Supplemental Reports Related to the US-APWR Design Certification Application
This page provides access to the following documents, which Mitsubishi Heavy Industries, Ltd. (MHI), submitted to the U.S. Nuclear Regulatory Commission's (NRC), to supplement its design certification application for the U.S. Advanced Pressurized-Water Reactor (US-APWR):
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Topical Reports
Note that the following topical reports relate specifically to the US-APWR design certification application. For a collection of similar safety-related reports with broader applicability to prospective NRC licensees, see Topical Reports.
Date |
Description |
03/31/08 |
FINDS: Mitsubishi Fuel Assemblies Seismic Analysis Code
|
07/20/07 |
Large Break LOCA Code Applicability Report for US-APWR
|
07/20/07 |
Large Mass and Energy Release Analysis Code Applicability Report for US-APWR
|
07/20/07 |
Small Break LOCA Methodology for US-APWR
|
07/20/07 |
Non-LOCA Methodology
|
05/25/07 |
Thermal Design Methodology
|
05/25/07 |
Fuel Design Criteria and Methodology
|
04/10/07
07/03/07 |
Defense in Depth and Diversity
|
04/10/07
07/03/07 |
Human System Interface (HSI) System Description and Human Factors Engineering (HFE) Process
|
03/02/07
07/03/07 |
Safety System Digital Platform - MELTAC
|
03/02/07
07/03/07 |
Safety I&C System Description and Design Process
|
03/02/07 |
Revised Version of US-APWR Advanced Accumulator Topical Report
|
01/26/07 |
US-APWR Advanced Accumulator Topical Report
|
01/23/07
10/15/07 |
Submittal of Quality Assurance Program (QAP) Description for Design Certification of the Mitsubishi Heavy Industries, LTD. US-APWR
Submittal of Revised Quality Assurance Program (QAP) Description for Design Certification of the Mitsubishi Heavy Industries, LTD. US-APWR
|
Technical Reports
Date |
Description |
04/25/08 |
Dynamic Analysis of the Coupled RCL-R/B-PCCV-CIS Lumped Mass Stick |
02/29/08 |
US-APWR Fuel System Design |
02/29/08 |
Subcompartment Analyses for US-APWR Design Confirmation |
02/29/08 |
Enhanced Information for PS/B Design |
02/27/08 |
US-APWR Sump Strainer Performance |
02/27/08 |
Criticality Analysis for US-APWR New and Spent Fuel Storage Racks |
12/31/07 |
Comprehensive Vibration Assessment Program for US-APWR Reactor Internals |
12/31/07 |
Defense-in-Depth and Diversity Coping Analysis |
12/31/07 |
FMEA of Control Rod Drive Mechanism Control System |
12/31/07 |
US-APWR Incore Power Distribution Evaluation Methodology |
12/31/07 |
Justification for Deviations between NUREG-1431 Rev. 3.1 and US-APWR Technical Specifications |
12/31/07 |
Validation of the MHI Criticality Safety Methodology |
12/31/07 |
Probability of Missile Generation from Low Pressure Turbines |
12/31/07 |
Qualification of Nuclear Design Methodology using PARAGON/ANC |
12/31/07 |
Structural Analysis for US-APWR Reactor Coolant Pump Motor Flywheel |
12/31/07 |
Mitsubishi Reload Evaluation Methodology |
12/31/07 |
APWR Reactor Internals 1/5 Scale Model Flow Test Report |
12/31/07 |
US-APWR Technical Report Software Program Manual |
12/31/07 |
Probabilistic Evaluation of Turbine Valve Test Frequency |
12/31/07 |
Small Break LOCA Sensitivity Analyses for US-APWR |
12/31/07 |
US-APWR Fuel System Design Parameters |
12/05/07 |
Qualification and Test Plan of Class 1E Gas Turbine Generator System |
11/01/07 |
Common Cause Failure Potential for Safety System Digital Platform |