Document: NUREG-0800
Document ID: de4e4c58-fcfd-4b28-8207-5ae6fc761ee2
Document Type: srp
Title: for the LWMS and GWMS, respectively.
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1502/ML15029A174.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.3
CFR Part: 
CFR Title: 

Content:
on, storage methods and procedures to avoid 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 the SWMS is protected from the effects of the detonation of explosive mixtures, exothermic reactions, and combustion of 11.4-21 Revision 4 – January 2016 radioactive wastes, and that the functions of its systems will not be compromised in meeting radiation protection dose standards for workers and effluent concentration limits of 10 CFR Part 20 associated with releases of contaminated fire protection water and combustion gases and smoke. Specific NRC guidance in meeting the requirements of GDC 3 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. This evaluation is performed in parallel with the fire protection analysis (FPA) addressed using the guidance in SRP Section 9.5.1.1 for plant areas identified with the presence of combustible or flammable radioactive materials. The RGs 1.189 and 1.205 explain the primary objectives of fire protection programs at nuclear power plants, and describe the regulatory framework the NRC has established, including but not limited to GDC 3, and the radiological exposure criteria of 10 CFR Part 20. NRC guidance, using the guidance in RGs 1.189 and 1.205, explains 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 are in 10 CFR 20.1201 and 10 CFR 20.1202 for plant workers, 10 CFR 20.1301 and 10 CFR