Document: NUREG-0800
Document ID: bfe08773-10ce-45c6-9767-3cbe51c1726f
Document Type: srp
Title: - 12.4
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0707/ML070720019.pdf
Revision Date: 2023-06
Chapter: 12
Section ID: 12.3
CFR Part: 
CFR Title: 

Content:
the extent practicable, the contamination of the facility and the generation of radioactive waste 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 1For Part 50 applicants not listed in 10 CFR 50.34(f), the provisions of 50.34(f) will be made a requirement during the licensing process. 12.3-12.4-6 Revision 3 - March 2007 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) 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)(vii)1 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, as it relates to procedures and criteria for radiation monitoring in areas where special nuclear material is stored and handled 12. 10 CFR 52.47(b)(1), which requires that a DC FSAR contain the proposed inspections, tests, analyses, and acceptance criteria (ITAAC) that are necessary and sufficient to provide reasonable assurance that, if the inspections, tests, and analyses are performed and the acceptance criteria met, a plant that