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:
riate regulatory guidance for a design methodology that is acceptable to the staff for protecting containment internal structures from the effects of dynamic loads. Meeting these requirements provides assurance that the internal structures of the containment will function as designed, will be capable of maintaining their structural integrity, and will perform their intended safety function.132 5. Compliance with GDC 5 prohibits the sharing of structures important to safety by multiple nuclear power units unless it can be shown that such sharing will not significantly impair the ability to perform their intended safety function, including, in the 3.8.3-35 DRAFT Rev. 2 - April 1996 event of an accident in one unit, an orderly shutdown and cooldown of the remaining units. GDC 5 applies to this SRP section because it ensures that the use of common structures in multiple-unit plants will not significantly affect the orderly and safe shutdown and cooldown in remaining units in the event of an accident in one unit. The loads that result during normal operation and the design basis accident are so combined in the load combination equations that the resulting design of the structures accounts for the presence of shared structures. Meeting this requirement provides assurance that structures other than containment and its associated components will continue to perform their required safety function even if they are shared by multiple nuclear power units.133 6. Compliance with GDC 50 requires that the reactor containment structure, including access openings, penetrations, and the containment heat removal system, be designed so that the containment structure and its internal compartments can accommodate, without exceeding the design leakage rate and with sufficient margin, the calculated pressure and temperature conditions resulting from any LOCA. SRP Section 3.8.3 provides detailed acceptance criteria and cites appropriate regulatory guidance for design methodology, material