Document: NUREG-0800
Document ID: 55e187c7-8e17-41ed-a88e-0205d1317fb6
Document Type: srp
Title: - 12.4
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1315/ML13151A475.pdf
Revision Date: 2023-06
Chapter: 12
Section ID: 12.3
CFR Part: 
CFR Title: 

Content:
sessment for controlling the intake of radioactive materials. 4. 10 CFR 20.1301 and 10 CFR 20.1302, as they relate to the facility design features that impact the radiation exposure to a member of the public from non-effluent sources associated with normal operations and AOOs. 5. 10 CFR 20.1406, as it relates to the design features that will facilitate eventual decommissioning and minimize, to the extent practicable, the contamination of the facility, the environment, and the generation of radioactive waste. 12.3-12.4-12 Revision 5 – September 2013 6. 10 CFR 20.1601, 10 CFR 20.1602, 10 CFR 20.1901, 10 CFR 20.1902, 10 CFR 20.1903, and 10 CFR 20.1904, as they relate to the identification of potential sources of radiation exposure and the controls of access to and work within areas of the facility with a high potential for radiation exposure. 7. 10 CFR 20.1801, as it relates to securing licensed materials against unauthorized removal from the place of storage. 8. General Design Criterion (GDC) 19 found in Appendix A to 10 CFR Part 50, as it relates to the provision of adequate radiation protection to permit access to areas necessary for occupancy after an accident, without personnel receiving radiation exposures in excess of 50 millisievert (mSv) (5 rem) Total Effective Dose Equivalent (TEDE) as defined in 10 CFR 50.2, to the whole body or the equivalent to any part of the whole body for the duration of the accident in accordance with 10 CFR 50.34(f)(2)(vii)1 and NUREG 0737, Item II.B.2. 9. GDC 61, as it relates to occupational radiation protection aspects of fuel storage, handling, radioactive waste, and other systems that may contain radioactivity, designed to ensure adequate safety during normal and postulated accident conditions, with suitable shielding and appropriate containment and filtering systems. 10. GDC 63, as it relates to detecting excessive radiation levels in the facility. 11. 10 CFR 50.68 or 10 CFR 70.24 as it relates to procedures and criteria for