Document: NRC Regulatory Guide
Document ID: b2dd9fac-b26b-4819-a1b3-6e1765b4cfa3
Document Type: regulatory_guide
Title: Constraint on Releases of Airborne Radioactive Materials to the Environment for Licensees other than Power Reactors + HISTORY - HISTORY 04/2017 – Periodic Review of Revision 1 – Issues identified for future consideration 04/2010 – DG-4018 , Proposed Revision 1 12/1995 – Draft DG-8016
Source: NRC Regulatory Guide Division 4
Source URL: https://www.nrc.gov/docs/ML1720/ML17208A922.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-4.20
CFR Part: 
CFR Title: 

Content:
s not consistent with the regulatory changes incorporated in the 1991 revision of 10 CFR Part 20, “Standards for Protection Against Radiation.” For example, the discussion in Section C to RG 8.30, Regulatory Position 2.2, “Surveys for Airborne Yellowcake,” still refer to the terms “soluble” and “insoluble” instead of the inhalation classes D, W, and Y (the classification of a compound as Class D, W, or Y, is discussed in Appendix B to 10 CFR Part 20, “Annual Limits on Intake (ALIs) and Derived Air Concentrations (DACs) of Radionuclides for Occupational Exposure; Effluent Concentrations; Concentrations for Release to Sewerage”). Also, Regulatory Position 2.2, does not address yellowcake processed at uranium ISR facilities. Specifically, it does not address how to evaluate a uranium compound (uranyl peroxide) if it is not listed in Appendix B to 10 CFR Part 20. Section C, Regulatory Position 2.5, “Surveys for Surface Contamination in Restricted Area,” is using older dosimetry models (it is based on requirements of 10 CFR Part 20 prior to the 1991 revision). As a result, certain terminology is not consistent with what is being used currently by the NRC staff and licensees (e.g., “inactive area” and “active area” vs. “restricted area” and “unrestricted area”). Section C, Regulatory Position 2.6, “Surveys for Contamination of Skin and Personal Clothing,” and Regulatory Position 2.7, “Surveys of Equipment Prior to Release to Unrestricted Areas,” do not address beta-gamma-emitting radionuclides found in contamination at uranium recovery facilities. Section C, Regulatory Position 3, “Intake and Exposure Calculations,” although it includes technically correct guidance, it should be expanded to discuss 10 CFR 20.1204(g), “Determination of internal exposures,” to assist the uranium recovery industry on how to apply the regulatory requirement correctly at uranium ISRs. NOTE: This review was conducted in April 2017 and