Document: NUREG-0800
Document ID: 65414bbc-012c-477d-8c25-466f94c1671f
Document Type: srp
Title: GASEOUS WASTE MANAGEMENT SYSTEMS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350105.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.3
CFR Part: 
CFR Title: 

Content:
positions contained in the following regulatory guides: a. Regulatory Guide 1.140 as it relates to the design testing and maintenance of normal ventilation exhaust systems 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 and structures housing the systems and the provisions used to control leakages. 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 5 millirems to the total body or 15 millirems to the skin. b. The calculated annual total quantity of all radioactive iodine and radioactive material in particulate form released from each reactor at the site In effluents to the atmosphere will not result in an estimated annual dose or dose commitment from such radioactive iodine and radioactive material in particulate form 11.3-3 Rev. 2 - July 1981 for any individual in an unrestricted area from all pathways of exposure in excess of 15 millirems to any organ. c. In addition to a. and b., above, the gaseous waste management systems should include all items of reasonably demonstrated technology that when added to the system sequentially and in order of diminishing cost-benefit return, can for a favorable cost-benefit ratio effect reductions in dose to the population reasonably expected to be within 50 miles of the reactor. d. The concentrations of radioactive materials in gaseous effluents released to an unrestricted area should not exceed the limits specified in 10