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ANS 59.1-1986

Withdrawn

Withdrawn

A Withdrawn Standard is one, which is removed from sale, and its unique number can no longer be used. The Standard can be withdrawn and not replaced, or it can be withdrawn and replaced by a Standard with a different number.

COOLING WATER SYSTEMS FOR LIGHT WATER REACTORS, NUCLEAR SAFETY RELATED,

Available format(s)

Hardcopy , PDF

Withdrawn date

23-07-2013

Language(s)

English

Published date

12-01-2013

€86.14
Excluding VAT

Describes the provisions of NSRCWS for LWRs. Establishes nuclear safety requirements in the areas of materials, design, fabrication, placement and testing of systems. Applies to open and closed NSRCW systems.

DocumentType
Standard
Pages
0
PublisherName
American Nuclear Society
Status
Withdrawn
Supersedes

ANS 59.2-1985 NUCLEAR POWER PLANTS - HVAC SYSTEMS LOCATED OUTSIDE PRIMARY CONTAINMENT, SAFETY CRITERIA FOR,
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

IEEE 497-2010 IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations
ASME NQA 2 : 89 SPECIAL NOTICE QUALITY ASSURANCE REQUIREMENTS FOR NUCLEAR FACILITY APPLICATIONS
ANS 58.8-1994(R2017) TIME RESPONSE DESIGN CRITERIA FOR SAFETY-RELATED OPERATOR ACTIONS
IEEE 379-2014 IEEE Standard for Application of the Single-Failure Criterion to Nuclear Power Generating Station Safety Systems
ANS 58.6-1996(R2001) CRITERIA FOR REMOTE SHUTDOWN FOR LIGHT WATER REACTORS
ANSI OM 2 : 1982 NUCLEAR - REQUIREMENTS FOR PERFORMANCE TESTING OF NUCLEAR POWER PLANT CLOSED COOLING WATER SYSTEMS
ANS 5.1 : 2014 DECAY HEAT POWER IN LIGHT WATER REACTORS
ANS 51.1-1983(R1988) NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY PRESSURIZED WATER REACTOR PLANTS
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
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
ASME NQA 1 : 2015 Quality Assurance Requirements for Nuclear Facility Applications (NQA-1 - 2015)
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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