IEEE 649-2006
Withdrawn
A Withdrawn Standard is one, which is removed from sale, and its unique number can no longer be used. The Standard can be withdrawn and not replaced, or it can be withdrawn and replaced by a Standard with a different number.
IEEE Standard for Qualifying Class 1E Motor Control Centers for Nuclear Power Generating Stations
Hardcopy , PDF
24-03-2022
English
29-12-2006
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1 Overview
1.1 Scope
1.2 Purpose
2 Normative references
3 Definitions
4 Other information
4.1 General
5 Principles of qualification
5.1 General
5.2 Specific application to MCCs
6 Environmental conditions
6.1 General
7 Margin
7.1 General
8 Equipment specification
8.1 General
9 Qualification procedures
9.1 General
9.2 Inspection
9.3 Baseline data measurement
9.4 Aging
9.5 Seismic qualification
9.6 Harsh environment events
9.7 Final functional tests and inspection
9.8 Determination of qualification
9.9 Extension of qualified life
10 Modifications
10.1 Modifications during qualification
10.2 Modifications after qualification
11 Documentation
11.1 General
11.2 Equipment qualification data
11.3 Supporting documentation
Annex A (informative) Use of experience data in seismic
qualification of motor control centers
Annex B (informative) Glossary
Annex C (informative) Typical functions of motor control centers
Specifies the basic principles, requirements, and methods for qualifying Class 1E motor control centers for both harsh and mild environment applications in nuclear power generating stations.
| Committee |
Nuclear Power Engineering Committee
|
| DevelopmentNote |
Supersedes IEEE DRAFT 649. (01/2007)
|
| DocumentType |
Standard
|
| ISBN |
978-0-7381-5287-5
|
| Pages |
30
|
| PublisherName |
Institute of Electrical & Electronics Engineers
|
| Status |
Withdrawn
|
| Supersedes |
| IEEE 946-2004 | IEEE Recommended Practice for the Design of DC Auxiliary Power Systems for Generating Systems |
| BS IEC/IEEE 60780-323 : 2016 | NUCLEAR FACILITIES - ELECTRICAL EQUIPMENT IMPORTANT TO SAFETY - QUALIFICATION |
| ANSI/NEMA AB 3:2013 | Molded-Case Circuit Breakers and Their Application |
| IEC/IEEE 60780-323:2016 | Nuclear facilities - Electrical equipment important to safety - Qualification |
| BS EN 60780-323:2017 | Nuclear facilities. Electrical equipment important to safety. Qualification |
| 15/30249614 DC : 0 | BS IEC/IEEE 60780-323 ED 1.0 - NUCLEAR FACILITIES - ELECTRICAL EQUIPMENT IMPORTANT TO SAFETY - QUALIFICATION |
| 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 |
| I.S. EN 60780-323:2017 | NUCLEAR FACILITIES - ELECTRICAL EQUIPMENT IMPORTANT TO SAFETY - QUALIFICATION |
| 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 |
| ANSI N13.4 : 71(R1983) | PORTABLE X-OR GAMMA RADIATION SURVEY INSTRUMENTS, SPECIFICATION OF, |
| IEEE 323-2003 | IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations |
| IEEE 946-2020 | IEEE Recommended Practice for the Design of DC Power Systems for Stationary Applications |
| IEEE 7-4.3.2-2003 | IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations |
| IEEE 344-2013 | IEEE Standard for Seismic Qualification of Equipment for Nuclear Power Generating Stations |
| IEEE 101 : 1987 | GUIDE FOR THE STATISTICAL ANALYSIS OF THERMAL LIFE TEST DATA |
| NFPA 70 : 2017 | NATIONAL ELECTRICAL CODE |
| IEEE 344-2004 | IEEE Recommended Practice for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations |
| IEEE 323-2003 | IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations |
| NEMA ICS 1 : 2000(R2015) | INDUSTRIAL CONTROL AND SYSTEMS: GENERAL REQUIREMENTS |
| IEEE C37.98-2013 | IEEE Standard for Seismic Qualification Testing of Protective Relays and Auxiliaries for Nuclear Facilities |
| IEEE 603-1998 | IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations |
| IEEE C37.98-1987 | IEEE Standard Seismic Testing of Relays |
| 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 |
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