Document: NUREG-0800
Document ID: 0513eafb-8911-4410-853b-e2ec7a00ee07
Document Type: srp
Title: RADIATION SOURCES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070616.pdf
Revision Date: 2023-06
Chapter: 12
Section ID: 12.2
CFR Part: 
CFR Title: 

Content:
106 - "Concentrations in effluents to unrestricted areas,"§20.1301 - "Dose limits for individual members of the public," as it relates to determination of 6 radiation levels and radioactive materials concentrations within the components of waste treatment systems. 5. 10 CFR Part 20, §20.207 - "Storage of licensed materials,"§20.1801 - "Security of stored material," as it relates to securing licensed materials against unauthorized removal. 7 12.2-3 DRAFT Rev. 3 - April 1996 6. 10 CFR Part 50, General Design Criterion 61 - "Fuel storage and handling and radioactivity control," as it relates to systems which may contain radioactive materials. The following Regulatory Guides and NUREGs provide information, recommendations, and guidance, and in general describe a basis acceptable to the staff for implementing the requirements of 10 CFR Part 20, §20.101, §20.103, §20.104, §20.106, and §20.207§20.1201, §20.1202, §20.1203, §20.1204, §20.1206, §20.1207, §20.1301, and §20.1801 . 8 1. Regulatory Guide 1.3, "Assumption Used for Evaluating the Potential Radiological Consequences of a Loss-of-Coolant Accident for Boiling Water Reactors," as it relates to assumptions used in evaluating gaseous concentrations of radionuclides in containment and plant systems, following a loss-of-coolant accident for BWRs. 2. Regulatory Guide 1.4, "Assumptions Used for Evaluating the Potential radiological Consequences of a Loss-of-Coolant Accident for Pressurized Water Reactors," as it relates to assumptions used in evaluating gaseous concentrations of radionuclides in containment and plant systems, following a loss-of-coolant accident for PWRs. 3. Regulatory Guide 1.7, "Control of Combustible Gas Concentrations in Containment Following a Loss-of-Coolant Accident," as it relates to methods for determining gaseous concentrations of radionuclides in containment following an accident. 4. Regulatory Guide 1.112 "Calculation of Releases of Radioactive Materials in Gaseous and Liquid