Document: NUREG-0800
Document ID: 97794ae3-595f-4668-8cfe-f438587bc747
Document Type: srp
Title: COMBUSTIBLE GAS CONTROL IN CONTAINMENT
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0706/ML070620006.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6.2.5
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CFR Title: 

Content:
REVIEW RESPONSIBILITIES Primary - Organization responsible for review of containment integrity Secondary - None I. AREAS OF REVIEW 10 CFR 50.44, “Combustible Gas Control for Nuclear Power Reactors,” is applicable to all power reactors. Regulatory Guide (RG) 1.7, Revision 3, “Control of Combustible Gas Concentrations in Containment” describes methods that are acceptable to the NRC staff for implementing 10 CFR 50.44. Note: This standard review plan (SRP) is primarily intended to cover new water-cooled reactor plant applications with characteristics (e.g., type and quantity of cladding materials) such that the potential for production of combustible gases is comparable to light water reactor designs licensed as of October 16, 2003 (the effective date of a major revision of 10 CFR 50.44). Guidance for a plant which had already received its operating license as of October 16, 2003, or for non-water-cooled reactor plants or water-cooled reactor plants that do not fall within the description above, may be found in RG 1.7, Revision 3. 6.2.5-2 Revision 3 - March 2007 This section covers the information presented in the applicant’s safety analysis report (SAR) or design control document (DCD) concerning the control of combustible gases in the containment following a beyond-design-basis accident involving 100 percent fuel clad-coolant reaction or postulated accident to ensure conformance with the requirements of General Design Criteria (GDC) 5, 41, 42, and 43, and 10 CFR 50.44. Following an accident, hydrogen and oxygen may accumulate inside the containment. After an accident, combustible gas is predominantly generated within the containment as a result of: (a) Fuel clad-coolant reaction between the fuel cladding and the reactor coolant. (b) Molten core-concrete interaction in a severe core melt sequence with a failed reactor vessel. If a sufficient amount of combustible gas is generated, it may react with the oxygen present in the containment at a rate rapid enough