IEEE 7-4.3.2-2016

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IEEE Standard Criteria for Programmable Digital Devices in Safety Systems of Nuclear Power Generating Stations

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Published date: 25-08-2016

Publisher: Institute of Electrical & Electronics Engineers

Table of Contents - (Show below) - (Hide below)

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

Abstract - (Show below) - (Hide below)

Gives minimum functional and design requirements for computers used as components of a safety system.

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Committee	Nuclear Power Engineering Committee
Document Type	Standard
ISBN
Pages
Published
Publisher	Institute of Electrical & Electronics Engineers
Status	Current
Supersedes	IEEE 7-4.3.2-2010 REDLINE

Standards Referenced By This Book - (Show below) - (Hide below)

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
N290.4-11 (R2016)	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 REDLINE	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 REDLINE	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

Standards Referencing This Book - (Show below) - (Hide below)

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 REDLINE	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 : 83(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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