Document: NUREG-0800
Document ID: 3e34268a-a6f4-4ce5-ba4d-7f2cec5a192e
Document Type: srp
Title: NUREG-0800
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070481.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6
CFR Part: 
CFR Title: 

Content:
of 10 CFR 50, §50.34(f)(3)(v)(A)(1), applicants subject to this article should evaluate an accident that releases hydrogen generated from a 100% fuel clad metal-water reaction. The evaluation should demonstrate that the appropriate article 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 either hydrogen burning in containment or initiation of the post-accident inerting system, if installed, should be analyzed. Unless specifically known, the post-accident inerting gas should be assumed to be carbon dioxide. 21 k. In meeting the requirements of 10 CFR 50, §50.34(f)(3)(v)(B)(1), applicants subject to this article should evaluate the containment design's capability to withstand full actuation of the post-accident inerting system, if installed. The peak pressure caused by inadvertent actuation of the post-accident inerting system should be less than the containment design pressure.22 Technical Rationale:23 The technical rationale for application of the above acceptance criteria to PWR dry containments is discussed in the following paragraphs: 1. 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. This SRP Section evaluates the peak pressure and temperature conditions for which the containment must be designed. Containment must be leak tight and withstand accidents because it is the final barrier against the release of radioactivity to the environment. DRAFT Rev. 3 - April 1996 6.2.1.1.A-6 Meeting GDC 16 provides assurance that radioactivity will not be released to the environment. 2. GDC 50 requires the containment structure and associated heat removal system to be designed with margin to accommodate any loss-of-coolant