Document: NUREG-0800
Document ID: 919b8fa0-8b11-41bd-9694-2c62120b843b
Document Type: srp
Title: Revision 7 - March 2007
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0636/ML063600403.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6
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100% fuel clad metal-water reaction. The evaluation should demonstrate that the appropriate articles for service level C limits (considering pressure and dead load only), for either concrete or steel containments, from ASME Boiler Pressure Vessel Code, Section III, are met. In addition to the containment pressurization caused directly by this accident, the increase in pressure from hydrogen burning in containment should be analyzed. 6.2.1.1.C-8 Revision 7 - March 2007 Technical Rationale The technical rationale for application of these acceptance criteria to the areas of review addressed by this SRP section 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 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