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:
pingement, impact forces associated with the postulated ruptures of piping, and loads applicable to some structures such as drag forces in the PWR ice-condenser containment. In addition for structures or structural components located in or above the suppression pools of BWR Mark III containments the applicable LOCA-related or LOCA/SRV-related hydrodynamic loads manifested as jet loads and/or pressure loads should be considered. The various combinations of the above loads that are normally postulated and reviewed include the following: normal operating loads; normal operating loads with severe environmental loads; normal operating loads with extreme environmental loads; normal operating loads with abnormal loads; normal operating loads with severe environmental and abnormal loads; and normal operating with extreme environmental and abnormal loads. 3.8.3-6 Rev. 1 - July 1981 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 "Specifi- cation 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 III 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). For steel pressure-resist- ing 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, Div. 1, (Ref. 5) as augmented by Regulatory Guide 1.57 (Ref. 9). 4. Design and Analysis Procedures The design and analysis procedures utilized .for the containment internal structures are reviewed with emphasis on