This page contains the most relevant IAEA Supporting Documents for Safety Assessment.

Click here for the full collection of IAEA Supporting Documents  

 

    
 

 INSAG Reports

 
  
  
Basic Safety Principles for Nuclear Power Plants-75-INSAG-3 Rev. 1 INSAG-12.pdf
  
Common Basis for Judging the Safety of Nuclear Power Plants Built to Earlier Standards-INSAG-8.pdf
  
Defence in Depth in Nuclear Safety-INSAG-10.pdf
  
NS Infrastructure for a National Nuclear Power programme Supported by the IAEA Fundamental Safety principles-INSAG-22.pdf
  
Probabilistic Safety Assessment-INSAG-6.pdf
  
Strengthening the Global Nuclear Safety Regime-INSAG-21.pdf
  
 
 

 Safety Assessment Safety Series

 
  
  
Accident Analysis for Nuclear Power Plants with Graphite moderated Boiling Water RBMK Reactors-SRS-43.pdf
  
Accident Analysis for Nuclear Power Plants with Modular High Temperature Gas Cooled Reactors-SRS-54.pdf
  
Accident Analysis for Nuclear Power Plants with Pressuized Heavy Water Reactors-SRS-29.pdf
  
Accident Analysis for Nuclear Power Plants with Pressurized Water Reactors-SRS-30.pdf
  
Accident Analysis for Nuclear Power Plants-SRS-23.pdf
  
Application of Configuration Management in Nuclear Power Plants-SRS-65.pdf
  
Approaches and Tools for Severe Accident Analysis for Nuclear Power Plants-SRS-56.pdf
  
Assessment of Defence in Depth for Nuclear Power Plants-SRS-46.pdf
  
Best Estimate Safety for Nuclear Power Plants - Uncertainty Evaluation-SRS-52.pdf
  
Implementation of Accident Management Programmes in Nuclear Power Plants-SRS-32.pdf
  
Proactive Management of Ageing for Nuclear Power Plants-SRS-62.pdf
  
Safe Long Term Operation of Nuclear Power Plants-SRS-57.pdf
  
 
 

 Safety Assessment TECDOC's

 
  
  
IAEA-TECDOC-1200 Application of Probalistic Safety Assessment (PSA) for Nuclear Power Plants.pdf
  
IAEA-TECDOC-1209 Risk Management - A Tool for Improving Nuclear Power Plants Performance.pdf
  
IAEA-TECDOC-1267 Procedures for Conducting Probabilistic Safety Assessment for Non-Reactor Nuclear Facilities.pdf
  
IAEA-TECDOC-1332 Safety Margins of Operating Reactors.pdf
  
IAEA-TECDOC-1351 Incorporation of Advanced Accident Analysis Methodology into Safety Analysis Reports.pdf
  
IAEA-TECDOC-1379 Use of Computational Fluid Dynamics Codes for Safety Analysis of Nuclear Reactor Systems.pdf
  
IAEA-TECDOC-1381 Analysis of Differences in Fuel Safety Criteria for WWER and Western PWR Nuclear Power Plants.pdf
  
IAEA-TECDOC-1395 Intercomparison and Validation of Computer Codes for Thermalhydraulic Safety Analysis of PHWR.pdf
  
IAEA-TECDOC-1417 Precursor Analysis - The Use of DSA and PSA Based Methods in the Event Investigation Process at NPPs.pdf
  
IAEA-TECDOC-1418 Implication of Power Uprates on Safety Margins of Nuclear Power Plants.pdf
  
IAEA-TECDOC-1421 Experience Gained from Fires in Nuclear Power Plants - Lessons Learned.pdf
  
IAEA-TECDOC-1436 Risk Informed Regulation of Nuclear Facilities - Overview of the Current Status.pdf
  
IAEA-TECDOC-1440 Overview of Training Methodology for Accident Management at Nuclear Power Plants.pdf
  
IAEA-TECDOC-1470 Assessment and Management of Ageing of Major NPP Components Important to Safety-BWR pressure Vessels.pdf
  
IAEA-TECDOC-1471 Assessment and Management of Ageing of Major NPP Components Important to Safety-BWR PV Internals.pdf
  
IAEA-TECDOC-1477 Trending of Low Level Events and Near Misses to Enhance Safety Performance in Nuclear Power Plants.pdf
  
IAEA-TECDOC-1511 Determining the Quality of Probabilistic Safety Assessment (PSA) for Applications in Nuclear Power Plants.pdf
  
IAEA-TECDOC-1539 Use and Development of Coupled Computer Codes for the Analysis of Accidents at Nuclear Power Plants.pdf
  
IAEA-TECDOC-1550 Deterministic Analysis of Operational Events in Nuclear Power Plants.pdf
  
IAEA-TECDOC-1554 Generic Safety Issues for NPP with PHWR and Measures for their Resolution.pdf
  
IAEA-TECDOC-1555 Managing the First Nuclear Power Plant Project.pdf
  
IAEA-TECDOC-1556 Assessment and Management of Ageing of Major NPP Components Important to Safety - PWR Pressure Vessels.pdf
  
IAEA-TECDOC-1557 Assessment and Management of Ageing of Major NPP Components Important to Safety - PWR Vessel Internals.pdf
  
IAEA-TECDOC-1570 Proposal for a Technology-Neutral Safety Approach for New Reactor Designs.pdf
  
IAEA-TECDOC-1578 Comput. Analysis of the Behaviour of Nuclear Fuel  Steady State, Transient and Accident Conditions.pdf
  
IAEA-TECDOC-1584 Advanced Applications of Water Cooled Nuclear Power Plants.pdf
  
IAEA-TECDOC-1594 Analysis of Severe Accident in Pressurized Heavy Water Reactors.pdf
  
IAEA-TECDOC-1610 Safety Analysis of WWER-440 NPP - Potential Consequences of a Large Primary to Secondary LOCA.pdf
  
IAEA-TECDOC-1643 Periodic Safety Review of Nuclear Power Plants - Experience of Member States.pdf
  
IAEA-TECDOC-1661 Mitigation of Hydrogen Hazards in Severe Accidents in Nuclear Power Plants.pdf