IEEE 627-2010
Superseded
Superseded
A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.
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superseded
A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.
IEEE Standard for Qualification of Equipment Used in Nuclear Facilities
Available format(s)
PDF
Superseded date
11-18-2019
Language(s)
English
Published date
06-04-2010
1. Overview
2. Normative references
3. Definitions
4. Qualification principles
5. Elements of an equipment qualification program
6. Selection of qualification methods
7. Documentation
Annex A (informative) - Safety terminology
Annex B (informative) - Bibliography
Covers the basic principles for qualification of equipment used in nuclear facilities.
| Committee |
Nuclear Power Engineering Committee
|
| DocumentType |
Standard
|
| Pages |
28
|
| PublisherName |
Institute of Electrical & Electronics Engineers
|
| Status |
Superseded
|
| SupersededBy | |
| Supersedes |
| IEEE DRAFT 387 : D9A MAR 95 | DRAFT STANDARD CRITERIA FOR DIESEL-GENERATOR UNITS APPLIED AS STANDBY POWER SUPPLIES FOR NUCLEAR POWER GENERATING STATIONS |
| IEEE 383-2015 | IEEE Standard for Qualifying Electric Cables and Splices for Nuclear Facilities |
| 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 |
| 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 |
| IEEE 387-1995 | IEEE Standard Criteria for Diesel-Generator Units Applied as Standby Power Supplies for Nuclear Power Generating Stations |
| IEEE 946-2004 | IEEE Recommended Practice for the Design of DC Auxiliary Power Systems for Generating Systems |
| IEEE 1115-2014 | IEEE Recommended Practice for Sizing Nickel-Cadmium Batteries for Stationary Applications |
| 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 C37.82-1987 | IEEE Standard for the Qualification of Switchgear Assemblies for Class 1E Applications in Nuclear Power Generating Stations |
| ANSI N13.4 : 71(R1983) | PORTABLE X-OR GAMMA RADIATION SURVEY INSTRUMENTS, SPECIFICATION OF, |
| 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 485-2010 | IEEE Recommended Practice for Sizing Lead-Acid Batteries for Stationary Applications |
| 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 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 |
| CFR 10(PTS0-199) : JAN 87 | ENERGY - NUCLEAR REGULATORY COMMISSION |
| IEEE 383-2003 | IEEE Standard for Qualifying Class 1E Electric Cables and Field Splices for Nuclear Power Generating Stations |
| IEEE 383-2015 | IEEE Standard for Qualifying Electric Cables and Splices for Nuclear Facilities |
| ASME QME 1 : 2012 | QUALIFICATION OF ACTIVE MECHANICAL EQUIPMENT USED IN NUCLEAR FACILITIES |
| IEEE C37.82-1987 | IEEE Standard for the Qualification of Switchgear Assemblies for Class 1E Applications in Nuclear Power Generating Stations |
| ASME PV CODE 3 SET : 2013 | ASME BOILER AND PRESSURE VESSEL CODE (BPVC) - RULES FOR CONSTRUCTION OF NUCLEAR FACILITY COMPONENTS (SET) |
| 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 334-2006 | IEEE Standard for Qualifying Continuous Duty Class 1E Motors for Nuclear Power Generating Stations |
| ANS 51.1 : 83(R1988) | NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY PRESSURIZED WATER REACTOR PLANTS |
| IEEE 101 : 1987 | GUIDE FOR THE STATISTICAL ANALYSIS OF THERMAL LIFE TEST DATA |
| IEEE 279-1971 | IEEE Standard: Criteria for Protection Systems for Nuclear Power Generating Stations |
| 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 344-2004 | IEEE Recommended Practice for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations |
| 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 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 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 |
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PDF - English
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