Federal Register / Vol. 86, No. 124 / Thursday, July 1, 2021 / Proposed Rules 35023 

b. During the interval from the date of 

application for a license to the date the 

Commission makes its finding required by 

§ 52.103(g), the report must be submitted 

semiannually. Updates to the plant-specific 

DCD must be submitted annually and may be 

submitted along with amendments to the 

application. 

c. After the Commission makes the finding 

required by § 52.103(g), the reports and 

updates to the plant-specific DCD must be 

submitted, along with updates to the sitespecific portion of the final safety analysis 

report for the facility, at the intervals 

required by 10 CFR 50.59(d)(2) and 

50.71(e)(4), respectively, or at shorter 

intervals as specified in the license. 

Dated: June 25, 2021. 

For the Nuclear Regulatory Commission. 

Annette Vietti-Cook, 

Secretary of the Commission. 

[FR Doc. 2021–13940 Filed 6–30–21; 8:45 am] 

BILLING CODE 7590–01–P 

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. 

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: Dawn.Forder@nrc.gov. For 

technical questions contact the 

individuals listed in the FOR FURTHER

INFORMATION CONTACT section of this 

document. 

• Email comments to: 

Rulemaking.Comments@nrc.gov. 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: 

Dennis.Andrukat@nrc.gov, or James 

Shea, Office of Nuclear Reactor 

Regulation, telephone: 301–415–1388, 

email: James.Shea@nrc.gov. 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 publiclyavailable 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 

PDR.Resource@nrc.gov. 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 

PDR.Resource@nrc.gov 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 

Library.Resource@nrc.gov 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 


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1The requirement for modifications in DC 

renewals to address § 50.150 was added to 

§ 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. 

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-andcomment 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 § 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 § 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 § 21.3. For the 

NRC to issue a rule granting the DC 

renewal under § 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 § 50.150, 

‘‘Aircraft impact assessment.’’ 1

A DC renewal applicant may propose 

to amend the design under § 52.59(c). 

An amendment is an applicantproposed change that is not an update 

under § 52.57(a) or a change to meet the 

renewal standards in § 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 § 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 

§ 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 § 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 § 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 


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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. 

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 reanalysis amendment and the necessary 

changes to meet the requirements of 

§ 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 § 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, ‘‘NearTerm 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 

§ 50.155, ‘‘Mitigation of beyond-designbasis events,’’ the Commission 

determined that it would be 

inappropriate to impose mitigation 

strategies requirements on DCs.2

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 nonsubstantive 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 Toshibaspecific 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 § 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 § 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 


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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 § 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 § 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

Document 

ADAMS Accession 

No./ 

Federal Register 

Citation 

SECY–20–0112, ‘‘Direct Final Rule–Advanced Boiling Water Reactor Design Certification Renewal (RIN 3150–AK04; 

NRC–2017–0090),’’ December 9, 2020.

ML20170A520 

GE-Hitachi ABWR Design Control Document Tier 1 & 2, Revision 7, October 2019 (includes correction noted, as of March 

2020).

ML20093K254 

GE-Hitachi Nuclear Energy, Transmittal of ABWR Standard Plant Design Certification Renewal Application Design Control 

Document, Revision 5, Tier 1 and Tier 2, December 7, 2010.

ML110040176 

GE-Hitachi ABWR Design Control Document Tier 1 & 2, Revision 5, December 7, 2010 ......................................................... ML110040323 

Technical Report NEDO–33875, ABWR U.S. Certified Design—Aircraft Impact Assessment, Licensing Basis Information 

and Design Details for Key Design Features, Rev. 3 (M170049), February 2017.

ML17059C523 

Licensing Technical Report NEDO–33878, ABWR ECCS Suction Strainer Evaluation of Long-Term Recirculation Capability, Rev. 3 (M180068), March 2018.ML18092A306 

Final Safety Evaluation Report and Supplements 

NUREG–1503, Supplement 2, ‘‘Final Safety Evaluation Report Related to the Certification of the Advanced Boiling Water 

Reactor Design,’’ October 2020.

ML20301A886 

NUREG–1503, Supplement 1, ‘‘Final Safety Evaluation Report Related to the Certification of the Advanced Boiling Water 

Reactor Design,’’ May 1997.

ML080710134 

NUREG–1503, Vols. 1–2, ‘‘Final Safety Evaluation Report Related to the Certification of the Advanced Boiling Water Reactor Design,’’ July 1994.ML080670592 

Environmental Review 

Environmental Assessment by the U.S. Nuclear Regulatory Commission Relating to Renewal of the Certification of the 

ABWR Standard Design, June 2021.

ML21147A381 

Staff Technical Analysis in Support of the Advanced Boiling Water Reactor Design Certification Renewal Environmental Assessment.ML20024D602 

MFN 16–062, ‘‘Applicant’s Supplemental Environmental Report—Amendment to Standard Design Certification (ABWR Renewal Docket 52–045),’’ August 2016.ML16235A415 

25A5680AA, ‘‘Amendment to Technical Support Document for the ABWR,’’ Sheet 1, November 30, 2010 (Renewal Application).ML110040178 

SECY–97–077, ‘‘Certification of Two Evolutionary Designs,’’ April 15, 1996 (Original ABWR Environmental Assessment) .... ML003708129 

Letter from GE Nuclear Energy Submitting the Enclosed ...........................................................................................................

‘‘Technical Support Document for the ABWR,’’ December 21, 1994 (Original NEPA/SAMDA Submittal) .................................

ML100210563 

Commission Papers, Original Design Certification, Interim Rule Amendments, and Other Supporting Documents 

SECY–19–0066, ‘‘Staff Review of NuScale Power’s Mitigation Strategy for Beyond-Design-Basis External Events,’’ June 

26, 2019.

ML19148A443 

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,’’ February 17, 2012.

ML12039A111 


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3The 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. 

DOCUMENTS RELATED TO U.S. ABWR DESIGN CERTIFICATION RENEWAL RULE—Continued 

Document 

ADAMS Accession 

No./ 

Federal Register 

Citation 

SECY–11–0093, ‘‘Near-Term Report and Recommendations for Agency Actions Following the Events in Japan,’’ July 12, 

2011.

ML11186A950 

The Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident, July 12, 2011 ..................................... ML111861807 

Staff Requirements Memorandum on SECY–90–377, ‘‘Requirements for Design Certification Under 10 CFR Part 52,’’ February 15, 1991.ML003707892 

SECY–90–377, ‘‘Requirements for Design Certification under 10 CFR Part 52,’’ November 8, 1990 ....................................... ML003707889 

NUREG-1948, ‘‘Final Safety Evaluation Report Related to the Aircraft Impact Amendment to the U.S. Advanced Boiling 

Water Reactor (ABWR) Design Certification,’’ June 2011.

ML11182A163 

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Presidential Memorandum, ‘‘Plain Language in Government Writing,’’ June 10, 1998 .............................................................. 63 FR 31883 

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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. 

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] 

BILLING CODE 7590–01–P 

DEPARTMENT OF TRANSPORTATION 

Federal Aviation Administration 

14 CFR Part 39 

[Docket No. FAA–2021–0212; Project 

Identifier 2018–CE–032–AD] 

RIN 2120–AA64 

Airworthiness Directives; DG 

Flugzeugbau GmbH Gliders 

AGENCY: Federal Aviation 

Administration (FAA), DOT. 

ACTION: Notice of proposed rulemaking 

(NPRM). 

SUMMARY: The FAA proposes to adopt a 

new airworthiness directive (AD) for all 


khammond on DSKJM1Z7X2PROD with PROPOSALS