ANS 56.6-1986
Withdrawn
A Withdrawn Standard is one, which is removed from sale, and its unique number can no longer be used. The Standard can be withdrawn and not replaced, or it can be withdrawn and replaced by a Standard with a different number.
VENTILATION SYSTEMS, PRESSURIZED WATER REACTOR CONTAINMENT
Hardcopy , PDF
28-07-2000
English
01-01-1986
Important note : Users cannot be edited or removed once added to your Multi user PDF.Describes criteria for the design of ventilation systems, including ductwork, equipment, and control devices, utilized for providing heat removal, atmospheric clean up, heating, and general ventilation within PWR primary containment structures. Also addresses systems used to ventilate containment structures.
| DocumentType |
Standard
|
| Pages |
26
|
| PublisherName |
American Nuclear Society
|
| Status |
Withdrawn
|
| Supersedes |
| ANS 56.5-79(R1987) | PWR AND BWR CONTAINMENT SPRAY SYSTEM DESIGN CRITERIA |
| ANS 59.2-1985 | NUCLEAR POWER PLANTS - HVAC SYSTEMS LOCATED OUTSIDE PRIMARY CONTAINMENT, SAFETY CRITERIA FOR, |
| ANS 59.4-1979 | GENERIC REQUIREMENTS FOR LIGHT WATER NUCLEAR POWER PLANT FIRE PROTECTION |
| ANS 56.8-2002(R2016) | CONTAINMENT SYSTEM LEAKAGE TESTING REQUIREMENTS |
| ASME AG 1 : 2012 | CODE ON NUCLEAR AIR AND GAS TREATMENT |
| IEEE 334 : 2007 | QUALIFYING CONTINUOUS DUTY CLASS 1E MOTORS FOR NUCLEAR POWER GENERATING STATIONS |
| IEEE 344-2013 | IEEE Standard for Seismic Qualification of Equipment for Nuclear Power Generating Stations |
| 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 |
| IEEE 323-2003 | IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations |
| ASME NQA 1 : 2015 | Quality Assurance Requirements for Nuclear Facility Applications (NQA-1 - 2015) |
| ASTM D 3843 : 2016 : REDLINE | Standard Practice for Quality Assurance for Protective Coatings Applied to Nuclear Facilities |
| ANS 56.2-1984(R1989) | NUCLEAR POWER PLANTS - CONTAINMENT ISOLATION PROVISIONS FOR FLUID SYSTEMS AFTER A LOCA |
| IEEE 308-2012 REDLINE | IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations |
| IEEE 603-2009 REDLINE | IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations |
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