Document: NUREG-0800
Document ID: 06ca0ca1-d4e9-478b-ad5d-c52597a36b46
Document Type: srp
Title: COOLANT SOURCE TERMS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1305/ML13058A173.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.1
CFR Part: 
CFR Title: 

Content:
es of Radioactive Materials in Gaseous and Liquid Effluents from Light-Water-Cooled Power Reactors,” NUREG-0016 and NUREG-0017 as the basis of the BWR-gaseous and liquid effluent (GALE) and PWR-GALE codes, and industry guidance provided in ANSI/ANS 18.1-1999, as adjusted to reflect specific design features. 11.1-8 Draft Revision 4 –August 2014 These models and parameters are based on operating experience with large, existing PWRs. Differences in design features and operating characteristics of PWRs or BWRs should be evaluated and used to make specific adjustments to the parameters used in the PWR-GALE Code and BWR-GALE Code or in ANSI/ANS 18.1-1999. Differences may also exist in the operational configuration and sequence of treatment of waste management systems for various process streams and effluent releases. The use of PWR-GALE86 or BWR-GALE86 in place of the earlier PWR-GALE Code (see NUREG-0017) or BWR-GALE Code (see NUREG-0016) is endorsed by Interim Staff Guidance (ISG) DC/COL-ISG-5, “GALE86 Code for Calculation of Routine Radioactive Releases in Gaseous and Liquid Effluents to Support Design Certification and Combined License Applications.” Whenever adjustments are made to parameters used in either code, applicants should provide sufficient information for the staff to conduct an independent evaluation of the applicant’s use of alternative code parameters. The relevant RGs and ISG are as follows: 1. RG 1.110, “Cost-Benefit Analysis for Radwaste Systems for Light-Water-Cooled Nuclear Power Reactors,” as it relates to the cost-benefit analysis for radioactive waste management systems and equipment. 2. RG 1.112, “Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Light-Water-Cooled Power Reactors.” as it relates to the method of calculating releases of radioactive materials in liquid and gaseous effluents from nuclear power plants. 3. RG 1.140, “Design, Inspection, and Testing Criteria for Air Filtration