6 Quality assurance <\/td>\n<\/tr>\n | ||||||
32<\/td>\n | 5.7 Procurement <\/td>\n<\/tr>\n | ||||||
33<\/td>\n | Annex A (informative) Reliability program management <\/td>\n<\/tr>\n | ||||||
38<\/td>\n | Annex B (informative) Case study\u2014Application of Excelsior Power Company\u2019s reliabil-ity program plan to service water pumps <\/td>\n<\/tr>\n | ||||||
40<\/td>\n | Annex C (informative) Sample RAM specification for replacement service water pumps <\/td>\n<\/tr>\n | ||||||
48<\/td>\n | Annex D (informative) Bibliography <\/td>\n<\/tr>\n<\/table>\n","protected":false},"excerpt":{"rendered":" IEEE Guide for the Definition of Reliability Program Plans for Nuclear Power Generating Stations<\/b><\/p>\n |