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ANS 56.2-1984(R1989)

Withdrawn

Withdrawn

A Withdrawn Standard is one, which is removed from sale, and its unique number can no longer be used. The Standard can be withdrawn and not replaced, or it can be withdrawn and replaced by a Standard with a different number.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 POWER PLANTS - CONTAINMENT ISOLATION PROVISIONS FOR FLUID SYSTEMS AFTER A LOCA

Available format(s)

Hardcopy , PDF

Withdrawn date

26-04-1989

Language(s)

English

Published date

26-04-1989

€220.74
Excluding VAT

Describes minimum actuation, design, testing and maintenance requirements for the containment isolation of fluid systems after a LOCA. These systems penetrate the primary containment of LWR's and include piping systems for all fluids entering or leaving the containment.

DocumentType
Standard
Pages
76
PublisherName
American Nuclear Society
Status
Withdrawn
Supersedes

ANS 56.6-1986 VENTILATION SYSTEMS, PRESSURIZED WATER REACTOR CONTAINMENT
ANS 59.1-1986 COOLING WATER SYSTEMS FOR LIGHT WATER REACTORS, NUCLEAR SAFETY RELATED,
ANS 56.7-1978(R1987) VENTILATION SYSTEMS, BOILING WATER REACTOR CONTAINMENT
ANS 51.1-1983(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

ANS 59.4-1979 GENERIC REQUIREMENTS FOR LIGHT WATER NUCLEAR POWER PLANT FIRE PROTECTION
ANS 56.8-2002(R2016) CONTAINMENT SYSTEM LEAKAGE TESTING REQUIREMENTS
ANS 58.8-1994(R2017) TIME RESPONSE DESIGN CRITERIA FOR SAFETY-RELATED OPERATOR ACTIONS
ASME B16.41 : 83(R1989) POWER OPERATED ACTIVE VALVE ASSEMBLIES FOR NUCLEAR POWER PLANTS, FUNCTIONAL QUALIFICATION REQUIREMENTS FOR,
ANS 4.5-80(R1986) ACCIDENT MONITORING FUNCTIONS IN LIGHT-WATER-COOLED REACTORS, CRITERIA FOR
ANS 51.1-1983(R1988) NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY PRESSURIZED WATER REACTOR PLANTS
IEEE 384-2008 REDLINE IEEE Standard Criteria for Independence of Class 1E Equipment and Circuits
ANS 58.2-1988 DESIGN BASIS FOR PROTECTION OF LIGHT WATER NUCLEAR POWER PLANTS AGAINST THE EFFECTS OF POSTULATED PIPE RUPTURE
ANS 52.1-83(R1988) NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY BOILING WATER REACTOR PLANTS
IEEE 308-2012 REDLINE IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations

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