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ANS 52.1 : 83(R1988)

Withdrawn
Withdrawn

A Withdrawn Standard is one, which is removed from sale, and its unique number can no longer be used. The Standard can be withdrawn and not replaced, or it can be withdrawn and replaced by a Standard with a different number.

NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY BOILING WATER REACTOR PLANTS
Withdrawn date

23-07-2013

Published date

12-01-2013

Specifies the functional design requirements and nuclear safety criteria of structures, components and systems of stationary boiling water reactor power plants. Ensures that plants can be designed and constructed to operate safely and without risk to the public. Also defines existing practices consistent with the US Nuclear Regulatory Commission (NRC) licensing requirements.

DocumentType
Standard
PublisherName
American Nuclear Society
Status
Withdrawn
Supersedes

ANS 58.8 : 1994(R2017) TIME RESPONSE DESIGN CRITERIA FOR SAFETY-RELATED OPERATOR ACTIONS
ANS 56.5 : 79(R1987) PWR AND BWR CONTAINMENT SPRAY SYSTEM DESIGN CRITERIA
ANS 55.4 : 1993(R2007) GASEOUS RADIOACTIVE WASTE PROCESSING SYSTEMS FOR LIGHT WATER REACTOR PLANTS
ANS 59.2 : 1985 NUCLEAR POWER PLANTS - HVAC SYSTEMS LOCATED OUTSIDE PRIMARY CONTAINMENT, SAFETY CRITERIA FOR,
ASME QME 1 : 2017 QUALIFICATION OF ACTIVE MECHANICAL EQUIPMENT USED IN NUCLEAR FACILITIES
ANS 57.1 : 1992(R2015) DESIGN REQUIREMENTS FOR LIGHT WATER REACTOR FUEL HANDLING SYSTEMS
IEEE DRAFT 379 : D5 2000 DRAFT STANDARD 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 59.1 : 1986 COOLING WATER SYSTEMS FOR LIGHT WATER REACTORS, NUCLEAR SAFETY RELATED,
ANS 56.2 : 84(R1989) NUCLEAR POWER PLANTS - CONTAINMENT ISOLATION PROVISIONS FOR FLUID SYSTEMS AFTER A LOCA
ANS 56.7 : 78(R1987) VENTILATION SYSTEMS, BOILING WATER REACTOR CONTAINMENT
ANS 59.51 : 1997(R2015) FUEL OIL SYSTEMS FOR SAFETY-RELATED EMERGENCY DIESEL GENERATORS
IEEE 7-4.3.2-2016 IEEE Standard Criteria for Programmable Digital Devices in Safety Systems of Nuclear Power Generating Stations
ANS 55.6 : 1993(R2007)(W2017) LIQUID RADIOACTIVE WASTE PROCESSING SYSTEM FOR LIGHT WATER REACTOR PLANTS
ANS 58.11 : 1995(R2002) DESIGN CRITERIA FOR SAFE SHUTDOWN FOLLOWING SELECTED DESIGN BASIS EVENTS IN LIGHT WATER REACTORS
IEEE 627-2010 IEEE Standard for Qualification of Equipment Used in Nuclear Facilities
ANS 57.10 : 1996(R2006) DESIGN CRITERIA FOR CONSOLIDATION OF LWR SPENT FUEL
IEEE DRAFT 603 : D7 JUN 96 CRITERIA FOR SAFETY SYSTEMS FOR NUCLEAR POWER GENERATING STATIONS
ANS 57.2 : 1983 LIGHT WATER REACTOR SPENT FUEL STORAGE FACILITIES, REQUIREMENTS FOR,
ANS 59.3 : 1992(R2002) NUCLEAR SAFETY CRITERIA FOR CONTROL AIR SYSTEMS
ISA 67.01 : 1994 TRANSDUCER AND TRANSMITTER INSTALLATION FOR NUCLEAR SAFETY APPLICATIONS
ANS 56.4 : 83(R1988) PRESSURE AND TEMPERATURE TRANSIENT ANALYSIS FOR LIGHT WATER REACTOR CONTAINMENTS
IEEE 352-1987 IEEE Guide for General Principles of Reliability Analysis of Nuclear Power Generating Station Safety Systems

ANS 59.1 : 1986 COOLING WATER SYSTEMS FOR LIGHT WATER REACTORS, NUCLEAR SAFETY RELATED,
ASME PV CODE 3 NF DIV 1 : 2017 BOILER AND PRESSURE VESSEL CODE - RULES FOR THE CONSTRUCTION OF NUCLEAR FACILITY COMPONENTS - SUPPORTS
ACI 301 : 2016 SPECIFICATIONS FOR STRUCTURAL CONCRETE
IEEE 577-2012 IEEE Standard Requirements for Reliability Analysis in the Design and Operation of Safety Systems for Nuclear Power Generating Stations
ANS 59.4 : 1979 GENERIC REQUIREMENTS FOR LIGHT WATER NUCLEAR POWER PLANT FIRE PROTECTION
ASME PV CODE 3 ND DIV 1 : 2017 BOILER AND PRESSURE VESSEL CODE - RULES FOR THE CONSTRUCTION OF NUCLEAR FACILITY COMPONENTS - CLASS 3 COMPONENTS
ANS 2.12 : 1978 NATURAL AND EXTERNAL MAN-MADE HAZARDS AT POWER REACTOR SITES, GUIDELINES FOR COMBINING,
ANS 56.8 : 2002(R2016) CONTAINMENT SYSTEM LEAKAGE TESTING REQUIREMENTS
ASME PV CODE 3 NCA DIV 1&2 : 2017 BPVC Section III-Rules for Constructions of Nuclear Facility Components BOILER AND PRESSURE VESSEL CODE - RULES FOR THE CONSTRUCTION OF NUCLEAR FACILITY COMPONENTS - GENERAL REQUIREMENTS FOR DIVISION 1 AND DIVISION 2
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
ACI 318 : 2014 BUILDING CODE REQUIREMENTS FOR STRUCTURAL CONCRETE AND COMMENTARY
IEEE 383-2015 IEEE Standard for Qualifying Electric Cables and Splices for Nuclear Facilities
ANS 55.1 : 1992(R2017) SOLID RADIOACTIVE WASTE PROCESSING SYSTEM FOR LIGHT-WATER-COOLED REACTOR PLANTS
ANS 56.3 : 77(R1987) OVERPRESSURE PROTECTION OF LOW-PRESSURE SYSTEMS CONNECTED TO THE REACTOR COOLANT PRESSURE BOUNDARY
ANS 56.5 : 79(R1987) PWR AND BWR CONTAINMENT SPRAY SYSTEM DESIGN CRITERIA
ANS 58.4 : 1979 TECHNICAL SPECIFICATIONS FOR NUCLEAR POWER STATIONS, CRITERIA FOR,
ANS 58.6 : 1996(R2001) CRITERIA FOR REMOTE SHUTDOWN FOR LIGHT WATER REACTORS
IEEE 334 : 2007 QUALIFYING CONTINUOUS DUTY CLASS 1E MOTORS FOR NUCLEAR POWER GENERATING STATIONS
ASME PV CODE 3 NC DIV 1 : 2017 BOILER AND PRESSURE VESSEL CODE - RULES FOR THE CONSTRUCTION OF NUCLEAR FACILITY COMPONENTS - CLASS 2 COMPONENTS
IEEE 344-2013 IEEE Standard for Seismic Qualification of Equipment for Nuclear Power Generating Stations
ANS 55.4 : 1993(R2007) GASEOUS RADIOACTIVE WASTE PROCESSING SYSTEMS FOR LIGHT WATER REACTOR PLANTS
ASME PV CODE 3 NB DIV 1 : 2017 BOILER AND PRESSURE VESSEL CODE - RULES FOR THE CONSTRUCTION OF NUCLEAR FACILITY COMPONENTS - CLASS 1 COMPONENTS
ANS 2.13 : 79(R1988) EVALUATION OF SURFACE-WATER SUPPLIES FOR NUCLEAR POWER SITES
ANS 55.6 : 1993(R2007)(W2017) LIQUID RADIOACTIVE WASTE PROCESSING SYSTEM FOR LIGHT WATER REACTOR PLANTS
ASME PV CODE 3 DIV 2 : 2017 BOILER AND PRESSURE VESSEL CODE - RULES FOR THE CONSTRUCTION OF NUCLEAR FACILITY COMPONENTS - CODE FOR CONCRETE CONTAINMENTS
ANS 2.8 : 1992 DETERMINING DESIGN BASIS FLOODING AT POWER REACTOR SITES
ANS 2.10 : 2003 CRITERIA FOR THE HANDLING AND INITIAL EVALUATION OF RECORDS FROM NUCLEAR POWER PLANT SEISMIC INSTRUMENTATION
ANS 2.7 : 1982 SURFACE FAULTING AT NUCLEAR POWER SITES, CRITERIA AND GUIDELINES FOR ASSESSING CAPABILITY FOR,
IEEE 279-1971 IEEE Standard: Criteria for Protection Systems for Nuclear Power Generating Stations
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
ANS 57.2 : 1983 LIGHT WATER REACTOR SPENT FUEL STORAGE FACILITIES, REQUIREMENTS FOR,
ANS 2.11 : 78(R1990) GUIDELINES FOR EVALUATING SITE-RELATED GEOTECHNICAL PARAMETERS AT NUCLEAR POWER SITES
IEEE 450-2010 REDLINE IEEE Recommended Practice for Maintenance, Testing, and Replacement of Vented Lead-Acid Batteries for Stationary Applications
ACI 349 : 2013 CODE REQUIREMENTS FOR NUCLEAR SAFETY-RELATED CONCRETE STRUCTURES AND COMMENTARY
ANS 58.9 : 2002(R2015) SINGLE FAILURE CRITERIA FOR LWR SAFETY-RELATED FLUID SYSTEMS
ANS 57.1 : 1992(R2015) DESIGN REQUIREMENTS FOR LIGHT WATER REACTOR FUEL HANDLING SYSTEMS
ANS 6.4 : 2006(R2016) NUCLEAR ANALYSIS AND DESIGN OF CONCRETE RADIATION SHIELDING FOR NUCLEAR POWER PLANTS
ICC 2009 INTERNATIONAL BUILDING CODE : 2009 INTERNATIONAL BUILDING CODE
ANS 2.9 : 80(R1989) EVALUATION OF GROUND WATER SUPPLY FOR NUCLEAR POWER SITES
ASME PV CODE 3 NE DIV 1 : 2017 BOILER AND PRESSURE VESSEL CODE - RULES FOR THE CONSTRUCTION OF NUCLEAR FACILITY COMPONENTS - CLASS MC COMPONENTS
ASME NQA 1 : 2015 Quality Assurance Requirements for Nuclear Facility Applications (NQA-1 - 2015)
ASME PV CODE 3 APP DIV 1 : 2017 BOILER AND PRESSURE VESSEL CODE - RULES FOR THE CONSTRUCTION OF NUCLEAR FACILITY COMPONENTS - APPENDICES
API 650 : 2013 WELDED TANKS FOR OIL STORAGE
ANS 56.7 : 78(R1987) VENTILATION SYSTEMS, BOILING WATER REACTOR CONTAINMENT
ASTM E 185 : 2016 : REDLINE Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
ANS 3.3 : 1988 SECURITY FOR NUCLEAR POWER PLANTS,
IEEE 352-1987 IEEE Guide for General Principles of Reliability Analysis of Nuclear Power Generating Station Safety Systems
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
ANS 56.2 : 84(R1989) NUCLEAR POWER PLANTS - CONTAINMENT ISOLATION PROVISIONS FOR FLUID SYSTEMS AFTER A LOCA
IEEE 338-2012 IEEE Standard for Criteria for the Periodic Surveillance Testing of Nuclear Power Generating Station Safety
IEEE 308-2012 REDLINE IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations
ASME PV CODE 3 NG DIV 1 : 2017 BOILER AND PRESSURE VESSEL CODE - RULES FOR THE CONSTRUCTION OF NUCLEAR FACILITY COMPONENTS - CORE SUPPORT STRUCTURES
AISC S326 : 1978 SPECIFICATION FOR THE DESIGN, FABRICATION AND ERECTION OF STRUCTURAL STEEL FOR BUILDINGS (WITH COMMENTARY)

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