Document: NUREG-0800
Document ID: 7024eeeb-1819-4d56-9b72-fb63eab3836b
Document Type: srp
Title: and 3.9.3.
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1006/ML100620981.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.9.2
CFR Part: 
CFR Title: 

Content:
ct the orderly and safe shutdown and cooldown in one plant in the event of an accident in another. The load combination equations combine loads from normal operation and design-basis accidents so that the resulting structural designs provide for mutual independence of shared structures. Meeting this requirement provides assurance that containment internal structures and their associated components are capable of performing their required safety functions, even if they are shared by multiple nuclear power units. 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 testing, and construction techniques that are acceptable to the staff. GDC 50 requires that the internal structures of the containment be designed to withstand the effects of natural phenomena, combined with those of normal and accident conditions, including LOCA loads, without a loss of capability to perform their safety function. The load combinations and specifications cited in this SRP section provide acceptable engineering criteria to accomplish that function. 3.8.3-28 Revision 3 - May 2010 Meeting these requirements and criteria provide assurance that the internal structures of the containment will perform their intended safety function with sufficient margin when subjected to LOCA loads in combination with other applicable loads. 7. Compliance with 10 CFR Part 50, Appendix B, requires that applicants establish and maintain a quality assurance program for the design, construction, and operation of SSCs. SRP Section 3.8.3 provides