ANS 59.1-1986
Withdrawn
A Withdrawn Standard is one, which is removed from sale, and its unique number can no longer be used. The Standard can be withdrawn and not replaced, or it can be withdrawn and replaced by a Standard with a different number.
COOLING WATER SYSTEMS FOR LIGHT WATER REACTORS, NUCLEAR SAFETY RELATED,
Hardcopy , PDF
23-07-2013
English
12-01-2013
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Withdrawn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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