Document: NUREG-0800
Document ID: a28650b3-fa03-428d-a2bd-4a27f583710b
Document Type: srp
Title: NUREG-0800
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070484.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6
CFR Part: 
CFR Title: 

Content:
dent inerting system should be less than the containment design pressure.59 Technical Rationale:60 The technical rationale for application of the above acceptance criteria to pressure-suppression type BWR containments is discussed in the following paragraphs: 1. GDC 4 requires that structures, systems, and components important to safety be designed to withstand the environmental conditions and dynamic effects associated with normal DRAFT Rev. 7 - April 1996 6.2.1.1.C-8 operations, maintenance, testing, and postulated accidents. This SRP Section reviews containment design and related analyses of postulated accident conditions. Containment is the final barrier against the spread of contamination that is released from the reactor or its systems during an accident. It must be designed to function under the harsh environmental conditions and severe dynamic effects associated with accidents such as a LOCA or steam rupture. Meeting GDC 4 provides assurance that containment will prevent the release of radioactivity to the environment under the most challenging conditions it is expected to face. 2. GDC 16 requires containment to be designed as a leak tight barrier that will withstand the most extreme accident conditions for the duration of any postulated accident. Containment must be leak tight and withstand accidents because it is the final barrier against the release of radioactivity to the environment. Meeting GDC 16 provides assurance that radioactivity will not be released to the environment. 3. GDC 50 requires the containment structure and associated heat removal systems to be designed with margin to accommodate any loss-of-coolant accident such that the containment design leak rate is not exceeded. A loss-of-coolant accident potentially causes the greatest pressure surge and release of fission products when compared to any other accident. Since it is the most severe challenge expected, containment must be designed to definitively withstand this accident. Following GDC