IEEE 603-2009 REDLINE
Superseded
Superseded
A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.
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IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations
Available format(s)
PDF
Superseded date
17-12-2018
Superseded by
Language(s)
English
Published date
05-11-2009
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1. Overview
1.1 Scope
1.2 Illustration
1.3 Application
2. Normative references
3. Definitions
4. Safety system design basis
5. Safety system criteria
5.1 Single-failure criterion
5.2 Completion of protective action
5.3 Quality
5.4 Equipment qualification
5.5 System integrity
5.6 Independence
5.7 Capability for testing and calibration
5.8 Information displays
5.9 Control of access
5.10 Repair
5.11 Identification
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 - Functional and design
requirements
6.1 Automatic control
6.2 Manual control
6.3 Interaction between the sense and command
features and other systems
6.4 Derivation of system inputs
6.5 Capability for testing and calibration
6.6 Operating bypasses
6.7 Maintenance bypass
6.8 Setpoints
7. Execute features - Functional and design requirements
7.1 Automatic control
7.2 Manual control
7.3 Completion of protective action
7.4 Operating bypass
7.5 Maintenance bypass
8. Power source requirements
8.1 Electrical power sources
8.2 Non-electrical power sources
8.3 Maintenance bypass
Annex A (informative) - Illustration of some basic concepts
for developing the scope of a safety system
Annex B (informative) - Electromagnetic compatibility
Annex C (informative) - Bibliography
Defines minimum functional and design requirements for the power, instrumentation, and control portions of safety systems for nuclear power generating stations.
| Committee |
Nuclear Power Engineering Committee
|
| DocumentType |
Standard
|
| Pages |
52
|
| PublisherName |
Institute of Electrical & Electronics Engineers
|
| Status |
Superseded
|
| SupersededBy | |
| Supersedes |
| IEEE 497-2010 | IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations |
| IEEE 741-2007 | IEEE Standard Criteria for the Protection of Class 1E Power Systems and Equipment in Nuclear Power Generating Stations |
| BS IEC 61888:2002 | Nuclear power plants. Instrumentation important to safety. Determination and maintenance of trip setpoints |
| IEEE DRAFT 387 : D9A MAR 95 | DRAFT STANDARD CRITERIA FOR DIESEL-GENERATOR UNITS APPLIED AS STANDBY POWER SUPPLIES FOR NUCLEAR POWER GENERATING STATIONS |
| ANS 56.6-1986 | VENTILATION SYSTEMS, PRESSURIZED WATER REACTOR CONTAINMENT |
| ISA 67.06.01 : 2002 | PERFORMANCE MONITORING FOR NUCLEAR SAFETY-RELATED INSTRUMENT CHANNELS IN NUCLEAR POWER PLANTS |
| IEEE 1023-2004 REDLINE | IEEE Recommended Practice for the Application of Human Factors Engineering to Systems, Equipment, and Facilities of Nuclear Power Generating Stations and Other Nuclear Facilities |
| IEEE DRAFT 833 : D3 2004 | PRACTICE FOR THE PROTECTION OF ELECTRIC EQUIPMENT IN NUCLEAR POWER GENERATING STATIONS FROM WATER HAZARDS |
| IEEE 650-2006 | IEEE Standard for Qualification of Class 1E Static Battery Chargers and Inverters for Nuclear Power Generating Stations |
| ASME AG-1 : 2019 | CODE ON NUCLEAR AIR AND GAS TREATMENT |
| ASME AG 1 : 2012 | CODE ON NUCLEAR AIR AND GAS TREATMENT |
| 15/30249614 DC : 0 | BS IEC/IEEE 60780-323 ED 1.0 - NUCLEAR FACILITIES - ELECTRICAL EQUIPMENT IMPORTANT TO SAFETY - QUALIFICATION |
| BS IEC/IEEE 60780-323 : 2016 | NUCLEAR FACILITIES - ELECTRICAL EQUIPMENT IMPORTANT TO SAFETY - QUALIFICATION |
| IEC 63147:2017 | Criteria for accident monitoring instrumentation for nuclear power generating stations |
| IEC 61888:2002 | Nuclear power plants - Instrumentation important to safety - Determination and maintenance of trip setpoints |
| IEC TR 62987:2015 | Nuclear power plants - Instrumentation and control systems important to safety - Use of Failure Mode and Effects Analysis (FMEA) and related methods to support the justification of systems |
| IEEE 497-2016 | IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations |
| IEEE/IEC 63147-2017 | IEEE/IEC International Standard - Criteria for accident monitoring instrumentation for nuclear power generating stations |
| IEEE 387-1995 | IEEE Standard Criteria for Diesel-Generator Units Applied as Standby Power Supplies for Nuclear Power Generating Stations |
| PD IEC/TR 62987:2015 | Nuclear power plants. Instrumentation and control systems important to safety. Use of Failure Mode and Effects Analysis (FMEA) and related methods to support the justification of systems |
| IEEE DRAFT 379 : D5 2000 | DRAFT STANDARD APPLICATION OF THE SINGLE-FAILURE CRITERION TO NUCLEAR POWER GENERATING STATION SAFETY SYSTEMS |
| IEEE 1290-2015 | IEEE Guide for Motor-Operated Valve (MOV) Motor Application, Protection, Control, and Testing in Nuclear Power-Generating Stations |
| IEEE 946-2004 | IEEE Recommended Practice for the Design of DC Auxiliary Power Systems for Generating Systems |
| IEEE DRAFT 338 : D4 2006 | CRITERIA FOR THE PERIODIC SURVEILLANCE TESTING OF NUCLEAR POWER GENERATING STATION SAFETY SYSTEMS |
| ANS 59.1-1986 | COOLING WATER SYSTEMS FOR LIGHT WATER REACTORS, NUCLEAR SAFETY RELATED, |
| IEEE 7-4.3.2-2016 | IEEE Standard Criteria for Programmable Digital Devices in Safety Systems of Nuclear Power Generating Stations |
| BS EN 60780-323:2017 | Nuclear facilities. Electrical equipment important to safety. Qualification |
| PD IEC/TR 63084:2017 | Nuclear power plants. Instrumentation and control important to safety. Platform qualification for systems important to safety |
| IEEE 279-1971 | IEEE Standard: Criteria for Protection Systems for Nuclear Power Generating Stations |
| IEC/IEEE 60780-323:2016 | Nuclear facilities - Electrical equipment important to safety - Qualification |
| IEEE 323-2003 | IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations |
| IEEE 1786-2011 | IEEE Guide for Human Factors Applications of Computerized Operating Procedure Systems (COPS) at Nuclear Power Generating Stations and Other Nuclear Facilities |
| IEEE 1205-2014 | IEEE Guide for Assessing, Monitoring, and Mitigating Aging Effects on Electrical Equipment Used in Nuclear Power Generating Stations and Other Nuclear Facilities |
| IEEE 577-2012 | IEEE Standard Requirements for Reliability Analysis in the Design and Operation of Safety Systems for Nuclear Power Generating Stations |
| IEEE 1819-2016 | IEEE Standard for Risk-Informed Categorization and Treatment of Electrical and Electronic Equipment at Nuclear Power Generating Stations and Other Nuclear Facilities |
| I.S. EN 60780-323:2017 | NUCLEAR FACILITIES - ELECTRICAL EQUIPMENT IMPORTANT TO SAFETY - QUALIFICATION |
| ISA 67.01.01 : 2002 | TRANSDUCER AND TRANSMITTER INSTALLATION FOR NUCLEAR SAFETY APPLICATIONS |
| IEC TR 63084:2017 | Nuclear power plants - Instrumentation and control important to safety - Platform qualification for systems important to safety |
| IEEE C37.82-1987 | IEEE Standard for the Qualification of Switchgear Assemblies for Class 1E Applications in Nuclear Power Generating Stations |
| BS IEC 63147:2017 | Criteria for accident monitoring instrumentation for nuclear power generating stations |
| EN 60780-323:2017 | Nuclear facilities - Electrical equipment important to safety - Qualification |
| IEEE 627-2010 | IEEE Standard for Qualification of Equipment Used in Nuclear Facilities |
| IEEE 384-2008 REDLINE | IEEE Standard Criteria for Independence of Class 1E Equipment and Circuits |
| IEEE 308-2012 REDLINE | IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations |
| IEEE 338-2012 | IEEE Standard for Criteria for the Periodic Surveillance Testing of Nuclear Power Generating Station Safety |
| IEEE DRAFT 741 : D1 2006 | CRITERIA FOR THE PROTECTION OF CLASS 1E POWER SYSTEMS AND EQUIPMENT IN NUCLEAR POWER GENERATING STATIONS |
| IEEE 649-2006 | IEEE Standard for Qualifying Class 1E Motor Control Centers for Nuclear Power Generating Stations |
| IEEE 379-2014 | IEEE Standard for Application of the Single-Failure Criterion to Nuclear Power Generating Station Safety Systems |
| ANSI N13.4 : 71(R1983) | PORTABLE X-OR GAMMA RADIATION SURVEY INSTRUMENTS, SPECIFICATION OF, |
| IEEE 420-2013 REDLINE | IEEE Standard for the Design and Qualification of Class 1E Control Boards, Panels, and Racks Used in Nuclear Power Generating Stations |
| IEEE 317-2013 REDLINE | IEEE Standard for Electric Penetration Assemblies in Containment Structures for Nuclear Power Generating Stations |
| ISA 67.01 : 1994 | TRANSDUCER AND TRANSMITTER INSTALLATION FOR NUCLEAR SAFETY APPLICATIONS |
| ISA 67.04.01 : 2006 | SETPOINTS FOR NUCLEAR SAFETY-RELATED INSTRUMENTATION |
| IEEE 352-1987 | IEEE Guide for General Principles of Reliability Analysis of Nuclear Power Generating Station Safety Systems |
| IEEE 1682-2011 | IEEE Standard for Qualifying Fiber Optic Cables, Connections, and Optical Fiber Splices for Use in Safety Systems in Nuclear Power Generating Stations |
| IEEE 741-2017 | IEEE Standard for Criteria for the Protection of Class 1E Power Systems and Equipment in Nuclear Power Generating Stations |
| IEEE 7-4.3.2-2010 REDLINE | IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations |
| IEEE 420-2013 REDLINE | IEEE Standard for the Design and Qualification of Class 1E Control Boards, Panels, and Racks Used in Nuclear Power Generating Stations |
| IEEE 497-2010 | IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations |
| IEEE 577-2012 | IEEE Standard Requirements for Reliability Analysis in the Design and Operation of Safety Systems for Nuclear Power Generating Stations |
| CFR 10(PTS0-199) : JAN 87 | ENERGY - NUCLEAR REGULATORY COMMISSION |
| IEEE 7-4.3.2-2003 | IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations |
| IEEE 497-2002 | IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations |
| IEEE 379-2014 | IEEE Standard for Application of the Single-Failure Criterion to Nuclear Power Generating Station Safety Systems |
| ANS 59.3-1992(R2002) | NUCLEAR SAFETY CRITERIA FOR CONTROL AIR SYSTEMS |
| ANS 4.5-80(R1986) | ACCIDENT MONITORING FUNCTIONS IN LIGHT-WATER-COOLED REACTORS, CRITERIA FOR |
| ISA 67.04.01 : 2006 | SETPOINTS FOR NUCLEAR SAFETY-RELATED INSTRUMENTATION |
| IEEE 338-2006 | IEEE Standard Criteria for the Periodic Surveillance Testing of Nuclear Power Generating Station Safety Systems |
| IEEE 420-2001 | IEEE Standard for the Design and Qualification of Class 1E Control Boards, Panels, and Racks Used in Nuclear Power Generating Stations |
| IEEE 279-1971 | IEEE Standard: Criteria for Protection Systems for Nuclear Power Generating Stations |
| IEEE 384-2008 REDLINE | IEEE Standard Criteria for Independence of Class 1E Equipment and Circuits |
| IEEE 308-2001 | IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations |
| IEEE 323-2003 | IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations |
| IEEE 379-2000 | IEEE Standard Application of the Single-Failure Criterion to Nuclear Power Generating Station Safety Systems |
| IEC 60231A:1969 | Supplement A - General principles of nuclear reactor instrumentation |
| ANS 58.9-2002(R2015) | SINGLE FAILURE CRITERIA FOR LWR SAFETY-RELATED FLUID SYSTEMS |
| ASME NQA 1 : 2015 | Quality Assurance Requirements for Nuclear Facility Applications (NQA-1 - 2015) |
| IEEE 1023-2004 REDLINE | IEEE Recommended Practice for the Application of Human Factors Engineering to Systems, Equipment, and Facilities of Nuclear Power Generating Stations and Other Nuclear Facilities |
| IEEE 352-1987 | IEEE Guide for General Principles of Reliability Analysis of Nuclear Power Generating Station Safety Systems |
| IEEE 338-2012 | IEEE Standard for Criteria for the Periodic Surveillance Testing of Nuclear Power Generating Station Safety |
| IEEE 308-2012 REDLINE | IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations |
| IEEE 7-4.3.2-2016 | IEEE Standard Criteria for Programmable Digital Devices in Safety Systems of Nuclear Power Generating Stations |
| IEEE 577-2004 | IEEE Standard Requirements for Reliability Analysis in the Design and Operation of Safety Systems for Nuclear Facilities |
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