Document: NUREG-0800
Document ID: 42e7682f-df25-4a6a-94f4-7d44ea029702
Document Type: srp
Title: STEAM SYSTEM PIPING FAILURES INSIDE AND OUTSIDE OF CONTAINMENT
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070677.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.1.5
CFR Part: 
CFR Title: 

Content:
" 34. 10 CFR Part 50, General Design Criterion 28, "Reactivity Limits." 45. 10 CFR Part 50, General Design Criterion 31, "Fracture Prevention of Reactor Coolant Pressure Boundary." 56. 10 CFR Part 50, General Design Criterion 35, "Emergency Core Cooling." 6. NUREG-0694, "TMI-Related Requirements for New Operating Licenses."72 7. NUREG-0718, "Licensing Requirements for Pending Applications for Construction Permits and Manufacturing Licenses." 8. NUREG-0737, "Classification of TMI Action Plan Requirements." 9. Generic Letter 83-010A - Resolution of TMI Action item II.K.3.5, "Automatic Trip of Reactor Coolant Pumps," sent to all Licensees with Combustion Engineering (CE) Designed Nuclear Steam Supply Systems (NSSSs), February 8, 1983. 10. Generic Letter 83-010B - Resolution of TMI Action item II.K.3.5, "Automatic Trip of Reactor Coolant Pumps," sent to all Licensees with Combustion Engineering (CE) Designed Nuclear Steam Supply Systems (NSSSs), February 8, 1983. 11. Generic Letter 83-010C - Resolution of TMI Action item II.K.3.5, "Automatic Trip of Reactor Coolant Pumps," sent to all Licensees with Westinghouse Designed Nuclear Steam Supply Systems (NSSSs), February 8, 1983. 12. Generic Letter 83-010D - Resolution of TMI Action item II.K.3.5, "Automatic Trip of Reactor Coolant Pumps," sent to all Licensees with Westinghouse Designed Nuclear Steam Supply Systems (NSSSs), February 8, 1983. 15.1.5-15 DRAFT Rev. 3 - April 1996 13. Generic Letter 83-010E - Resolution of TMI Action item II.K.3.5, "Automatic Trip of Reactor Coolant Pumps," sent to all Licensees with Babcock & Wilcox (B&W) Designed Nuclear Steam Supply Systems (NSSSs), February 8, 1983. 14. Generic Letter 83-010F - Resolution of TMI Action item II.K.3.5, "Automatic Trip of Reactor Coolant Pumps," sent to all Licensees with Babcock & Wilcox (B&W) Designed Nuclear Steam Supply Systems (NSSSs), February 8, 1983. 15. Generic Letter 85-012 - Implementation of TMI Action item II.K.3.5, "Automatic Trip of Reactor