Document: NUREG-0800
Document ID: 23331bab-fa00-40fd-8357-d8db908b4532
Document Type: srp
Title: GASEOUS WASTE MANAGEMENT SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0707/ML070710366.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.3
CFR Part: 
CFR Title: 

Content:
of radioactive materials in gaseous effluents to unrestricted areas during normal plant operation and anticipated operational occurrences will not result in offsite radiation doses exceeding the dose objectives specified in Appendix I to 10 CFR Part 50 and concentrations of radioactive materials in gaseous effluents in any unrestricted area exceeding the limits specified in Table 2, Column 1, of Appendix B to 10 CFR Part 20. 6. Compliance with GDC 61 requires that the GWMS and other systems (either as permanently installed systems or in combination with mobile equipment) that may contain radioactivity shall be designed to assure adequate safety under normal and postulated accident conditions. This criterion specifies that such facilities shall be designed with a capability to permit inspection and testing of components important to safety and with suitable shielding for radiation protection. Regulatory Guide 1.140 provides design guidance acceptable to the NRC staff relating to design, testing, and maintenance criteria for air filtration and adsorption units, and Regulatory Guide 1.143 describes design guidance acceptable to the NRC staff relating to seismic and quality group classification and quality assurance provisions for the GRS portion of the GWMS structures and components, involving gaseous wastes produced during normal operation and anticipated operational occurrences. Meeting the requirements of GDC 61 provides assurance that releases of radioactive materials during normal operation and during anticipated operational occurrences will not result in radiation doses that exceed the limits specified in 10 CFR 20.1302. In addition, meeting these requirements will help to assure that the GWMS will continue to perform its safety function(s) under postulated accident conditions, given the guidance of Regulatory Guide 1.52. 7. Appendix I to 10 CFR Part 50 provides numerical guidance for design objectives to meet the requirements that radiation doses from