IEEE 7-4.3.2-2016
Current
Current
The latest, up-to-date edition.
IEEE Standard Criteria for Programmable Digital Devices in Safety Systems of Nuclear Power Generating Stations
Published date
25-08-2016
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1 Scope
2 Normative references
3 Definitions and abbreviations
4 Safety system design basis
5 Safety system criteria
6 Sense and command features - functional and design
requirements
7 Execute features - functional and design
requirements
8 Power source requirements
Annex A (informative) - Mapping of IEEE Std 603-2009 to IEEE
Std 7-4.3.2
Annex B (informative) - Diversity requirements determination
Annex C (informative) - Dedication of existing commercial computers
Annex D (informative) - Identification and resolution of hazards
Annex E (informative) - Communication independence
Annex F (informative) - Computer reliability
Annex G (informative) - Glossary
Annex H (informative) - Bibliography
Bibliography
Gives minimum functional and design requirements for computers used as components of a safety system.
| Committee |
Nuclear Power Engineering Committee
|
| DocumentType |
Standard
|
| PublisherName |
Institute of Electrical & Electronics Engineers
|
| Status |
Current
|
| Supersedes |
| 15/30300357 DC : 0 | BS IEC 62859 ED 1.0 - NUCLEAR POWER PLANTS - INSTRUMENTATION AND CONTROL SYSTEMS - REQUIREMENTS FOR COORDINATING SAFETY AND CYBERSECURITY |
| CSA N290.4:19 | Requirements for reactor control systems of nuclear power plants |
| IEEE 650-2006 | IEEE Standard for Qualification of Class 1E Static Battery Chargers and Inverters for Nuclear Power Generating Stations |
| ASME NQA 1 : 2017 | QUALITY ASSURANCE REQUIREMENTS FOR NUCLEAR FACILITY APPLICATIONS |
| ASME AG-1 : 2019 | CODE ON NUCLEAR AIR AND GAS TREATMENT |
| IEEE/IEC 63147-2017 | IEEE/IEC International Standard - Criteria for accident monitoring instrumentation for nuclear power generating stations |
| IEEE 627-2019 | IEEE Standard for Qualification of Equipment Used in Nuclear Facilities |
| IEEE 497-2016 | IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations |
| ASME AG 1 : 2012 | CODE ON NUCLEAR AIR AND GAS TREATMENT |
| EN 60780-323:2017 | Nuclear facilities - Electrical equipment important to safety - Qualification |
| BS IEC/IEEE 60780-323 : 2016 | NUCLEAR FACILITIES - ELECTRICAL EQUIPMENT IMPORTANT TO SAFETY - QUALIFICATION |
| CSA N290.0 & N290.1 PACKAGE : 2013 | CONSISTS OF N290.0-11, GENERAL REQUIREMENTS FOR SAFETY SYSTEMS OF NUCLEAR POWER PLANTS AND N290.1-13, REQUIREMENTS FOR THE SHUTDOWN SYSTEMS OF NUCLEAR POWER PLANTS |
| CSAN290.4 : 2011 | REQUIREMENTS FOR REACTOR CONTROL SYSTEMS OF NUCLEAR POWER PLANTS |
| IEC 63147:2017 | Criteria for accident monitoring instrumentation for nuclear power generating stations |
| 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 |
| 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 |
| 17/30309594 DC : 0 | BS IEC 62138 - NUCLEAR POWER PLANTS - INSTRUMENTATION AND CONTROL SYSTEMS IMPORTANT TO SAFETY - SOFTWARE ASPECTS FOR COMPUTER-BASED SYSTEMS PERFORMING CATEGORY B OR C FUNCTIONS |
| IEC/IEEE 60780-323:2016 | Nuclear facilities - Electrical equipment important to safety - Qualification |
| IEEE 603-2009 REDLINE | IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations |
| BS EN 60780-323:2017 | Nuclear facilities. Electrical equipment important to safety. Qualification |
| IEEE 497-2010 | IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations |
| PD IEC/TR 63084:2017 | Nuclear power plants. Instrumentation and control important to safety. Platform qualification for systems important to safety |
| 15/30249614 DC : 0 | BS IEC/IEEE 60780-323 ED 1.0 - NUCLEAR FACILITIES - ELECTRICAL EQUIPMENT IMPORTANT TO SAFETY - QUALIFICATION |
| ANSI N13.4 : 71(R1983) | PORTABLE X-OR GAMMA RADIATION SURVEY INSTRUMENTS, SPECIFICATION OF, |
| IEEE 1707-2015 | IEEE Recommended Practice for the Investigation of Events at Nuclear Facilities |
| IEEE 730-2014 | IEEE Standard for Software Quality Assurance Processes |
| IEEE 1786-2011 | IEEE Guide for Human Factors Applications of Computerized Operating Procedure Systems (COPS) at Nuclear Power Generating Stations and Other Nuclear Facilities |
| I.S. EN 60780-323:2017 | NUCLEAR FACILITIES - ELECTRICAL EQUIPMENT IMPORTANT TO SAFETY - QUALIFICATION |
| 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 |
| IEEE DRAFT 497 : DE FEB 2001 | DRAFT STANDARD CRITERIA FOR ACCIDENT MONITORING INSTRUMENTATION FOR NUCLEAR POWER GENERATING STATIONS |
| IEEE 338-2012 | IEEE Standard for Criteria for the Periodic Surveillance Testing of Nuclear Power Generating Station Safety |
| IEEE 649-2006 | IEEE Standard for Qualifying Class 1E Motor Control Centers for Nuclear Power Generating Stations |
| IEEE 308-2012 REDLINE | IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations |
| IEEE 379-2014 | IEEE Standard for Application of the Single-Failure Criterion to Nuclear Power Generating Station Safety Systems |
| IEEE C37.105 : 2010 | QUALIFYING CLASS 1E PROTECTIVE RELAYS AND AUXILIARIES FOR NUCLEAR POWER GENERATING STATIONS |
| IEEE 323-2003 | IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations |
| IEEE 2420-2019 | IEEE Standard Criteria for Combustion Turbine-Generator Units Applied as Standby Power Supplies for Nuclear Power Generating Stations |
| IEEE 338-2022 | IEEE Standard for Criteria for the Periodic Surveillance Testing of Nuclear Power Generating Station Safety Systems |
| IEEE 308-2020 | IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations |
| IEEE 1786-2022 | IEEE Guide for Human Factors Applications of Computerized Operating Procedure Systems (COPS) at Nuclear Power Generating Stations and Other Nuclear Facilities |
| IEEE 650-2017 | IEEE Standard for Qualification of Class 1E Static Battery Chargers, Inverters, and Uninterruptible Power Supply Systems for Nuclear Power Generating Stations |
| IEEE 379.1-2024 | IEEE Guide for Application of the Single-Failure Criterion to Nuclear Power Generating Station Safety Systems |
| IEEE 497-2010 | IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations |
| CFR 10(PTS0-199) : JAN 87 | ENERGY - NUCLEAR REGULATORY COMMISSION |
| IEEE 730-2014 | IEEE Standard for Software Quality Assurance Processes |
| IEEE 610.12-1990 | IEEE Standard Glossary of Software Engineering Terminology |
| IEEE 828-2012 | IEEE Standard for Configuration Management in Systems and Software Engineering |
| IEEE 379-2014 | IEEE Standard for Application of the Single-Failure Criterion to Nuclear Power Generating Station Safety Systems |
| IEEE 344-2013 | IEEE Standard for Seismic Qualification of Equipment for Nuclear Power Generating Stations |
| IEEE/ISO/IEC 12207-2008 | ISO/IEC/IEEE International Standard - Systems and software engineering -- Software life cycle processes |
| IEEE 1012A : 1998 | STANDARD FOR SOFTWARE VERIFICATION AND VALIDATION PLANS - CONTENT MAP TO IEEE 12207.1 |
| IEEE 1233-1998 | IEEE Guide for Developing System Requirements Specifications |
| ISO/IEC 15288:2008 | Systems and software engineering — System life cycle processes |
| ANS 51.1-1983(R1988) | NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY PRESSURIZED WATER REACTOR PLANTS |
| MIL-STD-882 Revision E:2012 | System Safety |
| ISO/IEC 12207:2008 | Systems and software engineering — Software life cycle processes |
| IEEE 384-2008 REDLINE | IEEE Standard Criteria for Independence of Class 1E Equipment and Circuits |
| IEC 60880:2006 | Nuclear power plants - Instrumentation and control systems important to safety - Software aspects for computer-based systems performing category A functions |
| ANS 52.1-83(R1988) | NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY BOILING WATER REACTOR PLANTS |
| IEEE 323-2003 | IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations |
| IEEE 1012-2012 | IEEE Standard for System and Software Verification and Validation |
| IEC 60231A:1969 | Supplement A - General principles of nuclear reactor instrumentation |
| IEEE 352-1987 | IEEE Guide for General Principles of Reliability Analysis of Nuclear Power Generating Station Safety Systems |
| IEC 61784-3:2016+AMD1:2017 CSV | Industrial communication networks - Profiles - Part 3: Functional safety fieldbuses - General rules and profile definitions |
| IEEE/ISO/IEC 15288-2008 REDLINE | ISO/IEC/IEEE International Standard - Systems and software engineering System life cycle processes |
| IEEE 603-2009 REDLINE | IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations |
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