US-APWR Final Safety Evaluations
The following table provides access to Final Safety Evaluations that the NRC has issued in connection with its review of the DCD application that Mitsubishi Heavy Industries, Ltd. (MHI) submitted for the U.S. Advanced Pressurized-Water Reactor (US-APWR):
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| Chapter |
Description |
Date |
| 1 |
Introduction and General Description of the Plant |
TBD |
| 2 |
Site Characteristics |
TBD |
| 3 |
Design of Structures, Systems, Components, and Equipment |
TBD |
| 4 |
Reactor |
TBD |
| 5 |
Reactor Coolant and Connecting Systems |
TBD |
| 6 |
Engineered Safety Features |
TBD |
| 7 |
Instrumentation and Controls |
TBD |
| 8 |
Electric Power |
TBD |
| 9 |
Auxiliary Systems |
TBD |
| 10 |
Steam and Power Conversion System |
TBD |
| 11 |
Radioactive Waste Management |
TBD |
| 12 |
Radiation Protection |
TBD |
| 13 |
Conduct of Operations |
TBD |
| 14 |
Verification Programs |
TBD |
| 15 |
Transient and Accident Analyses |
TBD |
| 16 |
Technical Specifications |
TBD |
| 17 |
Quality Assurance and Reliability Assurance |
TBD |
| 18 |
Human Factors Engineering |
TBD |
| 19 |
Probabilistic Risk Assessment and Severe Accident Evaluation |
TBD |
