Document: NUREG-0800
Document ID: faf774de-7226-41f8-ba11-7cf612907af6
Document Type: srp
Title: GASEOUS WASTE MANAGEMENT SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1306/ML13065A119.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.3
CFR Part: 
CFR Title: 

Content:
tem. When spent- activated carbon is stored in bulk quantities, storage methods and procedures should consider the potential for spontaneous heating and auto-ignition of activated carbon, which may be due to radioactive decay heat and adsorption of various vapors and gases, including oxygen. With regard to the GRS portion of the GWMS, if a potential for explosive hydrogen and oxygen mixtures exists, then designing the GRS to withstand the effects of such an explosion or providing the GRS with dual instrumentation and design features to annunciate and prevent the buildup of potentially explosive mixtures, satisfies the requirements of GDC 3. Using GDC 3 as guidance for SSCs important to safety provides assurance that the GRS is protected from the effects of an explosive mixture of hydrogen and oxygen, and that the safety functions of other SSCs will not be compromised in meeting effluent discharge concentrations of 10 CFR Part 20 associated with releases of contaminated 11.3-18 Draft Revision 4 – August 2014 fire protection water and combustion gases and smoke. Specific NRC guidance is provided in RG 1.189 and 1.205, IE Information Notices 83-14, 84-72, 88-08, and 90-50, and in NUREG/CR-4601. 5. Compliance with GDC 60 requires that each nuclear power plant design shall include means to control releases of radioactive materials in gaseous effluents to the environment during normal reactor operation, including AOOs. GDC 60 requires that the waste management systems provide for a holdup capacity sufficient to retain radioactive waste, particularly where unfavorable site environmental conditions may impose unusual operational limitations upon the release of effluents. The holdup capacityshould provide sufficient decay time for shorter-lived radionuclides before they are processed further or released to the environment. The holdup times are used in the source term calculations based on the methods described in RG 1.112 and NUREG-0016 (BWRs) or NUREG-0017 (PWRs) and