Document: NUREG-0800
Document ID: e1414316-0ddd-4451-9c60-e44c83bd70d8
Document Type: srp
Title: SOURCE TERMS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350098.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.1
CFR Part: 
CFR Title: 

Content:
uipment containing radioactive material. d. PWR liquid wastes, consisting of primary coolant processed to control boron concentration (shim bleed); leakage collected in equipment and floor drains from buildings housing equipment and components that may contain radioactive fluids; steam generator blowdown; condensate demineralizer regenerant solutions; contaminated liquids from antici- pated plant operations such as resin sluices, filter backwashes, decontamination solutions, and sample station drains; and detergent wastes. 2. The releases of radioactive materials-.in liquid and gaseous effluents calculated by ETSB will be used in SRP Sections 11.2 and 11.3 to evaluate the liquid and gaseous waste systems. II. ACCEPTANCE CRITERIA ETSB will accept the source terms used as the design basis for expected releases if the following Commission regulations are met: 1. 10 CFR Part 20 as it relates to radioactivity in effluents to unrestricted areas. 2. 10 CFR Part 50, Appendix I as it relates to the numerical guides for design objectives and limiting conditions for operation to meet the criterion "as low as is reasonably achievable" given in the Appendix I. 3. General Design Criterion 60 as it relates to the radioactive waste manage- ment systems being designed to control releases of radioactive materials to the environment. The requirement of the Commission regulations identified above are met by using the regulatory positions contained in the following regulatory guides: a. Regulatory Guide 1.110 as it relates to the cost-benefit analysis for radioactive waste management systems and equipment. b. Regulatory Guide 1:112 as it relates to the method of calculating release of radioactive materials in effluents from nuclear power plants. c. Regulatory Guide 1.140 as it relates to the design testing and main- tenance of normal ventilation exhaust systems at nuclear power plants. 11.1-2 1Rev. 2 - July 1981 Specific criteria necessary to meet the relevant requirements of 10 CFR