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ANS 58.2 : 1988

Withdrawn
Withdrawn

A Withdrawn Standard is one, which is removed from sale, and its unique number can no longer be used. The Standard can be withdrawn and not replaced, or it can be withdrawn and replaced by a Standard with a different number.

DESIGN BASIS FOR PROTECTION OF LIGHT WATER NUCLEAR POWER PLANTS AGAINST THE EFFECTS OF POSTULATED PIPE RUPTURE
Withdrawn date

23-07-2013

Published date

12-01-2013

Publisher

American Nuclear Society

Describes design bases for LWR nuclear power plant structures and components essential for the protection of public health and safety from the potential adverse effects of jet impingement, pipe whip, pressurization of compartments outside containment, environmental conditions and flooding associated with a postulated pipe rupture.

DocumentType
Standard
PublisherName
American Nuclear Society
Status
Withdrawn
Supersedes

ANS 56.6 : 1986 VENTILATION SYSTEMS, PRESSURIZED WATER REACTOR CONTAINMENT
ANS 2.8 : 1992 DETERMINING DESIGN BASIS FLOODING AT POWER REACTOR SITES
IEEE DRAFT 833 : D3 2004 PRACTICE FOR THE PROTECTION OF ELECTRIC EQUIPMENT IN NUCLEAR POWER GENERATING STATIONS FROM WATER HAZARDS
ANS 59.2 : 1985 NUCLEAR POWER PLANTS - HVAC SYSTEMS LOCATED OUTSIDE PRIMARY CONTAINMENT, SAFETY CRITERIA FOR,
ANS 56.10 : 82(R1987) NUCLEAR REACTORS - SUBCOMPARTMENT PRESSURE AND TEMPERATURE TRANSIENT ANALYSIS IN LIGHT WATER REACTORS
ANS 56.11 : 1998 DESIGN CRITERIA FOR PROTECTION AGAINST THE EFFECTS OF COMPARTMENT FLOODING IN LIGHT WATER REACTOR PLANTS
ANS 56.2 : 84(R1989) NUCLEAR POWER PLANTS - CONTAINMENT ISOLATION PROVISIONS FOR FLUID SYSTEMS AFTER A LOCA
ANS 51.10 : 1991(R2008) AUXILIARY FEED-WATER SYSTEM FOR PRESSURIZED WATER REACTORS
IEEE 384-2008 REDLINE IEEE Standard Criteria for Independence of Class 1E Equipment and Circuits
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
ANS 56.4 : 83(R1988) PRESSURE AND TEMPERATURE TRANSIENT ANALYSIS FOR LIGHT WATER REACTOR CONTAINMENTS

ASME B31.1 : 2016 POWER PIPING
ANS 58.8 : 1994(R2017) TIME RESPONSE DESIGN CRITERIA FOR SAFETY-RELATED OPERATOR ACTIONS
ANS 56.11 : 1998 DESIGN CRITERIA FOR PROTECTION AGAINST THE EFFECTS OF COMPARTMENT FLOODING IN LIGHT WATER REACTOR PLANTS
ANS 56.10 : 82(R1987) NUCLEAR REACTORS - SUBCOMPARTMENT PRESSURE AND TEMPERATURE TRANSIENT ANALYSIS IN LIGHT WATER REACTORS
ANS 58.9 : 2002(R2015) SINGLE FAILURE CRITERIA FOR LWR SAFETY-RELATED FLUID SYSTEMS
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

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