[Federal Register Volume 86, Number 124 (Thursday, July 1, 2021)]
[Proposed Rules]
[Pages 35023-35027]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2021-13802]


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NUCLEAR REGULATORY COMMISSION

10 CFR Part 52

[NRC-2017-0090]
RIN 3150-AK04


Advanced Boiling Water Reactor (ABWR) Design Certification 
Renewal

AGENCY: Nuclear Regulatory Commission.

ACTION: Proposed rule and environmental assessment.

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SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is proposing to 
amend its regulations to renew the U.S. Advanced Boiling Water Reactor 
standard design certification. Applicants or licensees intending to 
construct and operate a U.S. Advanced Boiling Water Reactor standard 
design may do so by referencing this design certification rule. The 
applicant for the renewal of the U.S. Advanced Boiling Water Reactor 
standard design certification is General Electric-Hitachi Nuclear 
Energy Americas, LLC. The NRC invites public comment on this proposed 
rule and environmental assessment.

DATES: Submit comments by August 2, 2021. Comments received after this 
date will be considered if it is practical to do so, but the NRC is 
able to ensure consideration only for comments received on or before 
this date.

ADDRESSES: You may submit comments by any of the following methods 
(unless this document describes a different method for submitting 
comments on a specific subject):
     Federal Rulemaking Website: Go to https://www.regulations.gov and search for Docket ID NRC-2017-0090. Address 
questions about NRC dockets to Dawn Forder; telephone: 301-415-3407; 
email: [email protected]. For technical questions contact the 
individuals listed in the FOR FURTHER INFORMATION CONTACT section of 
this document.
     Email comments to: [email protected]. If you do 
not receive an automatic email reply confirming receipt, then contact 
us at 301-415-1677.
    For additional direction on obtaining information and submitting 
comments, see ``Obtaining Information and Submitting Comments'' in the 
SUPPLEMENTARY INFORMATION section of this document.

FOR FURTHER INFORMATION CONTACT: Dennis Andrukat, Office of Nuclear 
Material Safety and Safeguards, telephone: 301-415-3561, email: 
[email protected], or James Shea, Office of Nuclear Reactor 
Regulation, telephone: 301-415-1388, email: [email protected]. Both 
are staff of the U.S. Nuclear Regulatory Commission, Washington, DC 
20555-0001.

SUPPLEMENTARY INFORMATION:

Table of Contents

I. Obtaining Information and Submitting Comments
II. Rulemaking Procedure
III. Background
IV. Voluntary Consensus Standards
V. Plain Writing
VI. Environmental Assessment and Final Finding of No Significant 
Impact
VII. Paperwork Reduction Act Statement
VIII. Availability of Documents

I. Obtaining Information and Submitting Comments

A. Obtaining Information

    Please refer to Docket ID NRC-2017-0090 when contacting the NRC 
about the availability of information for this action. You may obtain 
publicly available information related to this action by any of the 
following methods:
     Federal Rulemaking Website: Go to https://www.regulations.gov and search for Docket ID NRC-2017-0090.
     NRC's Agencywide Documents Access and Management System 
(ADAMS): You may obtain publicly-available documents online in the 
ADAMS Public Documents collection at https://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``Begin Web-based ADAMS 
Search.'' For problems with ADAMS, please contact the NRC's Public 
Document Room (PDR) reference staff at 1-800-397-4209, at 301-415-4737, 
or by email to [email protected]. For the convenience of the reader, 
instructions about obtaining materials referenced in this document are 
provided in the Availability of Documents section.
     Attention: The Public Document Room (PDR), where you may 
examine and order copies of public documents is currently closed. You 
may submit your request to the PDR via email at [email protected] or 
call 1-800-397-4209 between 8:00 a.m. and 4:00 p.m. (EST), Monday 
through Friday, except Federal holidays.
     Attention: The Technical Library, which is located at Two 
White Flint North, 11545 Rockville Pike, Rockville, Maryland 20852, is 
open by appointment only. Interested parties may make appointments to 
examine documents by contacting the NRC Technical Library by email at 
[email protected] between 8:00 a.m. and 4:00 p.m. (EST), Monday 
through Friday, except Federal holidays.

B. Submitting Comments

    The NRC encourages electronic comment submission through the 
Federal Rulemaking Website (https://www.regulations.gov). Please 
include Docket ID NRC-2017-0090 in your comment submission.
    The NRC cautions you not to include identifying or contact 
information that you do not want to be publicly disclosed in your 
comment submission. The NRC will post all comment submissions at 
https://www.regulations.gov as well as enter the comment submissions 
into ADAMS. The NRC does not routinely edit comment submissions to 
remove identifying or contact information.
    If you are requesting or aggregating comments from other persons 
for submission to the NRC, then you should inform those persons not to 
include identifying or contact information that they do not want to be 
publicly disclosed in their comment submission. Your request should 
state that the NRC does not routinely edit comment submissions to 
remove such information before making the comment submissions available 
to the public or entering the comment into ADAMS.

II. Rulemaking Procedure

    Because the NRC anticipates that this action will be non-
controversial, the NRC is publishing this proposed rule concurrently 
with a direct final rule in the Rules and Regulations section of this 
issue of the Federal Register. The direct final rule will become 
effective on September 29, 2021. However, if the NRC receives 
significant adverse

[[Page 35024]]

comments on this proposed rule or environment assessment by August 2, 
2021, then the NRC will publish a document that withdraws the direct 
final rule. If the direct final rule is withdrawn, the NRC would 
address the comments received in response to these proposed revisions 
in any subsequent final rule. Absent significant modifications to the 
proposed revisions requiring republication, the NRC does not intend to 
initiate a second comment period on this action in the event the direct 
final rule is withdrawn.
    A significant adverse comment is a comment in which the commenter 
explains why the rule (including the environmental assessment) would be 
inappropriate, including challenges to the rule's underlying premise or 
approach, or would be ineffective or unacceptable without a change. A 
comment is adverse and significant if it meets the following criteria:
    (1) The comment opposes the rule and provides a reason sufficient 
to require a substantive response in a notice-and-comment process. For 
example, a substantive response is required when--
    (a) The comment causes the NRC to reevaluate (or reconsider) its 
position or conduct additional analysis;
    (b) The comment raises an issue serious enough to warrant a 
substantive response to clarify or complete the record; or
    (c) The comment raises a relevant issue that was not previously 
addressed or considered by the NRC.
    (2) The comment proposes a change or an addition to the rule, and 
it is apparent that the rule would be ineffective or unacceptable 
without incorporation of the change or addition.
    (3) The comment causes the NRC to make a change (other than 
editorial) to the rule.
    For additional information, including procedural information, see 
the direct final rule published in the Rules and Regulations section of 
this issue of the Federal Register.

III. Background

    The General Electric Company (GE) submitted the U.S. Advanced 
Boiling Water Reactor (U.S. ABWR) standard design certification initial 
application on September 29, 1987. The NRC initially docketed the 
application (Docket No. STN 50-605) on February 22, 1988, but later 
changed the docket number to 52-001 on March 20, 1992 (57 FR 9749) to 
reflect GE's request [or the applicant's request] to review the 
application under part 52, ``Licenses, Certifications, and Approvals 
for Nuclear Power Plants,'' of title 10 of the Code of Federal 
Regulations (10 CFR). The NRC documented its review in NUREG-1503, 
``Final Safety Evaluation Report Related to the Certification of the 
Advanced Boiling Water Reactor Design,'' in July 1994 (ADAMS Accession 
No. ML080670592), and NUREG-1503, Supplement 1, ``Final Safety 
Evaluation Report Related to the Certification of the Advanced Boiling 
Water Reactor Design,'' in May 1997 (ADAMS Accession No. ML080710134). 
The NRC issued the agency's first design certification (DC) rule, for 
the U.S. ABWR, in the Federal Register (62 FR 25800), effective June 
11, 1997. In 2007, GE and Hitachi Nuclear Energy formed an alliance, 
and General Electric-Hitachi Nuclear Energy Americas, LLC, (GEH) became 
the entity retaining the U.S. ABWR design from GE.
    On December 7, 2010, GEH submitted its application to renew the 
certification of the U.S. ABWR standard design to the NRC under subpart 
B, ``Standard design certifications,'' to 10 CFR part 52. The NRC 
published a notice of receipt of the application in the Federal 
Register on January 27, 2011 (76 FR 4948). On February 18, 2011, the 
NRC formally accepted the design certification renewal application for 
docketing (76 FR 9612). The preapplication information submitted before 
the NRC formally accepted the application for docketing can be found in 
ADAMS under Docket No. PROJ0774.
    Subpart B to 10 CFR part 52 presents the process for obtaining 
standard design certifications. Under Sec.  52.57(a), an application 
for DC renewal must contain all information necessary to bring the 
information and data contained in the previous application up to date. 
Updates under Sec.  52.57(a) include clarifications consistent with the 
original understanding of the design information, and changes to 
correct known errors, typographical errors, or defects, as defined in 
Sec.  21.3. For the NRC to issue a rule granting the DC renewal under 
Sec.  52.59(a), the design, either as originally certified or as 
modified during the rulemaking on renewal, must comply with (1) the 
Atomic Energy Act of 1954, as amended (AEA), (2) the NRC regulations 
applicable and in effect at the time the certification was issued, and 
(3) the applicable requirements of Sec.  50.150, ``Aircraft impact 
assessment.'' \1\
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    \1\ The requirement for modifications in DC renewals to address 
Sec.  50.150 was added to Sec.  52.59(a) by a rule published June 
12, 2009, requiring applicants for new nuclear power reactors to 
perform a design-specific assessment of the effects of the impact of 
a large, commercial aircraft (74 FR 28111). This requirement is 
applicable to the U.S. ABWR DC renewal because this is its first 
renewal and the U.S. ABWR DC was in effect on July 13, 2009.
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    A DC renewal applicant may propose to amend the design under Sec.  
52.59(c). An amendment is an applicant-proposed change that is not an 
update under Sec.  52.57(a) or a change to meet the renewal standards 
in Sec.  52.59(a). Amendments must comply with the AEA and the NRC's 
regulations applicable and in effect at the time of renewal rather than 
the Sec.  52.29(a) standards. If the amendment request entails such an 
extensive change to the certified design that an essentially new 
standard design is being proposed, a new DC application must be 
submitted.
    In addition, NRC regulations at Sec.  52.59(b) state that the 
Commission may impose other requirements if it determines any of the 
following:
    1. They are necessary for adequate protection to public health and 
safety or common defense and security;
    2. They are necessary for compliance with the NRC's regulations and 
orders applicable and in effect at the time the certification was 
issued; or
    3. There is a substantial increase in overall protection of the 
public health and safety or the common defense and security to be 
derived from the new requirements, and the direct and indirect costs of 
implementing those requirements are justified in view of this increased 
protection.
    The final U.S. ABWR DC rule for the original certification, 
Supplementary Information, Section II.A.1, ``Finality,'' stated that 
the NRC ``does not plan or expect to be able to conduct a de novo 
review of the entire design if a certification renewal application is 
filed under Sec.  52.59[,]'' ``Criteria for renewal'' (62 FR 25800, 
25805). Instead, the NRC stated that it expects that the focus of the 
review would be on changes to the design that are proposed by the 
applicant and insights from relevant operating experience with the 
certified design or other designs, or other material new information 
arising after the NRC staff's review of the design certification. 
Furthermore, the standards in Sec.  52.59(b) control the imposition of 
new requirements during the review of applications for renewal. When 
GEH applied to renew the U.S. ABWR DC, the NRC affirmed this position, 
reviewed only those aspects of the design that were amended or 
modified, and determined whether operating experience or other material 
new information indicated that additional changes to the design were 
necessary. The staff reviewed GEH's proposed amendments and 
modifications to the design; the staff did not impose changes under 10 
CFR 52.59(b).
    On June 12, 2009, the NRC published a rule requiring applicants for 
new

[[Page 35025]]

nuclear power reactors to perform a design-specific assessment of the 
effects of the impact of a large, commercial aircraft (74 FR 28111). By 
letter dated December 7, 2010, GEH submitted its application to renew 
the U.S. ABWR DC to the NRC, which included Revision 5 to the design 
control document. This revision includes a containment re-analysis 
amendment and the necessary changes to meet the requirements of Sec.  
50.150, ``Aircraft impact assessment.'' Revision 5 of the DCD also 
describes the aircraft impact assessment results and identifies and 
incorporates design features and functional capabilities to show, with 
reduced use of operator actions, that the reactor core remains cooled 
and spent fuel pool integrity is maintained.
    In a letter dated July 20, 2012, the NRC identified proposed 
changes that were regulatory improvements or that could meet the 
criteria in Sec.  52.59(b). The NRC suggested that GEH consider the 
recommendations contained in SECY-12-0025, ``Proposed Orders and 
Requests for Information in Response to Lessons Learned from Japan's 
March 11, 2011, Great Tohoku Earthquake and Tsunami,'' dated February 
17, 2012, addressing Recommendations 4.2, 7.1, and 9.3 from SECY-11-
0093, ``Near-Term Report and Recommendations for Agency Actions 
Following the Events in Japan,'' enclosure, ``Recommendations for 
Enhancing Reactor Safety in the 21st Century; The Near-Term Task Force 
Review of Insights from the Fukushima Dai-Ichi Accident report,'' dated 
July 12, 2011. Subsequently, during the Mitigation of Beyond-Design-
Basis Events rulemaking that resulted in Sec.  50.155, ``Mitigation of 
beyond-design-basis events,'' the Commission determined that it would 
be inappropriate to impose mitigation strategies requirements on 
DCs.\2\
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    \2\ In the Mitigation of Beyond-Design-Basis Events proposed 
rule regulatory analysis, dated October 2015, the Commission 
explained that its proposal to make the Mitigation of Beyond-Design-
Basis Events rule inapplicable to existing DCs, which included the 
U.S. ABWR, was based on concluding that ``[t]he issues that may be 
resolved in a DC and accorded issue finality may not include 
operational matters, such as the elements of the [Mitigation of 
Beyond-Design-Basis Events] proposed rule.'' However, as discussed 
in SECY-19-0066, ``Staff Review of NuScale Power's Mitigation 
Strategy for Beyond-Design-Basis External Events,'' the design 
certification can provide for finality under 10 CFR 52.63 and 
Section VI of appendix A to 10 CFR part 52 for the adequacy of the 
structures, systems, and components to perform their mitigation 
strategies functions, as analyzed in the final safety analysis 
report.
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    After the NRC's July 20, 2012, letter to GEH, the NRC issued 
several requests for additional information to identity additional 
items or clarify the items communicated in the 2012 letter. By letter 
dated February 19, 2016, GEH submitted DCD, Revision 6, to incorporate 
changes to the U.S. ABWR DCD made in response to NRC's 2012 letter and 
to the NRC's requests for additional information. In addition, this 
revision transmitted corrections of typographical errors that were 
identified during document development, and other required formatting 
changes. These corrections represent non-substantive changes that are 
editorial in nature. The NRC reviewed these typographical changes and 
determined that the changes do not affect the NRC's findings in the 
final safety evaluation report for original certification and are 
acceptable. On December 20, 2019, the applicant submitted DCD, Revision 
7, that incorporated the remaining changes provided in earlier 
responses to requests for additional information. The NRC reviewed DCD, 
Revision 7, against the changes proposed in responses to requests for 
additional information and noted that two short paragraphs were missing 
from Chapter 5. On March 16, 2020, the applicant resubmitted DCD, 
Revision 7, Chapter 5, including the previously missing paragraphs. To 
ensure that the public can reference a single ADAMS package for this 
document, the NRC copied the original DCD, Revision 7, ADAMS package, 
and replaced Chapter 5 with the corrected file. This corrected ADAMS 
package is the collection of DCD, Revision 7, chapters that the NRC has 
reviewed (ADAMS Accession No. ML20093K254). The NRC's review is 
documented in Supplement 2 to NUREG-1503, ``Final Safety Evaluation 
Report Related to the Certification of the Advanced Boiling Water 
Reactor Design'' (ADAMS Accession No. ML20301A886). This proposed rule 
would certify Revision 7 of the U.S. ABWR DCD as provided in ADAMS 
Accession No. ML20093K254.
    Separately, Toshiba Corporation Energy Systems and Solutions 
Company (Toshiba) sought renewal of the U.S. ABWR DC, incorporating the 
Toshiba-specific aircraft impact assessment amendment used in the 
STPNOC DCD. On June 9, 2016, Toshiba withdrew its renewal application 
for the U.S. ABWR DC. The Toshiba ABWR was to incorporate the Toshiba-
specific aircraft impact assessment amendment of the U.S. ABWR design 
certification, identified in the current appendix A to 10 CFR part 52 
as the South Texas Project Nuclear Operating Company (STPNOC) DCD. The 
original U.S. ABWR design certification has expired, along with its 
STPNOC DCD aircraft impact assessment amendment, and Toshiba has 
withdrawn its renewal U.S. ABWR DC application; therefore, Toshiba's 
STPNOC DCD with its Toshiba-specific aircraft impact assessment 
amendment is not considered to be in timely renewal as described in 
Sec.  52.57(b).
    On June 22, 2018, the only U.S. ABWR combined license (COL) holder, 
Nuclear Innovation North America LLC, requested NRC approval to 
withdraw the COLs for South Texas Project, Units 3 and 4. The NRC 
approved the termination of these COLs on July 12, 2018. Since the only 
COLs that referenced the Toshiba STPNOC DCD has been terminated, and no 
other license or application referencing the U.S. ABWR DC exists, the 
Toshiba STPNOC DCD no longer meets the requirement for validity beyond 
the date of expiration under Sec.  52.55(b). Finally, GEH has not 
requested to renew the STPNOC amendment. For all these reasons, the NRC 
is not retaining the original DCD or the STPNOC DCD option in Appendix 
A to 10 CFR part 52. Instead, the NRC is proposing to replace appendix 
A to 10 CFR part 52 with a rule certifying the renewed GEH U.S. ABWR 
design.

IV. Voluntary Consensus Standards

    The National Technology Transfer and Advancement Act of 1995, 
Public Law 104-113, requires that Federal agencies use technical 
standards that are developed or adopted by voluntary consensus 
standards bodies unless the use of such a standard is inconsistent with 
applicable law or otherwise impractical. In this proposed rule, the NRC 
intends to certify the renewal for the U.S. ABWR standard design for 
use in nuclear power plant licensing under 10 CFR part 50, ``Domestic 
licensing of production and utilization facilities,'' or part 52. 
Design certifications are not generic rulemakings establishing a 
generally applicable standard with which all 10 CFR parts 50 and 52 
nuclear power plant licensees must comply. Design certifications are 
Commission approvals of specific nuclear power plant designs by 
rulemaking. Furthermore, design certifications are initiated by an 
applicant for rulemaking, rather than by the NRC. This action does not 
constitute the establishment of a standard that contains generally 
applicable requirements.

V. Plain Writing

    The Plain Writing Act of 2010 (Pub. L. 111-274) requires Federal 
agencies to write documents in a clear, concise, and well-organized 
manner that also follows other best practices appropriate to the

[[Page 35026]]

subject or field and the intended audience. The NRC has written this 
document to be consistent with the Plain Writing Act as well as the 
Presidential Memorandum, ``Plain Language in Government Writing,'' 
published June 10, 1998 (63 FR 31883). The NRC requests comment on the 
proposed rule with respect to clarity and effectiveness of the language 
used.

VI. Environmental Assessment and Final Finding of No Significant Impact

    The NRC has determined under the National Environmental Policy Act 
of 1969, as amended (NEPA), and the NRC's regulations in subpart A of 
10 CFR part 51, that this proposed rule, if issued, would not be a 
major Federal action significantly affecting the quality of the human 
environment and, therefore, an environmental impact statement is not 
required. The Commission has determined in Sec.  51.32 that there is no 
significant environmental impact associated with the issuance of the 
standard design certification or its amendment, as applicable. This 
reflects the fact that a DC rule does not authorize the siting, 
construction, or operation of a facility referencing any particular 
design, but only codifies a standard design certification in a rule 
(the U.S. ABWR DC renewal in this case). The NRC will evaluate the 
environmental impacts and issue an environmental impact statement as 
appropriate under NEPA as part of the application for the construction 
and operation of a facility referencing a DC rule. Comments on the 
environmental assessment will be limited to the consideration of severe 
accident mitigation design alternatives as required by Sec.  51.30(d).

VII. Paperwork Reduction Act Statement

    This proposed rule does not contain any new or amended collections 
of information subject to the Paperwork Reduction Act of 1995 (44 
U.S.C. 3501 et seq.). Existing collections of information were approved 
by the Office of Management and Budget, control number 3150-0151.

Public Protection Notification

    The NRC may not conduct or sponsor, and a person is not required to 
respond to, a collection of information unless the document requesting 
or requiring the collection displays a currently valid OMB control 
number.

VIII. Availability of Documents

    The documents identified in the following table are available to 
interested persons through one or more of the following methods, as 
indicated.

    Documents Related to U.S. ABWR Design Certification Renewal Rule
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                                                 ADAMS Accession No./
                  Document                     Federal Register Citation
------------------------------------------------------------------------
SECY-20-0112, ``Direct Final Rule-Advanced    ML20170A520
 Boiling Water Reactor Design Certification
 Renewal (RIN 3150-AK04; NRC-2017-0090),''
 December 9, 2020.
GE-Hitachi ABWR Design Control Document Tier  ML20093K254
 1 & 2, Revision 7, October 2019 (includes
 correction noted, as of March 2020).
GE-Hitachi Nuclear Energy, Transmittal of     ML110040176
 ABWR Standard Plant Design Certification
 Renewal Application Design Control
 Document, Revision 5, Tier 1 and Tier 2,
 December 7, 2010.
GE-Hitachi ABWR Design Control Document Tier  ML110040323
 1 & 2, Revision 5, December 7, 2010.
Technical Report NEDO-33875, ABWR U.S.        ML17059C523
 Certified Design--Aircraft Impact
 Assessment, Licensing Basis Information and
 Design Details for Key Design Features,
 Rev. 3 (M170049), February 2017.
Licensing Technical Report NEDO-33878, ABWR   ML18092A306
 ECCS Suction Strainer Evaluation of Long-
 Term Recirculation Capability, Rev. 3
 (M180068), March 2018.
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             Final Safety Evaluation Report and Supplements
------------------------------------------------------------------------
NUREG-1503, Supplement 2, ``Final Safety      ML20301A886
 Evaluation Report Related to the
 Certification of the Advanced Boiling Water
 Reactor Design,'' October 2020.
NUREG-1503, Supplement 1, ``Final Safety      ML080710134
 Evaluation Report Related to the
 Certification of the Advanced Boiling Water
 Reactor Design,'' May 1997.
NUREG-1503, Vols. 1-2, ``Final Safety         ML080670592
 Evaluation Report Related to the
 Certification of the Advanced Boiling Water
 Reactor Design,'' July 1994.
------------------------------------------------------------------------
                          Environmental Review
------------------------------------------------------------------------
Environmental Assessment by the U.S. Nuclear  ML21147A381
 Regulatory Commission Relating to Renewal
 of the Certification of the ABWR Standard
 Design, June 2021.
Staff Technical Analysis in Support of the    ML20024D602
 Advanced Boiling Water Reactor Design
 Certification Renewal Environmental
 Assessment.
MFN 16-062, ``Applicant's Supplemental        ML16235A415
 Environmental Report--Amendment to Standard
 Design Certification (ABWR Renewal Docket
 52-045),'' August 2016.
25A5680AA, ``Amendment to Technical Support   ML110040178
 Document for the ABWR,'' Sheet 1, November
 30, 2010 (Renewal Application).
SECY-97-077, ``Certification of Two           ML003708129
 Evolutionary Designs,'' April 15, 1996
 (Original ABWR Environmental Assessment).
Letter from GE Nuclear Energy Submitting the  ML100210563
 Enclosed.
``Technical Support Document for the ABWR,''
 December 21, 1994 (Original NEPA/SAMDA
 Submittal).
------------------------------------------------------------------------
     Commission Papers, Original Design Certification, Interim Rule
               Amendments, and Other Supporting Documents
------------------------------------------------------------------------
SECY-19-0066, ``Staff Review of NuScale       ML19148A443
 Power's Mitigation Strategy for Beyond-
 Design-Basis External Events,'' June 26,
 2019.
SECY-12-0025, ``Proposed Orders and Requests  ML12039A111
 for Information in Response to Lessons
 Learned from Japan's March 11, 2011, Great
 Tohoku Earthquake and Tsunami,'' February
 17, 2012.

[[Page 35027]]

 
SECY-11-0093, ``Near-Term Report and          ML11186A950
 Recommendations for Agency Actions
 Following the Events in Japan,'' July 12,
 2011.
The Near-Term Task Force Review of Insights   ML111861807
 from the Fukushima Dai-Ichi Accident, July
 12, 2011.
Staff Requirements Memorandum on SECY-90-     ML003707892
 377, ``Requirements for Design
 Certification Under 10 CFR Part 52,''
 February 15, 1991.
SECY-90-377, ``Requirements for Design        ML003707889
 Certification under 10 CFR Part 52,''
 November 8, 1990.
NUREG[dash]1948, ``Final Safety Evaluation    ML11182A163
 Report Related to the Aircraft Impact
 Amendment to the U.S. Advanced Boiling
 Water Reactor (ABWR) Design
 Certification,'' June 2011.
U.S. Advanced Boiling Water Reactor Aircraft  76 FR 78096
 Impact Design Certification Amendment,
 December 16, 2011.
LBP-11-07, Atomic Safety and Licensing Board  ML110591049
 Memorandum and Order in the South Texas
 Project Electric Generating Station Units 3
 and 4 Combined License Proceeding, February
 28, 2011.
GE Hitachi Nuclear Energy; Acceptance for     76 FR 9612
 Docketing of an Application for Renewal of
 the U.S. Advanced Boiling Water Reactor
 Design Certification, February 18, 2011
 (Acceptance Application).
GE Hitachi Nuclear Energy; Notice of Receipt  76 FR 4948
 and Availability of an Application for
 Renewal of the U.S. Advanced Boiling Water
 Reactor Design Certification, January 27,
 2011 (Notice of Receipt of the Application).
ABWR-LIC-09-621, Revision 0, ``Applicant's    ML093170455
 Supplemental Environmental Report-Amendment
 to ABWR Standard Design Certification,''
 November 2009.
Consideration of Aircraft Impacts for New     74 FR 28111
 Nuclear Power Reactors, June 12, 2009.
Licenses, Certifications, and Approvals for   72 FR 49351
 Nuclear Power Plants, August 28, 2007
 (Revision of 10 CFR Parts 50 and 52).
Presidential Memorandum, ``Plain Language in  63 FR 31883
 Government Writing,'' June 10, 1998.
Policy Statement on Adequacy and              62 FR 46517
 Compatibility of Agreement States Programs,
 September 3, 1997.
Standard Design Certification for the U.S.    62 FR 25800
 Advanced Boiling Water Reactor Design, May
 12, 1997.
(Original U.S. ABWR Design Certification)...
GE-Hitachi Nuclear Energy, Transmittal of     ML20076D961
 ABWR Standard Plant Design Certification
 Renewal Application Design Control Document
 Revision 7, Chapter 5, March 16, 2020.
GE-Hitachi Nuclear Energy--ABWR Standard      ML20007E274
 Plant Design Certification Renewal
 Application Design Control Document
 Revision 7, Tier 1 and Tier 2, December 20,
 2019.
GE-Hitachi Nuclear Energy, Submittal of ABWR  ML16081A268
 Standard Plant Design Certification Renewal
 Application Design Control, Document,
 Revision 6, Tier 1 and Tier 2, February 19,
 2016.
GE-Hitachi Nuclear Energy--ABWR Standard      ML16214A015
 Plant Design Certification Renewal
 Application Design Control Document
 Revision 6, Tier 1 and Tier 2, February 19,
 2016.
Mitigation of Beyond-Design-Basis Events      ML15266A133
 (MBDBE)--Regulatory Analysis--Proposed Rule
 Post-SRM, October 2015.
Letter from Nuclear Innovation North America  ML18179A217
 LLC, South Texas Project Units 3 and 4
 Termination of Combined Licenses NPF-97 and
 NPF-98, July 12, 2018.
South Texas Project, Units 3 and 4, Request   ML18184A338
 for Withdrawal of Combined Licenses, June
 22, 2018.
Withdrawal of Toshiba Advanced Boiling Water  ML16173A310
 Reactor Design Certification Rule Renewal
 Application, June 9, 2016.
GE-Hitachi Nuclear Energy--U.S. Advanced      ML12125A385
 Boiling Water Design Certification Renewal
 Application, July 20, 2012.
Reactor Regulatory History on Design          ML003761550
 Certification Rules, April 26, 2000 \3\.
Notice of Issuance of Revised Final Design    59 FR 61647
 Approval for U.S. ABWR Standard Design,
 December 1, 1994.
Letter to GE Nuclear Energy Transmitting the  ML20077A747
 Revised Final Design Approval for [the]
 U.S. ABWR Standard Design, November 23,
 1994.
Issuance of Final Design Approval Pursuant    59 FR 37058
 to 10 CFR Part 52, Appendix O; U.S.
 Advanced Boiling Water Reactor Design; GE
 Nuclear Energy, July 20, 1994.
Final Design Approval FDA-0 for GE Nuclear    ML20070L506
 Energy U.S. ABWR Standard Design, July 13,
 1994 (Docket No. 52-001).
GE Nuclear Energy; Receipt of Application     57 FR 9749
 for Design Certification, March 20, 1992
 (Initial Application).
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    The NRC may post materials related to this document, including 
public comments, on the Federal Rulemaking website at https://www.regulations.gov under Docket ID NRC-2017-0090.
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    \3\ The regulatory history of the NRC's design certification 
reviews is a package of documents that is available in the NRC's PDR 
and NRC Library: Reactor Regulatory History on Design Certification 
Rules, April 26, 2000. This history spans the period during which 
the NRC simultaneously developed the regulatory standards for 
reviewing these designs and the form and content of the rules that 
certified the designs. This document predates this rulemaking and 
therefore does not contain a regulatory history for this rulemaking.

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    Dated: June 23, 2021.

    For the Nuclear Regulatory Commission.
Annette Vietti-Cook,
Secretary of the Commission.
[FR Doc. 2021-13802 Filed 6-30-21; 8:45 am]
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