Document: NUREG-0800
Document ID: 23331bab-fa00-40fd-8357-d8db908b4532
Document Type: srp
Title: GASEOUS WASTE MANAGEMENT SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0707/ML070710366.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.3
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CFR Title: 

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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," to 10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities." V. IMPLEMENTATION The staff will use this SRP section in performing safety evaluations of DC applications and license applications submitted by applicants pursuant to 10 CFR Part 50 or 10 CFR Part 52. Except when the applicant proposes an acceptable alternative method for complying with specified portions of the Commission’s regulations, the staff will use the method described herein to evaluate conformance with Commission regulations. The provisions of this SRP section apply to reviews of applications submitted six months or more after the date of issuance of this SRP section, unless superseded by a later revision. 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 50.34a, “Design Objective for Equipment to Control Releases of Radioactive Materials in Effluents—Nuclear Power Reactors.” 6. 10 CFR 50.36a, “Technical Specifications on Effluents from Nuclear Power Reactors.” 7. 10 CFR Part 50, Appendix A, General Design Criterion 3, “Fire Protection.” 8. 10 CFR Part 50, Appendix A, General Design Criterion 60, “Control of Releases of Radioactive Materials to the Environment.” 9. 10 CFR Part 50, Appendix A, General Design Criterion 61, “Fuel Storage and Handling and Radioactivity Control.” 10. 10 CFR Part 50, Appendix I, “Numerical Guides for Design Objectives and