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Title page 1

Contents 5

ABSTRACT 4

ABBREVIATIONS 8

1. INTRODUCTION 10

2. EARLY CONSIDERATIONS OF SEVERE ACCIDENTS 12

3. PROTECTION AGAINST SEVERE ACCIDENTS FOLLOWING THE TMI-2 ACCIDENT 14

3.1. Lessons Learned from the TMI-2 Accident 14

3.2. Hydrogen Rule 16

3.3. Emergency Planning and Preparedness 16

3.4. Source Term Reassessment 17

3.5. Safety Goal Policy Statement 18

3.6. Backfit Rule 19

3.7. Severe Accident Policy Statement 20

3.8. Integration Plan for Closure of Severe Accident Issues 20

3.8.1. Individual Plant Locations 20

3.8.2. Containment Performance Improvements 20

3.8.3. Improved Plant Operations 22

3.8.4. Severe Accident Research 22

3.8.5. External Events 23

3.8.6. Accident Management 23

3.9. Severe Accident Mitigation Alternatives 23

3.10. Severe Accident Requirements for New Reactors 24

3.11. Risk-Informed Regulations and Practices 25

4. POST-FUKUSHIMA SAFETY ENHANCEMENTS TO BETTER PREPARE AGAINST SEVERE ACCIDENTS 27

4.1. Lessons Learned from the Fukushima Dai-Ichi Events 27

4.2. Recommended Actions in Response to Fukushima Lessons Learned 31

4.3. Implementation of Lessons Learned from Fukushima 36

4.3.1. Mitigation Strategies Order, EA-12-049 36

4.3.2. Spent Fuel Pool Instrumentation Order, EA-12-051 36

4.3.3. Reliable Hardened Containment Vents for Boiling-Water Reactors with Mark I & II Designs (Orders EA-12-050 and EA-13-109) 37

4.3.4. Flooding and Seismic Hazard Walkdowns 37

4.3.5. Flooding Hazard Reevaluations 38

4.3.6. Seismic Hazard Reevaluations 38

4.4. The Risk Management Task Force 39

5. SEVERE ACCIDENT CONSIDERATIONS FOR ADVANCED REACTORS 40

5.1. Policy Statement on the Regulation of Advanced Reactors 40

5.2. Categorization of Event Sequences for Safety Evaluation Based on Probabilistic Risk Assessment 40

5.2.1. Preapplication Safety Evaluation of Modular High-Temperature Gas-Cooled Reactor and Power Reactor Innovative Small Modular Reactor Designs 40

5.2.2. Westinghouse Risk-Informed Safety Analysis Approach 42

5.2.3. Licensing-Basis Event Selection for the Pebble Bed Modular Reactor 42

5.2.4. Feasibility for a Risk-Informed and Performance-Based Regulatory Structure for Future Plant Licensing (NUREG-1860) 43

5.2.5. Next Generation Nuclear Plant Licensing Basis Event SelectionWhite Paper 45

5.2.6. Licensing Modernization Project Approach to Selecting Licensing Basis Events 45

5.3. Industry-Led Licensing Modernization Project 47

5.4. Rulemaking on a Risk-Informed, Technology-Inclusive Regulatory Framework for Advanced Reactors 47

6. SUMMARY AND CONCLUSIONS 50

7. REFERENCES 52

Figures 7

Figure 1. Comparison of Various Frequency-Based Categorizations of Event Sequences 41

Figure 2. The F-C Limit Curve from NUREG-1860 (NRC, 2007) 44

Figure 3. F-C Target Proposed for the LMP (Southern Company, 2019) 46

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