Design Limits, Loading Combinations, Materials, Construction and Testing of Concrete Containments, 41071-41072 [2020-14645]
Download as PDF
Federal Register / Vol. 85, No. 131 / Wednesday, July 8, 2020 / Notices
specific licenses authorizing the
medical use of this material. These
requirements and provisions provide for
the radiation safety of workers, the
general public, patients, and human
research subjects. Part 35 contains
mandatory requirements that apply to
NRC licensees authorized to administer
byproduct material or radiation to
humans for medical use. These
requirements also provide voluntary
provisions for specialty boards to apply
to have their certification processes
recognized by the NRC so that their
board certified individuals can use the
certifications as proof of training and
experience.
Dated: July 2, 2020.
For the Nuclear Regulatory Commission.
David C. Cullison,
NRC Clearance Officer, Office of the Chief
Information Officer.
[FR Doc. 2020–14656 Filed 7–7–20; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[NRC–2020–0159]
Design Limits, Loading Combinations,
Materials, Construction and Testing of
Concrete Containments
Nuclear Regulatory
Commission.
ACTION: Draft regulatory guide; request
for comment.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) is issuing for public
comment draft regulatory guide (DG),
DG–1372, ‘‘Design Limits, Loading
Combinations, Materials, Construction
and Testing of Concrete Containments.’’
This draft guide is proposed Revision 4
of regulatory guide (RG) 1.136 of the
same name. It updates the guidance for
materials, design, construction,
fabrication, examination, and testing of
concrete containments in nuclear power
plants through endorsement, with
exceptions, of the 2019 edition of the
American Society of Mechanical
Engineers Boiler & Pressure Vessel
Code, Section III, Division 2 (American
Concrete Institute Standard 359–19),
‘‘Code for Concrete Containments.’’
DATES: Submit comments by September
8, 2020. 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.
Although a time limit is given,
comments and suggestions in
connection with items for inclusion in
guides currently being developed or
jbell on DSKJLSW7X2PROD with NOTICES
SUMMARY:
VerDate Sep<11>2014
17:17 Jul 07, 2020
Jkt 250001
improvements in all published guides
are encouraged at any time.
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–2020–0159. Address
questions about NRC docket 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.
• Mail comments to: Office of
Administration, Mail Stop: TWFN–7–
A60M, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001, ATTN: Program Management,
Announcements and Editing Staff.
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:
George Thomas, Office of Nuclear
Reactor Regulation, telephone: 301–
415–6181, email: George.Thomas@
nrc.gov; and Edward O’Donnell, Office
of Nuclear Regulatory Research,
telephone: 301–415–3317, email:
Edward.ODonnell@nrc.gov. Both are
staff of the U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001.
SUPPLEMENTARY INFORMATION:
I. Obtaining Information and
Submitting Comments
A. Obtaining Information
Please refer to Docket ID NRC–2020–
0159 when contacting the NRC about
the availability of information regarding
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–2020–0159.
• 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. DG–1372 is available in
ADAMS under Accession No.
ML20105A215 and the regulatory
analysis for DG–1372 is available in
PO 00000
Frm 00110
Fmt 4703
Sfmt 4703
41071
ADAMS under Accession No.
ML20105A216.
B. Submitting Comments
Please include Docket ID NRC–2020–
0159 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 posts all comment
submissions at https://
www.regulations.gov as well as enters
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 submissions into
ADAMS.
II. Additional Information
The NRC is issuing for public
comment a draft guide in the NRC’s
‘‘Regulatory Guide’’ series. This series
was developed to describe methods that
are acceptable to the NRC staff for
implementing specific parts of the
agency’s regulations, to explain
techniques that the staff uses in
evaluating specific issues or postulated
events, and to describe information that
the staff needs in its review of
applications for permits and licenses.
The DG, titled ‘‘Design Limits,
Loading Combinations, Materials,
Construction and Testing of Concrete
Containments,’’ is a proposed revision
temporarily identified by its task
number, DG–1372. It is proposed
revision 4 of RG 1.136 of the same
name. The guide proposes revised
guidance to meet regulatory
requirements for materials, design,
construction, fabrication, examination,
and testing of concrete containments in
nuclear power plants.
This revision of the guide endorses,
with exceptions, the 2019 edition of the
American Society of Mechanical
Engineers (ASME) Boiler & Pressure
Vessel Code (B&PV), Section III,
Division 2 (American Concrete Institute
Standard 359–19), ‘‘Code for Concrete
Containments.’’ This revision of the
guide also addresses the acceptability of
the Section III Code Cases related to
E:\FR\FM\08JYN1.SGM
08JYN1
41072
Federal Register / Vol. 85, No. 131 / Wednesday, July 8, 2020 / Notices
Nuclear Regulatory
Commission.
ACTION: Regulatory guide; issuance.
Transportation of Radioactive and
Nonnuclear Hazardous Materials, N14
Subcommittee of the American National
Standards Institute (ANSI) in ANSI
N14.5–2014, ‘‘American National
Standard for Radioactive Materials—
Leakage Tests on Packages for
Shipment,’’ dated June 19, 2014.
DATES: Revision 2 to RG 7.4 is available
on July 8, 2020.
ADDRESSES: Please refer to Docket ID
NRC–2019–0091 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–2019–0091. Address
questions about NRC docket IDs in
Regulations.gov to Jennifer Borges;
telephone: 301–287–9127; email:
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.
Regulatory guides are not
copyrighted, and NRC approval is not
required to reproduce them.
FOR FURTHER INFORMATION CONTACT:
JoAnn Ireland, Office of Nuclear
Material Safety and Safeguards,
telephone: 301–415–6950, email:
JoAnn.Ireland@nrc.gov and Harriet
Karagiannis, Office of Nuclear
Regulatory Research, telephone: 301–
415–2493, email: Harriet.Karagiannis@
nrc.gov, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001.
SUPPLEMENTARY INFORMATION:
The U.S. Nuclear Regulatory
Commission (NRC) is issuing Revision 2
to Regulatory Guide (RG) 7.4, ‘‘Leakage
Tests on Packages for Shipment of
Radioactive Material.’’ This RG
(Revision 2) endorses the methods and
procedures developed by the Standards
Committee on Packaging and
I. Discussion
The NRC issues RGs to describe
methods that are acceptable to the staff
for implementing specific parts of the
agency’s regulations, to explain
techniques that the staff uses in
evaluating specific issues or postulated
events, and to describe information that
Division 2 of the ASME B&PV Code,
Section III.
The staff is also issuing for public
comment a draft regulatory analysis
(ADAMS Accession No. ML20105A216).
The staff developed a draft regulatory
analysis to assess the value of issuing or
revising a regulatory guide as well as
alternative courses of action.
III. Backfitting, Forward Fitting, and
Issue Finality
This regulatory guide provides
guidance for materials, design,
construction, fabrication, examination,
and testing of concrete containments in
nuclear power plants through
endorsement, with exceptions, of the
2019 edition of the American Society of
Mechanical Engineers Boiler & Pressure
Vessel Code, Section III, Division 2
(American Concrete Institute Standard
359 19), ‘‘Code for Concrete
Containments.’’ The issuance of this
regulatory guide does not constitute
backfitting as defined in section 50.109
of title 10 of the Code of Federal
Regulations (CFR), ‘‘Backfitting,’’ and as
described in NRC Management Directive
8.4, ‘‘Management of Backfitting,
Forward Fitting, Issue Finality, and
Information Requests,’’ or affect issue
finality of any approval issued under 10
CFR part 52, ‘‘Licenses, Certificates, and
Approvals for Nuclear Power Plants,’’
because, as explained in this regulatory
guide, licensees are not required to
comply with the positions set forth in
this regulatory guide.
Dated: July 1, 2020.
For the Nuclear Regulatory Commission.
Meraj Rahimi,
Chief, Regulatory Guidance and Generic
Issues Branch, Division of Engineering, Office
of Nuclear Regulatory Research.
[FR Doc. 2020–14645 Filed 7–7–20; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[NRC–2019–0091]
Leakage Tests on Packages for
Shipment of Radioactive Material
AGENCY:
jbell on DSKJLSW7X2PROD with NOTICES
SUMMARY:
VerDate Sep<11>2014
17:17 Jul 07, 2020
Jkt 250001
PO 00000
Frm 00111
Fmt 4703
Sfmt 4703
the staff needs in its review of
applications for permits and licenses.
Regulatory guides are not NRC
regulations and compliance with them
is not required. Methods and solutions
that differ from those set forth in RGs
are acceptable if supported by a basis for
the issuance or continuance of a permit
or license by the Commission.
Revision 2 of RG 7.4 was issued with
a temporary identification of Draft
Regulatory Guide, DG–7010. RG 7.4
(Revision 2) endorses an update to ANSI
N14.5–2014, ‘‘American National
Standard for Radioactive Materials—
Leakage Tests on Packages for
Shipment,’’ that has new information,
corrections, and clarifications, to ensure
integrity of radioactive material
containers and to minimize the
distribution of contamination to the
environment.
II. Additional Information
The NRC published a notice of the
availability of DG–7010 in the Federal
Register on April 8, 2019 (84 FR 13969)
for a 60-day public comment period.
The public comment period closed on
June 7, 2019, and the NRC received four
comment documents. Public comments
on DG–7010 and the staff responses to
the public comments are available in
ADAMS under Accession No.
ML19240B379. Revision 2 to RG 7.4 and
the regulatory analysis may be found in
ADAMS under Accession Nos.
ML19240B383 and ML20034F254,
respectively.
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
As discussed in Section D,
‘‘Implementation,’’ of RG 7.4, the NRC
staff does not intend to use the guidance
in this regulatory guide to support NRC
staff actions in a manner that would
constitute backfitting as that term is
defined in section 50.109 of title 10 of
the Code of Federal Regulations (10
CFR), ‘‘Backfitting,’’ and as described in
NRC Management Directive 8.4,
‘‘Management of Backfitting, Forward
Fitting, Issue Finality, and Information
Requests,’’ nor does the NRC staff
intend to use the guidance to affect the
issue finality of an approval under 10
CFR part 52, ‘‘Licenses, Certifications,
and Approvals for Nuclear Power
Plants.’’ The staff also does not intend
to use the guidance to support NRC staff
E:\FR\FM\08JYN1.SGM
08JYN1
Agencies
[Federal Register Volume 85, Number 131 (Wednesday, July 8, 2020)]
[Notices]
[Pages 41071-41072]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2020-14645]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[NRC-2020-0159]
Design Limits, Loading Combinations, Materials, Construction and
Testing of Concrete Containments
AGENCY: Nuclear Regulatory Commission.
ACTION: Draft regulatory guide; request for comment.
-----------------------------------------------------------------------
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing for
public comment draft regulatory guide (DG), DG-1372, ``Design Limits,
Loading Combinations, Materials, Construction and Testing of Concrete
Containments.'' This draft guide is proposed Revision 4 of regulatory
guide (RG) 1.136 of the same name. It updates the guidance for
materials, design, construction, fabrication, examination, and testing
of concrete containments in nuclear power plants through endorsement,
with exceptions, of the 2019 edition of the American Society of
Mechanical Engineers Boiler & Pressure Vessel Code, Section III,
Division 2 (American Concrete Institute Standard 359-19), ``Code for
Concrete Containments.''
DATES: Submit comments by September 8, 2020. 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. Although a time limit is given, comments and suggestions in
connection with items for inclusion in guides currently being developed
or improvements in all published guides are encouraged at any time.
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-2020-0159. Address
questions about NRC docket IDs in Regulations.gov to Jennifer Borges;
telephone: 301-287-9127; email: [email protected]. For technical
questions, contact the individuals listed in the FOR FURTHER
INFORMATION CONTACT section of this document.
Mail comments to: Office of Administration, Mail Stop:
TWFN-7-A60M, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001, ATTN: Program Management, Announcements and Editing Staff.
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: George Thomas, Office of Nuclear
Reactor Regulation, telephone: 301-415-6181, email:
[email protected]; and Edward O'Donnell, Office of Nuclear
Regulatory Research, telephone: 301-415-3317, email:
[email protected]. Both are staff of the U.S. Nuclear Regulatory
Commission, Washington, DC 20555-0001.
SUPPLEMENTARY INFORMATION:
I. Obtaining Information and Submitting Comments
A. Obtaining Information
Please refer to Docket ID NRC-2020-0159 when contacting the NRC
about the availability of information regarding 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-2020-0159.
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 [email protected]. DG-1372 is available in ADAMS under
Accession No. ML20105A215 and the regulatory analysis for DG-1372 is
available in ADAMS under Accession No. ML20105A216.
B. Submitting Comments
Please include Docket ID NRC-2020-0159 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 posts all comment submissions at https://www.regulations.gov as well as enters 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 submissions into ADAMS.
II. Additional Information
The NRC is issuing for public comment a draft guide in the NRC's
``Regulatory Guide'' series. This series was developed to describe
methods that are acceptable to the NRC staff for implementing specific
parts of the agency's regulations, to explain techniques that the staff
uses in evaluating specific issues or postulated events, and to
describe information that the staff needs in its review of applications
for permits and licenses.
The DG, titled ``Design Limits, Loading Combinations, Materials,
Construction and Testing of Concrete Containments,'' is a proposed
revision temporarily identified by its task number, DG-1372. It is
proposed revision 4 of RG 1.136 of the same name. The guide proposes
revised guidance to meet regulatory requirements for materials, design,
construction, fabrication, examination, and testing of concrete
containments in nuclear power plants.
This revision of the guide endorses, with exceptions, the 2019
edition of the American Society of Mechanical Engineers (ASME) Boiler &
Pressure Vessel Code (B&PV), Section III, Division 2 (American Concrete
Institute Standard 359-19), ``Code for Concrete Containments.'' This
revision of the guide also addresses the acceptability of the Section
III Code Cases related to
[[Page 41072]]
Division 2 of the ASME B&PV Code, Section III.
The staff is also issuing for public comment a draft regulatory
analysis (ADAMS Accession No. ML20105A216). The staff developed a draft
regulatory analysis to assess the value of issuing or revising a
regulatory guide as well as alternative courses of action.
III. Backfitting, Forward Fitting, and Issue Finality
This regulatory guide provides guidance for materials, design,
construction, fabrication, examination, and testing of concrete
containments in nuclear power plants through endorsement, with
exceptions, of the 2019 edition of the American Society of Mechanical
Engineers Boiler & Pressure Vessel Code, Section III, Division 2
(American Concrete Institute Standard 359 19), ``Code for Concrete
Containments.'' The issuance of this regulatory guide does not
constitute backfitting as defined in section 50.109 of title 10 of the
Code of Federal Regulations (CFR), ``Backfitting,'' and as described in
NRC Management Directive 8.4, ``Management of Backfitting, Forward
Fitting, Issue Finality, and Information Requests,'' or affect issue
finality of any approval issued under 10 CFR part 52, ``Licenses,
Certificates, and Approvals for Nuclear Power Plants,'' because, as
explained in this regulatory guide, licensees are not required to
comply with the positions set forth in this regulatory guide.
Dated: July 1, 2020.
For the Nuclear Regulatory Commission.
Meraj Rahimi,
Chief, Regulatory Guidance and Generic Issues Branch, Division of
Engineering, Office of Nuclear Regulatory Research.
[FR Doc. 2020-14645 Filed 7-7-20; 8:45 am]
BILLING CODE 7590-01-P