Document: NUREG-0800
Document ID: c544c383-46ca-4e10-8688-4fd295af8a61
Document Type: srp
Title: provide guidance in evaluating the source terms and doses from gaseous effluents
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1304/ML13044A644.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.4
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CFR Title: 

Content:
tions that underlie SRP acceptance criteria and meet NRC regulatory requirements under 10 CFR 50.34(h), 10 CFR 52.17(a)(1)(xii), 10 CFR 52.47(a)(9), and 10 CFR 52.79(a)(41) for ESP, CP, DC, OL and COL applications. 11.2-33 Draft Revision 5 – August 2014 VI. REFERENCES 1. 10 CFR 20.1301, “Dose Limits for Individual Members of the Public.” 2. 10 CFR 20.1302, “Compliance with Dose Limits for Individual Members of the Public.” 3. 10 CFR 20.1406, “Minimization of Contamination.” 4. 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." 5. 10 CFR 50.34, “Contents of applications; technical information.” 6. 10 CFR 50.34a, “Design objectives for equipment to control releases of radioactive material in effluents nuclear power reactors.” 7. 10 CFR 50.36a, “Technical specifications on effluents from nuclear power reactors.” 8. 10 CFR 50.59, “Changes, Tests, and Experiments.” 9. 10 CFR Part 50, Appendix A, GDC 2, “Design bases for protection against natural phenomena.” 10. 10 CFR Part 50, Appendix A, GDC 3, “Fire protection.” 11. 10 CFR Part 50, Appendix A, GDC 60, “Control of releases of radioactive materials to the environment.” 12. 10 CFR Part 50, Appendix A, GDC 61, “Fuel storage and handling and radioactivity control.” 13. 10 CFR Part 50, Appendix B, “Quality assurance criteria for nuclear power plants and fuel reprocessing plants.” 14. 10 CFR Part 50, Appendix I, “Numerical Guides for Design Objectives and Limiting Conditions for Operation to Meet the Criterion “As Low As Is Reasonably Achievable” for Radioactive Material in Light Water Cooled Nuclear Power Reactor Effluents.” 15. 10 CFR 52.39, “Finality of early site permit determinations.” 16. 10 CFR 52.47, “Contents of applications; technical information.” 17. 10 CFR 52.63, “Finality of standard design