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:
nce that the nuclear power reactors will meet the requirement that controlled releases of radioactive material in effluents to the 11.3-9 DRAFT Rev. 3 - April 1996 environment of unrestricted areas in the vicinity of a nuclear facility will be kept as low as is reasonably achievable and that the gaseous waste management system will have the necessary design features and equipment to control releases of gaseous effluent to the environment in accordance with the requirements of 10 CFR Part 20, § 1302; 10 CFR Part 50, Appendix I; and GDC 60 and 61.53 3. General Design Criterion 3 provides that structures, systems, and components important to safety shall be designed and located to minimize, consistent with other safety requirements, the probability and effect of fires and explosions. With regard to the GRS portion of the Gaseous Waste Management System, this GDC requires that if a potential for explosive hydrogen/oxygen mixtures exist, then the GRS must be designed to withstand the effects of such an explosion, or be provided with dual instrumentation and design features to annunciate and prevent the buildup of potentially explosive mixtures, respectively. Meeting the requirements of GDC 3 provide assurance that the GRS is protected from the effects of an explosive mixture of hydrogen and oxygen and that the safety functions of other structures, systems, and components will not be compromised.54 4. Compliance with GDC 60 requires that design provisions be included in the nuclear power unit to control suitably the release of radioactive materials in gaseous effluents to the environment during normal reactor operation, including anticipated operational occurrences. GDC 60 specifies that the radwaste processing systems provide for a holdup capacity sufficient to retain the 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