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Design Certification Renewal Application Review - ABWR GE-Hitachi Nuclear Energy

On July 13, 1994, the U.S. Nuclear Regulatory Commission (NRC) issued the final design approval (FDA), along with the "Final Safety Evaluation Report (FSER) related to certification of the Advanced Boiling Water Reactor Design" (NUREG-1503). On May 12, 1997, the NRC issued the final design certification rule (DCR) for the Advanced Boiling Water Reactor (ABWR) design in the Federal Register (62 FR 25800). Applicants or licensees intending to construct and operate a plant based on the ABWR design may do so by referencing its DCR, as set forth in Appendix A to Title 10, Part 52, of the Code of Federal Regulations (10 CFR Part 52, Appendix A). A DCR is valid for 15 years from the date of issuance under 10 CFR 52.55(a). A DCR may be renewed for a period of 10 to 15 years.

By letter dated December 7, 2010, GE-Hitachi Nuclear Energy submitted an application to renew the ABWR Design Certification (DC). The purpose of this renewal is to update the ABWR DC. For additional detail, see the following topics on this page:

Application Review Schedule

Key Milestones Completion Date
Actual - A
Target - T
Application
Received Design Certification Renewal Application
12/07/10 - A
 
Acceptance Review
NRC to issue Acceptance Review Determination Letter
02/14/11 - A

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Applicant Documents

The following table provides access to the documents submitted to support the U.S. Nuclear Regulatory Commission (NRC) staff's review of GE-Hitachi Nuclear Energy application to renew the ABWR DC.

Date Description
02/19/16 ABWR Standard Plant Design Certification Renewal Application Design Control Document, Revision 6, Tier 1 and Tier 2
02/19/16 GE-Hitachi ABWR Design Control Document Tier 1 & 2, Revision 6
03/17/14 GE Hitachi Nuclear Energy - United States Advanced Boiling Water Reactor ABWR) Design Certification Renewal Application - Submittal Date for ABWR DCD Revision 6
10/31/13 NRC Review of GE Hitachi Nuclear Energy - US Advanced Boiling Water Reactor Design Certification Renewal Application
12/07/10 GE-Hitachi ABWR Design Control Document Tier 1 & 2, Revision 5
12/07/10 Submittal of GE Hitachi, Application for Renewal of the Design Certification Rule for the U.S. Advanced Boling Water Reactor

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NRC Documents

This section lists documents in which the staff of the U.S. Nuclear Regulatory Commission (NRC) sent documents to GE-Hitachi Nuclear Energy in association with GE-Hitachi Nuclear Energy's application to renew the ABWR DCR.

Date Description
08/03/17 GE Hitachi Nuclear Energy - U. S. Advanced Boiling Water Reactor Design Certification Renewal Review Schedule
08/30/16 GE Hitachi Nuclear Energy - U. S. Advanced Boiling Water Reactor Design Certification Renewal Review Schedule
07/20/12 GE Hitachi Nuclear Energy - U.S. Advanced Boiling Water Reactor Design Certification Renewal Application
02/14/11 Acceptance Review In The GE-Hitachi Nuclear Energy Design Certification Renewal Application For The U.S. Advanced Boiling Water Reactor
01/19/11 Acknowledgment of Receipt of The Design Certification Renewal Application For The U.S. ABWR and Associated Federal Register Notice

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Requests for Additional Information

For all safety-related RAIs and the applicant's related responses, please refer to the eRAI Safety Report. Note that some RAIs and related responses may not be publicly available because they contain sensitive information.

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Safety Evaluations

The following table provides access to Safety Evaluations with no Open Items that the NRC has issued in conjunction with its review of the application submitted by GE-Hitachi Nuclear Energy to renew the ABWR DC.

Chapter Description Date
2 Site Characteristics
Section 2.3 "Meteorology"
06/20/18
Section 2.5 "Geological, Seismological, and Geotechnical Engineering"
06/12/17
Section 2.6.2 "Water Level (Flood) Design Site Parameters"
12/11/17
Section 2.6.8 "Requirements for Determination of ABWR Site Acceptability"
04/11/17
3 Design of Structures, Components, Equipment and Systems
Section 3.3 "Wind and Tornado Loadings"
06/20/18
Section 3.5.1.4 "Missiles Generated by Natural Phenomena"
06/20/18
Section 3.7.3 "Seismic Subsystem Analysis"
07/26/18
5 Reactor Coolant System and Connected Systems
Section 5.2.5 "Reactor Coolant Pressure Boundary Leakage Detection"
05/07/18
9 Auxiliary Systems
Section 9.1.1 "New Fuel Storage"
07/23/18
Section 9.1.4 "Light Load Handling System (Related to Refueling)"
07/23/18
Section 9.1.5 "Overhead Heavy Load Handling Systems"
07/23/18
Section 9.5.1 "Fire Protection"
03/08/18
11 Radioactive Waste Management
Section 11.4 "Solid Waste Management System"
06/12/17
12 Radiation Protection
Section 12.2 "Radiation Sources"
02/01/18
Section 12.3 "Radiation Protection Design Features"
04/11/17
13 Conduct Of Operations
Section 13.3 "Emergency Planning"
06/21/18
Section 13.5 "Plant Procedures"
07/02/18
14 Initial Test Program
Section 14.3.2.3.6 "Structural Task Group Review"
12/06/17
19 Severe Accidents
Section 19.2.3.3.4 "ABWR Containment Vent Design"
06/12/17

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Contacts

Contacts for the ABWR Design Certification Renewal
Lead Project Manager Adrian Muniz
Contact a Public Affairs Officer

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Page Last Reviewed/Updated Monday, August 13, 2018