Document: NUREG-0800
Document ID: 2f527583-f167-477c-9a93-bc8f7db676b6
Document Type: srp
Title: for the LWMS and GWMS, respectively.
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1307/ML13072A545.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.3
CFR Part: 
CFR Title: 

Content:
ved from gas delay tanks or beds). 6. Radioactive materials should be processed, handled, and stored using equipment, methods, and procedures that avoid or minimize potential releases of radioactivity in the event of a fire. The GDC 3 relates to fire protection features for SSCs important to safety and can be used to provide guidance for SWMS design features and operational safeguards to prevent, for example, introduction and mixing of chemical additives with ion-exchange resins in avoiding the generation of exothermic reactions and explosive gas mixtures. 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. Using GDC 3 provides reasonable assurance that radioactive materials are protected from the effects of fires and that the function of plant systems and components will not be compromised in meeting effluent discharge concentration limits of 10 CFR Part 20 associated with releases of contaminated fire protection water and combustion gases and smoke. In considering fire protection, RGs 1.189 and 1.205 explains the primary objectives of fire protection programs at nuclear power plants, and describes the NRC regulatory framework. RG 1.189 and 1.205 explain that in order to meet NRC regulations, a fire hazards analysis should demonstrate that the plant will maintain the ability to minimize the potential for radioactive releases in plant areas and to the environment in the event of a fire. Such events are treated as AOOs, which should not result in unacceptable radiological consequences under the criteria of 10 CFR Part 20. The requirements and dose limits for protection against radiation during plant operations appear in 10 CFR 20.1201 and 10 CFR 20.1202 for plant workers, 10 CFR 20.1301 and 10 CFR 20.1302 for members of the public, and