Document: NUREG-0800
Document ID: acc638c2-20fb-4686-892d-e70277acd189
Document Type: srp
Title: CONTAINMENT FUNCTIONAL DESIGN
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0702/ML070220505.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6.2.1
CFR Part: 
CFR Title: 

Content:
., there is reasonable assurance that the actual temperatures and pressures for the postulated accidents will not exceed these profiles anywhere within the specified environmental zones, except in the break zone. IV. 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apply to reviews of applications submitted six months or more after the date of issuance of this SRP section, unless superseded by a later revision. V. REFERENCES 1. 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." 2. 10 CFR Part 50, Appendix A, General Design Criterion 4, "Environmental and Dynamic Effects19 Design Bases." 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." 6.2.1-5 Revision 3 - March 2007 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." 9. 10 CFR Part 50, Appendix A, General Design Criterion 64, "Monitoring Radioactivity Releases." 10. RELAP4 MOD5, A Computer Program for Transient Thermal-Hydraulic Analysis of Nuclear Reactors and Related Systems Users Manual, ANCR-NUREG-1335, September 1976. 11.