Document: NUREG-0800
Document ID: 723c7d66-7b0b-443a-af9b-ec3026461a0c
Document Type: srp
Title: - 12.4
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1130/ML113081427.pdf
Revision Date: 2023-06
Chapter: 12
Section ID: 12.3
CFR Part: 
CFR Title: 

Content:
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apply to reviews of applications submitted 6 months or more after the date of issuance of this SRP section, unless superseded by a later revision. The referenced RGs and NUREGs contain the implementation schedules for conformance to parts of the method discussed herein. VI. REFERENCES 1. 10 CFR Part 20, “Standards for Protection Against Radiation.” 2. 10 CFR Part 50, “Domestic Licensing of Production and Utilization Facilities.” 3. 10 CFR Part 52, “Early Site Permits; Standard Design Certifications; and Combined Licenses for Nuclear Power Plants.” 4. RG 1.3, “Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss-of-Coolant Accident for Boiling Water Reactors.” 5. RG 1.4, “Assumptions Used for Evaluation of the Potential Radiological Consequences of a Loss-of-Coolant Accident for Pressurized Water Reactors.” 6. RG 1.7, “Control of Combustible Gas Concentrations in Containment Following a Loss-of Coolant Accident.” 7. RG 1.52, “Design, Testing, and Maintenance Criteria for Post Accident Engineered-Safety-Feature Atmosphere Cleanup System Air Filtration and Absorption Units of Light-Water-Cooled Nuclear Power Plants.” 8. RG 1.69, “Concrete Radiation Shields for Nuclear Power Plants.” 9. RG 1.70, “Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants.” 10. RG 1.97, Revision 4, “Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident.” 11. RG 1.183, “Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors.” 12. RG 8.8, “Information Relevant to Ensuring that Occupational Radiation Exposures at Nuclear Power