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  • ASME PV CODE 3 NCA DIV 1&2 : 2017

    Superseded A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.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

    Available format(s):  Hardcopy

    Superseded date:  05-07-2019

    Language(s):  English

    Published date:  01-07-2017

    Publisher:  American Society of Mechanical Engineers

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    Table of Contents - (Show below) - (Hide below)

    List of Sections
    Foreword
    Statement of Policy on the Use of the Certification Mark and
     Code Authorization in Advertising
    Statement of Policy on the Use of ASME Marking to Identify
     Manufactured Items
    Submittal of Technical Inquiries to the Boiler and Pressure
     Vessel Standards Committees
    Personnel
    The American Concrete Institute
    Organization of Section III
    Summary of Changes
    List of Changes in Record Number Order
    Cross-Referencing and Stylistic Changes in the Boiler and
     Pressure Vessel Code
    Article NCA-1000 - Scope of Section III
    Article NCA-2000 - Classification of Components and Supports
    Article NCA-3000 - Responsibilities and Duties
    Article NCA-4000 - Quality Assurance Requirements
    Article NCA-5000 - Authorized Inspection
    Article NCA-7000 - Reference Standards
    Article NCA-8000 - Certificates, Nameplates, Certification Mark,
                       and Data Reports
    Article NCA-9000 - Glossary

    Abstract - (Show below) - (Hide below)

    The rules of this Section constitute requirements for the design, construction, stamping, and overpressure protection of items used in nuclear power plants and other nuclear facilities.

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

    Document Type Standard
    Publisher American Society of Mechanical Engineers
    Status Superseded
    Superseded By
    Supersedes

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

    BS IEC 63147 : 2017 CRITERIA FOR ACCIDENT MONITORING INSTRUMENTATION FOR NUCLEAR POWER GENERATING STATIONS
    IEEE 497 : 2010 CRITERIA FOR ACCIDENT MONITORING INSTRUMENTATION FOR NUCLEAR POWER GENERATING STATIONS
    ASME PV CODE 3 NH DIV 1 : 2015 BOILER AND PRESSURE VESSEL CODE - RULES FOR THE CONSTRUCTION OF NUCLEAR FACILITY COMPONENTS - CLASS 1 COMPONENTS IN ELEVATED TEMPERATURE SERVICE
    ASME PTB 8 : 2014 Procurement Guidelines for Metallic Materials (PTB-8 - 2014)
    API 941 REDLINE : 2008 STEELS FOR HYDROGEN SERVICE AT ELEVATED TEMPERATURES AND PRESSURES IN PETROLEUM REFINERIES AND PETROCHEMICAL PLANTS
    CSA N285.8 : 2015 TECHNICAL REQUIREMENTS FOR IN-SERVICE EVALUATION OF ZIRCONIUM ALLOY PRESSURE TUBES IN CANDU REACTORS
    BS 7910(2005) : 2005 GUIDE TO METHODS FOR ASSESSING THE ACCEPTABILITY OF FLAWS IN METALLIC STRUCTURES
    ASCE/SEI 4 16 : 2017 SEISMIC ANALYSIS OF SAFETY - RELATED NUCLEAR STRUCTURES
    ASTM A 358/A358M : 2015 : REDLINE Standard Specification for Electric-Fusion-Welded Austenitic Chromium-Nickel Stainless Steel Pipe for High-Temperature Service and General Applications
    ANS 52.1 : 83(R1988) NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY BOILING WATER REACTOR PLANTS
    B622-14 (R2019) Selection and use of highway tanks, TC portable tanks, and ton containers for the transportation of dangerous goods, Class 2
    NBR 11816 : 2003 STERILIZATION - VACUUM STEAM STERILIZERS FOR HEALTH PRODUCTS
    ASME OM S/G : 2007 Standards and Guides for Operation and Maintenance of Nuclear Power Plants (OM-S/G - 2007)
    IEC 63147:2017 Criteria for accident monitoring instrumentation for nuclear power generating stations
    ASME AG-1 : 2019 CODE ON NUCLEAR AIR AND GAS TREATMENT
    ASME AG 1 : 2012 CODE ON NUCLEAR AIR AND GAS TREATMENT
    B620-14 (R2019) Highway tanks and TC portable tanks for the transportation of dangerous goods
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