Document: NUREG-0800
Document ID: ab4f353d-c299-479d-ab25-834f97196988
Document Type: srp
Title: CONCRETE AND STEEL INTERNAL STRUCTURES OF STEEL OR CONCRETE
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070326.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.8.3
CFR Part: 
CFR Title: 

Content:
rating loads with abnormal loads, normal operating loads with severe environmental and abnormal loads, and normal operating with extreme environmental and abnormal loads. b. In addition, the following information is reviewed: i. The extent to which the applicant's criteria comply with the "Code Requirements for Nuclear Safety-Related Concrete Structures," ACI 349-76 (Ref. 2) for concrete and with the AISC N690, 16*17 18 19 "Specification for Design, Fabrication and Erection of Structural Steel for Buildings" (Ref. 3) for steel, as applicable. ii. For concrete portions of the divider barrier of the PWR ice-condenser containment and for concrete portions of the drywell of the Mark III20 BWR containment, the extent to which the applicant's loading criteria comply with Article CC-3000 of the ASME Section III, Division 2 Code for "Concrete Reactor Vessels and Containments," (Ref. 4). "(ACI 359). 21 DRAFT Rev. 2 - April 1996 3.8.3-8 For steel pressure-resisting portions of these two structures, the extent to which the applicant's loading criteria comply with Article NE-3000 of Subsection NE of the ASME Code, Section III, Division 1, (Ref. 5) as 22 augmented by Regulatory Guide 1.57 (Ref. 9).23 4. Design and Analysis Procedures The design and analysis procedures utilized for the containment internal structures are reviewed with emphasis on the extent of compliance with the applicable codes as indicated in subsection I.3 of this SRP section, including those applicable to the following areas: a. For PWR Dry Containment Internal Structures i. Concrete Supports for Reactor Coolant System The support system for the reactor vessel and steam generators, as described in subsSection I of this SRP Section, should be designed to 24 resist various combinations of loadings, including normal operating loads, seismic loads, and loss of coolant and other pipe rupture accident loads. Analytical procedures for determining seismic loads are as described in Standard Review PlanSRP Section