IEEE 317-2013 REDLINE
Withdrawn
A Withdrawn Standard is one, which is removed from sale, and its unique number can no longer be used. The Standard can be withdrawn and not replaced, or it can be withdrawn and replaced by a Standard with a different number.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 Electric Penetration Assemblies in Containment Structures for Nuclear Power Generating Stations
Hardcopy , PDF
21-03-2024
English
17-07-2013
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1. Overview
2. Normative references
3. Definitions
4. Service classification and ratings
5. Design requirements
6. Qualification
7. Production tests
8. Installation and field testing as part of installation
9. Quality control and quality assurance requirements
10. Requirements for purchaser's specification
Annex A (informative) - Preferred values
Annex B (informative) - Electric penetration interfaces
Annex C (informative) - Penetration assembly
Annex D (informative) - Thermal-life test procedures
Annex E (informative) - Bibliography
Describes the requirements for the design, construction, qualification, test, and installation of electric penetration assemblies in nuclear containment structures for stationary nuclear power generating stations.
| Committee |
Nuclear Power Engineering Committee
|
| DocumentType |
Standard
|
| ISBN |
978-0-7381-8488-3
|
| Pages |
132
|
| PublisherName |
Institute of Electrical & Electronics Engineers
|
| Status |
Withdrawn
|
| Supersedes |
| EN 60780-323:2017 | Nuclear facilities - Electrical equipment important to safety - Qualification |
| IEEE 741-2007 | IEEE Standard Criteria for the Protection of Class 1E Power Systems and Equipment in Nuclear Power Generating Stations |
| ANS 56.5-79(R1987) | PWR AND BWR CONTAINMENT SPRAY SYSTEM DESIGN CRITERIA |
| IEEE 383-2015 | IEEE Standard for Qualifying Electric Cables and Splices for Nuclear Facilities |
| IEEE/ANSI N42.4-1971 | American National Standard for High Voltage Connectors for Nuclear Instruments |
| 15/30249614 DC : 0 | BS IEC/IEEE 60780-323 ED 1.0 - NUCLEAR FACILITIES - ELECTRICAL EQUIPMENT IMPORTANT TO SAFETY - QUALIFICATION |
| BS IEC/IEEE 60780-323 : 2016 | NUCLEAR FACILITIES - ELECTRICAL EQUIPMENT IMPORTANT TO SAFETY - QUALIFICATION |
| IEEE DRAFT 338 : D4 2006 | CRITERIA FOR THE PERIODIC SURVEILLANCE TESTING OF NUCLEAR POWER GENERATING STATION SAFETY SYSTEMS |
| ANS 56.7-1978(R1987) | VENTILATION SYSTEMS, BOILING WATER REACTOR CONTAINMENT |
| BS EN 60780-323:2017 | Nuclear facilities. Electrical equipment important to safety. Qualification |
| 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 627-2010 | IEEE Standard for Qualification of Equipment Used in Nuclear Facilities |
| IEEE 308-2012 REDLINE | IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations |
| IEEE 338-2012 | IEEE Standard for Criteria for the Periodic Surveillance Testing of Nuclear Power Generating Station Safety |
| IEEE DRAFT 741 : D1 2006 | CRITERIA FOR THE PROTECTION OF CLASS 1E POWER SYSTEMS AND EQUIPMENT IN NUCLEAR POWER GENERATING STATIONS |
| ANSI N13.4 : 71(R1983) | PORTABLE X-OR GAMMA RADIATION SURVEY INSTRUMENTS, SPECIFICATION OF, |
| IEEE 741-2017 | IEEE Standard for Criteria for the Protection of Class 1E Power Systems and Equipment in 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 308-2020 | IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations |
| IEEE 741-2022 | IEEE Standard for Criteria for the Protection of Class 1E Power Systems and Equipment in Nuclear Power Generating Stations |
| IEEE 572-2019 | IEEE Standard for Qualification of Class 1E Connection Assemblies for Nuclear Power Generating Stations and Other Nuclear Facilities |
| NEMA WC 74 : 2012 | 5-46 KV SHIELDED POWER CABLE FOR USE IN THE TRANSMISSION AND DISTRIBUTION OF ELECTRIC ENERGY |
| 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 |
| 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 C37.20.2-2015 | IEEE Standard for Metal-Clad Switchgear |
| IEEE 344-2013 | IEEE Standard for Seismic Qualification of Equipment for Nuclear Power Generating Stations |
| ISA MC96.1 : 1982 | TEMPERATURE MEASUREMENT THERMOCOUPLES |
| IEEE 101 : 1987 | GUIDE FOR THE STATISTICAL ANALYSIS OF THERMAL LIFE TEST DATA |
| NFPA 70 : 2017 | NATIONAL ELECTRICAL CODE |
| IEEE C37.09-1999 | IEEE Standard Test Procedure for AC High-Voltage Circuit Breakers Rated on a Symmetrical Current Basis |
| IEEE C37.20.2-1999 | IEEE Standard for Metal-Clad Switchgear |
| 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 |
| TIA/EIA 455-171 : A2001 | ATTENUATION BY SUBSTITUTION MEASUREMENT FOR SHORT-LENGTH MULTIMODE GRADED-INDEX AND SINGLE-MODE OPTICAL FIBER-CABLE ASSEMBLIES |
| IEEE 98-2002 | IEEE Standard for the Preparation of Test Procedures for the Thermal Evaluation of Solid Electrical Insulating Materials |
| IEEE 323-2003 | IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations |
| IEEE 627-2010 | IEEE Standard for Qualification of Equipment Used in Nuclear Facilities |
| ASME NQA 1 : 2015 | Quality Assurance Requirements for Nuclear Facility Applications (NQA-1 - 2015) |
| ASME PV CODE SET : 2017 | BOILER AND PRESSURE VESSEL CODE - COMPLETE SET |
| IEEE 603-2009 REDLINE | IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations |
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