Design Limits, Loading Combinations, Materials, Construction and Testing of Concrete Containments, 10602-10603 [2021-03457]

Download as PDF 10602 Federal Register / Vol. 86, No. 33 / Monday, February 22, 2021 / Notices it to be a major rule as defined in the Congressional Review Act. IV. Backfitting, Forward Fitting, and Issue Finality Revision 4 of RG 1.105 endorses ANSI/ISA 67.04.01–2018 and does not constitute backfitting as defined in 10 CFR 50.109, ‘‘Backfitting,’’ and as described in NRC Management Directive (MD) 8.4, ‘‘Management of Backfitting, Forward Fitting, Issue Finality, and Information Requests’’; constitute forward fitting as that term is defined and described in MD 8.4; or affect the issue finality of any approval issued under 10 CFR part 52. As explained in Revision 4 to RG 1.105, applicants and licensees are not required to comply with the positions set forth in the RG. Dated: February 16, 2021. For the Nuclear Regulatory Commission. Meraj Rahimi, Chief, Regulatory Guidance and Generic Issues Branch, Division of Engineering, Office of Nuclear Regulatory Research. [FR Doc. 2021–03466 Filed 2–19–21; 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: Regulatory guide; issuance. AGENCY: 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: tkelley on DSKBCP9HB2PROD with NOTICES SUMMARY: VerDate Sep<11>2014 19:48 Feb 19, 2021 Jkt 253001 • 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: Stacy.Schumann@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 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 pdr.resource@ nrc.gov. 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 pdr.resource@nrc.gov 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: George.Thomas2@ 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. 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 PO 00000 Frm 00073 Fmt 4703 Sfmt 4703 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. E:\FR\FM\22FEN1.SGM 22FEN1 Federal Register / Vol. 86, No. 33 / Monday, February 22, 2021 / Notices 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] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [NRC–2019–0253] Final Revision to Branch Technical Position 7–19 Guidance for Evaluation of Defense in Depth and Diversity to Address Common-Cause Failure Due to Latent Design Defects in Digital Safety Systems; Correction Nuclear Regulatory Commission. ACTION: Standard review plan-final section revision; issuance; correction. AGENCY: The U.S. Nuclear Regulatory Commission (NRC) is correcting a notice that was published in the Federal Register on January 29, 2021, regarding the final revision to Branch Technical Position (BTP) 7–19, ‘‘Guidance for Evaluation of Defense in Depth and Diversity to Address Common-Cause Failure Due to Latent Design Defects in Digital Safety Systems.’’ This action is necessary to correct the Agency Document Access and Management System (ADAMS) Accession number for the staff responses to public comments on the draft version of BTP 7–19. DATES: The correction takes effect on February 22, 2021. ADDRESSES: Please refer to Docket ID NRC–2019–0253 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–2019–0253. Address questions about Docket IDs in Regulations.gov to Stacy Schumann; telephone: 301–415–0624; email: Stacy.Schumann@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 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 tkelley on DSKBCP9HB2PROD with NOTICES SUMMARY: VerDate Sep<11>2014 19:48 Feb 19, 2021 Jkt 253001 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 final revision 8 of BTP 7– 19, Final Revision to Branch Technical Position 7–19 Guidance for Evaluation of Defense in Depth and Diversity to Address Common-Cause Failure Due to Latent Design Defects in Digital Safety Systems is available in ADAMS under Accession No. ML20339A642. • 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 pdr.resource@nrc.gov 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. FOR FURTHER INFORMATION CONTACT: Mark D. Notich, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001; telephone: 301–415– 3053, email: Mark.Notich@nrc.gov. SUPPLEMENTARY INFORMATION: On January 29, 2021 the NRC issued a notice in the Federal Register for the final revision of BTP 7–19 (86 FR 7577). The notice included the incorrect ADAMS Accession Number for the BTP 7–19, Revision 8, public comment resolution document. This document corrects the ADAMS Accession Number for the BTP 7–19, Revision 8, public comment resolution document. The public comment resolution document is available in ADAMS under Accession No. ML20339A646. Dated: February 16, 2021. For the Nuclear Regulatory Commission. Dennis C. Morey, Chief, Licensing Project Branch, Division of Operating Reactors, Office of Nuclear Reactor Regulation. [FR Doc. 2021–03435 Filed 2–19–21; 8:45 am] BILLING CODE 7590–01–P 10603 a. Holtec International (HI–STORE Consolidated Interim Storage Facility), Sierra Club Appeal of LBP–20–6 (Tentative) b. DTE Electric Co. (Fermi 2), Appeal of LBP–20–7 (Denial of Hearing Request Related to Spent Fuel Pool License Amendment) (Tentative) (Contact: Wesley Held: 301–287– 3591) Additional Information: Due to COVID–19, there will be no physical public attendance. The public is invited to attend the Commission’s meeting live in one of two ways; via webcast at the Web address—https://video.nrc.gov/ or via teleconference. Details for joining the teleconference in listen only mode may be found at https://www.nrc.gov/ pmns/mtg. 10:00 a.m. Briefing on Equal Employment Opportunity, Affirmative Employment, and Small Business (Public Meeting) (Contact: Nadim Khan: 301–415– 1119) Additional Information: Due to COVID–19, there will be no physical public attendance. The public is invited to attend the Commission’s meeting live in one of two ways; via webcast at the Web address—https://video.nrc.gov/ or via teleconference. Details for joining the teleconference in listen only mode may be found at https://www.nrc.gov/ pmns/mtg. Week of February 22, 2021—Tentative There are no meetings scheduled for the week of February 22, 2021. Week of March 1, 2021—Tentative There are no meetings scheduled for the week of March 1, 2021. Week of March 8, 2021—Tentative There are no meetings scheduled for the week of March 8, 2021. Week of March 15, 2021—Tentative NUCLEAR REGULATORY COMMISSION There are no meetings scheduled for the week of March 15, 2021. [NRC–2021–0001] Week of March 22, 2021—Tentative Sunshine Act Meetings There are no meetings scheduled for the week of March 22, 2021. Weeks of February 15, 22, March 1, 8, 15, 22, 29, 2021. PLACE: Commissioners’ Conference Room, 11555 Rockville Pike, Rockville, Maryland. STATUS: Public. TIME AND DATE: Week of February 15, 2021 Thursday, February 18, 2021 9:55 a.m. Affirmation Session (Public Meeting) (Tentative) PO 00000 Frm 00074 Fmt 4703 Sfmt 4703 Week of March 29, 2021—Tentative There are no meetings scheduled for the week of March 29, 2021. CONTACT PERSON FOR MORE INFORMATION: For more information or to verify the status of meetings, contact Wesley Held at 301–287–3591 or via email at Wesley.Held@nrc.gov. The schedule for Commission meetings is subject to change on short notice. E:\FR\FM\22FEN1.SGM 22FEN1

Agencies

[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.

-----------------------------------------------------------------------

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]
BILLING CODE 7590-01-P