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:
latory 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 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. 12.3-12.4-7 Revision 3 - March 2007 1. Regulatory Guide 1.32, as it relates to assumptions used in evaluating gaseous concentrations of radionuclides in containment and plant systems following a loss-of-coolant accident for boiling-water reactors (BWRs). 2. Regulatory Guide 1.42, as it relates to assumptions used in evaluating gaseous concentrations of radionuclides in containment and plant systems following a loss-of-coolant accident for pressurized-water reactors (PWRs). 3. Regulatory Guide 1.7, as it relates to methods for determining gaseous radionuclides in containment following an accident. 4. Regulatory Guide 1.52, as it relates to radiation protection considerations for engineered safety feature (ESF) atmosphere cleanup systems operable under postulated design- basis accident (DBA) conditions, to be designated as “primary systems.” 5. Regulatory Guide 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. Regulatory Guide 1.97, Revision 3, as it relates to a method acceptable to the staff for complying with the Commission’s regulations to provide instrumentation for radiation monitoring following an accident in a light-water-cooled nuclear power plant. 7. Regulatory Guide 1.1833, as it relates to the assumptions and methods for evaluating doses to