ASME RA-S : 2008
Superseded
A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.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
Hardcopy , PDF
29-12-2021
01-01-2008
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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Superseded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 |
| 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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