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:
he drywell that resist pressure and are not backed by concrete, such as the drywell head, the appropriate sect- ions of Subsection NE of the ASME Code, Section III, Division 1, (Ref. 5) should be used together with the applicable loads, load combinations, and acceptance criteria of Regulatory Guide 1.57 (Ref. 11). Specifically, the load combinations of subsection II.3 of Standard Review Plan Section 3.8.2 apply. For the lower vent portion of the drywell: (i) If the main reinforcement of the drywell is carried down between the vent holes and the reinforced concrete section is relied upon for structural. purposes, the criteria that apply to concrete portions of the drywell as described above will apply. (ii) If the main reinforcement of the drywell is terminated above the vent holes and two steel plates lining both faces of the drywell are a line utilized for structural purposes, the cri- teria that apply to steel portions of the drywell as described above will apply. (iii) If other structural systems are used in the vent region, the loads and load combinations are reviewed and judged on a case-by-case basis. 4. Design and Analysis Procedures The design and analysis procedures utilized for the interior structures of the containment are acceptable if found in accordance with the following: a. For PWR Dry Containment Internal Structures (i) Primary Shield Wall and Reactor Cavity The design and analysis procedures utilized for the shield wall are acceptable if in accordance with the ACI 349 Code (Ref. 2). This code is based on the strength design method. However, the use of ACI 318 Code working stress design method where actual elastic/linear stresses in the concrete and reinforcement are determined and compared with, their corresponding allowables, is considered acceptable. Analyses for loss-of-coolant accident loads applicable to the primary shield wall, such as for the cavity differential pres- sure combined with pipe rupture reaction forces, are acceptable if these