[Federal Register Volume 86, Number 181 (Wednesday, September 22, 2021)]
[Proposed Rules]
[Pages 52619-52622]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2021-20227]


========================================================================
Proposed Rules
                                                Federal Register
________________________________________________________________________

This section of the FEDERAL REGISTER contains notices to the public of 
the proposed issuance of rules and regulations. The purpose of these 
notices is to give interested persons an opportunity to participate in 
the rule making prior to the adoption of the final rules.

========================================================================


Federal Register / Vol. 86, No. 181 / Wednesday, September 22, 2021 / 
Proposed Rules

[[Page 52619]]



NUCLEAR REGULATORY COMMISSION

10 CFR Part 52

[NRC-2020-0269]
RIN 3150-AK56


Extending the Duration of the AP1000 Design Certification

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 update the design to reflect changes provided 
by Westinghouse Electric Company LLC and to extend the duration of the 
AP1000 design certification for an additional 5 years. The NRC invites 
public comment on this proposed rule and environmental assessment.

DATES: Submit comments by October 22, 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):
    <bullet> Federal Rulemaking Website: Go to https://www.regulations.gov and search for Docket ID NRC-2020-0269. Address 
questions about NRC dockets to Dawn Forder; telephone: 301-415-3407; 
email: <a href="/cdn-cgi/l/email-protection#dc98bdabb2f29ab3aeb8b9ae9cb2aebff2bbb3aa"><span class="__cf_email__" data-cfemail="f7b3968099d9b19885939285b7998594d9909881">[email protected]</span></a>. For technical questions contact the 
individuals listed in the FOR FURTHER INFORMATION CONTACT section of 
this document.
    <bullet> Email comments to: <a href="/cdn-cgi/l/email-protection#6133140d040c000a080f064f220e0c0c040f1512210f13024f060e17"><span class="__cf_email__" data-cfemail="a3f1d6cfc6cec2c8cacdc48de0cccecec6cdd7d0e3cdd1c08dc4ccd5">[email protected]</span></a>. 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: Daniel Doyle, Office of Nuclear 
Material Safety and Safeguards, telephone: 301-415-3748, email: 
<a href="/cdn-cgi/l/email-protection#fcb89d92959990d2b893859099bc928e9fd29b938a"><span class="__cf_email__" data-cfemail="9bdffaf5f2fef7b5dff4e2f7fedbf5e9f8b5fcf4ed">[email protected]</span></a>, or Bruce Bavol, Office of Nuclear Reactor 
Regulation, telephone: 301-415-6715, email: <a href="/cdn-cgi/l/email-protection#b4f6c6c1d7d19af6d5c2dbd8f4dac6d79ad3dbc2"><span class="__cf_email__" data-cfemail="d290a0a7b1b7fc90b3a4bdbe92bca0b1fcb5bda4">[email protected]</span></a>. 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. Plain Writing
V. Environmental Assessment and Final Finding of No Significant 
Impact
VI. Paperwork Reduction Act
VII. Voluntary Consensus Standards
VIII. Availability of Documents

I. Obtaining Information and Submitting Comments

A. Obtaining Information

    Please refer to Docket ID NRC-2020-0269 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:
    <bullet> Federal Rulemaking Website: Go to https://www.regulations.gov and search for Docket ID NRC-2020-0269.
    <bullet> 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 reference staff at 1-800-397-4209, at 301-415-4737, or by 
email to <a href="/cdn-cgi/l/email-protection#e2b2a6b0ccb087918d97908187a28c9081cc858d94"><span class="__cf_email__" data-cfemail="79293d2b572b1c0a160c0b1a1c39170b1a571e160f">[email protected]</span></a>. For the convenience of the reader, 
instructions about obtaining materials referenced in this document are 
provided in the Availability of Documents section.
    <bullet> Attention: The Public Document Room, where you may examine 
and order copies of public documents, is currently closed. You may 
submit your request via email at <a href="/cdn-cgi/l/email-protection#79293d2b572b1c0a160c0b1a1c39170b1a571e160f"><span class="__cf_email__" data-cfemail="8cdcc8dea2dee9ffe3f9feefe9cce2feefa2ebe3fa">[email protected]</span></a> or call 1-800-
397-4209 between 8:00 a.m. and 4:00 p.m. (ET), Monday through Friday, 
except Federal holidays.
    <bullet> 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 
<a href="/cdn-cgi/l/email-protection#561a3f342437242f7804332539232435331638243578313920"><span class="__cf_email__" data-cfemail="e2ae8b809083909bccb087918d97908187a28c9081cc858d94">[email protected]</span></a> between 8:00 a.m. and 4:00 p.m. (ET), 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-2020-0269 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 December 6, 2021. However, if the NRC receives significant 
adverse comments on this proposed rule or environmental assessment by 
October 22, 2021, then the NRC will publish a document that withdraws 
the direct final rule and will subsequently address the comments 
received in any final rule as a response to this proposed rule. Absent 
significant

[[Page 52620]]

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 NRC is amending the design certification (DC) for the AP1000 
standard plant design to extend the duration of the DC for 5 years, as 
proposed by the NRC staff in SECY-20-0082, ``Rulemaking Plan to Extend 
the Duration of the AP1000 Design Certification,'' dated September 8, 
2020 (``rulemaking plan''), and approved by the Commission in SRM-SECY-
20-0082, dated November 17, 2020. To issue this extension, the NRC must 
conclude that the standard design continues to meet the applicable 
standards and requirements of the Atomic Energy Act of 1954, as amended 
(the AEA), and the Commission's regulations. This action would allow an 
applicant to reference the AP1000 design certification while the 
Commission considers potential changes to the duration and renewal of 
future and currently valid design certifications more broadly in a 
separate, ongoing rulemaking (Alignment of Licensing Processes and 
Lessons Learned from New Reactor Licensing NRC-2009-0196; RIN 3150-
AI66). The NRC also is updating the DC to reflect changes provided by 
Westinghouse Electric Company LLC (Westinghouse), by letter dated March 
19, 2021 (ADAMS Accession No. ML21081A023).
    The purpose of the amendment is to extend by 5 years the period 
that the AP1000 DC is valid for referencing by an applicant and to 
include design changes previously approved by the NRC in multiple 
combined license proceedings. The extended duration would align with 
the extended renewal period previously granted by the NRC to 
Westinghouse for the AP1000 DC in its exemption issued by letter dated 
February 14, 2018 (ADAMS Accession No. ML17265A099). With this proposed 
duration extension, the AP1000 DC would remain valid for referencing 
until February 27, 2026.
    The AP1000 DC in appendix D, ``Design Certification Rule for the 
AP1000 Design,'' to part 52, ``Licenses, Certifications, and Approvals 
for Nuclear Power Plants,'' of title 10 of the Code of Federal 
Regulations (10 CFR) expired on February 27, 2021. By letter dated June 
26, 2020, Westinghouse requested that the NRC extend the duration of 
the AP1000 DC by 5 years, retroactive to the expiration date.

IV. Discussion

    In the rulemaking plan, the NRC staff acknowledged that there were 
known design issues that it would need to assess in the rulemaking to 
determine their impact on the necessary safety and environmental 
findings. The following five aspects of the design were discovered to 
have issues after the NRC updated the design certification rule to 
incorporate Revision 19 of the AP1000 design control document (DCD) 
(ADAMS Accession No. ML11171A500) on December 30, 2011: (1) Passive 
core cooling system containment condensate return, (2) main control 
room dose, (3) main control room heatup, (4) hydrogen vent inspections, 
tests, analyses, and acceptance criteria (ITAAC), and (5) neutron flux 
logic operating bypass. Combined license holders and applicants have 
previously referenced and resolved these five design issues, and the 
NRC has approved the same changes to address the issues in multiple 
combined license applications and amendments.
    After the NRC staff began assessing the known design issues for the 
rulemaking, Westinghouse indicated its preference to update the design 
to reflect the changes made in the previous applications referencing 
the AP1000 design. By letter dated March 19, 2021 (ADAMS Accession No. 
ML21081A023), Westinghouse submitted applicable AP1000 DCD markups and 
references that illustrate how: (1) The five issues have been corrected 
based on construction of the current AP1000 reactors for Southern 
Nuclear Company Vogtle Electric Generating Plant, Units 3 and 4, and 
(2) Westinghouse has marked up the referenced DCD in accordance with 
those changes. The NRC staff used these references to verify the 
Westinghouse submitted DCD markups are the same as the design changes 
the NRC has previously reviewed and approved to address the design 
issues.
    The NRC staff verified, as documented in the NRC staff's 
Verification Evaluation Report, that the corrected information provided 
in the markups is the same as has been previously reviewed and approved 
by the NRC for various combined license and license amendment 
applications. In reviewing those applications, the NRC staff determined 
that the design changes resolved the identified design issues, met the 
applicable regulations, and that the design as modified met the 
applicable requirements of the AEA and the NRC's regulations. Neither 
the applicable provisions of the AEA nor the NRC's regulations have 
changed since those applications were approved. Therefore, the NRC 
concludes that the relevant safety findings reached in the NRC staff 
reviews of those prior applications apply to the AP1000 design changes 
incorporated by the direct final rule and that the standard design, as 
modified by those changes, meets the applicable standards of the AEA 
and the NRC's regulations.

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 
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 31885). 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

[[Page 52621]]

NRC's regulations in subpart A, ``National Environmental Policy Act--
Regulations Implementing Section 102(2),'' of 10 CFR part 51, 
``Environmental Protection Regulations for Domestic Licensing and 
Related Regulatory Functions,'' 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 NRC's generic determination in this 
regard, reflected in Sec.  51.32(b)(1), is based upon the following 
considerations. A design certification 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 (extending the AP1000 design certification and incorporating 
changes to the design 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 any particular design 
certification 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). The environmental 
assessment is available as indicated in the Availability of Documents 
section.

VII. Paperwork Reduction Act

    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 Office of 
Management and Budget control number.

VIII. 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. 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.

IX. 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.

------------------------------------------------------------------------
                                           ADAMS Accession No./ Federal
                Document                        Register citation
------------------------------------------------------------------------
Environmental Assessment by the U.S.     ML21181A109
 Nuclear Regulatory Commission Relating
 to Extension of the AP1000 Standard
 Design Certification Docket No. 52-
 006, dated September 1, 2021.
Reactor Regulatory History on Design     ML003761550
 Certification Rules, dated April 26,
 2000 \1\.
SECY-20-0082, ``Rulemaking Plan to       ML20252A153
 Extend the Duration of the AP1000
 Design Certification,'' dated
 September 8, 2020.
Staff Requirements Memorandum for SECY-  ML20322A047
 20-0082, ``Rulemaking Plan to Extend
 the Duration of the AP1000 Design
 Certification,'' dated November 17,
 2020.
U.S. Nuclear Regulatory Commission       ML21131A221
 Verification Evaluation Report, dated
 May 11, 2021.
Westinghouse AP1000 Design Control       ML11171A500
 Document Revision 19, dated June 13,
 2011.
NRC Letter for the Staff Evaluation of   ML17265A099
 the Westinghouse Request for
 Exemptions Related to the Duration of
 the AP1000 Design Certification, dated
 February 14, 2018.
Westinghouse Electric Company LLC--      ML20178A640
 AP1000 Design Certification Extension
 Request, dated June 26, 2020.
Westinghouse Electric Company LLC,       ML21081A023
 Supplemental Information to Support
 the AP1000 Design Certification
 Extension (Non-proprietary),
 DCP_NRC_003343, dated March 19, 2021.
Safety Evaluation--Issuance of           ML17024A307
 Amendment Nos. 72 and 71 for Southern
 Nuclear Company, Inc., Vogtle Units 3
 and 4, Respectively, License Amendment
 Request (LAR) 16-026, dated February
 27, 2017.
Safety Evaluation--Amendment Nos. 123    ML18085A628
 and 122 for Southern Nuclear Company,
 Inc., Vogtle Electric Generating Plant
 Units 3 and 4, Respectively, LAR-17-
 023, dated April 20, 2018.
Safety Evaluation--Amendment Nos. 108    ML18011A894
 and 107 for Southern Nuclear Company,
 Inc., Vogtle Units 3 and 4,
 Respectively, LAR-17-001, dated
 February 1, 2018.
Safety Evaluation--Amendment Nos. 84     ML17213A224
 and 83 for Southern Nuclear Company,
 Inc., Vogtle Units 3 and 4,
 Respectively, LAR-17-003, dated August
 23, 2017.
Safety Evaluation--Amendment Nos. 71     ML16320A174
 and 70 for Southern Nuclear Company,
 Inc., Vogtle Units 3 and 4,
 Respectively, LAR-16-006, dated
 February 24, 2017.
Safety Evaluation--Florida Power and     ML16266A185
 Light Company's Turkey Point Nuclear
 Generating Units 6 and 7, FSER Chapter
 16, ``Technical Specifications,''
 dated November 10, 2016.
------------------------------------------------------------------------
\1\ The regulatory history of the NRC's design certification reviews is
  a package of documents that is available in the NRC's Public Document
  Room 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.

    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-2020-0269.

List of Subjects in 10 CFR Part 52

    Administrative practice and procedure, Antitrust, Combined license, 
Early site permit, Emergency planning,

[[Page 52622]]

Fees, Incorporation by reference, Inspection, Issue finality, Limited 
work authorization, Nuclear power plants and reactors, Probabilistic 
risk assessment, Prototype, Reactor siting criteria, Redress of site, 
Penalties, Reporting and recordkeeping requirements, Standard design, 
Standard design certification.

    Dated September 1, 2021.

    For the Nuclear Regulatory Commission.
Margaret M. Doane,
Executive Director for Operations.
[FR Doc. 2021-20227 Filed 9-21-21; 8:45 am]
BILLING CODE 7590-01-P


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