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:
explosive mixture of hydrogen and oxygen. 4. General Design Criterion 60 (GDC 60) as it relates to the radioactive gaseous 28 waste management systems being designed to control releases of radioactive materials to the environment. 5. General Design Criterion 61 (GDC 61) as it relates to radioactivity control in 29 gaseous waste management systems and ventilation systems associated with fuel storage and handling areas. 6. 10 CFR Part 50 Appendix I, Sections II.B., II.C., and II.D., as it relates to the numerical guides for design objectives and limiting conditions for operation to meet the "as low as is reasonably achievable" criterion. The requirements of the Commission regulations identified above are met by using the regulatory positions contained in the following regulatory guides: a. Regulatory Guide 1.140 as it relates to the design testing and 30 maintenance of normal ventilation exhaust systems air filtration and adsorption units at nuclear power plants. b. Regulatory Guide 1.143 as it relates to the seismic design and quality group classification of components used in the gaseous waste treatment system GRS and structures housing the systems GRS and the provisions 31 used to control leakages. 7. Branch Technical Position (BTP) ETSB 11-5 as it relates to potential releases of radioactive materials as a result of postulated leakage or failure of a waste gas storage tank or offgas system.32 11.3-5 DRAFT Rev. 3 - April 1996 B. Specific criteria necessary to meet the relevant requirements of the Commission regulations are as follows: 1. The gaseous waste management systems should have the capability to meet the dose design objectives and include provisions to treat gaseous radioactive wastes such that: a. The calculated annual total quantity of all radioactive material released from each reactor at the site to the atmosphere will not result in an estimated annual external dose from gaseous effluents to any individual in unrestricted areas in excess of 0.05 mSv (5