Document: NRC Regulatory Guide
Document ID: 0ae1e098-eccd-43e7-b12e-43b05aa1fe48
Document Type: regulatory_guide
Title: Safety-Related Concrete Structures for Nuclear Power Plants (Rev. 3)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1617/ML16172A240.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.142
CFR Part: 
CFR Title: 

Content:
U.S. NUCLEAR REGULATORY COMMISSION DRAFT REGULATORY GUIDE DG-1283 Proposed Revision 3 to Regulatory Guide 1.142 Issue Date: April 2019 Technical Lead: M. Sircar This RG is being issued in draft form to involve the public in the development of regulatory guidance in this area. It has not receiv approval and does not represent a final NRC staff position. Public comments are being solicited on this DG and its associated regu should be accompanied by appropriate supporting data. Comments may be submitted through the Federal rulemaking Web site, ht searching for draft regulatory guide DG-1283. Alternatively, comments may be submitted to the Rules, Announcements, and Dire Administration, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001. Comments must be submitted by the date in Register notice. Electronic copies of this DG, previous versions of DGs, and other recently issued guides are available through the NRC’s public Web site under the Regulatory Guides document collection of the NRC Library at https://nrcweb.nrc.gov/reading-rm/doc- collections/reg-guides/. The DG is also available through the NRC’s Agencywide Documents Access and Management System (ADAMS) at http://www.nrc.gov/reading-rm/adams.html, under Accession No. ML16172A240. The regulatory analysis may be found in ADAMS under Accession No. ML16172A239. SAFETY-RELATED CONCRETE STRUCTURES FOR NUCLEAR POWER PLANTS (OTHER THAN REACTOR VESSELS AND CONTAINMENTS) A. INTRODUCTION Purpose This regulatory guide (RG) describes methods and procedures that the staff of the U.S. Nuclear Regulatory Commission (NRC) considers acceptable to demonstrate compliance with NRC regulations for the analysis, design, construction, testing, and evaluation of safety related nuclear concrete structures, excluding concrete reactor vessels and concrete containments. Applicability This RG applies to applicants and licensees subject to Title 10 of the Code of Federal Regulations (10 CFR) Part 50, “Domestic Licensing of