US-APWR Design Control Document and Environmental Report
This page provides access to the following documents, which Mitsubishi Heavy Industries, Ltd. (MHI), submitted to the U.S. Nuclear Regulatory Commission’s (NRC), in connection with its application for certification of the U.S. Advanced Pressurized-Water Reactor (US-APWR) as a standard design for a 4,451-MWt pressurized-water reactor (PWR):
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Design Control Document
The applicant's design control document (DCD) provides information to support the NRC's approval and certification of the standard US-APWR design, under the provisions of Title 10, Part 52, of the Code of Federal Regulations (10 CFR Part 52), "Licenses, Certifications, and Approvals for Nuclear Power Plants." The DCD is divided into two parts (called "tiers"):
The Tier 1 material, which is derived from the more-detailed Tier 2 document, provides high-level information on the plant design. As such, it includes the principal performance characteristics and safety functions of the plant's structures, systems, and components (SSCs). It also includes inspections, tests, analyses, and acceptance criteria (ITAAC) to provide reasonable assurance that the as-built plant will operate in conformance with the combined license (COL), the provisions of the Atomic Energy Act, and applicable NRC regulations. In addition, the Tier 1 document identifies significant site parameters and requirements for significant interfaces between the standard US-APWR design and those aspects of the plant design that are site-specific.
The separate Tier 2 document provides more-detailed information on the plant design. This information is to be approved, but not certified, by the NRC.
|Revision 1 to Revision 2 Change List||3||03/31/11|
|Tier 1||1–3||Tier 1 DCD for the US-APWR||3||03/31/11|
|Tier 2||1||Introduction and General Description of the Plant||3||03/31/11|
|3||Design of Structures, Systems, Components, and Equipment||3||03/31/11|
|5||Reactor Coolant and Connecting Systems||3||03/31/11|
|6||Engineered Safety Features||3||03/31/11|
|7||Instrumentation and Controls||3||03/31/11|
|10||Steam and Power Conversion System||3||03/31/11|
|11||Radioactive Waste Management||3||03/31/11|
|13||Conduct of Operations||3||03/31/11|
|15||Transient and Accident Analyses||3||03/31/11|
|17||Quality Assurance and Reliability Assurance||3||03/31/11|
|18||Human Factors Engineering||3||03/31/11|
|19||Probabilistic Risk Assessment and Severe Accident Evaluation||3||03/31/11|
The applicant's environmental report presents an evaluation of severe accident mitigation design alternatives (SAMDA) for the US-APWR design. This evaluation addresses the costs and benefits of the SAMDA, as well as the bases for not incorporating the SAMDA in the US-APWR design.
|08/29/08||MUAP-DC021, Revision 1, "Applicant's Environmental Report - Standard Design Certification."|
|08/29/08||US-APWR ER Revision 0 to Revision 1 Change List|
|10/30/09||Mitsubishi Heavy Industries, Ltd - Submittal of Environmental Report Revision 2 in Support of the US-APWR Design Certification Application|
|10/31/09||Revision 2 to MUAP-DC021, "Applicant's Environmental Report - Standard Design Certification"|
|10/31/09||US-APWR Environmental Report - Revision 1 to Revision 2 Change List.|