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:
6 The NRC staff will review the use of Section F.1.3 on a case-by-case basis. For example, the staff will review the use of Equations (RF-7) or (RF-8) instead of the shear provisions of ACI 349-13, as suggested in Section RF.5 with reference to Section F.1.3 of ACI 349-13. 4.4.7 In the case of the reaction shear (beam action) at the supports in section F.5 of ACI 349-13, effective width of the critical section for the shear capacity at the supports is to be determined according to the zone of influence induced by the DG-1283, Page 15 local loads instead of the entire width of the support (see Regulatory Position 2.8). The zone of influence induced by the concentrated loads may be determined, for example, by an analysis. 5. Regulatory Position 5 The applicant or licensee needs to carefully examine and establish the applicability of the standards in ACI 349-13 and ACI 359-15 for other-than-containment safety-related concrete structures that frame into concrete containment structures, and for a foundation base mat that supports containment structures and other nuclear safety-related concrete structures. Those other-than-containment safety- related concrete structures and common foundation base mat should meet the provisions and load combinations in ACI 349-13 and ACI 359-15, as appropriate, to capture structure-to-structure interaction effects such as the effects on one structure resulting from loadings applied to a separate but monolithically connected structure. DG-1283, Page 16 D. IMPLEMENTATION The purpose of this section is to provide information on how applicants and licensees 1 may use this guide and information regarding the NRC’s plans for using this RG. In addition, it describes how the NRC staff complies with 10 CFR 50.109, “Backfitting” and any applicable finality provisions in 10 CFR Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants.” Use by Applicants and Licensees Applicants and licensees may voluntarily 2 use the