Document: NUREG-0800
Document ID: ecb92ac6-97df-4e4b-a20a-81638c2d573b
Document Type: srp
Title: - 15.3.4
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350157.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.3.3
CFR Part: 
CFR Title: 

Content:
and Hydraulic Safety." 12. Standard Review Plan Section 4.2, "Fuel System Design." 13. Standard Review Plan Section 7.2, "Reactor Trip System." 14. Standard Review Plan Section 7.3, "Engineered Safety Features System." 15. Standard Review Plan Section 7.4, "Systems Required for Safe Shutdown." 16. Standard Review Plan Section 7.5, "Safety-Related Display Instrumentation." 17. 10 CFR Part 5, Appendix A, General Design Criterion 31, "Fracture Preven- tion of Reactor Coolant Pressure Boundry." 15.3.3-7 Rev. 2 - July 1981 18. 10 CFR Part 50, Appendix A, General Design Criterion 31, "Fracture Prevention of Reactor Coolant Pressure Boundary." 19. NUREG-0718, "Licensing Requirements for Pending Applications for Construction Permits and Manufacturing License." 20. NUREG-0737, "Clarification of TMI Action Plan Requirements." 21. 10 CFR Part 50, Appendix A, General Design Criterion 28, "Reactivity Limits. " 15.3.3-8 Rev. 2 - July 1981