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ANS 59.3 : 1992(R2002)

Withdrawn
Withdrawn

A Withdrawn Standard is one, which is removed from sale, and its unique number can no longer be used. The Standard can be withdrawn and not replaced, or it can be withdrawn and replaced by a Standard with a different number.

NUCLEAR SAFETY CRITERIA FOR CONTROL AIR SYSTEMS
Withdrawn date

07-23-2013

Published date

01-12-2013

Publisher

American Nuclear Society

Describes nuclear safety criteria for the control air system that furnishes compressed air to safety related components in nuclear power plants. Applicable only to the air supply system and not applicable to air operated devices. It provides: the system nuclear safety design requirements for piping, equipment, instruments and controls that constitute the control air supply system and the nuclear safety design requirements to accommodate testing and maintenance necessary to ensure adequate nuclear safety performance of the control air system.

DocumentType
Standard
PublisherName
American Nuclear Society
Status
Withdrawn
Supersedes

ANS 59.2 : 1985 NUCLEAR POWER PLANTS - HVAC SYSTEMS LOCATED OUTSIDE PRIMARY CONTAINMENT, SAFETY CRITERIA FOR,
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ISA 7.0.01 : 1996 QUALITY STANDARD FOR INSTRUMENT AIR

ANS 4.5 : 80(R1986) ACCIDENT MONITORING FUNCTIONS IN LIGHT-WATER-COOLED REACTORS, CRITERIA FOR
ANS 51.1 : 83(R1988) NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY PRESSURIZED WATER REACTOR PLANTS
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
ASME NQA 1 : 2015 Quality Assurance Requirements for Nuclear Facility Applications (NQA-1 - 2015)
ISA S7.3 : 75(R1981) QUALITY STANDARD FOR INSTRUMENT AIR,
ANS 58.3 : 1992(R2008) PHYSICAL PROTECTION FOR NUCLEAR SAFETY-RELATED SYSTEMS AND COMPONENTS
ASME PV CODE 11 : 2017 BOILER AND PRESSURE VESSEL CODE - RULES FOR INSERVICE INSPECTION OF NUCLEAR POWER PLANT COMPONENTS
IEEE 308-2012 REDLINE IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations

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