Revision Standard – Active. Minimum functional and design criteria for the power, instrumentation, and control portions of nuclear power generating station safety systems are established in this standard. 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, preventive interlock features, or any other systems, structures, or equipment related to safety.<\/p>\n
| PDF Pages<\/th>\n | PDF Title<\/th>\n<\/tr>\n | ||||||
|---|---|---|---|---|---|---|---|
| 1<\/td>\n | IEEE Std 603-2009 Front Cover <\/td>\n<\/tr>\n | ||||||
| 3<\/td>\n | Title page \n <\/td>\n<\/tr>\n | ||||||
| 6<\/td>\n | Introduction \n <\/td>\n<\/tr>\n | ||||||
| 8<\/td>\n | Notice to users \n Laws and regulations \n Copyrights \n Updating of IEEE documents \n Errata \n Interpretations \n <\/td>\n<\/tr>\n | ||||||
| 9<\/td>\n | Patents \n Participants \n <\/td>\n<\/tr>\n | ||||||
| 11<\/td>\n | Contents \n <\/td>\n<\/tr>\n | ||||||
| 13<\/td>\n | Important notice \n 1. Overview 1.1 Scope 1.2 Illustration <\/td>\n<\/tr>\n | ||||||
| 17<\/td>\n | 1.3 Application 2. Normative references <\/td>\n<\/tr>\n | ||||||
| 19<\/td>\n | 3. Definitions <\/td>\n<\/tr>\n | ||||||
| 21<\/td>\n | 4. Safety system design basis <\/td>\n<\/tr>\n | ||||||
| 22<\/td>\n | 5. Safety system criteria 5.1 Single-failure criterion <\/td>\n<\/tr>\n | ||||||
| 23<\/td>\n | 5.2 Completion of protective action 5.3 Quality 5.4 Equipment qualification 5.5 System integrity <\/td>\n<\/tr>\n | ||||||
| 24<\/td>\n | 5.6 Independence <\/td>\n<\/tr>\n | ||||||
| 25<\/td>\n | 5.7 Capability for testing and calibration 5.8 Information displays <\/td>\n<\/tr>\n | ||||||
| 26<\/td>\n | 5.9 Control of access 5.10 Repair 5.11 Identification <\/td>\n<\/tr>\n | ||||||
| 27<\/td>\n | 5.12 Auxiliary features 5.13 Multi-unit stations 5.14 Human factors considerations 5.15 Reliability 5.16 Common-cause failure criteria 6. Sense and command features\u2014Functional and design requirements <\/td>\n<\/tr>\n | ||||||
| 28<\/td>\n | 6.1 Automatic control 6.2 Manual control 6.3 Interaction between the sense and command features and other systems <\/td>\n<\/tr>\n | ||||||
| 29<\/td>\n | 6.4 Derivation of system inputs <\/td>\n<\/tr>\n | ||||||
| 30<\/td>\n | 6.5 Capability for testing and calibration 6.6 Operating bypasses 6.7 Maintenance bypass 6.8 Setpoints <\/td>\n<\/tr>\n | ||||||
| 31<\/td>\n | 7. Execute features\u2014Functional and design requirements 7.1 Automatic control 7.2 Manual control 7.3 Completion of protective action 7.4 Operating bypass <\/td>\n<\/tr>\n | ||||||
| 32<\/td>\n | 7.5 Maintenance bypass 8. Power source requirements 8.1 Electrical power sources 8.2 Non-electrical power sources 8.3 Maintenance bypass <\/td>\n<\/tr>\n | ||||||
| 33<\/td>\n | Annex A (informative) \nIllustration of some basic concepts for developing the scope of a safetysystem A.1 Purpose A.2 Discussion A.3 Typical safety system scope development <\/td>\n<\/tr>\n | ||||||
| 41<\/td>\n | A.4 Safety group <\/td>\n<\/tr>\n | ||||||
| 42<\/td>\n | A.5 Other auxiliary features <\/td>\n<\/tr>\n | ||||||
| 44<\/td>\n | Annex B (informative) \nElectromagnetic compatibility B.1 Background B.2 Discussion B.3 Definition of the electromagnetic environment <\/td>\n<\/tr>\n | ||||||
| 48<\/td>\n | Annex C (informative) \nBibliography <\/td>\n<\/tr>\n<\/table>\n","protected":false},"excerpt":{"rendered":" IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations<\/b><\/p>\n |