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    ASME RA-S : 2008

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    Superseded A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.
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    LEVEL 1/LARGE EARLY RELEASE FREQUENCY PROBABILISTIC RISK ASSESSMENT FOR NUCLEAR POWER PLANT APPLICATIONS

    Available format(s):  Hardcopy, PDF

    Superseded date:  29-12-2021

    Language(s): 

    Published date:  01-01-2008

    Publisher:  American Society of Mechanical Engineers

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

    Foreword
    Preparation of Technical Inquires to the Committee
    on Nuclear Risk Management
    Committee Roster
    Preface
    PART 1 - GENERAL REQUIREMENTS FOR A
             LEVEL 1 PRA, INCLUDING LARGE
             EARLY RELEASE FREQUENCY
    PART 2 - REQUIREMENTS FOR INTERNAL-EVENTS
             AT-POWER PRA
    PART 3 - REQUIREMENTS FOR INTERNAL FLOOD
             AT-POWER PRA
    PART 4 - REQUIREMENTS FOR INTERNAL FIRES
             AT-POWER PRA
    PART 5 - REQUIREMENTS FOR SEISMIC EVENTS
             AT-POWER PRA
    PART 6 - REQUIREMENTS FOR SCREENING AND
             CONSERVATIVE ANALYSIS OF
             OTHER HAZARDS AT-POWER
    PART 7 - REQUIREMENTS FOR HIGH-WIND
             EVENTS\AT-POWER PRA
    PART 8 - REQUIREMENTS FOR EXTERNAL FLOOD
             EVENTS AT-POWER PRA
    PART 9 - REQUIREMENTS FOR OTHER HAZARDS
             AT-POWER PRA
    PART 10 - SEISMIC MARGIN ASSESSMENT
              REQUIREMENTS AT-POWER

    Abstract - (Show below) - (Hide below)

    Specifies requirements for probabilistic risk assessments (PRAs) used to support risk-informed decisions for commercial nuclear power plants, and describes a method for applying these requirements for specific applications.

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

    Development Note Supersedes ANS 58.21 and ANS 58.23. (09/2010)
    Document Type Standard
    Product Note NEW CHILD ERR 1 IS NOW ADDED NEW CHILD ADD B IS NOW ADDED NEW CHILD ADD A IS NOW ADDED.
    Publisher American Society of Mechanical Engineers
    Status Superseded
    Superseded By
    Supersedes

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

    IEEE 338-2012 IEEE Standard for Criteria for the Periodic Surveillance Testing of Nuclear Power Generating Station Safety
    NFPA 806 : 2015 PERFORMANCE-BASED STANDARD FOR FIRE PROTECTION FOR ADVANCED NUCLEAR REACTOR ELECTRIC GENERATING PLANTS CHANGE PROCESS
    VDI 4003:2007-03 Reliability management
    CSA N289.1 : 2008 : INC : UPD 1 : 2014: R201300 GENERAL REQUIREMENTS FOR SEISMIC DESIGN AND QUALIFICATION OF CANDU NUCLEAR POWER PLANTS
    CSA N289.1 : 2008 GENERAL REQUIREMENTS FOR SEISMIC DESIGN AND QUALIFICATION OF CANDU NUCLEAR POWER PLANTS
    N289.1-08 (R2013) General requirements for seismic design and qualification of CANDU nuclear power plants
    CSA N289.1 : 2008 : INC : UPD 1 : 2015 : R201300 GENERAL REQUIREMENTS FOR SEISMIC DESIGN AND QUALIFICATION OF CANDU NUCLEAR POWER PLANTS
    N290.17-17 Probabilistic safety assessment for nuclear power plants
    IEC 62502:2010 Analysis techniques for dependability - Event tree analysis (ETA)
    BS EN 62502:2011 Analysis techniques for dependability. Event tree analysis (ETA)
    ANS/ASME 58.22 : DRAFT 2014 REQUIREMENTS FOR LOW POWER AND SHUTDOWN PROBABILISTIC RISK ASSESSMENT
    ACI 349.3R : 2018 REPORT ON EVALUATION AND REPAIR OF EXISTING NUCLEAR SAFETY-RELATED CONCRETE STRUCTURES
    IEEE 577-2012 IEEE Standard Requirements for Reliability Analysis in the Design and Operation of Safety Systems for Nuclear Power Generating Stations
    ASME PV CODE 11 : 2017 BOILER AND PRESSURE VESSEL CODE - RULES FOR INSERVICE INSPECTION OF NUCLEAR POWER PLANT COMPONENTS
    ASME/ANS RA-S-1.2 : DRAFT 2014 SEVERE ACCIDENT PROGRESSION AND RADIOLOGICAL RELEASE (LEVEL 2) PRA STANDARD FOR NUCLEAR POWER PLANT APPLICATIONS FOR LIGHT WATER REACTORS (LWRS)
    ASME STP-NU-001 : 2005 RISK INITIATIVES IN ASME NUCLEAR CODES AND STANDARDS
    IEEE 933-2013 REDLINE IEEE Guide for the Definition of Reliability Program Plans for Nuclear Generating Stations and Other Nuclear Facilities

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

    ANS 2.27 : 2008(R2016) CRITERIA FOR INVESTIGATIONS OF NUCLEAR FACILITY SITES FOR SEISMIC HAZARD ASSESSMENTS
    ASME CODE CASE NC : 2017 CODE CASES: NUCLEAR COMPONENTS
    NFPA 805 : 2015 PERFORMANCE-BASED STANDARD FOR FIRE PROTECTION FOR LIGHT WATER REACTOR ELECTRIC GENERATING PLANTS
    ANS 58.21 : 2007 EXTERNAL EVENTS IN PRA METHODOLOGY
    ANS 2.29 : 2008(R2016) PROBABILISTIC SEISMIC HAZARD ANALYSIS
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