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Federal Register / Vol. 86, No. 124 / Thursday, July 1, 2021 / Rules and Regulations
Chapters 1 through 22 and Volume 2
Appendices; 2 NUREG1503, Supplement 1, published in May 1997;
and 3 NUREG1503, Supplement 2, published in October 2020. NUREG
1503 and NUREG1503, Supplement 1, document the staffs review of the original certified DC.3 NUREG1503, Supplement 2, documents the NRC
staffs review of Revision 7 of the U.S.
ABWR DCD. The original final safety evaluation report and its supplements are available as indicated in Section XVI, Availability of Documents, in this document.
U.S. ABWR DC Renewal Rule The following discussion describes the purpose and key aspects of each section of the U.S. ABWR DC renewal rule. This rule is unique because it is the first DC renewal. In addition to the GEH
U.S. ABWR design certification, the current appendix A to 10 CFR part 52
includes discussions related to the U.S.
ABWR design certified for the STPNOC
acting together with Toshiba. As described in Section III, Background, of this document, the NRC has terminated the COLs that relied on the U.S. ABWR design certification rule as amended, and Toshiba has withdrawn its U.S. ABWR DC renewal application.
Therefore, the NRC believes that the best approach for this renewal is to completely replace appendix A to 10
CFR part 52 with this final rule certifying the renewed GEH U.S. ABWR
design. There is no discussion of the removal of STPNOC/Toshiba specific parts of the existing appendix A to 10
CFR part 52. The U.S. ABWR DC
renewal rule maintains the structure of existing DC rules, with certain modifications where necessary to account for differences in the U.S.
ABWR design documentation, design features, and environmental assessment including severe accident mitigation design alternatives. As a result, DC
rules are standardized to the extent practical.

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A. Introduction Section I
The purpose of Section I of appendix A to 10 CFR part 52 is to identify the standard design approved by this U.S.
ABWR DC renewal final rule and the applicant for certification of the standard design. Identification of the DC
3 NUREG1948, Final Safety Evaluation Report Related to the Aircraft Impact Amendment to the U.S. Advanced Boiling Water Reactor ABWR
Design Certification, which documents the staff evaluation of the U.S. ABWR DC amendment to comply with requirements in 50.150, is inapplicable to this U.S. ABWR DC renewal rule because the renewal DCD, Revision 7, incorporates a different set of changes to comply with the requirements in 50.150 and 52.59.

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applicant is necessary to implement appendix A to 10 CFR part 52 for two reasons. First, 52.63c identifies the DC applicant as a potential source for an applicant for a COL to obtain the generic DCD and supporting design information.
If the COL applicant does not obtain the design information from the DC
applicant, but instead uses a different entity, then the COL applicant must meet the requirements in 52.73, Relationship to other subparts.
Second, paragraph X.A.1 of this final rule requires that the identified DC
applicant maintain the generic DCD
throughout the time that appendix A to 10 CFR part 52 may be referenced.
B. Definitions Section II
The purpose of Section II of appendix A to 10 CFR part 52 is to define specific terminology with respect to this final DC rule. During development of the first two DC rules, the NRC decided that there would be both generic master design control documents maintained by the NRC and the design certification applicant, as well as individual plantspecific DCDs maintained by each applicant or licensee that references a certified standard design. This distinction is necessary in order to specify the relevant plant-specific requirements to applicants and licensees referencing appendix A to 10
CFR part 52. In order to facilitate the maintenance of the master design control documents, the NRC requires that each application for a standard design certification be updated to include an electronic copy of the final version of the DCD. The final version is required to incorporate all amendments to the DCD submitted since the original application, as well as any changes directed by the NRC as a result of its review of the original DCD or as a result of any public input that the staff determined was valid. In the case of the U.S. ABWR DC renewal, there was no significant public participation in the staff review. This final version is the master DCD incorporated by reference in the design certification rule. The master DCD will be revised as needed to include generic changes to the version of the DCD that is approved in this design certification final rule. These changes would occur as the result of generic rulemaking by the NRC, under the change criteria in Section VIII of appendix A to 10 CFR part 52.
The NRC also requires each applicant and licensee referencing appendix A to 10 CFR part 52 to submit and maintain a plant-specific DCD as part of the COL
final safety analysis report. This plantspecific DCD must either include or incorporate by reference the information
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in the generic DCD. The plant-specific DCD would be updated as necessary to reflect the generic changes to the DCD
that the NRC may adopt through rulemaking, plant-specific departures from the generic DCD that the NRC
imposed on the licensee by order, and any plant-specific departures that the licensee chooses to make in accordance with the relevant processes in Section VIII. Therefore, the plant-specific DCD
functions similarly to an updated final safety analysis report because it provides the most complete and accurate information on a plants design basis for that part of the plant that would be within the scope of appendix A to 10 CFR part 52.
The NRC is treating the technical specifications in Chapter 16, Technical Specifications, of the generic DCD as a special category of information and designating them as generic technical specifications in order to facilitate the special treatment of this information under appendix A to 10 CFR part 52. A
COL applicant must submit plantspecific technical specifications that consist of the generic technical specifications, which may be modified as specified in paragraph VIII.C, and the remaining site-specific information needed to complete the technical specifications. The final safety analysis report that is required by 52.79, Contents of applications; technical information in final safety analysis report, will consist of the plant-specific DCD, the site-specific final safety analysis report, and the plant-specific technical specifications.
The terms Tier 1, Tier 2, and Tier 2
are defined, and the term COL action items COL license information is described in appendix A to 10 CFR part 52 because these concepts were not envisioned when 10 CFR part 52 was developed. The DC applicants and the NRC use these terms in implementing the two-tiered rule structure the DCD is divided into Tiers 1 and 2 to support the rule structure that was proposed by representatives of the nuclear industry after publication of 10 CFR part 52. The Commission approved the use of a twotiered rule structure in its staff requirements memorandum, dated February 15, 1991, on SECY90377, Requirements for Design Certification under 10 CFR part 52, dated November 8, 1990.
Tier 1 information means the portion of the design-related information contained in the generic DCD that is approved and certified by this appendix. Tier 2 information means the portion of the design-related information contained in the generic DCD that is approved but not certified
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