{"id":194753,"date":"2024-10-19T12:21:28","date_gmt":"2024-10-19T12:21:28","guid":{"rendered":"https:\/\/pdfstandards.shop\/product\/uncategorized\/ieee-603-2018\/"},"modified":"2024-10-25T04:52:33","modified_gmt":"2024-10-25T04:52:33","slug":"ieee-603-2018","status":"publish","type":"product","link":"https:\/\/pdfstandards.shop\/product\/publishers\/ieee\/ieee-603-2018\/","title":{"rendered":"IEEE 603 2018"},"content":{"rendered":"
Revision Standard – Active. Minimum functional and design criteria for the power, instrumentation, and control portions of nuclear power generating station safety systems are established. The criteria are to be applied to those systems required to protect the public health and safety by functioning to mitigate the consequences of design basis events. The intent is to promote appropriate practices for design and evaluation of safety system performance and reliability. Although the standard is limited to safety systems, many of the principles may have applicability to equipment provided for safe shutdown, post-accident monitoring display instrumentation, interlock features, or any otherre systems, structures, or equipment related to safety.<\/p>\n
PDF Pages<\/th>\n | PDF Title<\/th>\n<\/tr>\n | ||||||
---|---|---|---|---|---|---|---|
1<\/td>\n | IEEE Std 603\u2122-2018 Front cover <\/td>\n<\/tr>\n | ||||||
2<\/td>\n | Title page <\/td>\n<\/tr>\n | ||||||
4<\/td>\n | Important Notices and Disclaimers Concerning IEEE Standards Documents <\/td>\n<\/tr>\n | ||||||
7<\/td>\n | Participants <\/td>\n<\/tr>\n | ||||||
9<\/td>\n | Introduction <\/td>\n<\/tr>\n | ||||||
12<\/td>\n | Contents <\/td>\n<\/tr>\n | ||||||
13<\/td>\n | 1.\u2002Overview 1.1\u2002Scope 1.2\u2002Illustration <\/td>\n<\/tr>\n | ||||||
16<\/td>\n | 1.3\u2002Application 1.4\u2002Word Usage 1.5\u2002Conformance <\/td>\n<\/tr>\n | ||||||
17<\/td>\n | 2.\u2002Normative references 3.\u2002Definitions <\/td>\n<\/tr>\n | ||||||
20<\/td>\n | 4.\u2002Safety system design basis <\/td>\n<\/tr>\n | ||||||
21<\/td>\n | 5.\u2002Safety system criteria 5.1\u2002Single-failure criterion <\/td>\n<\/tr>\n | ||||||
22<\/td>\n | 5.2\u2002Completion of protective action 5.3\u2002Quality 5.4\u2002Equipment qualification 5.5\u2002System integrity 5.6\u2002Independence <\/td>\n<\/tr>\n | ||||||
24<\/td>\n | 5.7\u2002Capability for testing and calibration 5.8\u2002Information displays <\/td>\n<\/tr>\n | ||||||
25<\/td>\n | 5.9\u2002Control of access 5.10\u2002Repair 5.11\u2002Identification 5.12\u2002Auxiliary features 5.13\u2002Multi-unit stations <\/td>\n<\/tr>\n | ||||||
26<\/td>\n | 5.14\u2002Human factors considerations 5.15\u2002Reliability 5.16\u2002Common-cause failure 6.\u2002Sense and command features\u2014Functional and design requirements <\/td>\n<\/tr>\n | ||||||
27<\/td>\n | 6.1\u2002Automatic control 6.2\u2002Manual Control 6.3\u2002Interaction between the sense and command features and other systems <\/td>\n<\/tr>\n | ||||||
28<\/td>\n | 6.4\u2002Derivation of system inputs <\/td>\n<\/tr>\n | ||||||
29<\/td>\n | 6.5\u2002Capability for testing and calibration 6.6\u2002Operating bypasses 6.7\u2002Maintenance bypass <\/td>\n<\/tr>\n | ||||||
30<\/td>\n | 6.8\u2002Setpoints 7.\u2002Execute features\u2014Functional and design requirements 7.1\u2002Automatic control 7.2\u2002Manual control 7.3\u2002Completion of protective action 7.4\u2002Operating Bypass <\/td>\n<\/tr>\n | ||||||
31<\/td>\n | 7.5\u2002Maintenance Bypass 8.\u2002Power source requirements 8.1\u2002Electrical power sources 8.2\u2002Non-electrical power sources 8.3\u2002Maintenance bypass <\/td>\n<\/tr>\n | ||||||
32<\/td>\n | Annex\u00a0A (informative) Illustration of some basic concepts for developing the scope of a safety system A.1\u2002Purpose A.2\u2002Discussion <\/td>\n<\/tr>\n | ||||||
33<\/td>\n | A.3\u2002Typical safety system scope development <\/td>\n<\/tr>\n | ||||||
39<\/td>\n | A.4\u2002Safety group <\/td>\n<\/tr>\n | ||||||
42<\/td>\n | A.5\u2002Other auxiliary features <\/td>\n<\/tr>\n | ||||||
43<\/td>\n | Annex\u00a0B (informative) Bibliography <\/td>\n<\/tr>\n | ||||||
44<\/td>\n | Back cover <\/td>\n<\/tr>\n<\/table>\n","protected":false},"excerpt":{"rendered":" IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations<\/b><\/p>\n |