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IEEE 308-2012 REDLINE

Superseded
Superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.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superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.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 Criteria for Class 1E Power Systems for Nuclear Power Generating Stations
Available format(s)

PDF

Superseded date

19-03-2020

Language(s)

English

Published date

16-01-2013

1. Overview
2. Normative references
3. Definitions
4. Principal design criteria
5. Supplementary design criteria
6. Surveillance and test requirements
7. Multiunit station considerations
8. Documentation

Covers Class 1E portions of ac and dc power systems and I&C power systems in single-unit and multiunit nuclear power generating stations.

Committee
Nuclear Power Engineering Committee
DevelopmentNote
Supersedes IEEE DRAFT 308. (08/2002)
DocumentType
Standard
Pages
67
PublisherName
Institute of Electrical & Electronics Engineers
Status
Superseded
SupersededBy
Supersedes

IEEE 741-2007 IEEE Standard Criteria for the Protection of Class 1E Power Systems and Equipment in Nuclear Power Generating Stations
IEEE 384-2008 REDLINE IEEE Standard Criteria for Independence of Class 1E Equipment and Circuits
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
ANS 56.6 : 1986 VENTILATION SYSTEMS, PRESSURIZED WATER REACTOR CONTAINMENT
IEEE 383-2015 IEEE Standard for Qualifying Electric Cables and Splices for Nuclear Facilities
IEEE DRAFT 833 : D3 2004 PRACTICE FOR THE PROTECTION OF ELECTRIC EQUIPMENT IN NUCLEAR POWER GENERATING STATIONS FROM WATER HAZARDS
IEEE 650-2006 IEEE Standard for Qualification of Class 1E Static Battery Chargers and Inverters for Nuclear Power Generating Stations
ANS 59.2 : 1985 NUCLEAR POWER PLANTS - HVAC SYSTEMS LOCATED OUTSIDE PRIMARY CONTAINMENT, SAFETY CRITERIA FOR,
IEEE 497-2010 IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations
IEEE/ANSI N42.4-1971 American National Standard for High Voltage Connectors for Nuclear Instruments
IEEE 946-2004 IEEE Recommended Practice for the Design of DC Auxiliary Power Systems for Generating Systems
IEEE 279-1971 IEEE Standard: Criteria for Protection Systems for Nuclear Power Generating Stations
IEC 63147:2017 Criteria for accident monitoring instrumentation for nuclear power generating stations
IEEE 497-2016 IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations
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 384-2018 IEEE Standard Criteria for Independence of Class 1E Equipment and Circuits
IEEE DRAFT 379 : D5 2000 DRAFT STANDARD APPLICATION OF THE SINGLE-FAILURE CRITERION TO NUCLEAR POWER GENERATING STATION SAFETY SYSTEMS
IEEE 535-2013 IEEE Standard for Qualification of Class 1E Vented Lead Acid Storage Batteries for Nuclear Power Generating Stations
IEEE DRAFT 338 : D4 2006 CRITERIA FOR THE PERIODIC SURVEILLANCE TESTING OF NUCLEAR POWER GENERATING STATION SAFETY SYSTEMS
ANS 59.1 : 1986 COOLING WATER SYSTEMS FOR LIGHT WATER REACTORS, NUCLEAR SAFETY RELATED,
ANS 56.2 : 84(R1989) NUCLEAR POWER PLANTS - CONTAINMENT ISOLATION PROVISIONS FOR FLUID SYSTEMS AFTER A LOCA
IEEE 603-2009 REDLINE IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations
ANS 51.10 : 1991(R2008) AUXILIARY FEED-WATER SYSTEM FOR PRESSURIZED WATER REACTORS
ANS 56.7 : 78(R1987) VENTILATION SYSTEMS, BOILING WATER REACTOR CONTAINMENT
ANS 59.51 : 1997(R2015) FUEL OIL SYSTEMS FOR SAFETY-RELATED EMERGENCY DIESEL GENERATORS
IEEE DRAFT 765 : 0 PREFERRED POWER SUPPLY (PPS) FOR NUCLEAR POWER GENERATING STATIONS (NPGS)
IEEE 628-2011 IEEE Standard Criteria for the Design, Installation, and Qualification of Raceway Systems for Class 1E Circuits for Nuclear Power Generating Stations
ANS 56.3 : 77(R1987) OVERPRESSURE PROTECTION OF LOW-PRESSURE SYSTEMS CONNECTED TO THE REACTOR COOLANT PRESSURE BOUNDARY
ANSI N13.4 : 71(R1983) PORTABLE X-OR GAMMA RADIATION SURVEY INSTRUMENTS, SPECIFICATION OF,
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 577-2012 IEEE Standard Requirements for Reliability Analysis in the Design and Operation of Safety Systems for Nuclear Power Generating Stations
IEEE 765-2012 IEEE Standard for Preferred Power Supply (PPS) for Nuclear Power Generating Stations (NPGS)
IEEE 1792-2011 IEEE Recommended Practice for Nuclear Power Generating Station (NPGS) Preferred Power Supply (PPS) Reliability
ANS 58.6 : 1996(R2001) CRITERIA FOR REMOTE SHUTDOWN FOR LIGHT WATER REACTORS
BS IEC 63147:2017 Criteria for accident monitoring instrumentation for nuclear power generating stations
IEEE 627-2010 IEEE Standard for Qualification of Equipment Used in Nuclear Facilities
IEEE DRAFT 741 : D1 2006 CRITERIA FOR THE PROTECTION OF CLASS 1E POWER SYSTEMS AND EQUIPMENT IN NUCLEAR POWER GENERATING STATIONS
IEEE 338-2012 IEEE Standard for Criteria for the Periodic Surveillance Testing of Nuclear Power Generating Station Safety
ANS 51.1 : 83(R1988) NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY PRESSURIZED WATER REACTOR PLANTS
IEEE 379-2014 IEEE Standard for Application of the Single-Failure Criterion to Nuclear Power Generating Station Safety Systems
ANS 57.2 : 1983 LIGHT WATER REACTOR SPENT FUEL STORAGE FACILITIES, REQUIREMENTS FOR,
ANS 59.3 : 1992(R2002) NUCLEAR SAFETY CRITERIA FOR CONTROL AIR SYSTEMS
IEEE 323-2003 IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations
IEEE 450-2010 REDLINE IEEE Recommended Practice for Maintenance, Testing, and Replacement of Vented Lead-Acid Batteries for Stationary Applications
ANS 52.1 : 83(R1988) NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY BOILING WATER REACTOR PLANTS
IEEE 741-2017 IEEE Standard for Criteria for the Protection of Class 1E Power Systems and Equipment in Nuclear Power Generating Stations
IEEE 1792-2017 IEEE Recommended Practice for Nuclear Power Generating Station Preferred Power Supply Reliability

IEEE 494-1974 IEEE Standard Method for Identification of Documents Related to Class 1E Equipment and Systems for Nuclear Power Generating Stations
IEEE 577-2012 IEEE Standard Requirements for Reliability Analysis in the Design and Operation of Safety Systems for Nuclear Power Generating Stations
CFR 10(PTS0-199) : JAN 87 ENERGY - NUCLEAR REGULATORY COMMISSION
IEEE 741-2007 IEEE Standard Criteria for the Protection of Class 1E Power Systems and Equipment in Nuclear Power Generating Stations
IEEE 535-2006 IEEE Standard for Qualification of Class 1E Lead Storage Batteries for Nuclear Power Generating Stations
IEEE 379-2014 IEEE Standard for Application of the Single-Failure Criterion to Nuclear Power Generating Station Safety Systems
IEEE 7-4.3.2-2010 REDLINE IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations
IEEE 317-1983 IEEE Standard for Electric Penetration Assemblies in Containment Structures for Nuclear Power Generating Stations
IEEE 484-2002 IEEE Recommended Practice for Installation Design and Installation of Vented Lead-Acid Batteries for Stationary Applications
IEEE 384-2008 REDLINE IEEE Standard Criteria for Independence of Class 1E Equipment and Circuits
IEEE 323-2003 IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations
IEEE 379-2000 IEEE Standard Application of the Single-Failure Criterion to Nuclear Power Generating Station Safety Systems
IEEE 450-2010 REDLINE IEEE Recommended Practice for Maintenance, Testing, and Replacement of Vented Lead-Acid Batteries for Stationary Applications
ASME NQA 1 : 2015 Quality Assurance Requirements for Nuclear Facility Applications (NQA-1 - 2015)
IEEE 946-2004 IEEE Recommended Practice for the Design of DC Auxiliary Power Systems for Generating Systems
IEEE 387-1995 IEEE Standard Criteria for Diesel-Generator Units Applied as Standby Power Supplies for Nuclear Power Generating Stations
IEEE 352-1987 IEEE Guide for General Principles of Reliability Analysis of Nuclear Power Generating Station Safety Systems
IEEE 415-1986 IEEE Guide for Planning of Preoperational Testing Programs for Class 1E Power Systems for Nuclear Power Generating Stations
IEEE 765-2012 IEEE Standard for Preferred Power Supply (PPS) for Nuclear Power Generating Stations (NPGS)
IEEE 485-2010 IEEE Recommended Practice for Sizing Lead-Acid Batteries for Stationary Applications
IEEE 338-2012 IEEE Standard for Criteria for the Periodic Surveillance Testing of Nuclear Power Generating Station Safety
IEEE 317-2013 REDLINE IEEE Standard for Electric Penetration Assemblies in Containment Structures for Nuclear Power Generating Stations
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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