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IEEE 497-2010
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IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations
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ANS 56.5 : 79(R1987)
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PWR AND BWR CONTAINMENT SPRAY SYSTEM DESIGN CRITERIA
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|
ASME AG-1 : 2019
|
CODE ON NUCLEAR AIR AND GAS TREATMENT
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ANS 59.2 : 1985
|
NUCLEAR POWER PLANTS - HVAC SYSTEMS LOCATED OUTSIDE PRIMARY CONTAINMENT, SAFETY CRITERIA FOR,
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|
ASME AG 1 : 2012
|
CODE ON NUCLEAR AIR AND GAS TREATMENT
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IEEE/ANSI N42.4-1971
|
American National Standard for High Voltage Connectors for Nuclear Instruments
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ANS 54.1 : 1989
|
GENERAL SAFETY DESIGN CRITERIA FOR A LIQUID METAL REACTOR NUCLEAR POWER PLANT
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|
ANS 56.10 : 82(R1987)
|
NUCLEAR REACTORS - SUBCOMPARTMENT PRESSURE AND TEMPERATURE TRANSIENT ANALYSIS IN LIGHT WATER REACTORS
|
|
IEC 63147:2017
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Criteria for accident monitoring instrumentation for nuclear power generating stations
|
|
IEEE DRAFT 338 : D4 2006
|
CRITERIA FOR THE PERIODIC SURVEILLANCE TESTING OF NUCLEAR POWER GENERATING STATION SAFETY SYSTEMS
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|
ANS 59.1 : 1986
|
COOLING WATER SYSTEMS FOR LIGHT WATER REACTORS, NUCLEAR SAFETY RELATED,
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ANS 51.10 : 1991(R2008)
|
AUXILIARY FEED-WATER SYSTEM FOR PRESSURIZED WATER REACTORS
|
|
IEEE 3006.7-2013
|
IEEE Recommended Practice for Determining the Reliability of 7x24 Continuous Power Systems in Industrial and Commercial Facilities
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|
ANS 56.7 : 78(R1987)
|
VENTILATION SYSTEMS, BOILING WATER REACTOR CONTAINMENT
|
|
IEEE 603-2009 REDLINE
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IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations
|
|
IEEE 7-4.3.2-2016
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IEEE Standard Criteria for Programmable Digital Devices in Safety Systems of Nuclear Power Generating Stations
|
|
ANS 56.3 : 77(R1987)
|
OVERPRESSURE PROTECTION OF LOW-PRESSURE SYSTEMS CONNECTED TO THE REACTOR COOLANT PRESSURE BOUNDARY
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|
IEEE 279-1971
|
IEEE Standard: Criteria for Protection Systems for Nuclear Power Generating Stations
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IEEE 577-2012
|
IEEE Standard Requirements for Reliability Analysis in the Design and Operation of Safety Systems for Nuclear Power Generating Stations
|
|
IEEE 1819-2016
|
IEEE Standard for Risk-Informed Categorization and Treatment of Electrical and Electronic Equipment at Nuclear Power Generating Stations and Other Nuclear Facilities
|
|
ANS 58.6 : 1996(R2001)
|
CRITERIA FOR REMOTE SHUTDOWN FOR LIGHT WATER REACTORS
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|
BS IEC 63147:2017
|
Criteria for accident monitoring instrumentation for nuclear power generating stations
|
|
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
|
|
ANS 51.1 : 83(R1988)
|
NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY PRESSURIZED WATER REACTOR PLANTS
|
|
ANSI N13.4 : 71(R1983)
|
PORTABLE X-OR GAMMA RADIATION SURVEY INSTRUMENTS, SPECIFICATION OF,
|
|
ANS 52.1 : 83(R1988)
|
NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY BOILING WATER REACTOR PLANTS
|
|
ANS 56.4 : 83(R1988)
|
PRESSURE AND TEMPERATURE TRANSIENT ANALYSIS FOR LIGHT WATER REACTOR CONTAINMENTS
|
|
IEEE 308-2020 REDLINE
|
IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations
|
|
IEEE 384-2018
|
IEEE Standard Criteria for Independence of Class 1E Equipment and Circuits
|
|
IEEE/IEC 63147-2017
|
IEEE/IEC International Standard - 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
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