Document: NUREG-0800
Document ID: 808cea66-69b8-4f91-9fb2-62b3b99bc87a
Document Type: srp
Title: NUREG-0800
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340579.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3
CFR Part: 
CFR Title: 

Content:
alytical proced- ures for determining pool swell loads are reviewed by the Containment Systems Branch (CSB). Design and analysis proced- ures for these plantforms are reviewed with particular emphasis on the framing and structural behavior under loads. d. Design Reports A design report described in Appendix C to subsection 3.8.4 of this SRP section is reviewed. e. Structural Audit A structural audit is conducted. 5. Structural Acceptance Criteria The design limits imposed on the various parameters that serve to quantify the structural behavior of the various interior structures of the contain- ment are reviewed, specifically with respect to stresses, strains, deformations, and factors of safety against structural failure, with emphasis on the extent of compliance with the applicable codes as indicated in subsection I.3 of this SRP section. 3.8.3-11 Rev. 1 - July 1981 6. Materials, Quality Control, and Special Construction Techniques Information provided on the materials that are used in the construction of the containment internal structures is reviewed. Among the major materials of construction that are reviewed are the concrete ingredients, reinforcing bars and splicers, and structural steel and'various supports and anchors. The quality control program that is proposed for the fabrication and construction of the containment interior structures is reviewed including nondestructive examination of the materials to determine physical properties, placement of concrete, and erection tolerances. Special, new, or unique construction techniques, if proposed, are reviewed on a case-by-case basis to determine their effects on the structural integrity of the completed interior structure. In addition, the following information should be provided. (a) The extent to which the materials and quality control programs comply with the "Code Requirements for Nuclear Safety-Related Concrete Structures" ACI 349 (Ref. 2), for concrete, and with the AISC "Specifications for Design,