IEEE 344-2013
Superseded
Superseded
A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.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 for Seismic Qualification of Equipment for Nuclear Power Generating Stations
Available format(s)
PDF
Superseded date
11-10-2021
Superseded by
Language(s)
English
Published date
22-11-2013
Important note : Users cannot be edited or removed once added to your Multi user PDF.
1 Overview
2 Normative references
3 Definitions
4 General discussion of earthquake environment and equipment
response
5 Seismic qualification approach
6 Damping
7 Analysis
8 Testing
9 Combined analysis and testing
10 Experience
11 Documentation
Annex A (informative) - Measurement of zero period acceleration
Annex B (informative) - Frequency content and stationarity
Annex C (informative) - Fragility testing
Annex D (informative) - Test duration and number of cycles
Annex E (informative) - Statistically independent motions
Annex F (informative) - Bibliography
Specifies methods for establishing seismic qualification procedures that will yield quantitative data to demonstrate that the equipment can meet its performance requirements.
| Committee |
Nuclear Power Engineering Committee
|
| DocumentType |
Standard
|
| Pages |
74
|
| PublisherName |
Institute of Electrical & Electronics Engineers
|
| Status |
Superseded
|
| SupersededBy | |
| Supersedes |
| CSA N289.1 : 2008 | GENERAL REQUIREMENTS FOR SEISMIC DESIGN AND QUALIFICATION OF CANDU NUCLEAR POWER PLANTS |
| IEEE 497-2010 | IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations |
| AHRI 1270 (I-P) : 2015 | REQUIREMENTS FOR SEISMIC QUALIFICATION OF HVACR EQUIPMENT |
| IEEE DRAFT 382 : D05 2006 | QUALIFICATION OF SAFETY-RELATED ACTUATORS FOR NUCLEAR POWER GENERATING STATIONS |
| 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 |
| CEI 45-100 : 1ED 2018 | TECHNICAL GUIDE FOR THE SEISMIC QUALIFICATION OF ALTERNATING CURRENT GENERATING SETS DRIVEN BY INTERNAL COMBUSTION ENGINES |
| IEEE DRAFT C57.16 : D10 AUG 95 | TERMINOLOGY AND TEST CODE FOR DRY-TYPE AIR-CORE SERIES CONNECTED REACTORS |
| IEEE 382-2006 | IEEE Standard for Qualification of Safety-Related Actuators for Nuclear Power Generating Stations |
| IEEE C37.20.2-2015 | IEEE Standard for Metal-Clad Switchgear |
| IEEE 693-2005 | IEEE Recommended Practice for Seismic Design of Substations |
| IEEE DRAFT 833 : D3 2004 | PRACTICE FOR THE PROTECTION OF ELECTRIC EQUIPMENT IN NUCLEAR POWER GENERATING STATIONS FROM WATER HAZARDS |
| IEEE C37.23-2003 | IEEE Standard for Metal-Enclosed Bus |
| 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 |
| 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 |
| 18/30376682 DC : DRAFT APR 2018 | BS IEC/IEEE 63113 - NUCLEAR FACILITIES - INSTRUMENTATION IMPORTANT TO SAFETY - SPENT FUEL POOL INSTRUMENTATION |
| IEEE/ANSI N42.4-1971 | American National Standard for High Voltage Connectors for Nuclear Instruments |
| ASCE 25 06 : 2008 | EARTHQUAKE ACTUATED AUTOMATIC GAS SHUTOFF DEVICES |
| IEEE 334 : 2007 | QUALIFYING CONTINUOUS DUTY CLASS 1E MOTORS FOR NUCLEAR POWER GENERATING STATIONS |
| 15/30249614 DC : 0 | BS IEC/IEEE 60780-323 ED 1.0 - NUCLEAR FACILITIES - ELECTRICAL EQUIPMENT IMPORTANT TO SAFETY - QUALIFICATION |
| 17/30357475 DC : 0 | BS IEC/IEEE 63113 - NUCLEAR FACILITIES - INSTRUMENTATION IMPORTANT TO SAFETY - SPENT FUEL POOL INSTRUMENTATION |
| BS IEC/IEEE 60780-323 : 2016 | NUCLEAR FACILITIES - ELECTRICAL EQUIPMENT IMPORTANT TO SAFETY - QUALIFICATION |
| CSA N290.1 : 2013 | REQUIREMENTS FOR THE SHUTDOWN SYSTEMS OF CANDU NUCLEAR POWER PLANTS |
| ASCE 25 97 : 1999 | EARTHQUAKE-ACTUATED AUTOMATIC GAS SHUTOFF DEVICES |
| IEEE C37.81-1989 | IEEE Guide for Seismic Qualification of Class 1E Metal-Enclosed Power Switchgear Assemblies |
| ISA 67.03 : 1982 | STANDARD FOR LIGHT WATER REACTOR COOLANT PRESSURE BOUNDARY LEAK DETECTION |
| IEC 63147:2017 | Criteria for accident monitoring instrumentation for nuclear power generating stations |
| ASCE 7 02 : 2003 | MINIMUM DESIGN LOADS FOR BUILDINGS AND OTHER STRUCTURES |
| IEEE/IEC 60780-323-2016 | IEC/IEEE International Standard - Nuclear facilities -- Electrical equipment important to safety -- Qualification |
| 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 |
| IEEE 387-2017 | IEEE Standard for Criteria for Diesel Generator Units Applied as Standby Power Supplies for Nuclear Power Generating Stations |
| IEEE 627-2019 | IEEE Standard for Qualification of Equipment Used in Nuclear Facilities |
| IEEE 628-2020 | IEEE Standard Criteria for the Design, Installation, and Qualification of Raceway Systems for Class 1E Circuits for Nuclear Power Generating Stations |
| IEEE 535-2013 | IEEE Standard for Qualification of Class 1E Vented Lead Acid Storage Batteries for Nuclear Power Generating Stations |
| IEEE 572-2006 | IEEE Standard for Qualification of Class 1E Connection Assemblies for Nuclear Power Generating Stations |
| IEEE 638-2013 | IEEE Standard for Qualification of Class 1E Transformers for Nuclear Power Generating Stations |
| ASCE 7 98 : 2000 | MINIMUM DESIGN LOADS FOR BUILDINGS AND OTHER STRUCTURES |
| IEEE C37.105 : 2010 | QUALIFYING CLASS 1E PROTECTIVE RELAYS AND AUXILIARIES FOR NUCLEAR POWER GENERATING STATIONS |
| ANS 56.7-1978(R1987) | VENTILATION SYSTEMS, BOILING WATER REACTOR CONTAINMENT |
| CSA N289.1 : 2008 : INC : UPD 1 : 2014: R201300 | GENERAL REQUIREMENTS FOR SEISMIC DESIGN AND QUALIFICATION OF CANDU NUCLEAR POWER PLANTS |
| CSA N289.1 : 2008 : INC : UPD 1 : 2015 : R201300 | GENERAL REQUIREMENTS FOR SEISMIC DESIGN AND QUALIFICATION OF CANDU NUCLEAR POWER PLANTS |
| 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 |
| ANS 56.3-77(R1987) | OVERPRESSURE PROTECTION OF LOW-PRESSURE SYSTEMS CONNECTED TO THE REACTOR COOLANT PRESSURE BOUNDARY |
| 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 |
| I.S. EN 60780-323:2017 | NUCLEAR FACILITIES - ELECTRICAL EQUIPMENT IMPORTANT TO SAFETY - QUALIFICATION |
| IEEE DRAFT 572 : D4 2006 | QUALIFICATION OF CLASS 1E CONNECTION ASSEMBLIES FOR NUCLEAR POWER GENERATING STATIONS |
| ISA 67.01.01 : 2002 | TRANSDUCER AND TRANSMITTER INSTALLATION FOR NUCLEAR SAFETY APPLICATIONS |
| IEEE DRAFT 693 : D9 2004 | SEISMIC DESIGN OF SUBSTATIONS |
| IEEE 628-2011 | IEEE Standard Criteria for the Design, Installation, and Qualification of Raceway Systems for Class 1E Circuits for Nuclear Power Generating Stations |
| 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 |
| AHRI 1271 (SI) : 2015 | REQUIREMENTS FOR SEISMIC QUALIFICATION OF HVACR EQUIPMENT |
| 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 |
| ANS 51.1-1983(R1988) | NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY PRESSURIZED WATER REACTOR PLANTS |
| IEEE 649-2006 | IEEE Standard for Qualifying Class 1E Motor Control Centers for Nuclear Power Generating Stations |
| 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 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 |
| ISA 67.01 : 1994 | TRANSDUCER AND TRANSMITTER INSTALLATION FOR NUCLEAR SAFETY APPLICATIONS |
| ANS 52.1-83(R1988) | NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY BOILING WATER REACTOR PLANTS |
| ASCE/SEI 25 16 : 2016 | EARTHQUAKE-ACTUATED AUTOMATIC GAS SHUTOFF DEVICES |
| 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 C37.20.3-2013 REDLINE | IEEE Standard for Metal-Enclosed Interrupter Switchgear (1 kV-38 kV) |
| IEEE 2420-2019 | IEEE Standard Criteria for Combustion Turbine-Generator Units Applied as Standby Power Supplies for Nuclear Power Generating Stations |
| IEEE 1682-2023 | IEEE Standard for Qualifying Fiber Optic Cables, Connections, and Optical Fiber Splices for Use in Safety Systems in Nuclear Power Generating Stations |
| IEEE 946-2020 | IEEE Recommended Practice for the Design of DC Power Systems for Stationary Applications |
| IEEE 382-2019 | IEEE Standard for Qualification of Safety-Related Actuators for Nuclear Power Generating Stations and Other Nuclear Facilities |
| IEEE 572-2019 | IEEE Standard for Qualification of Class 1E Connection Assemblies for 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 C37.82-2017 | IEEE Standard for the Qualification of Switchgear Assemblies for Class 1E Applications in Nuclear Power Generating Stations |
| IEEE 382-2006 | IEEE Standard for Qualification of Safety-Related Actuators for Nuclear Power Generating Stations |
| ASCE 4 98 : 2000 | SEISMIC ANALYSIS OF SAFETY-RELATED NUCLEAR STRUCTURES AND COMMENTARY |
| MIL S 901 : D | SHOCK TESTS, HI [HIGH IMPACT] SHIPBOARD MACHINERY, EQUIPMENT AND SYSTEMS, REQUIREMENTS FOR |
| IEEE 323-2003 | IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations |
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