{"id":110996,"date":"2024-10-18T16:04:19","date_gmt":"2024-10-18T16:04:19","guid":{"rendered":"https:\/\/pdfstandards.shop\/product\/uncategorized\/ieee-1082-1997\/"},"modified":"2024-10-24T21:59:55","modified_gmt":"2024-10-24T21:59:55","slug":"ieee-1082-1997","status":"publish","type":"product","link":"https:\/\/pdfstandards.shop\/product\/publishers\/ieee\/ieee-1082-1997\/","title":{"rendered":"IEEE 1082 1997"},"content":{"rendered":"
New IEEE Standard – Active. A structured framework for the incorporation of human\/system interactions into probabilistic risk assessments is provided.<\/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 Participants <\/td>\n<\/tr>\n | ||||||
5<\/td>\n | CONTENTS <\/td>\n<\/tr>\n | ||||||
7<\/td>\n | 1. Overview 1.1 Scope 1.2 Purpose 2. Definitions <\/td>\n<\/tr>\n | ||||||
8<\/td>\n | 3. Overview of an integrated HRA 3.1 Overall evaluation issues <\/td>\n<\/tr>\n | ||||||
9<\/td>\n | 3.2 HRA process <\/td>\n<\/tr>\n | ||||||
11<\/td>\n | 4. Details of the HRA process <\/td>\n<\/tr>\n | ||||||
12<\/td>\n | 4.1 Select and train team <\/td>\n<\/tr>\n | ||||||
14<\/td>\n | 4.2 Familiarize team with plant 4.3 Build initial plant model <\/td>\n<\/tr>\n | ||||||
15<\/td>\n | 4.4 Screen human interactions <\/td>\n<\/tr>\n | ||||||
16<\/td>\n | 4.5 Characterize human interactions <\/td>\n<\/tr>\n | ||||||
17<\/td>\n | 4.6 Quantify human interactions 4.7 Evaluate additional recoverability <\/td>\n<\/tr>\n | ||||||
18<\/td>\n | 4.8 Update plant model 4.9 Review results <\/td>\n<\/tr>\n | ||||||
19<\/td>\n | 5. Documentation <\/td>\n<\/tr>\n | ||||||
20<\/td>\n | Annex A\u2014An example for documenting HRA data <\/td>\n<\/tr>\n | ||||||
23<\/td>\n | Annex B\u2014Bibliography <\/td>\n<\/tr>\n<\/table>\n","protected":false},"excerpt":{"rendered":" Guide for Incorporating Human Action Reliability Analysis for Nuclear Power Generating Stations<\/b><\/p>\n |