Document: NUREG-0800
Document ID: c0c5657a-82df-46c2-8cb5-fad0fd37fb58
Document Type: srp
Title: GASEOUS WASTE MANAGEMENT SYSTEMS1
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070610.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.3
CFR Part: 
CFR Title: 

Content:
he radioactive waste particularly where unfavorable site environmental conditions may impose unusual operational limitations upon the release of the effluent. The holdup capacity also provides time to allow the shorter lived isotopes a chance to decay before they are further processed or released to the atmosphere. Meeting the requirement of GDC 60 provides assurance that releases 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 limits specified in 10 CFR Part 50, Appendix I, and concentrations of radioactive material in gaseous effluents in any unrestricted area exceeding the limits specified in 10 CFR 20, Appendix B, Table 2, Column 1.55 5. Compliance with GDC 61 requires that the gaseous waste management system and other systems which 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. RG 1.140 furnishes design guidance acceptable to the NRC staff relating to design, testing, and maintenance criteria for air filtration and adsorption units and RG 1.143 furnishes design guidance acceptable to the NRC staff relating to seismic and quality DRAFT Rev. 3 - April 1996 11.3-10 group classification and quality assurance provisions for the GRS portion of the gaseous waste management system, structures, and components. Meeting the requirement 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 Part 20. In addition, meeting the requirement will help assure that the system will continue to perform its