Safety Related Concrete Structures for Nuclear Power Plants (Other Than Reactor Vessels and Containments), 32426-32427 [2020-11515]
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Federal Register / Vol. 85, No. 104 / Friday, May 29, 2020 / Notices
2001); 72 FR 3410 (Jan. 25, 2007)
amended to include exemptions
claimed pursuant to 5 U.S.C. 552a(k)(1),
and (k)(2), See 28 CFR 16.83.
[FR Doc. 2020–11528 Filed 5–28–20; 8:45 am]
BILLING CODE 4410–30–P
DEPARTMENT OF JUSTICE
[OMB Number 1105–0102]
Agency Information Collection
Activities; Proposed eCollection
eComments Requested; Guam World
War II Loyalty Recognition Program
Statement of Claim
Foreign Claims Settlement
Commission, Department of Justice.
ACTION: 30-Day notice.
AGENCY:
The Foreign Claims
Settlement Commission (Commission),
Department of Justice (DOJ), will be
submitting the following information
collection request to the Office of
Management and Budget (OMB) for
review and approval in accordance with
the Paperwork Reduction Act of 1995.
DATES: Comments are encouraged and
will be accepted for 30 days until June
29, 2020.
FOR FURTHER INFORMATION CONTACT:
Written comments and
recommendations for the proposed
information collection should be sent
within 30 days of publication of this
notice to www.reginfo.gov/public/do/
PRAMain. Find this particular
information collection by selecting
‘‘Currently under 30-day Review—Open
for Public Comments’’ or by using the
search function.
SUPPLEMENTARY INFORMATION: Written
comments and suggestions from the
public and affected agencies concerning
the proposed collection of information
are encouraged. Your comments should
address one or more of the following
four points:
—Evaluate whether the proposed
collection of information is
necessary for the proper
performance of the functions of the
Foreign Claims Settlement
Commission, including whether the
information will have practical
utility;
—Evaluate the accuracy of the agency’s
estimate of the burden of the
proposed collection of information,
including the validity of the
methodology and assumptions
used;
—Evaluate whether and if so how the
quality, utility, and clarity of the
information to be collected can be
enhanced; and
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SUMMARY:
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—Minimize the burden of the collection
of information on those who are to
respond, including through the use
of appropriate automated,
electronic, mechanical, or other
technological collection techniques
or other forms of information
technology, e.g., permitting
electronic submission of responses.
Overview of This Information
Collection
1. Type of Information Collection:
Extension.
2. The Title of the Form/Collection:
Statement of Claim for filing of Claims
in the Guam Claims Program Pursuant
to the Guam World War II Loyalty
Recognition Act, Title XVII, Public Law
114–328 (December 23, 2016)
3. The agency form number, if any,
and the applicable component of the
Department sponsoring the collection:
FCSC–2. Foreign Claims Settlement
Commission, Department of Justice.
4. Affected public who will be asked
or required to respond, as well as a brief
abstract:
Primary: Individuals.
Other: Estates.
Abstract: Information will be used as
a basis for the Commission to receive,
examine, adjudicate and render final
decisions with respect to claims for
compensation of claims pursuant to the
Guam World War II Loyalty Recognition
Act, Title XVII, Public Law 114–328
(December 23, 2016).
5. An estimate of the total number of
respondents and the amount of time
estimated for an average respondent to
respond: It is estimated that 5,000
individual respondents will complete
the application, and that the amount of
time estimated for an average
respondent to reply is approximately
two hours each.
6. An estimate of the total public
burden (in hours) associated with the
collection: 10,000 annual burden hours.
If additional information is required
contact: Melody D. Braswell,
Department Clearance Officer, United
States Department of Justice, Justice
Management Division, Policy and
Planning Staff, Two Constitution
Square, 145 N Street NE, 3E.405A,
Washington, DC 20530.
Dated: May 26, 2020.
Melody D. Braswell,
Department Clearance Officer for PRA, U.S.
Department of Justice.
[FR Doc. 2020–11599 Filed 5–28–20; 8:45 am]
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NUCLEAR REGULATORY
COMMISSION
[NRC–2019–0100]
Safety Related Concrete Structures for
Nuclear Power Plants (Other Than
Reactor Vessels and Containments)
Nuclear Regulatory
Commission.
ACTION: Regulatory guide; issuance.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) is issuing Revision 3
of Regulatory Guide (RG) 1.142, ‘‘Safety
Related Structures for Nuclear Power
Plants (Other than Reactor Vessels and
Containments).’’ The guide was revised
to endorse an updated version of
American Concrete Institute code (ACI)
349–2013, ‘‘Code Requirements for
Nuclear Safety-Related Concrete
Structures and Commentary.’’
DATES: Revision 3 to RG 1.142 is
available on May 29, 2020.
ADDRESSES: Please refer to Docket ID
NRC–2019–0100 when contacting the
NRC about the availability of
information regarding this document.
You may obtain publicly-available
information related to this document
using any of the following methods:
• Federal Rulemaking Website: Go to
https://www.regulations.gov and search
for Docket ID NRC–2019–0100. Address
questions about NRC dockets IDs in
Regulations.gov to Jennifer Borges;
telephone: 301–287–9127; email:
Jennifer.Borges@nrc.gov. For technical
questions, contact the individuals listed
in the FOR FURTHER INFORMATION
CONTACT section of this document.
• 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, 301–
415–4737, or by email to pdr.resource@
nrc.gov.
Revision 3 to RG 1.142 and the
regulatory analysis may be found in
ADAMS under Accession Nos.
ML20141L613 and ML16172A239,
respectively.
Regulatory guides are not
copyrighted, and NRC approval is not
required to reproduce them.
FOR FURTHER INFORMATION CONTACT:
Madhumita Sircar, telephone: 301–415–
1804; email: Madhumita.Sircar@nrc.gov,
and Edward O’Donnell, telephone: 301–
415–3317; email: Edward.Odonnell@
SUMMARY:
E:\FR\FM\29MYN1.SGM
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Federal Register / Vol. 85, No. 104 / Friday, May 29, 2020 / Notices
nrc.gov. Both are staff members of the
Office of Nuclear Regulatory Research,
U.S. Nuclear Regulatory Commission,
Washington, DC 20555–0001.
SUPPLEMENTARY INFORMATION:
I. Discussion
The NRC is issuing a revision to an
existing guide in the NRC’s ‘‘Regulatory
Guide’’ series. This series was
developed to describe and make
available to the public information
regarding methods that are acceptable to
the NRC staff for implementing specific
parts of the agency’s regulations,
techniques that the NRC staff uses in
evaluating specific issues or postulated
events, and data that the NRC staff
needs in its review of applications for
permits and licenses.
Revision 3 of RG 1.142 was issued
with a temporary identification of Draft
Regulatory Guide, DG–1283. This
revision (Revision 3) of RG 1.142
endorses, with certain exceptions,
American Concrete Institute (ACI) 349–
13, ‘‘Code Requirements for Nuclear
Safety-Related Concrete Structures and
Commentary,’’ except for Appendix D,
‘‘Anchoring to Concrete.’’ Appendix D
to ACI 349–13 is addressed by RG 1.199,
‘‘Anchoring Components and Structural
Supports in Concrete.’’
II. Additional Information
The NRC published a notice of the
availability of DG–1283 in the Federal
Register on April 23, 2019 (84 FR
16897) for a 60-day public comment
period. The public comment period
closed on June 24, 2019. Public
comments on DG–1283 and the staff
responses to the public comments are
available under ADAMS under
Accession No. ML20141L614.
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III. Congressional Review Act
This RG is a rule as defined in the
Congressional Review Act (5 U.S.C.
801–808). However, the Office of
Management and Budget has not found
it to be a major rule as defined in the
Congressional Review Act.
IV. Backfitting, Forward Fitting, and
Issue Finality
Issuance of this regulatory guide does
not constitute backfitting as defined in
title 10 of the Code of Federal
Regulations (10 CFR) section 50.109,
‘‘Backfitting,’’ and as described in NRC
Management Directive 8.4,
‘‘Management of Backfitting, Forward
Fitting, Issue Finality, and Information
Requests’’; constitute forward fitting as
that term is defined and described in
Management Directive 8.4; or affect
issue finality of any approval issued
under 10 CFR part 52, ‘‘Licenses,
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Certificates, and Approvals for Nuclear
Power Plants.’’ As explained in this
regulatory guide, applicants and
licensees are not required to comply
with the positions set forth in this
regulatory guide.
Dated: May 22, 2020.
For the Nuclear Regulatory Commission.
Edward F. O’Donnell,
Acting Chief, Regulatory Guidance and
Generic Issues Branch, Division of
Engineering, Office of Nuclear Regulatory
Research.
[FR Doc. 2020–11515 Filed 5–28–20; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[Docket Nos. 52–025 and 52–026; NRC–
2008–0252]
Southern Nuclear Operating Company,
Inc.; Vogtle Electric Generating Plant,
Units 3 and 4; Auxiliary Building Room
Heat-Up
Nuclear Regulatory
Commission.
ACTION: Exemption and combined
license amendment; issuance.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) is granting an
exemption to allow a departure from the
certification information of Tier 1 of the
generic design control document (DCD)
and is issuing License Amendment Nos.
181 and 180 to Combined Licenses
(COLs), NPF–91 and NPF–92,
respectively. The COLs were issued to
Southern Nuclear Operating Company,
Inc., and Georgia Power Company,
Oglethorpe Power Corporation, MEAG
Power SPVM, LLC, MEAG Power SPVJ,
LLC, MEAG Power SPVP, LLC, and the
City of Dalton, Georgia (collectively
SNC); for construction and operation of
the Vogtle Electric Generating Plant
(VEGP) Units 3 and 4, located in Burke
County, Georgia. The granting of the
exemption allows the changes to Tier 1
information asked for in the
amendment. Because the acceptability
of the exemption was determined in
part by the acceptability of the
amendment, the exemption and
amendment are being issued
concurrently.
DATES: The exemption and amendment
were issued on May 12, 2020.
ADDRESSES: Please refer to Docket ID
NRC–2008–0252 when contacting the
NRC about the availability of
information regarding this document.
You may obtain publicly-available
information related to this document
using any of the following methods:
SUMMARY:
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32427
• Federal Rulemaking Website: Go to
https://www.regulations.gov and search
for Docket ID NRC–2008–0252. Address
questions about NRC Docket IDs in
Regulations.gov to Jennifer Borges;
telephone: 301–287–9127; e-mail:
Jennifer.Borges@nrc.gov. For technical
questions, contact the individual listed
in the FOR FURTHER INFORMATION
CONTACT section of this document.
• 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, 301–
415–4737, or by email to pdr.resource@
nrc.gov. The ADAMS accession number
for each document referenced (if it is
available in ADAMS) is provided the
first time that it is mentioned in this
document. The request for the
amendment and exemption was
designated License Amendment Request
(LAR) 19–010 and submitted by letter
dated November 22, 2019 (ADAMS
Accession No. ML19326D430).
FOR FURTHER INFORMATION CONTACT:
Billy Gleaves, Office of Nuclear Reactor
Regulation, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001; telephone: 301–415–5848; email:
Bill.Gleaves@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Introduction
The NRC is issuing License
Amendment Nos. 181 and 180 to COLs
NPF–91 and NPF–92, respectively, and
is granting an exemption from Tier 1
information in the plant-specific DCD
for the AP1000. The AP1000 DCD is
incorporated by reference in Appendix
D, ‘‘Design Certification Rule for the
AP1000,’’ to part 52 of title 10 of the
Code of Federal Regulations (10 CFR).
The exemption, granted pursuant to
Paragraph A.4 of Section VIII,
‘‘Processes for Changes and
Departures,’’ of 10 CFR part 52,
appendix D, allows the licensee to
depart from the Tier 1 information. With
the requested amendment, SNC sought
proposed changes to the VEGP Tier 2
Updated Final Safety Analysis Report
(UFSAR) and related changes to plantspecific Tier 1 information and the
associated COL Appendix C.
Specifically, the LAR requested a
departure from current Tier 2 UFSAR
information as well as changes to the
plant-specific Tier 1 (and associated
COL Appendix C) information in Table
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Agencies
[Federal Register Volume 85, Number 104 (Friday, May 29, 2020)]
[Notices]
[Pages 32426-32427]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2020-11515]
=======================================================================
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[NRC-2019-0100]
Safety Related Concrete Structures for Nuclear Power Plants
(Other Than Reactor Vessels and Containments)
AGENCY: Nuclear Regulatory Commission.
ACTION: Regulatory guide; issuance.
-----------------------------------------------------------------------
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing
Revision 3 of Regulatory Guide (RG) 1.142, ``Safety Related Structures
for Nuclear Power Plants (Other than Reactor Vessels and
Containments).'' The guide was revised to endorse an updated version of
American Concrete Institute code (ACI) 349-2013, ``Code Requirements
for Nuclear Safety-Related Concrete Structures and Commentary.''
DATES: Revision 3 to RG 1.142 is available on May 29, 2020.
ADDRESSES: Please refer to Docket ID NRC-2019-0100 when contacting the
NRC about the availability of information regarding this document. You
may obtain publicly-available information related to this document
using any of the following methods:
Federal Rulemaking Website: Go to https://www.regulations.gov and search for Docket ID NRC-2019-0100. Address
questions about NRC dockets IDs in Regulations.gov to Jennifer Borges;
telephone: 301-287-9127; email: nrc.gov">[email protected]nrc.gov. For technical
questions, contact the individuals listed in the FOR FURTHER
INFORMATION CONTACT section of this document.
NRC's Agencywide Documents Access and Management System
(ADAMS): You may obtain publicly-available documents online in the
ADAMS Public Documents collection at https://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``Begin Web-based ADAMS
Search.'' For problems with ADAMS, please contact the NRC's Public
Document Room (PDR) reference staff at 1-800-397-4209, 301-415-4737, or
by email to nrc.gov">[email protected]nrc.gov.
Revision 3 to RG 1.142 and the regulatory analysis may be found in
ADAMS under Accession Nos. ML20141L613 and ML16172A239, respectively.
Regulatory guides are not copyrighted, and NRC approval is not
required to reproduce them.
FOR FURTHER INFORMATION CONTACT: Madhumita Sircar, telephone: 301-415-
1804; email: nrc.gov">[email protected]nrc.gov, and Edward O'Donnell, telephone:
301-415-3317; email: [email protected]
[[Page 32427]]
nrc.gov. Both are staff members of the Office of Nuclear Regulatory
Research, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001.
SUPPLEMENTARY INFORMATION:
I. Discussion
The NRC is issuing a revision to an existing guide in the NRC's
``Regulatory Guide'' series. This series was developed to describe and
make available to the public information regarding methods that are
acceptable to the NRC staff for implementing specific parts of the
agency's regulations, techniques that the NRC staff uses in evaluating
specific issues or postulated events, and data that the NRC staff needs
in its review of applications for permits and licenses.
Revision 3 of RG 1.142 was issued with a temporary identification
of Draft Regulatory Guide, DG-1283. This revision (Revision 3) of RG
1.142 endorses, with certain exceptions, American Concrete Institute
(ACI) 349-13, ``Code Requirements for Nuclear Safety-Related Concrete
Structures and Commentary,'' except for Appendix D, ``Anchoring to
Concrete.'' Appendix D to ACI 349-13 is addressed by RG 1.199,
``Anchoring Components and Structural Supports in Concrete.''
II. Additional Information
The NRC published a notice of the availability of DG-1283 in the
Federal Register on April 23, 2019 (84 FR 16897) for a 60-day public
comment period. The public comment period closed on June 24, 2019.
Public comments on DG-1283 and the staff responses to the public
comments are available under ADAMS under Accession No. ML20141L614.
III. Congressional Review Act
This RG is a rule as defined in the Congressional Review Act (5
U.S.C. 801-808). However, the Office of Management and Budget has not
found it to be a major rule as defined in the Congressional Review Act.
IV. Backfitting, Forward Fitting, and Issue Finality
Issuance of this regulatory guide does not constitute backfitting
as defined in title 10 of the Code of Federal Regulations (10 CFR)
section 50.109, ``Backfitting,'' and as described in NRC Management
Directive 8.4, ``Management of Backfitting, Forward Fitting, Issue
Finality, and Information Requests''; constitute forward fitting as
that term is defined and described in Management Directive 8.4; or
affect issue finality of any approval issued under 10 CFR part 52,
``Licenses, Certificates, and Approvals for Nuclear Power Plants.'' As
explained in this regulatory guide, applicants and licensees are not
required to comply with the positions set forth in this regulatory
guide.
Dated: May 22, 2020.
For the Nuclear Regulatory Commission.
Edward F. O'Donnell,
Acting Chief, Regulatory Guidance and Generic Issues Branch, Division
of Engineering, Office of Nuclear Regulatory Research.
[FR Doc. 2020-11515 Filed 5-28-20; 8:45 am]
BILLING CODE 7590-01-P