以下の米国における歴史、実践例(テキストの第2, 3章)について輪講形式で実施する。
2. The History of United States Nuclear Regulation
2.1. Before the Reactor Safety Study (RSS) - From the 1960s to 1975
2.2. WASH-1400: The Reactor Safety Study (RSS) – 1975
2.3. From the Reactor Safety Study to the 1990s: The Establishment of PRA
2.4. From the 1990s: The Growth of PRA
3. Case Studies
3.1. South Texas Nuclear Project Electric Generating Plant Electric Generating Station (STP) - Diagnostic Evaluation
3.2. STP - Emergency Diesel Generator (EDG) Failure
3.3. The Emergence of Outage Risk Management
3.4. Outage Duration and Risk Management
3.5. Component Risk Significance and Notification
3.6. Operator Training Insights based on Best-Estimate Accident Analysis
3.7. Utilizing Insights from Operating Experience
3.8. Risk Information and Insights in Operational Decision Making
3.9. Transfer of Emergency Diesel Generator (EDG) Maintenance from Shutdown to On-Line
3.10. Insights from a Spent Fuel Pool (SFP) PRA
3.11. Reactor Trip Rates
3.12. Generation Risk Assessment
3.13. Building a Safety Culture
3.14. Risk Monitoring to Integrate Risk Thinking into Daily Plant Status
3.15. Communicating Risk Insights
3.16. Successful application of risk-informed in-service inspection of reactor coolant system piping
3.17. Risk-Managed Technical Specifications (RMTS)
3.18. Reactor Oversight Process (ROP)
3.19. Limited Success of Risk-Informed Graded Quality Assurance (RI-GQA) or Rule 10 CFR 50.69
3.20. Risk-Informed In-Service Testing