We noticed you’re not on the correct regional site. Switch to our AMERICAS site for the best experience.
  • ANS 52.1 : 83(R1988)

    Cancelled Standard has been cancelled.
    Add to Watchlist
    This Standard has been added successfully to your Watchlist.
    Please visit My Watchlist to see all standards that you are watching.
    Please log in or to add this standard to your Watchlist.
    We could not add this standard to your Watchlist.
    Please retry or contact support for assistance.
    You need to be logged in to add this standard to your Watchlist.
    Please log in now or create an account to add.
    You already added this Product in the Watchlist.

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

    Available format(s): 

    Cancelled date:  23-07-2013

    Language(s): 

    Published date:  12-01-2013

    Publisher:  American Nuclear Society

    Add to Watchlist

    Sorry this product is not available in your region.

    Add To Cart

    Abstract - (Show below) - (Hide below)

    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.

    General Product Information - (Show below) - (Hide below)

    Document Type Standard
    Publisher American Nuclear Society
    Status Cancelled

    Standards Referenced By This Book - (Show below) - (Hide below)

    ANS 55.6 : 1993(R2007) LIQUID RADIOACTIVE WASTE PROCESSING SYSTEM FOR LIGHT WATER REACTOR PLANTS
    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 58.8 : 1994(R2017) TIME RESPONSE DESIGN CRITERIA FOR SAFETY-RELATED OPERATOR ACTIONS
    IEEE 627 : 2010 QUALIFICATION OF EQUIPMENT USED IN NUCLEAR FACILITIES
    ANS 57.1 : 1992(R2015) DESIGN REQUIREMENTS FOR LIGHT WATER REACTOR FUEL HANDLING SYSTEMS
    ANS 56.5 : 79(R1987) PWR AND BWR CONTAINMENT SPRAY SYSTEM DESIGN CRITERIA
    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 55.4 : 1993(R2007) GASEOUS RADIOACTIVE WASTE PROCESSING SYSTEMS FOR LIGHT WATER REACTOR PLANTS
    ANS 57.2 : 1983 LIGHT WATER REACTOR SPENT FUEL STORAGE FACILITIES, REQUIREMENTS FOR,
    ASME QME 1 : 2017 QUALIFICATION OF ACTIVE MECHANICAL EQUIPMENT USED IN NUCLEAR FACILITIES
    ANS 59.3 : 1992(R2002) NUCLEAR SAFETY CRITERIA FOR CONTROL AIR SYSTEMS
    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
    ISA 67.01 : 1994 TRANSDUCER AND TRANSMITTER INSTALLATION FOR NUCLEAR SAFETY APPLICATIONS
    ANS 59.51 : 1997(R2015) FUEL OIL SYSTEMS FOR SAFETY-RELATED EMERGENCY DIESEL GENERATORS
    ANS 56.4 : 83(R1988) PRESSURE AND TEMPERATURE TRANSIENT ANALYSIS FOR LIGHT WATER REACTOR CONTAINMENTS
    ANS 58.11 : 1995(R2002) DESIGN CRITERIA FOR SAFE SHUTDOWN FOLLOWING SELECTED DESIGN BASIS EVENTS IN LIGHT WATER REACTORS
    IEEE 352 : 1987 GENERAL PRINCIPLES OF RELIABILITY ANALYSIS OF NUCLEAR POWER GENERATING STATION SYSTEMS AND OTHER NUCLEAR FACILITIES
    IEEE 7-4.3.2:2016 STANDARD CRITERIA FOR DIGITAL COMPUTERS IN SAFETY SYSTEMS OF NUCLEAR POWER GENERATING STATIONS

    Standards Referencing This Book - (Show below) - (Hide below)

    ANS 59.1 : 1986 COOLING WATER SYSTEMS FOR LIGHT WATER REACTORS, NUCLEAR SAFETY RELATED,
    ACI 301 : 2016 SPECIFICATIONS FOR STRUCTURAL CONCRETE
    IEEE 577 : 2012 REQUIREMENTS FOR RELIABILITY ANALYSIS IN THE DESIGN AND OPERATION OF SAFETY SYSTEMS FOR NUCLEAR POWER GENERATING STATIONS
    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
    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 59.4 : 1979 GENERIC REQUIREMENTS FOR LIGHT WATER NUCLEAR POWER PLANT FIRE PROTECTION
    ASME PV CODE 3 NE DIV 1 : 2017 BOILER AND PRESSURE VESSEL CODE - RULES FOR THE CONSTRUCTION OF NUCLEAR FACILITY COMPONENTS - CLASS MC 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
    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 QUALIFYING ELECTRIC CABLES AND SPLICES FOR NUCLEAR FACILITIES
    ASME PV CODE 3 APP DIV 1 : 2017 BOILER AND PRESSURE VESSEL CODE - RULES FOR THE CONSTRUCTION OF NUCLEAR FACILITY COMPONENTS - APPENDICES
    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,
    ASME PV CODE 3 NF DIV 1 : 2017 BOILER AND PRESSURE VESSEL CODE - RULES FOR THE CONSTRUCTION OF NUCLEAR FACILITY COMPONENTS - SUPPORTS
    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
    IEEE 344 : 2013 SEISMIC QUALIFICATION OF EQUIPMENT FOR NUCLEAR POWER GENERATING STATIONS
    ANS 55.4 : 1993(R2007) GASEOUS RADIOACTIVE WASTE PROCESSING SYSTEMS FOR LIGHT WATER REACTOR PLANTS
    ANS 2.13 : 79(R1988) EVALUATION OF SURFACE-WATER SUPPLIES FOR NUCLEAR POWER SITES
    ANS 55.6 : 1993(R2007) LIQUID RADIOACTIVE WASTE PROCESSING SYSTEM FOR LIGHT WATER REACTOR PLANTS
    ASME PV CODE 3 NG DIV 1 : 2017 BOILER AND PRESSURE VESSEL CODE - RULES FOR THE CONSTRUCTION OF NUCLEAR FACILITY COMPONENTS - CORE SUPPORT STRUCTURES
    ANS 2.8 : 1992 DETERMINING DESIGN BASIS FLOODING AT POWER REACTOR SITES
    ASME PV CODE 3 NC DIV 1 : 2017 BOILER AND PRESSURE VESSEL CODE - RULES FOR THE CONSTRUCTION OF NUCLEAR FACILITY COMPONENTS - CLASS 2 COMPONENTS
    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 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
    ASME NQA 1 : 2015 Quality Assurance Requirements for Nuclear Facility Applications (NQA-1 - 2015)
    IEEE 450 : 2010 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
    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 58.9 : 2002(R2015) SINGLE FAILURE CRITERIA FOR LWR SAFETY-RELATED FLUID SYSTEMS
    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 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
    ANS 2.9 : 80(R1989) EVALUATION OF GROUND WATER SUPPLY FOR NUCLEAR POWER SITES
    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 GENERAL PRINCIPLES OF RELIABILITY ANALYSIS OF NUCLEAR POWER GENERATING STATION SYSTEMS AND OTHER NUCLEAR FACILITIES
    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
    ASME PV CODE 11 : 2017 BOILER AND PRESSURE VESSEL CODE - RULES FOR INSERVICE INSPECTION OF NUCLEAR POWER PLANT COMPONENTS
    IEEE 338 : 2012 CRITERIA FOR THE PERIODIC SURVEILLANCE TESTING OF NUCLEAR POWER GENERATING STATION SAFETY SYSTEMS
    IEEE 308 : 2012 STANDARD CRITERIA FOR CLASS 1E POWER SYSTEMS FOR NUCLEAR POWER GENERATING STATIONS
    AISC S326 : 1978 SPECIFICATION FOR THE DESIGN, FABRICATION AND ERECTION OF STRUCTURAL STEEL FOR BUILDINGS (WITH COMMENTARY)
    • Access your standards online with a subscription

      Features

      • Simple online access to standards, technical information and regulations
      • Critical updates of standards and customisable alerts and notifications
      • Multi - user online standards collection: secure, flexibile and cost effective