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ANS
ANS 51.10 : 1991(R2008)

ANS 51.10 : 1991(R2008)

Superseded

Superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

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superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

AUXILIARY FEED-WATER SYSTEM FOR PRESSURIZED WATER REACTORS

Superseded date

03-02-2021

Published date

01-12-2013

Publisher

American Nuclear Society

Provides the nuclear safety-related functional requirements, performance requirements, design criteria, design requirements for testing and maintenance, and interfaces for the nuclear safety-related portion of the auxiliary feed-water system (AFS) of pressurized water reactor (PWR) plants.

DocumentType
Standard
PublisherName
American Nuclear Society
Status
Superseded
SupersededBy
Supersedes

ANS 58.11 : 1995(R2002) DESIGN CRITERIA FOR SAFE SHUTDOWN FOLLOWING SELECTED DESIGN BASIS EVENTS IN LIGHT WATER REACTORS
ANS 58.14 : 2011(R2017) SAFETY AND PRESSURE INTEGRITY CLASSIFICATION CRITERIA FOR LIGHT WATER REACTORS

ANS 59.1 : 1986 COOLING WATER SYSTEMS FOR LIGHT WATER REACTORS, NUCLEAR SAFETY RELATED,
ANS 58.8 : 1994(R2017) TIME RESPONSE DESIGN CRITERIA FOR SAFETY-RELATED OPERATOR ACTIONS
ANS 58.11 : 1995(R2002) DESIGN CRITERIA FOR SAFE SHUTDOWN FOLLOWING SELECTED DESIGN BASIS EVENTS IN LIGHT WATER REACTORS
IEEE 379-2014 IEEE Standard for Application of the Single-Failure Criterion to Nuclear Power Generating Station Safety Systems
ANS 56.11 : 1998 DESIGN CRITERIA FOR PROTECTION AGAINST THE EFFECTS OF COMPARTMENT FLOODING IN LIGHT WATER REACTOR PLANTS
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
ANS 5.1 : 2014 DECAY HEAT POWER IN LIGHT WATER REACTORS
ANS 51.1 : 83(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 56.10 : 82(R1987) NUCLEAR REACTORS - SUBCOMPARTMENT PRESSURE AND TEMPERATURE TRANSIENT ANALYSIS IN LIGHT WATER REACTORS
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
ANS 59.2 : 1985 NUCLEAR POWER PLANTS - HVAC SYSTEMS LOCATED OUTSIDE PRIMARY CONTAINMENT, SAFETY CRITERIA FOR,
ASME NQA 1 : 2015 Quality Assurance Requirements for Nuclear Facility Applications (NQA-1 - 2015)
ANS 3.3 : 1988 SECURITY FOR NUCLEAR POWER PLANTS,
ANS 58.3 : 1992(R2008) PHYSICAL PROTECTION FOR NUCLEAR SAFETY-RELATED SYSTEMS AND COMPONENTS
ASME PV CODE 11 : 2017 BOILER AND PRESSURE VESSEL CODE - RULES FOR INSERVICE INSPECTION OF NUCLEAR POWER PLANT COMPONENTS
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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