APR1400 Design Control Document and Environmental Report

This page provides access to the following documents, which Korea Electric Power Corporation (KEPCO) and Korea Hydro & Nuclear Power Co., Ltd. (KHNP), submitted to the U.S. Nuclear Regulatory Commission’s (NRC), in connection with its application for certification of the Advanced Power Reactor 1400 (APR1400), a 4,000-MWt pressurized-water reactor (PWR):

This page includes links to files in non-HTML format. See Plugins, Viewers, and Other Tools for more information.

Design Control Document

The applicant's design control document (DCD) provides information to support the NRC's approval and certification of the standard APR1400 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 that is approved and certified by the NRC. 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 APR1400 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.

Part Chapter Title Rev Date
    Submittal Letter   08/13/18
Tier 1 1-3 Tier 1 DCD for the APR1400 3 08/13/18
Tier 2 1 Introduction and General Description of the Plant 3 08/13/18
2 Site Characteristics 3 08/13/18
3 Design of Structures, Systems, Components, and Equipment 3 08/13/18
4 Reactor 3 08/13/18
5 Reactor Coolant and Connecting Systems 3 08/13/18
6 Engineered Safety Features 3 08/13/18
7 Instrumentation and Controls 3 08/13/18
8 Electric Power 3 08/13/18
9 Auxiliary Systems 3 08/13/18
10 Steam and Power Conversion System 3 08/13/18
11 Radioactive Waste Management 3 08/13/18
12 Radiation Protection 3 08/13/18
13 Conduct of Operations 3 08/13/18
14 Verification Programs 3 08/13/18
15 Transient and Accident Analyses 3 08/13/18
16 Technical Specifications 3 08/13/18
17 Quality Assurance and Reliability Assurance 3 08/13/18
18 Human Factors Engineering 3 08/13/18
19 Probabilistic Risk Assessment and Severe Accident Evaluation 3 08/13/18

To top of page

Environmental Report

This report provides an evaluation of severe accident mitigation design alternatives (SAMDAs) for the APR1400 design. The evaluation was performed to address the potential costs and benefits of SAMDAs for the APR1400 design. Consideration of SAMDAs included identifying a broad range of potential alternatives and then determining whether implementation of the alternative would be feasible and beneficial on a cost-risk reduction basis.

Date Description
08/13/18 APR1400-K-X-ER-14001-NP, Revision 2, "Applicant's Environmental Report - Standard Design Certification."

To top of page