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ASME RA-S : 2008

Superseded
Superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

View Superseded by
superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

LEVEL 1/LARGE EARLY RELEASE FREQUENCY PROBABILISTIC RISK ASSESSMENT FOR NUCLEAR POWER PLANT APPLICATIONS
Amended by

ASME RA-S : 2008 : ERR 1

Available format(s)

Hardcopy , PDF

Superseded date

29-12-2021

Published date

01-01-2008

Publisher

American Society of Mechanical Engineers

Preview

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

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.

DevelopmentNote
Supersedes ANS 58.21 and ANS 58.23. (09/2010)
DocumentType
Standard
ISBN
9780791831403
Pages
1049
ProductNote
NEW CHILD ERR 1 IS NOW ADDED NEW CHILD ADD B IS NOW ADDED NEW CHILD ADD A IS NOW ADDED.
PublisherName
American Society of Mechanical Engineers
Status
Superseded
SupersededBy
Supersedes

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

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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Hardcopy - English
PDF - English - DRM
Hardcopy - English
PDF - English - DRM
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