ML19073A071: Difference between revisions
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
||
| Line 9: | Line 9: | ||
| docket = 05200048 | | docket = 05200048 | ||
| license number = | | license number = | ||
| contact person = Franovich R | | contact person = Franovich R | ||
| document type = Safety Evaluation Report | | document type = Safety Evaluation Report | ||
| page count = 71 | | page count = 71 | ||
Revision as of 11:28, 12 June 2019
| ML19073A071 | |
| Person / Time | |
|---|---|
| Site: | NuScale |
| Issue date: | 04/19/2019 |
| From: | Rani Franovich NRC/NRO/DLSE/LB1 |
| To: | |
| Franovich R | |
| References | |
| Download: ML19073A071 (71) | |
Text
Code of Regulations
Federal Register
Uses and Application of the Probabilistic Risk Assessment Quality of the Probabilistic Risk Assessment
Special Design/Operational Features
Level 1 Internal Events Probabilistic Risk Assessment for Operations at Power 19.1.4.4.1 Initiating Event Analysis
19.1.4.4.2 Success Criteria
19.1.4.4.3 Passive System Uncertainty
19.1.4.4.4 Accident Sequence Analysis
19.1.4.4.5 Systems Analysis
19.1.4.4.6 Human Reliability Analysis
19.1.4.4.7 Data Analysis
19.1.4.4.8 Quantification and Risk Insights
19.1.4.4.9 Conclusion Level 2 Internal Events Probabilistic Risk Assessment for Operations at Power
19.1.4.5.1 Methodology 19.1.4.5.2 Severe Accident Process and Phenomena
19.1.4.5.3 Level 2 Success Criteria
19.1.4.5.4 Containment Event Tree Analysis
19.1.4.5.5 Large Release Frequency and Conditional Containment Failure Probability
19.1.4.5.6 Importance Analysis 19.1.4.5.7 Key Sources of Uncertainty and Conclusion Level 1 Internal Events Probabilistic Risk Assessment for Low-Power Shutdown Operations 19.1.4.6.1 Plant Operating State Analysis
19.1.4.6.2 Initiating Event Analysis, Including Reactor Building Crane Failures
19.1.4.6.3 Success Criteria, Accident Sequence, and Systems Analyses
19.1.4.6.4 Human Reliability Analysis 19.1.4.6.5 Data Analysis
19.1.4.6.6 Quantification and Risk Insights
19.1.4.6.7 Conclusion Level 2 Internal Events Probabilistic Risk Assessment for Low-Power Shutdown Operations 19.1.4.7.1 Methodology
19.1.4.7.2 Quantification and Results
19.1.4.7.3 Conclusion External Events Probabilistic Risk Assessment for Operations at Power and Low-Power Shutdown
19.1.4.8.1 Seismic Risk Evaluation
19.1.4.8.2 Internal Fires Risk Evaluation
19.1.4.8.3 Internal Flooding Analysis
19.1.4.8.4 External Flooding Analysis
19.1.4.8.5 High-Winds Analysis
Evaluation of Multimodule Risk
Severe Accident Prevention
Severe Accident Mitigation 19.2.4.2.1 Scenario Selection for At-Power Accidents
19.2.4.2.2 Staff's Independent MELCOR Confirmatory Analysis
Containment Performance Capability 19.2.4.3.1 Deterministic Containment Performance
19.2.4.3.2 Probabilistic Containment Performance Accident Management Consideration of Potential Design Improvements
Federal RegisterFR Applicable Regulations Review Guidance Reasonably Formulated Assessment Design Features for Core Cooling
Key Design Features that Protect Core Cooling Design Features 19.5.3.3.1 Fire Barriers and Fire Protection Features 19.5.3.3.2 Reactor Building
19.5.3.3.3 Radwaste Building 19.5.3.3.4 Shock Damage Design Features for Maintaining an Intact Containment Spent Fuel Pool Integrity