Advanced Power Reactor 1400 (APR1400) Design Certification, 23500-23503 [2019-10716]
Download as PDF
<![CDATA[
23500
Proposed Rules
Federal Register
Vol. 84, No. 99
Wednesday, May 22, 2019
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.
NUCLEAR REGULATORY
COMMISSION
10 CFR Part 52
[NRC–2015–0224]
RIN 3150–AJ67
Advanced Power Reactor 1400
(APR1400) Design Certification
Nuclear Regulatory
Commission.
ACTION: Proposed rule.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) is proposing to
amend its regulations to certify the
Advanced Power Reactor 1400
(APR1400) standard design. Applicants
or licensees intending to construct and
operate an APR1400 standard design
may do so by referencing this design
certification (DC) rule. The applicant for
the certification of the APR1400
standard design is Korea Electric Power
Corporation and Korea Hydro & Nuclear
Power Co., Ltd. (KEPCO/KHNP).
DATES: Submit comments by June 21,
2019. 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:
• Federal Rulemaking Website: Go to
https://www.regulations.gov and search
for Docket ID NRC–2015–0224. Address
questions about NRC dockets to Carol
Gallagher; telephone: 301–415–3463;
email: Carol.Gallagher@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.
• Fax comments to: Secretary, U.S.
Nuclear Regulatory Commission at 301–
415–1101.
jbell on DSK3GLQ082PROD with PROPOSALS
SUMMARY:
VerDate Sep<11>2014
18:00 May 21, 2019
Jkt 247001
• Mail comments to: Secretary, U.S.
Nuclear Regulatory Commission,
Washington, DC 20555–0001, ATTN:
Rulemakings and Adjudications Staff.
• Hand deliver comments to: 11555
Rockville Pike, Rockville, Maryland
20852, between 7:30 a.m. and 4:15 p.m.
(Eastern Time) Federal workdays;
telephone: 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:
Yanely Malave, Office of Nuclear
Material Safety and Safeguards,
telephone: 301–415–1519, email:
Yanely.Malave@nrc.gov, or William
Ward, Office of New Reactors,
telephone: 301–415–7038, email:
William.Ward@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. Paperwork Reduction Act Statement
VII. Availability of Documents
I. Obtaining Information and
Submitting Comments
A. Obtaining Information
Please refer to Docket ID NRC–2015–
0224 when contacting the NRC about
the availability of information for this
action. You may obtain publiclyavailable 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–2015–0224.
• 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
‘‘ADAMS Public Documents’’ and then
select ‘‘Begin Web-based ADAMS
Search.’’ For problems with ADAMS,
please contact the NRC’s Public
Document Room (PDR) reference staff at
PO 00000
Frm 00001
Fmt 4702
Sfmt 4702
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.
• NRC’s PDR: You may examine and
purchase copies of public documents at
the NRC’s PDR, Room O1–F21, One
White Flint North, 11555 Rockville
Pike, Rockville, Maryland 20852.
B. Submitting Comments
Please include Docket ID NRC–2015–
0224 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 considers this action
to 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 19, 2019. However, if the
NRC receives significant adverse
comments on this proposed rule by June
21, 2019, 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
E:\FR\FM\22MYP1.SGM
22MYP1
jbell on DSK3GLQ082PROD with PROPOSALS
Federal Register / Vol. 84, No. 99 / Wednesday, May 22, 2019 / Proposed Rules
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 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:
(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 procedural information and the
regulatory analysis, see the direct final
rule published in the Rules and
Regulations section of this issue of the
Federal Register.
ML18087A364. The NRC will publish a
final safety evaluation report in a
NUREG titled, ‘‘Final Safety Evaluation
Report Related to the Certification of the
Advanced Power Reactor 1400 Standard
Design.’’ The final safety evaluation
report is based on the NRC’s review of
revision 3 of the APR1400 design
certification document.
III. Background
Part 52 of title 10 of the Code of
Federal Regulations (10 CFR),
‘‘Licenses, Certifications, and Approvals
for Nuclear Power Plants,’’ subpart B,
‘‘Standard Design Certifications,’’
presents the process for obtaining
standard design certifications. On
December 23, 2014, KEPCO/KHNP
submitted its application for
certification of the APR1400 standard
design (ADAMS Accession No.
ML15006A098) to the NRC under
subpart B of 10 CFR part 52. The NRC
published a notice of receipt of the
application in the Federal Register (80
FR 5792; February 3, 2015). On March
12, 2015, the NRC formally accepted the
application as a docketed application
for design certification (80 FR 13035;
March 12, 2015). The pre-application
information submitted before the NRC
formally accepted the application can be
found in ADAMS under Docket No.
PROJ0782.
The NRC issued the final safety
evaluation report for the APR1400
design on September 28, 2018. The final
safety evaluation report is available in
ADAMS under Accession No.
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 31883).
The NRC requests comment on the
proposed rule with respect to clarity
and effectiveness of the language used.
VerDate Sep<11>2014
18:00 May 21, 2019
Jkt 247001
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 proposes to certify the APR1400
standard design for use in nuclear
power plant licensing under 10 CFR
parts 50 or 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.
VI. Paperwork Reduction Act
This proposed rule contains (a) new
or amended collection(s) of information
subject to the Paperwork Reduction Act
of 1995 (44 U.S.C. 3501 et seq.). This
proposed rule has been submitted to the
Office of Management and Budget for
review and approval of the information
collection(s).
Type of submission, new or revision:
Revision.
The title of the information collection:
Appendix F to 10 CFR part 52 Design
PO 00000
Frm 00002
Fmt 4702
Sfmt 4702
23501
Certification Rule for the APR1400
Design.
The form number if applicable: NA.
How often the collection is required or
requested: On occasion.
Who will be required or asked to
respond: Applicant for a combined
license or a design certification
amendment.
An estimate of the number of annual
responses: 1 (0 annual responses and 1
recordkeeper).
The estimated number of annual
respondents: 1.
An estimate of the total number of
hours needed annually to comply with
the information collection requirement
or request: Approximately 37 hours of
additional recordkeeping burden. The
only burden associated with this rule
will be for recordkeeping by the
applicant for this design certification.
Abstract: The NRC is proposing to
amend its regulations to certify the
APR1400 standard design. This action is
necessary so that applicants or licensees
intending to construct and operate an
APR1400 standard design may do so by
referencing this DC rule. The applicant
for certification of the APR1400
standard design is KEPCO/KHNP.
The NRC is seeking public comment
on the potential impact of the
information collection contained in this
proposed rule and on the following
issues:
(1) Is the proposed information
collection necessary for the proper
performance of the functions of the
NRC, including whether the information
will have practical utility?
(2) Is the estimate of the burden of the
proposed information collection
accurate?
(3) Is there a way to enhance the
quality, utility, and clarity of the
information to be collected?
(4) How can the burden of the
proposed information collection on
respondents be minimized, including
the use of automated collection
techniques or other forms of information
technology?
A copy of the OMB clearance package
is available in ADAMS under Accession
No. ML18302A089 or may be viewed
free of charge at the NRC Public
Document Room, One White Flint
North, 11555 Rockville Pike, Room O1–
F21, Rockville, MD 20852. You may
obtain information and comment
submissions related to the OMB
clearance package by searching on
https://www.regulations.gov under
Docket ID NRC–2015–0224.
You may submit comments on any
aspect of these proposed information
collection(s), including suggestions for
E:\FR\FM\22MYP1.SGM
22MYP1
23502
Federal Register / Vol. 84, No. 99 / Wednesday, May 22, 2019 / Proposed Rules
reducing the burden and on the above
issues, by the following methods:
• Federal Rulemaking Website: Go to
https://www.regulations.gov and search
for Docket ID NRC–2015–0224.
• Mail comments to: Information
Services Branch, U.S. Nuclear
Regulatory Commission, Washington,
DC 20555–0001, or by email to
Infocollects.Resource@nrc.gov, and to
the Desk Officer, Office of Information
and Regulatory Affairs, NEOB–10202,
(3150–XXXX) Office of Management
and Budget, Washington, DC 20503;
email: oira_submission@omb.eop.gov.
Submit comments by June 21, 2019.
Comments received after this date will
be considered if it is practical to do so,
but the NRC staff is able to ensure
consideration only for comments
received on or before this date.
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.
VII. 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 APR1400 DESIGN CERTIFICATION RULE
ADAMS
Accession
No./web link/
Federal Register
citation
jbell on DSK3GLQ082PROD with PROPOSALS
Document
SECY–19–0020, ‘‘Direct Final Rule–Advanced Power Reactor 1400 Design Certification (RIN 3150–AJ67; NRC–2015–
0224)’’ .........................................................................................................................................................................................
KEPCO/KHNP Application for Design Certification of the APR1400 Design ...............................................................................
APR1400 Design Control Document, Revision 3 ..........................................................................................................................
APR1400 Final Safety Evaluation Report .....................................................................................................................................
APR1400 Environmental Assessment ...........................................................................................................................................
APR1400 Standard Design Approval ............................................................................................................................................
Regulatory History of Design Certification 1 ..................................................................................................................................
KEPCO/KHNP Topical and Technical Reports:
APR1400–E–B–NR–16001–NP, Evaluation of Main Steam and Feedwater Piping Applied to the Graded Approach for
the APR1400, Rev. 0 (July 2017) .......................................................................................................................................
APR1400–E–B–NR–16002–NP, Evaluation of Safety Injection and Shutdown Cooling Piping Applied to the Graded Approach for the APR1400, Rev. 1 (May 2018) .....................................................................................................................
APR1400–E–I–NR–14001–NP, Human Factors Engineering Program Plan, Rev. 4 (July 2018) ........................................
APR1400–E–I–NR–14002–NP, Operating Experience Review Implementation Plan, Rev. 2 (January 2018) ....................
APR1400–E–I–NR–14003–NP, Functional Requirements Analysis and Function Allocation Implementation Plan, Rev. 2
(January 2018) ....................................................................................................................................................................
APR1400–E–I–NR–14004–NP, Task Analysis Implementation Plan, Rev. 3 (May 2018) ....................................................
APR1400–E–I–NR–14006–NP, Treatment of Important Human Actions Implementation Plan, Rev. 3 (May 2018) ...........
APR1400–E–I–NR–14007–NP, Human-System Interface Design Implementation Plan, Rev. 3 (May 2018) ......................
APR1400–E–I–NR–14008–NP, Human Factors Verification and Validation Implementation Plan, Rev. 3 (May 2018) ......
APR1400–E–I–NR–14010–NP, Human Factors Verification and Validation Scenarios, Rev. 2 (January 2018) .................
APR1400–E–I–NR–14011–NP, Basic Human-System Interface, Rev. 3 (May 2018) ..........................................................
APR1400–E–I–NR–14012–NP, Style Guide, Rev. 2 (January 2018) ...................................................................................
APR1400–E–J–NR–14001–NP, Component Interface Module, Rev. 1 (March 2017) .........................................................
APR1400–E–J–NR–17001–NP, Secure Development and Operational Environment for APR1400 Computer-Based I&C
Safety Systems, Rev. 0 (September 2017) ........................................................................................................................
APR1400–E–N–NR–14001–NP, Design Features To Address GSI–191, Rev. 3 (February 2018) .....................................
APR1400–E–P–NR–14005–NP, Evaluations and Design Enhancements To Incorporate Lessons Learned from
Fukushima Dai-Ichi Nuclear Accident, Rev. 2 (July 2017) .................................................................................................
APR1400–E–S–NR–14004–NP, Evaluation of Effects of HRHF Response Spectra on SSCs, Rev. 3 (December 2017) ..
APR1400–E–S–NR–14005–NP, Evaluation of Structure-Soil-Structure Interaction (SSSI) Effects, Rev. 2 (December
2017) ...................................................................................................................................................................................
APR1400–E–S–NR–14006–NP, Stability Check for NI Common Basemat, Rev. 5 (May 2018) .........................................
APR1400–E–X–NR–14001–NP, Equipment Qualification Program, Rev. 4 (July 2018) ......................................................
APR1400–F–A–NR–14001–NP, Small Break LOCA Evaluation Model, Rev. 1 (March 2017) ............................................
APR1400–F–A–NR–14003–NP, Post-LOCA Long Term Cooling Evaluation Model, Rev. 1 (March 2017) ........................
APR1400–F–A–TR–12004–NP–A, Realistic Evaluation Methodology for Large-Break LOCA of the APR1400 (August
2018) ...................................................................................................................................................................................
APR1400–F–C–NR–14001–NP, CPC Setpoint Analysis Methodology for APR1400, Rev. 3 (June 2018) .........................
APR1400–F–C–NR–14002–NP, Functional Design Requirements for a Core Operating Limit Supervisory System for
APR1400, Rev. 1 (February 2017) .....................................................................................................................................
APR1400–F–C–NR–14003–NP, Functional Design Requirements for a Core Protection Calculator System for
APR1400, Rev. 1 (March 2017) .........................................................................................................................................
APR1400–F–C–TR–12002–NP–A, KCE–1 Critical Heat Flux Correlation for PLUS7 Thermal Design (April 2017) ...........
APR1400–F–M–TR–13001–NP–A, PLUS7 Fuel Design for the APR1400 (August 2018) ...................................................
APR1400–H–N–NR–14005–NP, Summary Stress Report for Primary Piping, Rev. 2 (September 2016) ...........................
APR1400–H–N–NR–14012–NP, Mechanical Analysis for New and Spent Fuel Storage Racks, Rev. 3 (August 2017) ....
APR1400–K–I–NR–14005–NP, Staffing and Qualifications Implementation Plan, Rev. 1 (February 2017) ........................
APR1400–K–I–NR–14009–NP, Design Implementation Plan, Rev. 1 (February 2017) .......................................................
APR1400–K–Q–TR–11005–NP–A, KHNP Quality Assurance Program Description (QAPD) for the APR1400 Design
Certification, Rev. 2 (October 2016) ...................................................................................................................................
APR1400–Z–A–NR–14006–NP, Non-LOCA Safety Analysis Methodology, Rev. 1 (February 2017) ..................................
APR1400–Z–A–NR–14007–NP, Mass and Energy Release Methodologies for LOCA and MSLB, Rev. 2 (May 2018) .....
VerDate Sep<11>2014
18:00 May 21, 2019
Jkt 247001
PO 00000
Frm 00003
Fmt 4702
Sfmt 4702
E:\FR\FM\22MYP1.SGM
22MYP1
ML18302A069
ML15006A037
ML18228A667
ML18087A364
ML18306A607
ML18261A187
ML003761550
ML18178A215
ML18178A217
ML18212A345
ML18081A101
ML18081A091
ML18178A223
ML18178A224
ML18178A212
ML18178A213
ML18081A088
ML18178A214
ML18081A096
ML17094A131
ML18108A470
ML18057B532
ML18044B042
ML18078A709
ML18078A699
ML18178A221
ML18214A563
ML17114A524
ML17114A526
ML18233A431
ML18199A563
ML17094A132
ML17114A522
ML17115A559
ML18232A140
ML18178A218
ML17244A015
ML17094A152
ML17094A153
ML18085B044
ML17094A139
ML18212A338
Federal Register / Vol. 84, No. 99 / Wednesday, May 22, 2019 / Proposed Rules
23503
DOCUMENTS RELATED TO APR1400 DESIGN CERTIFICATION RULE—Continued
ADAMS
Accession
No./web link/
Federal Register
citation
Document
APR1400–Z–A–NR–14011–NP, Criticality Analysis of New and Spent Fuel Storage Racks, Rev. 3 (May 2018) ..............
APR1400–Z–A–NR–14019–NP, CCF Coping Analysis, Rev. 3 (July 2018) .........................................................................
APR1400–Z–J–NR–14001–NP, Safety I&C System, Rev. 3 (May 2018) .............................................................................
APR1400–Z–J–NR–14002–NP, Diversity and Defense-in-Depth, Rev. 3 (May 2018) .........................................................
APR1400–Z–J–NR–14003–NP, Software Program Manual, Rev. 3 (May 2018) .................................................................
APR1400–Z–J–NR–14004–NP, Uncertainty Methodology and Application for Instrumentation, Rev. 2 (January 2018) ....
APR1400–Z–J–NR–14005–NP, Setpoint Methodology for Safety-Related Instrumentation, Rev. 2 (January 2018) ..........
APR1400–Z–J–NR–14012–NP, Control System CCF Analysis, Rev. 3 (May 2018) ............................................................
APR1400–Z–J–NR–14013–NP, Response Time Analysis of Safety I&C System, Rev. 2 (January 2018) ..........................
APR1400–Z–M–NR–14008–NP, Pressure-Temperature Limits Methodology for RCS Heatup and Cooldown, Rev. 1
(January 2018) ....................................................................................................................................................................
APR1400–Z–M–TR–12003–NP–A, Fluidic Device Design for the APR1400 (April 2017) ....................................................
Westinghouse Topical and Technical Report:
WCAP–10697–NP–A, Common Qualified Platform Topical Report, Rev. 3 (February 2013) ..............................................
WCAP–17889–NP (APR1400–A–N–NR–17001–NP), Validation of SCALE 6.1.2 with 238-Group ENDF/B–VII.0 Cross
Section Library for APR1400 Design Certification, Rev. 0 (June 2014) ............................................................................
Combustion Engineering, Inc. Technical Reports:
CEN–312–NP, Overview Description of the Core Operating Limit Supervisory System (COLSS), Rev. 01–NP (November 1986) .............................................................................................................................................................................
CEN–310–NP–A, CPC and Methodology Changes for the CPC Improvement Program (April 1986) .................................
ML18214A561
ML18225A340
ML18212A341
ML18214A557
ML18214A559
ML18086B757
ML18087A106
ML18212A343
ML18087A110
ML18087A112
ML17129A597
ML13112A108
ML18044B051
ML19066A067
ML19066A085
1 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. 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.
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–2015–0224. The
Federal Rulemaking website allows you
to receive alerts when changes or
additions occur in a docket folder. To
subscribe: (1) Navigate to the docket
folder (NRC–2015–0224); (2) click the
‘‘Sign up for Email Alerts’’ link; and (3)
enter your email address and select how
frequently you would like to receive
emails (daily, weekly, or monthly).
List of Subjects in 10 CFR Part 52
jbell on DSK3GLQ082PROD with PROPOSALS
Administrative practice and
procedure, Antitrust, Combined license,
Early site permit, Emergency planning,
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 at Rockville, Maryland, this 17th day
of May 2019.
For the Nuclear Regulatory Commission.
Annette Vietti-Cook,
Secretary of the Commission.
[FR Doc. 2019–10716 Filed 5–21–19; 8:45 am]
18:00 May 21, 2019
Table of Contents
39 CFR Part 3060
I. Background
II. Basis and Purpose of Proposed Rules
III. Proposed Rules
[Docket No. RM2019–5; Order No. 5097]
Accounting and Periodic Reporting
Rules
Postal Regulatory Commission.
ACTION: Proposed rulemaking.
AGENCY:
The Commission is proposing
an amendment to its rules involving the
calculation of the assumed Federal
income tax on competitive products by
the Postal Service each fiscal year. The
Commission invites public comment on
the proposed revisions.
DATES: Comments are due: June 21,
2019.
SUMMARY:
For additional information,
Order No.5097 can be accessed
electronically through the Commission’s
website at https://www.prc.gov. Submit
comments electronically via the
Commission’s Filing Online system at
https://www.prc.gov. Those who cannot
submit comments electronically should
contact the person identified in the FOR
FURTHER INFORMATION CONTACT section
by telephone for advice on filing
alternatives.
ADDRESSES:
FOR FURTHER INFORMATION CONTACT:
David A. Trissell, General Counsel, at
202–789–6820.
SUPPLEMENTARY INFORMATION:
BILLING CODE 7590–01–P
VerDate Sep<11>2014
POSTAL REGULATORY COMMISSION
Jkt 247001
PO 00000
Frm 00004
Fmt 4702
Sfmt 4702
I. Background
The Commission initiated this
proceeding to amend its regulations
governing the assumed Federal income
tax on competitive product income
appearing in existing 39 CFR part 3060.
The proposed amendments would
revise regulations concerning the annual
assumed Federal income tax calculation
for competitive products to reflect
changes to the Internal Revenue Code
made by the Tax Cuts and Jobs Act and
to remove other obsolete provisions.1
The Commission sought comments from
interested parties on whether it should
update its regulations to reflect the
changes and simplify the existing
regulations.
II. Basis and Purpose of Proposed Rules
Section 3634(b) of title 39 of the
United States Code requires the Postal
Service to calculate the assumed Federal
income tax on its competitive products
income each year and transfer the
amount of the assumed tax from the
Competitive Products Fund to the Postal
Service Fund. As required by 39 U.S.C.
2011(h)(2)(B)(ii), on December 18, 2008,
the Commission issued the substantive
1 See Tax Cuts and Jobs Act, Public Law 115–97,
131 Stat. 2054 (2017) (Tax Cuts and Jobs Act).
E:\FR\FM\22MYP1.SGM
22MYP1
]]>Agencies
[Federal Register Volume 84, Number 99 (Wednesday, May 22, 2019)]
[Proposed Rules]
[Pages 23500-23503]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2019-10716]
========================================================================
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. 84, No. 99 / Wednesday, May 22, 2019 /
Proposed Rules
[[Page 23500]]
NUCLEAR REGULATORY COMMISSION
10 CFR Part 52
[NRC-2015-0224]
RIN 3150-AJ67
Advanced Power Reactor 1400 (APR1400) Design Certification
AGENCY: Nuclear Regulatory Commission.
ACTION: Proposed rule.
-----------------------------------------------------------------------
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is proposing to
amend its regulations to certify the Advanced Power Reactor 1400
(APR1400) standard design. Applicants or licensees intending to
construct and operate an APR1400 standard design may do so by
referencing this design certification (DC) rule. The applicant for the
certification of the APR1400 standard design is Korea Electric Power
Corporation and Korea Hydro & Nuclear Power Co., Ltd. (KEPCO/KHNP).
DATES: Submit comments by June 21, 2019. 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:
Federal Rulemaking Website: Go to https://www.regulations.gov and search for Docket ID NRC-2015-0224. Address
questions about NRC dockets to Carol Gallagher; telephone: 301-415-
3463; 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.
Fax comments to: Secretary, U.S. Nuclear Regulatory
Commission at 301-415-1101.
Mail comments to: Secretary, U.S. Nuclear Regulatory
Commission, Washington, DC 20555-0001, ATTN: Rulemakings and
Adjudications Staff.
Hand deliver comments to: 11555 Rockville Pike, Rockville,
Maryland 20852, between 7:30 a.m. and 4:15 p.m. (Eastern Time) Federal
workdays; telephone: 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: Yanely Malave, Office of Nuclear
Material Safety and Safeguards, telephone: 301-415-1519, email:
[email protected], or William Ward, Office of New Reactors,
telephone: 301-415-7038, 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. Paperwork Reduction Act Statement
VII. Availability of Documents
I. Obtaining Information and Submitting Comments
A. Obtaining Information
Please refer to Docket ID NRC-2015-0224 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-2015-0224.
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 ``ADAMS Public Documents'' and
then 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.
NRC's PDR: You may examine and purchase copies of public
documents at the NRC's PDR, Room O1-F21, One White Flint North, 11555
Rockville Pike, Rockville, Maryland 20852.
B. Submitting Comments
Please include Docket ID NRC-2015-0224 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 considers this action to 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 19,
2019. However, if the NRC receives significant adverse comments on this
proposed rule by June 21, 2019, 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
[[Page 23501]]
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 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:
(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 procedural information and the regulatory analysis, see the
direct final rule published in the Rules and Regulations section of
this issue of the Federal Register.
III. Background
Part 52 of title 10 of the Code of Federal Regulations (10 CFR),
``Licenses, Certifications, and Approvals for Nuclear Power Plants,''
subpart B, ``Standard Design Certifications,'' presents the process for
obtaining standard design certifications. On December 23, 2014, KEPCO/
KHNP submitted its application for certification of the APR1400
standard design (ADAMS Accession No. ML15006A098) to the NRC under
subpart B of 10 CFR part 52. The NRC published a notice of receipt of
the application in the Federal Register (80 FR 5792; February 3, 2015).
On March 12, 2015, the NRC formally accepted the application as a
docketed application for design certification (80 FR 13035; March 12,
2015). The pre-application information submitted before the NRC
formally accepted the application can be found in ADAMS under Docket
No. PROJ0782.
The NRC issued the final safety evaluation report for the APR1400
design on September 28, 2018. The final safety evaluation report is
available in ADAMS under Accession No. ML18087A364. The NRC will
publish a final safety evaluation report in a NUREG titled, ``Final
Safety Evaluation Report Related to the Certification of the Advanced
Power Reactor 1400 Standard Design.'' The final safety evaluation
report is based on the NRC's review of revision 3 of the APR1400 design
certification document.
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
proposes to certify the APR1400 standard design for use in nuclear
power plant licensing under 10 CFR parts 50 or 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
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. Paperwork Reduction Act
This proposed rule contains (a) new or amended collection(s) of
information subject to the Paperwork Reduction Act of 1995 (44 U.S.C.
3501 et seq.). This proposed rule has been submitted to the Office of
Management and Budget for review and approval of the information
collection(s).
Type of submission, new or revision: Revision.
The title of the information collection: Appendix F to 10 CFR part
52 Design Certification Rule for the APR1400 Design.
The form number if applicable: NA.
How often the collection is required or requested: On occasion.
Who will be required or asked to respond: Applicant for a combined
license or a design certification amendment.
An estimate of the number of annual responses: 1 (0 annual
responses and 1 recordkeeper).
The estimated number of annual respondents: 1.
An estimate of the total number of hours needed annually to comply
with the information collection requirement or request: Approximately
37 hours of additional recordkeeping burden. The only burden associated
with this rule will be for recordkeeping by the applicant for this
design certification.
Abstract: The NRC is proposing to amend its regulations to certify
the APR1400 standard design. This action is necessary so that
applicants or licensees intending to construct and operate an APR1400
standard design may do so by referencing this DC rule. The applicant
for certification of the APR1400 standard design is KEPCO/KHNP.
The NRC is seeking public comment on the potential impact of the
information collection contained in this proposed rule and on the
following issues:
(1) Is the proposed information collection necessary for the proper
performance of the functions of the NRC, including whether the
information will have practical utility?
(2) Is the estimate of the burden of the proposed information
collection accurate?
(3) Is there a way to enhance the quality, utility, and clarity of
the information to be collected?
(4) How can the burden of the proposed information collection on
respondents be minimized, including the use of automated collection
techniques or other forms of information technology?
A copy of the OMB clearance package is available in ADAMS under
Accession No. ML18302A089 or may be viewed free of charge at the NRC
Public Document Room, One White Flint North, 11555 Rockville Pike, Room
O1-F21, Rockville, MD 20852. You may obtain information and comment
submissions related to the OMB clearance package by searching on
https://www.regulations.gov under Docket ID NRC-2015-0224.
You may submit comments on any aspect of these proposed information
collection(s), including suggestions for
[[Page 23502]]
reducing the burden and on the above issues, by the following methods:
Federal Rulemaking Website: Go to https://www.regulations.gov and search for Docket ID NRC-2015-0224.
Mail comments to: Information Services Branch, U.S.
Nuclear Regulatory Commission, Washington, DC 20555-0001, or by email
to [email protected], and to the Desk Officer, Office of
Information and Regulatory Affairs, NEOB-10202, (3150-XXXX) Office of
Management and Budget, Washington, DC 20503; email:
[email protected].
Submit comments by June 21, 2019. Comments received after this date
will be considered if it is practical to do so, but the NRC staff is
able to ensure consideration only for comments received on or before
this date.
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.
VII. 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 APR1400 Design Certification Rule
------------------------------------------------------------------------
ADAMS Accession
No./web link/
Document Federal Register
citation
------------------------------------------------------------------------
SECY-19-0020, ``Direct Final Rule-Advanced Power ML18302A069
Reactor 1400 Design Certification (RIN 3150-AJ67;
NRC-2015-0224)''....................................
KEPCO/KHNP Application for Design Certification of ML15006A037
the APR1400 Design..................................
APR1400 Design Control Document, Revision 3.......... ML18228A667
APR1400 Final Safety Evaluation Report............... ML18087A364
APR1400 Environmental Assessment..................... ML18306A607
APR1400 Standard Design Approval..................... ML18261A187
Regulatory History of Design Certification \1\....... ML003761550
KEPCO/KHNP Topical and Technical Reports:
APR1400-E-B-NR-16001-NP, Evaluation of Main Steam ML18178A215
and Feedwater Piping Applied to the Graded
Approach for the APR1400, Rev. 0 (July 2017)....
APR1400-E-B-NR-16002-NP, Evaluation of Safety ML18178A217
Injection and Shutdown Cooling Piping Applied to
the Graded Approach for the APR1400, Rev. 1 (May
2018)...........................................
APR1400-E-I-NR-14001-NP, Human Factors ML18212A345
Engineering Program Plan, Rev. 4 (July 2018)....
APR1400-E-I-NR-14002-NP, Operating Experience ML18081A101
Review Implementation Plan, Rev. 2 (January
2018)...........................................
APR1400-E-I-NR-14003-NP, Functional Requirements ML18081A091
Analysis and Function Allocation Implementation
Plan, Rev. 2 (January 2018).....................
APR1400-E-I-NR-14004-NP, Task Analysis ML18178A223
Implementation Plan, Rev. 3 (May 2018)..........
APR1400-E-I-NR-14006-NP, Treatment of Important ML18178A224
Human Actions Implementation Plan, Rev. 3 (May
2018)...........................................
APR1400-E-I-NR-14007-NP, Human-System Interface ML18178A212
Design Implementation Plan, Rev. 3 (May 2018)...
APR1400-E-I-NR-14008-NP, Human Factors ML18178A213
Verification and Validation Implementation Plan,
Rev. 3 (May 2018)...............................
APR1400-E-I-NR-14010-NP, Human Factors ML18081A088
Verification and Validation Scenarios, Rev. 2
(January 2018)..................................
APR1400-E-I-NR-14011-NP, Basic Human-System ML18178A214
Interface, Rev. 3 (May 2018)....................
APR1400-E-I-NR-14012-NP, Style Guide, Rev. 2 ML18081A096
(January 2018)..................................
APR1400-E-J-NR-14001-NP, Component Interface ML17094A131
Module, Rev. 1 (March 2017).....................
APR1400-E-J-NR-17001-NP, Secure Development and ML18108A470
Operational Environment for APR1400 Computer-
Based I&C Safety Systems, Rev. 0 (September
2017)...........................................
APR1400-E-N-NR-14001-NP, Design Features To ML18057B532
Address GSI-191, Rev. 3 (February 2018).........
APR1400-E-P-NR-14005-NP, Evaluations and Design ML18044B042
Enhancements To Incorporate Lessons Learned from
Fukushima Dai-Ichi Nuclear Accident, Rev. 2
(July 2017).....................................
APR1400-E-S-NR-14004-NP, Evaluation of Effects of ML18078A709
HRHF Response Spectra on SSCs, Rev. 3 (December
2017)...........................................
APR1400-E-S-NR-14005-NP, Evaluation of Structure- ML18078A699
Soil-Structure Interaction (SSSI) Effects, Rev.
2 (December 2017)...............................
APR1400-E-S-NR-14006-NP, Stability Check for NI ML18178A221
Common Basemat, Rev. 5 (May 2018)...............
APR1400-E-X-NR-14001-NP, Equipment Qualification ML18214A563
Program, Rev. 4 (July 2018).....................
APR1400-F-A-NR-14001-NP, Small Break LOCA ML17114A524
Evaluation Model, Rev. 1 (March 2017)...........
APR1400-F-A-NR-14003-NP, Post-LOCA Long Term ML17114A526
Cooling Evaluation Model, Rev. 1 (March 2017)...
APR1400-F-A-TR-12004-NP-A, Realistic Evaluation ML18233A431
Methodology for Large-Break LOCA of the APR1400
(August 2018)...................................
APR1400-F-C-NR-14001-NP, CPC Setpoint Analysis ML18199A563
Methodology for APR1400, Rev. 3 (June 2018).....
APR1400-F-C-NR-14002-NP, Functional Design ML17094A132
Requirements for a Core Operating Limit
Supervisory System for APR1400, Rev. 1 (February
2017)...........................................
APR1400-F-C-NR-14003-NP, Functional Design ML17114A522
Requirements for a Core Protection Calculator
System for APR1400, Rev. 1 (March 2017).........
APR1400-F-C-TR-12002-NP-A, KCE-1 Critical Heat ML17115A559
Flux Correlation for PLUS7 Thermal Design (April
2017)...........................................
APR1400-F-M-TR-13001-NP-A, PLUS7 Fuel Design for ML18232A140
the APR1400 (August 2018).......................
APR1400-H-N-NR-14005-NP, Summary Stress Report ML18178A218
for Primary Piping, Rev. 2 (September 2016).....
APR1400-H-N-NR-14012-NP, Mechanical Analysis for ML17244A015
New and Spent Fuel Storage Racks, Rev. 3 (August
2017)...........................................
APR1400-K-I-NR-14005-NP, Staffing and ML17094A152
Qualifications Implementation Plan, Rev. 1
(February 2017).................................
APR1400-K-I-NR-14009-NP, Design Implementation ML17094A153
Plan, Rev. 1 (February 2017)....................
APR1400-K-Q-TR-11005-NP-A, KHNP Quality Assurance ML18085B044
Program Description (QAPD) for the APR1400
Design Certification, Rev. 2 (October 2016).....
APR1400-Z-A-NR-14006-NP, Non-LOCA Safety Analysis ML17094A139
Methodology, Rev. 1 (February 2017).............
APR1400-Z-A-NR-14007-NP, Mass and Energy Release ML18212A338
Methodologies for LOCA and MSLB, Rev. 2 (May
2018)...........................................
[[Page 23503]]
APR1400-Z-A-NR-14011-NP, Criticality Analysis of ML18214A561
New and Spent Fuel Storage Racks, Rev. 3 (May
2018)...........................................
APR1400-Z-A-NR-14019-NP, CCF Coping Analysis, ML18225A340
Rev. 3 (July 2018)..............................
APR1400-Z-J-NR-14001-NP, Safety I&C System, Rev. ML18212A341
3 (May 2018)....................................
APR1400-Z-J-NR-14002-NP, Diversity and Defense-in- ML18214A557
Depth, Rev. 3 (May 2018)........................
APR1400-Z-J-NR-14003-NP, Software Program Manual, ML18214A559
Rev. 3 (May 2018)...............................
APR1400-Z-J-NR-14004-NP, Uncertainty Methodology ML18086B757
and Application for Instrumentation, Rev. 2
(January 2018)..................................
APR1400-Z-J-NR-14005-NP, Setpoint Methodology for ML18087A106
Safety-Related Instrumentation, Rev. 2 (January
2018)...........................................
APR1400-Z-J-NR-14012-NP, Control System CCF ML18212A343
Analysis, Rev. 3 (May 2018).....................
APR1400-Z-J-NR-14013-NP, Response Time Analysis ML18087A110
of Safety I&C System, Rev. 2 (January 2018).....
APR1400-Z-M-NR-14008-NP, Pressure-Temperature ML18087A112
Limits Methodology for RCS Heatup and Cooldown,
Rev. 1 (January 2018)...........................
APR1400-Z-M-TR-12003-NP-A, Fluidic Device Design ML17129A597
for the APR1400 (April 2017)....................
Westinghouse Topical and Technical Report:
WCAP-10697-NP-A, Common Qualified Platform ML13112A108
Topical Report, Rev. 3 (February 2013)..........
WCAP-17889-NP (APR1400-A-N-NR-17001-NP), ML18044B051
Validation of SCALE 6.1.2 with 238-Group ENDF/B-
VII.0 Cross Section Library for APR1400 Design
Certification, Rev. 0 (June 2014)...............
Combustion Engineering, Inc. Technical Reports:
CEN-312-NP, Overview Description of the Core ML19066A067
Operating Limit Supervisory System (COLSS), Rev.
01-NP (November 1986)...........................
CEN-310-NP-A, CPC and Methodology Changes for the ML19066A085
CPC Improvement Program (April 1986)............
------------------------------------------------------------------------
\1\ 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. 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.
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-2015-0224. The Federal
Rulemaking website allows you to receive alerts when changes or
additions occur in a docket folder. To subscribe: (1) Navigate to the
docket folder (NRC-2015-0224); (2) click the ``Sign up for Email
Alerts'' link; and (3) enter your email address and select how
frequently you would like to receive emails (daily, weekly, or
monthly).
List of Subjects in 10 CFR Part 52
Administrative practice and procedure, Antitrust, Combined license,
Early site permit, Emergency planning, 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 at Rockville, Maryland, this 17th day of May 2019.
For the Nuclear Regulatory Commission.
Annette Vietti-Cook,
Secretary of the Commission.
[FR Doc. 2019-10716 Filed 5-21-19; 8:45 am]
BILLING CODE 7590-01-P
