Document: NUREG-0800
Document ID: a397b98f-e122-4d15-8471-5259fb45b58b
Document Type: srp
Title: and BTP 11-6 since the use of durable and passive design features would provide
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1305/ML13051A458.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.2
CFR Part: 
CFR Title: 

Content:
med inventory of radioactive materials in the failed tank and components, assumed failure scenario, methods and assumptions used in modeling the transport of radioactivity into unrestricted areas, and definition of limiting exposure scenarios for direct and indirect uses of surface water or groundwater in unrestricted areas. The evaluation demonstrates that the results of the analysis are consistent with the SRP acceptance criterion in meeting the total dose criterion of 100 mrem (1 mSv) for surface water or groundwater used in unrestricted areas. The health physics staff confirmed that the proposed TS limiting the radioactivity content for the stated liquid- containing tank and components have been incorporated into Chapter 16, Section 5.5, “Programs and Manuals,” of the FSAR, and identified as a program element, as addressed in FSAR Sections 11.5 and 13.4 of COL applications. E. REFERENCES 1. 10 CFR 100.10, “Factors to be Considered When Evaluating Sites,” under Subpart A, “Evaluation Factors for Stationary Power Reactor Site Applications, before January 10, 1977 And For Testing Reactors.” 2. 10 CFR 100.20, “Factors to be Considered When Evaluating Sites,” under Subpart B, “Evaluation Factors for Stationary Power Reactor Site Applications,” on or after January 10, 1977.” 3. 10 CFR Part 20, Appendix B, "Annual Limits on Intake (ALIs) and Derived Air Concentrations (DACs) of Radionuclides for Occupational Exposure; Effluent Concentrations; Concentrations for Release to Sewerage." 4. 10 CFR 50.34a, “Design Objectives for Equipment to Control Releases of Radioactive Material in Effluents Nuclear Power Reactors.” 5. 10 CFR 50.36a, “Technical Specifications on Effluents from Nuclear Power Reactors.” 6. 10 CFR Part 50, Appendix A, GDC 2, “Design Bases for Protection Against Natural Phenomena.” 7. 10 CFR Part 50, Appendix A, GDC 60, “Control of Releases of Radioactive Materials to the Environment.” 8. 10 CFR Part 50, Appendix A, GDC