Document: NUREG-0800
Document ID: 3ea2f0ac-4d7e-464a-b1c4-390c3970f642
Document Type: srp
Title: provides specific thermal-hydraulic criteria.  The available radioactive fission product
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0707/ML070740002.pdf
Revision Date: 2023-06
Chapter: 4
Section ID: 4.4
CFR Part: 
CFR Title: 

Content:
on of the ITAAC, including design acceptance criteria, as applicable. 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apply to reviews of applications submitted six months or more after the date of issuance of this SRP section, unless superseded by a later revision. Implementation schedules for conformance to parts of the method discussed herein are contained in the referenced RGs and NUREGs. VI. REFERENCES 1. 10 CFR Part 50, “Domestic Licensing of Production and Utilization Facilities.” 2. 10 CFR 50.34, “Contents of Applications; Technical Information.” 3. 10 CFR 50.46, “Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors.” 4. 10 CFR 50.67, “Accident Source Term.” 5. 10 CFR Part 52, “Early Site Permits; Standard Design Certifications; and Combined Licenses for Nuclear Power Plants.” 6. 10 CFR 52.47, “Contents of Applications.” 7. 10 CFR 52.97, “Issuance of Combined Licenses.” 8. 10 CFR Part 100, “Reactor Site Criteria.” 9. 10 CFR Part 50, Appendix A, General Design Criterion 2, “Design Basis for Protection Against Natural Phenomena.” 10. 10 CFR Part 50, Appendix A, General Design Criterion 10, “Reactor Design.” 11. 10 CFR Part 50, Appendix A, General Design Criterion 27, “Combined Reactivity Control Systems Capability.” 12. 10 CFR Part 50, Appendix A, General Design Criterion 35, “Emergency Core Cooling.” 13. 10 CFR Part 50, Appendix K, “ECCS Evaluation Models.” 4.2-25 Revision 3 - March 2007 14. Regulatory Guide 1.3, “Assumptions Used for Evaluating