ANS 58.2-1988
Withdrawn
A Withdrawn Standard is one, which is removed from sale, and its unique number can no longer be used. The Standard can be withdrawn and not replaced, or it can be withdrawn and replaced by a Standard with a different number.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
Hardcopy , PDF
23-07-2013
English
12-01-2013
Important note : All end users must be registered with an Account prior to user licenses being assigned.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
|
| Pages |
80
|
| 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Withdrawn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 56.2-1984(R1989) | NUCLEAR POWER PLANTS - CONTAINMENT ISOLATION PROVISIONS FOR FLUID SYSTEMS AFTER A LOCA |
| IEEE 384-2008 REDLINE | IEEE Standard Criteria for Independence of Class 1E Equipment and Circuits |
| 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 56.4-1983(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 56.10-82(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 |
| ASME PV CODE 11 : 2017 | BOILER AND PRESSURE VESSEL CODE - RULES FOR INSERVICE INSPECTION OF NUCLEAR POWER PLANT COMPONENTS |
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