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Superseded
Superseded
A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.
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IEEE Standard for Qualification of Equipment Used in Nuclear Facilities
Available format(s)
PDF
Superseded date
18-11-2019
Superseded by
Language(s)
English
Published date
04-06-2010
Important note : Users cannot be edited or removed once added to your Multi user PDF.
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Superseded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 51.1-1983(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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