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ANS 56.7 : 78(R1987)

Withdrawn
Withdrawn

A Withdrawn Standard is one, which is removed from sale, and its unique number can no longer be used. The Standard can be withdrawn and not replaced, or it can be withdrawn and replaced by a Standard with a different number.

VENTILATION SYSTEMS, BOILING WATER REACTOR CONTAINMENT
Available format(s)

Hardcopy , PDF

Withdrawn date

07-23-2013

Language(s)

English

Published date

01-12-2013

Describes minimum requirements for installation, design, testing and maintenance for ventilation systems serving the containment of BWR's.

DocumentType
Standard
Pages
31
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Withdrawn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 52.1 : 83(R1988) NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY BOILING WATER REACTOR PLANTS
ANS 58.14 : 2011(R2017) SAFETY AND PRESSURE INTEGRITY CLASSIFICATION CRITERIA FOR LIGHT WATER REACTORS

IEEE 379-2014 IEEE Standard for Application of the Single-Failure Criterion to Nuclear Power Generating Station Safety Systems
NFPA 90A : 2018 INSTALLATION OF AIR-CONDITIONING AND VENTILATING SYSTEMS
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
IEEE 279-1971 IEEE Standard: Criteria for Protection Systems for Nuclear Power Generating Stations
ANS 52.1 : 83(R1988) NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY BOILING WATER REACTOR PLANTS
ANS 58.3 : 1992(R2008) PHYSICAL PROTECTION FOR NUCLEAR SAFETY-RELATED SYSTEMS AND COMPONENTS
ANS 56.2 : 84(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 317-2013 REDLINE IEEE Standard for Electric Penetration Assemblies in Containment Structures for Nuclear Power Generating Stations

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