Document: NUREG-0800
Document ID: 968e9bbe-e8ca-4639-a8d2-f96483377bae
Document Type: srp
Title: - 12.4
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1219/ML12191A219.pdf
Revision Date: 2023-06
Chapter: 12
Section ID: 12.3
CFR Part: 
CFR Title: 

Content:
ated to Technical Information Document (TID) 14844, “Calculation of Distance Factors for Power and Test Reactor Sites.” This guidance is applicable to a holder of an operating license issued prior to January 10, 1997 or a holder of a renewed license under 10 CFR Part 54 whose initial operating license was issued prior to January 10, 1997. These license holders may voluntarily revise the accident source term. 3Regulatory Guide1.183 is applicable to applicants or license holders issued after January 10,1997. 12.3-12.4-15 Draft Revision 5 – October 2012 11. RG 8.19, as it relates to a method acceptable to the staff for performing an assessment of collective occupational radiation dose as part of the ongoing design review process so that such exposures will be ALARA. 12. RG 8.25, as it relates to a method acceptable to the staff for continuous monitoring for airborne radioactive materials in plant spaces. 13. RG 8.38, as it relates to the physical controls for personnel access to high and very high radiation areas. 14. NUREG-1430, as it relates to radiation protection considerations in the applicability, format, and implementation of the Babcock and Wilcox Technical Specification package. 15. NUREG-1433, as it relates to radiation protection considerations in the applicability, format, and implementation of the General Electric (BWR/4) Technical Specification package. 16. NUREG-1434, as it relates to radiation protection considerations in the applicability, format, and implementation of the General Electric (BWR/6) Technical Specification package. 17. NUREG-1432, as it relates to radiation protection considerations in the applicability, format, and implementation of the Combustion Engineering Technical Specification package. 18. NUREG-1431, as it relates to radiation protection considerations in the applicability, format, and implementation of the Westinghouse Technical Specification package. 19. ANSI/ANS/HPSSC-6.8.1-1981, as it relates to criteria for the