ANS 56.2-1984(R1989)
Withdrawn
NUCLEAR POWER PLANTS - CONTAINMENT ISOLATION PROVISIONS FOR FLUID SYSTEMS AFTER A LOCA
Hardcopy , PDF
English
04-26-1989
04-26-1989
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Withdrawn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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