Document: NUREG-0800
Document ID: a55c61ec-57c4-4f3d-b403-d27c8f7c6427
Document Type: srp
Title: SOURCE TERMS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0707/ML070790010.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.1
CFR Part: 
CFR Title: 

Content:
to as COL license information in certain DCs) included in the referenced DC. Additionally, a COL applicant must address requirements and restrictions (e.g., interface requirements and site parameters) included in the referenced DC. 11.1-3 Revision 3 - March 2007 Review Interfaces Other SRP sections interface with this section as follows: 1. The reviewer responsible for review of effectiveness of the radwaste systems will use the coolant concentrations calculated above as inputs for evaluation of the liquid waste system, under SRP Section 11.2, and the gaseous waste systems, under SRP Section 11.3, to determine if these systems meet the dose design objectives of Appendix I to 10 CFR Part 50. 2. The reviewer responsible for review of effectiveness of the radwaste systems - monitoring instrumentation will review under SRP Section 11.5, “Process and Effluent Radiological Monitoring and Sampling Systems,” the monitoring and control provisions for all the applicable effluent release points identified in Subsection I.1, above. The specific acceptance criteria and review procedures are contained in the referenced SRP sections. II. ACCEPTANCE CRITERIA Requirements Acceptance criteria are based on meeting the relevant requirements of the following Commission regulations: 1. 10 CFR Part 20, as it relates to determining the operational source term that is used in calculations associated with potential radioactivity in effluents to unrestricted areas. Part 20 is not applicable to an ESP application. 2. 10 CFR Part 50, Appendix I, as it relates to determining the operational source term that is used in calculations associated with potential radioactivity in effluents considered in the context of numerical guides for design objectives and limiting conditions for operation to meet the criterion “as low as is reasonably achievable” (ALARA) for radioactive material in LWR effluents. 3. General Design Criterion 60 (GDC) as it relates to determining the operational source term