Document: NRC Regulatory Guide
Document ID: 96baa826-d3bb-478b-8f38-e74500f6d433
Document Type: regulatory_guide
Title: 06/2009 (Rev. 2)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML0911/ML091170109.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.21
CFR Part: 
CFR Title: 

Content:
rent-year effluents, (2) current-year direct radiation from the facility, and (3) accumulated radioactivity from prior-year effluents that are not already included in items 1 and 2. These requirements include the following considerations: 1. “Whole body and organ doses” (ICRP-2 concepts). 2. “Any member of the public” means any individual except when that individual is receiving an occupational dose. 3. The “unrestricted area” means in the general environment outside the (boundaries of) locations under the control of persons possessing or using radioactive material. This is the area outside the site boundary, excluding the controlled area and the restricted area. (See the definition of “generally applicable environmental radiation standards” in 10 CFR 20.1003, “Definitions.”) 4. “Current-year effluents” includes both normal and abnormal discharges to the unrestricted area. 5. “Current-year direct radiation” includes all direct radiation from the facility (e.g., radioactive waste storage and ISFSIs) but excludes doses from radioactive waste shipments. 6. “Cumulative” dose means the sum of (1) current-year effluent dose, (2) current-year direct radiation dose, and (3) dose from accumulated radioactivity if not already included in the first two categories. Rev. 2 of RG 1.21, Page 29 7. “Accumulated radioactivity” includes radioactive material in the unrestricted area from prior-year discharges that remains in the environment (e.g., tritium in lake water or radionuclides). 8. The “uranium fuel cycle” excludes uranium mining, radioactive waste shipping (in the unrestricted area), operations at waste disposal sites, and reuse of non-uranium special nuclear materials (see definition of “uranium fuel cycle” in 40 CFR Part 190, also in Glossary of this document). 5.7 Dose Assessments for 10 CFR Part 50, Appendix I Dose assessments to show compliance with technical specification requirements for meeting the numerical values of 10