Document: NUREG-0800
Document ID: b486e8d3-c8b0-4990-b7ec-211a3aae25c3
Document Type: srp
Title: CONTAINMENT FUNCTIONAL DESIGN
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070456.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6.2.1
CFR Part: 
CFR Title: 

Content:
en SRP sections listed above. VI. REFERENCES 18 21. 10 CFR 50.46, "Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors," and 10 CFR Part 50, Appendix K, "ECCS Evaluation Models." 12. 10 CFR Part 50, Appendix A, General Design Criterion 4, "Environmental and MissileDynamic Effects Design Bases."; 19 20 3. 10 CFR Part 50, Appendix A, General Design Criterion 13, "Instrumentation and Control."; 4. 10 CFR Part 50, Appendix A, General Design Criterion 16, "Containment Design."; 5. 10 CFR Part 50, Appendix A, General Design Criterion 38, "Containment Heat Removal."; 6. 10 CFR Part 50, Appendix A, General Design Criterion 39, "Inspection of Containment Heat Removal System."; 7. 10 CFR Part 50, Appendix A, General Design Criterion 40, "Testing of Containment Heat Removal System."; 8. 10 CFR Part 50, Appendix A, General Design Criterion 50, "Containment Design Basis."; Criterion 52, "Capability for Containment Leakage Rate Testing"; Criterion 53, "Provisions for Containment Testing and Inspection"; Criterion 54, "Systems Penetrating Containment"; Criterion 55, "Reactor Coolant Pressure Boundary Penetrating Containment"; Criterion 56, "Primary Containment Isolation"; Criterion 57, "Closed System Isolation Valves"; and21 9. 10 CFR Part 50, Appendix A, General Design Criterion 64, "Monitoring Radioactivity Releases." 22 DRAFT Rev. 3 - April 1996 6.2.1-6 510. RELAP4 MOD5, A Computer Program for Transient Thermal-Hydraulic Analysis of Nuclear Reactors and Related Systems Users Manual, ANCR-NUREG-1335, September 1976. 23 3611. U.S. Nuclear Regulatory Commission, "Mark II Containment Lead Plant Program Load Evaluation and Acceptance Criteria," USNRC Report NUREG-0487, October 1978. 3712. U.S. Nuclear Regulatory Commission, "Mark II Containment Lead Plant Program Load Evaluation and Acceptance Criteria," USNRC Report NUREG-0487, Supplement 1, October 1980. 3813. U.S. Nuclear Regulatory Commission, "Mark II Containment Lead Plant Program Load