[Federal Register Volume 86, Number 33 (Monday, February 22, 2021)]
[Notices]
[Pages 10602-10603]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2021-03457]
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NUCLEAR REGULATORY COMMISSION
[NRC-2020-0159]
Design Limits, Loading Combinations, Materials, Construction and
Testing of Concrete Containments
AGENCY: Nuclear Regulatory Commission.
ACTION: Regulatory guide; issuance.
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SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing
Revision 4 to Regulatory Guide (RG) 1.136, ``Design Limits, Loading
Combinations, Materials, Construction and Testing of Concrete
Containments.'' 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 (ASME) Boiler & Pressure Vessel (B&PV) Code, Section III,
Division 2 (American Concrete Institute (ACI) Standard 359-19), ``Code
for Concrete Containments.''
DATES: Revision 4 to RG 1.136 is available on February 22, 2021.
ADDRESSES: Please refer to Docket ID NRC-2020-0159 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-2020-0159. Address
questions about Docket IDs in Regulations.gov to Stacy Schumann;
telephone: 301-415-0624; email: [email protected]. 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 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]. Revision 4 to RG 1.136 and the
regulatory analysis may be found in ADAMS under Accession Nos.
ML20301A167 and ML20105A216, respectively.
Attention: The PDR, where you may examine and order copies
of public documents, is currently closed. You may submit your request
to the PDR via email at [email protected] or call 1-800-397-4209 or
301-415-4737, between 8:00 a.m. and 4:00 p.m. (EST), Monday through
Friday, except Federal holidays.
Regulatory guides are not copyrighted, and NRC approval is not
required to reproduce them.
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. 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, 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.
Revision 4 of RG 1.136 was issued with a temporary identification
of Draft Regulatory Guide, DG-1372. This revision provides 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 Division 2 of the ASME B&PV Code, Section III (ACI Standard
359-19), ``Code for Concrete Containments.'' This revision of the guide
also addresses the acceptability of the Section III Code Cases related
to Division 2 of the ASME B&PV Code, Section III.
II. Additional Information
The NRC published a notice of the availability of DG-1372 in the
Federal Register on July 8, 2020 (85 FR 41071) for a 60-day public
comment period. The public comment period closed on September 8, 2020.
Public comments on DG-1372 and the staff responses to the public
comments are available in ADAMS under Accession No. ML20301A168.
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
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 Division 2 of the ASME B&PV Code,
Section III (ACI 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: February 16, 2021.
[[Page 10603]]
For the Nuclear Regulatory Commission.
Meraj Rahimi,
Chief, Regulatory Guidance and Generic Issues Branch, Division of
Engineering, Office of Nuclear Regulatory Research.
[FR Doc. 2021-03457 Filed 2-19-21; 8:45 am]
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