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Chapter 45
PRA and Risk-Informed Analysis

Excerpt

Chapter 45, authored by Sidney A. Bernsen, Fredric A. Simonen and Kenneth R. Balky, traces the development of nuclear power plant probabilistic risk assessment (PRA) from its initial evolution as a means for evaluation of public safety through the recognition of its use to identify important safety concerns and ultimately to its use in helping to determine risk importance and the appropriate allocation of resources, and inservice activities. It also discusses the current status of Codes and Standards that provide rules and guidance for the development of probabilistic risk analysis to support nuclear power plant applications. The chapter also addresses several specific activities in place or underway to risk inform Code requirements for inservice testing and Code design rules. The authors were all active participants in the development and implementation of risk informed methods for ASME Code and Standards.

  • 45.1 Introduction
  • 45.2 Background
  • 45.3 ASME PRA Standard (ASME RA-Sa-2003)
  • 45.4 ASME BPV Section XI Inservice Inspection
  • 45.5 ASME BPVC Section XI Repair and Replacement
  • 45.6 ASME Operation and Maintenance Code
  • 45.7 Regulatory and Industry Interactions
  • 45.8 Future Plans for Risk-Informed Activities
  • 45.9 Summary and Conclusions
  • 45.10 References

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