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:
m radionuclides in systems used for determining gaseous concentrations in containment following an accident. 4. RG 1.52, as it relates to radiation protection considerations for ESF atmosphere cleanup systems operable under postulated design-basis accident (DBA) conditions, to be designated as “primary systems.” 5. RG 1.69, as it relates to the requirements and recommended practices acceptable for construction of facilities that apply to occupational radiation protection shielding structures for nuclear power plants. 6. RG 1.97, BTP 7-10 and the Memorandum from D.G. Eisenhut, Nuclear Reactor Regulation (NRR), to Regional Administrators dated August 16, 1982, as it relates to a method acceptable to the staff for complying with the Commission’s regulations to provide and calibrate instrumentation for radiation monitoring following an accident in a light-water-cooled nuclear power plant. 7. RG 1.1833, as it relates to the assumptions and methods for evaluating doses to individuals accessing the facility during and following an accident in accordance with NUREG-0737, item II.B.2. 8. RG 8.2, as it relates to general information on radiation monitoring programs for administrative personnel. 9. RG 8.8, as it relates to actions taken during facility design, engineering, construction, operation, and decommissioning to maintain ORE ALARA in accordance with 10 CFR 20.1101(b) and the definition of ALARA in 10 CFR 20.1003, concerning the radiation protection information to be supplied in SAR Section 12. 10. RG 8.10, as it relates to the commitment by management and vigilance by the radiation protection manager and staff to maintain ORE ALARA in accordance with 10 CFR 20.1101(b) and the definition of ALARA in 10 CFR 20.1003. 2 Regulatory Guides 1.3 and 1.4 provide guidance related 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