Document: NUREG-0800
Document ID: fabdf65c-d299-4b3a-a971-ae5b21a97177
Document Type: srp
Title: RADIATION SOURCES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1315/ML13151A413.pdf
Revision Date: 2023-06
Chapter: 12
Section ID: 12.2
CFR Part: 
CFR Title: 

Content:
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. RG 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. RG 1.1833, as it relates to the assumptions used in evaluating the concentrations of radionuclides in containment and plant systems following a loss-of-coolant accident. 4. RG 1.7, as it relates to radionuclides in systems used for determining gaseous concentrations in containment following an accident. 5. RG 1.112, as it relates to complying with the Commission’s regulations under 10 CFR 20.1301 concerning the calculation of realistic radiation levels and radioactive materials source terms for the evaluation of waste treatment systems. 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 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. 3 Regulatory Guide1.183 is applicable to applicants or holders of license issued after January 10, 1997. 12.2-8 Revision 4 – September 2013 6. NUREG-0737, Task Action Plan Item II.B.2, as it relates to the identification of specific post accident sources of radiation in the facility. 7. American National Standards Institute/American Nuclear Society (ANSI/ANS) Standard 18.1, as it relates to the establishment of typical long-term concentrations of principal radionuclides in fluid streams of light-water-cooled nuclear power plants. 8. RG 1.89, as it relates to the