IEEE 323-2003
Superseded
Superseded
A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.
View Superseded by
IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations
Available format(s)
PDF
Superseded date
19-02-2016
Superseded by
Language(s)
English
Published date
23-01-2004
Important note : Users cannot be edited or removed once added to your Multi user PDF.
1 Scope
2 References
3 Definitions
4 Principles of equipment qualification
4.1 Qualification objective
4.2 Qualified life and qualified condition
4.3 Qualification elements
4.4 Qualification documentation
5 Qualification methods
5.1 Initial qualification
5.2 Extension of qualified life
5.3 Condition monitoring
6 Qualification
6.1 Equipment specification
6.2 Qualification program plan
6.3 Qualification program implementation
6.4 Modifications
7 Documentation
7.1 Mild environment documentation
7.2 Harsh environment documentation
Annex A (informative) Bibliography
Defines the basic requirements for qualifying Class 1E equipment and interfaces that are to be used in nuclear power generating stations. The principles, methods, and procedures described are intended to be used for qualifying equipment, maintaining and extending qualification, and updating qualification, as required, if the equipment is modified.
| Committee |
Nuclear Power Engineering Committee
|
| DocumentType |
Standard
|
| Pages |
26
|
| PublisherName |
Institute of Electrical & Electronics Engineers
|
| Status |
Superseded
|
| SupersededBy | |
| Supersedes |
| IEEE DRAFT 382 : D05 2006 | QUALIFICATION OF SAFETY-RELATED ACTUATORS FOR NUCLEAR POWER GENERATING STATIONS |
| 10/30229944 DC : 0 | BS IEC 62582-2 - NUCLEAR POWER PLANTS - INSTRUMENTATION AND CONTROL IMPORTANT TO SAFETY - ELECTRICAL EQUIPMENT CONDITION MONITORING METHODS - PART 2: INDENTER MODULUS |
| BS IEC/IEEE 62582-2 : 2011 | NUCLEAR POWER PLANTS - INSTRUMENTATION AND CONTROL IMPORTANT TO SAFETY - ELECTRICAL EQUIPMENT CONDITION MONITORING METHODS - PART 2: INDENTER MODULUS |
| ANS 56.5-79(R1987) | PWR AND BWR CONTAINMENT SPRAY SYSTEM DESIGN CRITERIA |
| IEEE DRAFT 387 : D9A MAR 95 | DRAFT STANDARD CRITERIA FOR DIESEL-GENERATOR UNITS APPLIED AS STANDBY POWER SUPPLIES FOR NUCLEAR POWER GENERATING STATIONS |
| CSA N289.4 : 2012 | TESTING PROCEDURES FOR SEISMIC QUALIFICATION OF NUCLEAR POWER PLANT STRUCTURES, SYSTEMS, AND COMPONENTS |
| ANS 56.6-1986 | VENTILATION SYSTEMS, PRESSURIZED WATER REACTOR CONTAINMENT |
| IEEE 383-2015 | IEEE Standard for Qualifying Electric Cables and Splices for Nuclear Facilities |
| IEEE 382-2006 | IEEE Standard for Qualification of Safety-Related Actuators for Nuclear Power Generating Stations |
| IEEE DRAFT 485 : FEB 95 | RECOMMENDED PRACTICE FOR SIZING LEAD-ACID BATTERIES FOR STATIONARY APPLICATIONS |
| IEEE DRAFT 833 : D3 2004 | PRACTICE FOR THE PROTECTION OF ELECTRIC EQUIPMENT IN NUCLEAR POWER GENERATING STATIONS FROM WATER HAZARDS |
| EN 60544-5:2012 | Electrical insulating materials - Determination of the effects of ionizing radiation - Part 5: Procedures for assessment of ageing in service |
| ASME AG-1 : 2019 | CODE ON NUCLEAR AIR AND GAS TREATMENT |
| ANS 59.2-1985 | NUCLEAR POWER PLANTS - HVAC SYSTEMS LOCATED OUTSIDE PRIMARY CONTAINMENT, SAFETY CRITERIA FOR, |
| ASME AG 1 : 2012 | CODE ON NUCLEAR AIR AND GAS TREATMENT |
| ASME QME 1 : 2017 | QUALIFICATION OF ACTIVE MECHANICAL EQUIPMENT USED IN NUCLEAR FACILITIES |
| 11/30189460 DC : 0 | BS IEC 62582-3 - NUCLEAR POWER PLANTS - INSTRUMENTATION AND CONTROL IMPORTANT TO SAFETY - ELECTRICAL EQUIPMENT CONDITION MONITORING METHODS - PART 3: ELONGATION AT BREAK |
| IEEE/ANSI N42.4-1971 | American National Standard for High Voltage Connectors for Nuclear Instruments |
| IEEE 334 : 2007 | QUALIFYING CONTINUOUS DUTY CLASS 1E MOTORS FOR NUCLEAR POWER GENERATING STATIONS |
| CSA N290.1 : 2013 | REQUIREMENTS FOR THE SHUTDOWN SYSTEMS OF CANDU NUCLEAR POWER PLANTS |
| IEEE 279-1971 | IEEE Standard: Criteria for Protection Systems for Nuclear Power Generating Stations |
| CSA N290.13 : 2005 | ENVIRONMENTAL QUALIFICATION OF EQUIPMENT FOR CANDU NUCLEAR POWER PLANTS |
| IEEE C37.81-1989 | IEEE Guide for Seismic Qualification of Class 1E Metal-Enclosed Power Switchgear Assemblies |
| CEI EN 60544-5 : 2012 | ELECTRICAL INSULATING MATERIALS - DETERMINATION OF THE EFFECTS OF IONIZING RADIATION - PART 5: PROCEDURES FOR ASSESSMENT OF AGEING IN SERVICE |
| IEC 63147:2017 | Criteria for accident monitoring instrumentation for nuclear power generating stations |
| IEEE 497-2016 | IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations |
| IEEE C37.81-2017 | IEEE Guide for Seismic Qualification of Class 1E Metal-Enclosed Power Switchgear Assemblies |
| IEEE/IEC 63147-2017 | IEEE/IEC International Standard - Criteria for accident monitoring instrumentation for nuclear power generating stations |
| ANSI/NEMA AB 3:2013 | Molded-Case Circuit Breakers and Their Application |
| IEEE 535-2013 | IEEE Standard for Qualification of Class 1E Vented Lead Acid Storage Batteries for Nuclear Power Generating Stations |
| IEEE 532-2007 REDLINE | IEEE Guide for Selecting and Testing Jackets for Power, Instrumentation, and Control Cables |
| BS IEC/IEEE 62582-5:2015 | Nuclear power plants. Instrumentation and control important to safety. Electrical equipment condition monitoring methods Optical time domain reflectometry |
| IEEE 572-2006 | IEEE Standard for Qualification of Class 1E Connection Assemblies for Nuclear Power Generating Stations |
| IEEE DRAFT 338 : D4 2006 | CRITERIA FOR THE PERIODIC SURVEILLANCE TESTING OF NUCLEAR POWER GENERATING STATION SAFETY SYSTEMS |
| IEEE 638-2013 | IEEE Standard for Qualification of Class 1E Transformers for Nuclear Power Generating Stations |
| ANS 59.1-1986 | COOLING WATER SYSTEMS FOR LIGHT WATER REACTORS, NUCLEAR SAFETY RELATED, |
| IEEE 603-2009 REDLINE | IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations |
| IEC TR 62283:2010 | Optical fibres - Guidance for nuclear radiation tests |
| IEC/IEEE 62582-1:2011 | Nuclear power plants - Instrumentation and control important to safety - Electrical equipment condition monitoring methods - Part 1: General |
| IEEE 7-4.3.2-2016 | IEEE Standard Criteria for Programmable Digital Devices in Safety Systems of Nuclear Power Generating Stations |
| I.S. EN 60544-5:2012 | ELECTRICAL INSULATING MATERIALS - DETERMINATION OF THE EFFECTS OF IONIZING RADIATION - PART 5: PROCEDURES FOR ASSESSMENT OF AGEING IN SERVICE (IEC 60544-5:2011 (EQV)) |
| IEEE 497-2010 | IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations |
| PD IEC/TR 62283:2010 | Optical fibres. Guidance for nuclear radiation tests |
| ANS 56.3-77(R1987) | OVERPRESSURE PROTECTION OF LOW-PRESSURE SYSTEMS CONNECTED TO THE REACTOR COOLANT PRESSURE BOUNDARY |
| BS EN 60544-5:2012 | Electrical insulating materials. Determination of the effects of ionizing radiation Procedures for assessment of ageing in service |
| PD IEC/TR 63084:2017 | Nuclear power plants. Instrumentation and control important to safety. Platform qualification for systems important to safety |
| 14/30189466 DC : 0 | BS IEC/IEEE 62582-5 ED 1.0 - NUCLEAR POWER PLANTS - INSTRUMENTATION AND CONTROL IMPORTANT TO SAFETY - ELECTRICAL EQUIPMENT CONDITION MONITORING METHODS - PART 5: OPTICAL TIME DOMAIN REFLECTOMETRY |
| BS IEC/IEEE 62582-1:2011 | Nuclear power plants. Instrumentation and control important to safety. Electrical equipment condition monitoring methods General |
| BS IEC/IEEE 62582-4:2011 | Nuclear power plants. Instrumentation and control important to safety. Electrical equipment condition monitoring methods Oxidation induction techniques |
| 11/30244657 DC : 0 | BS EN 60544-5 - ELECTRICAL INSULATING MATERIALS - DETERMINATION OF THE EFFECTS OF IONISING RADIATION - PART 5: PROCEDURES FOR ASSESSMENT OF AGEING IN SERVICE |
| IEEE 1115-2014 | IEEE Recommended Practice for Sizing Nickel-Cadmium Batteries for Stationary Applications |
| IEEE 690-2004 | IEEE Standard for the Design and Installation of Cable Systems for Class 1E Circuits in Nuclear Power Generating Stations |
| IEC/IEEE 62582-4:2011 | Nuclear power plants - Instrumentation and control important to safety - Electrical equipment condition monitoring methods - Part 4: Oxidation induction techniques |
| 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 344-2013 | IEEE Standard for Seismic Qualification of Equipment 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 |
| IEEE DRAFT 572 : D4 2006 | QUALIFICATION OF CLASS 1E CONNECTION ASSEMBLIES FOR NUCLEAR POWER GENERATING STATIONS |
| ASTM D 1879 : 2006 | Standard Practice for Exposure of Adhesive Specimens to Ionizing Radiation |
| ASTM D 1879 : 2006 : R2014 | Standard Practice for Exposure of Adhesive Specimens to Ionizing Radiation |
| ISA 67.01.01 : 2002 | TRANSDUCER AND TRANSMITTER INSTALLATION FOR NUCLEAR SAFETY APPLICATIONS |
| IEC 60544-5:2011 | Electrical insulating materials - Determination of the effects of ionizing radiation - Part 5: Procedures for assessment of ageing in service |
| 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 627-2010 | IEEE Standard for Qualification of Equipment Used in Nuclear Facilities |
| BS IEC/IEEE 62582-3:2012 | Nuclear power plants. Instrumentation and control important to safety. Electrical equipment condition monitoring methods Elongation at break |
| 10/30229947 DC : 0 | BS IEC 62582-4 - NUCLEAR POWER PLANTS - INSTRUMENTATION AND CONTROL IMPORTANT TO SAFETY - ELECTRICAL EQUIPMENT CONDITION MONITORING METHODS - PART 4: OXYDATION INDUCTION TECHNIQUES |
| IEEE DRAFT 1205 : D3 99 | DRAFT GUIDE FOR ASSESSING, MONITORING AND MITIGATING AGING EFFECTS ON CLASS 1E EQUIPMENT USED IN NUCLEAR POWER GENERATING STATIONS |
| IEEE 338-2012 | IEEE Standard for Criteria for the Periodic Surveillance Testing of Nuclear Power Generating Station Safety |
| 10/30229941 DC : 0 | BS IEC 62582-1 - NUCLEAR POWER PLANTS - INSTRUMENTATION AND CONTROL IMPORTANT TO SAFETY - ELECTRICAL EQUIPMENT CONDITION MONITORING METHODS - PART 1: GENERAL |
| 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 |
| ANSI N13.4 : 71(R1983) | PORTABLE X-OR GAMMA RADIATION SURVEY INSTRUMENTS, SPECIFICATION OF, |
| ANS 57.2-1983 | LIGHT WATER REACTOR SPENT FUEL STORAGE FACILITIES, REQUIREMENTS FOR, |
| ANS 59.3-1992(R2002) | NUCLEAR SAFETY CRITERIA FOR CONTROL AIR SYSTEMS |
| IEEE C37.105 : 2010 | QUALIFYING CLASS 1E PROTECTIVE RELAYS AND AUXILIARIES FOR 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 C37.98-2013 | IEEE Standard for Seismic Qualification Testing of Protective Relays and Auxiliaries for Nuclear Facilities |
| IEEE 317-2013 REDLINE | IEEE Standard for Electric Penetration Assemblies in Containment Structures for Nuclear Power Generating Stations |
| IEEE 450-2010 REDLINE | IEEE Recommended Practice for Maintenance, Testing, and Replacement of Vented Lead-Acid Batteries for Stationary Applications |
| IEEE 485-2010 | IEEE Recommended Practice for Sizing Lead-Acid Batteries for Stationary Applications |
| ISA 67.01 : 1994 | TRANSDUCER AND TRANSMITTER INSTALLATION FOR NUCLEAR SAFETY APPLICATIONS |
| 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 344-2004 | IEEE Recommended Practice for Seismic Qualification of Class 1E Equipment for 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 334-2006 | IEEE Standard for Qualifying Continuous Duty Class 1E Motors for Nuclear Power Generating Stations |
| IEEE 650-2006 | IEEE Standard for Qualification of Class 1E Static Battery Chargers and Inverters for Nuclear Power Generating Stations |
| IEEE 535-2006 | IEEE Standard for Qualification of Class 1E Lead Storage Batteries for Nuclear Power Generating Stations |
| IEEE C37.82-2017 | IEEE Standard for the Qualification of Switchgear Assemblies for Class 1E Applications in Nuclear Power Generating Stations |
| IEEE C62.31-2006 | IEEE Standard Test Methods for Low-Voltage Gas-Tube Surge-Protective Device Components |
| 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 628-2011 | IEEE Standard Criteria for the Design, Installation, and Qualification of Raceway Systems for Class 1E Circuits for Nuclear Power Generating Stations |
| IEEE 382-2006 | IEEE Standard for Qualification of Safety-Related Actuators for Nuclear Power Generating Stations |
| IEEE 99-2007 REDLINE | IEEE Recommended Practice for the Preparation of Test Procedures for the Thermal Evaluation of Insulation Systems for Electrical Equipment |
| IEEE C62.41-1991 | IEEE Recommended Practice for Surge Voltages in Low-Voltage AC Power Circuits |
| IEEE 383-2015 | IEEE Standard for Qualifying Electric Cables and Splices for Nuclear Facilities |
| IEEE C37.82-1987 | IEEE Standard for the Qualification of Switchgear Assemblies for Class 1E Applications in Nuclear Power Generating Stations |
| IEEE 334 : 2007 | QUALIFYING CONTINUOUS DUTY CLASS 1E MOTORS FOR NUCLEAR POWER GENERATING STATIONS |
| IEEE 344-2013 | IEEE Standard for Seismic Qualification of Equipment for Nuclear Power Generating Stations |
| IEEE C37.81-1989 | IEEE Guide for Seismic Qualification of Class 1E Metal-Enclosed Power Switchgear Assemblies |
| IEEE 535-2013 | IEEE Standard for Qualification of Class 1E Vented Lead Acid Storage Batteries for Nuclear Power Generating Stations |
| IEEE 101 : 1987 | GUIDE FOR THE STATISTICAL ANALYSIS OF THERMAL LIFE TEST DATA |
| IEEE C37.105 : 2010 | QUALIFYING CLASS 1E PROTECTIVE RELAYS AND AUXILIARIES FOR NUCLEAR POWER GENERATING STATIONS |
| 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 638-2013 | IEEE Standard for Qualification of Class 1E Transformers for Nuclear Power Generating Stations |
| IEC 60780:1998 | Nuclear power plants - Electrical equipment of the safety system - Qualification |
| IEEE C37.98-2013 | IEEE Standard for Seismic Qualification Testing of Protective Relays and Auxiliaries for Nuclear Facilities |
| IEEE 572-2006 | IEEE Standard for Qualification of Class 1E Connection Assemblies 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 |
| IEEE 650-2006 | IEEE Standard for Qualification of Class 1E Static Battery Chargers and Inverters for Nuclear Power Generating Stations |
| 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 317-2013 REDLINE | IEEE Standard for Electric Penetration Assemblies in Containment Structures 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 603-2009 REDLINE | IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations |
| IEEE 649-2006 | IEEE Standard for Qualifying Class 1E Motor Control Centers for Nuclear Power Generating Stations |
Access your standards online with a subscription
Features
-
Simple online access to standards, technical information and regulations.
-
Critical updates of standards and customisable alerts and notifications.
-
Multi-user online standards collection: secure, flexible and cost effective.