ANS 59.2-1985
Withdrawn
A Withdrawn Standard is one, which is removed from sale, and its unique number can no longer be used. The Standard can be withdrawn and not replaced, or it can be withdrawn and replaced by a Standard with a different number.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 - HVAC SYSTEMS LOCATED OUTSIDE PRIMARY CONTAINMENT, SAFETY CRITERIA FOR,
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 criteria for the design of Heating, Ventilating and Air Conditioning Systems located outside the primary reactor containment of LWR nuclear power plants that could affect nuclear safety functions.
| DocumentType |
Standard
|
| Pages |
32
|
| PublisherName |
American Nuclear Society
|
| Status |
Withdrawn
|
| ANS 59.1-1986 | COOLING WATER SYSTEMS FOR LIGHT WATER REACTORS, NUCLEAR SAFETY RELATED, |
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| ANS 59.4-1979 | GENERIC REQUIREMENTS FOR LIGHT WATER NUCLEAR POWER PLANT FIRE PROTECTION |
| ANS 2.12-1978 | NATURAL AND EXTERNAL MAN-MADE HAZARDS AT POWER REACTOR SITES, GUIDELINES FOR COMBINING, |
| ANS 58.8-1994(R2017) | TIME RESPONSE DESIGN CRITERIA FOR SAFETY-RELATED OPERATOR ACTIONS |
| ASME N510 : 2007 | TESTING OF NUCLEAR AIR-TREATMENT SYSTEMS |
| IEEE 379-2014 | IEEE Standard for Application of the Single-Failure Criterion to Nuclear Power Generating Station Safety Systems |
| ANS 59.3-1992(R2002) | NUCLEAR SAFETY CRITERIA FOR CONTROL AIR SYSTEMS |
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| ANS 4.5-80(R1986) | ACCIDENT MONITORING FUNCTIONS IN LIGHT-WATER-COOLED REACTORS, CRITERIA FOR |
| ANS 58.6-1996(R2001) | CRITERIA FOR REMOTE SHUTDOWN FOR LIGHT WATER REACTORS |
| IEEE 344-2013 | IEEE Standard for Seismic Qualification of Equipment for Nuclear Power Generating Stations |
| ISA 5.2 : 1976 | BINARY LOGIC DIAGRAMS FOR PROCESS OPERATIONS |
| AHRI 410 : 2001 | FORCED-CIRCULATION AIR-HEATING AND AIR-COOLING COILS |
| ANS 56.6-1986 | VENTILATION SYSTEMS, PRESSURIZED WATER REACTOR CONTAINMENT |
| 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 323-2003 | IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations |
| ANS 58.9-2002(R2015) | SINGLE FAILURE CRITERIA FOR LWR SAFETY-RELATED FLUID SYSTEMS |
| IEEE 627-2010 | IEEE Standard for Qualification of Equipment Used in Nuclear Facilities |
| ASME NQA 1 : 2015 | Quality Assurance Requirements for Nuclear Facility Applications (NQA-1 - 2015) |
| ANS 56.7-1978(R1987) | VENTILATION SYSTEMS, BOILING WATER REACTOR CONTAINMENT |
| ANS 3.3-1988 | SECURITY FOR NUCLEAR POWER PLANTS, |
| ASHRAE 15 : 2013 | SAFETY STANDARD FOR REFRIGERATION SYSTEMS |
| IEEE 308-2012 REDLINE | IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations |
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