Document

Safety Related Concrete Structures for Nuclear Power Plants (Other Than Reactor Vessels and Containments)

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 Vessel...

PDF version Source Record

Nuclear Regulatory Commission

[NRC-2019-0100]

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: 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 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 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@ ( printed 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

Legal Citation

Federal Register Citation

Use this for formal legal and research references to the published document.

85 FR 32426

Web Citation

Suggested Web Citation

Use this when citing the archival web version of the document.

“Safety Related Concrete Structures for Nuclear Power Plants (Other Than Reactor Vessels and Containments),” thefederalregister.org (May 29, 2020), https://thefederalregister.org/documents/2020-11515/safety-related-concrete-structures-for-nuclear-power-plants-other-than-reactor-vessels-and-containments.