Document: NUREG-0800
Document ID: c1d42ca1-cc58-40db-812c-918554bfa81b
Document Type: srp
Title: FEEDWATER SYSTEM PIPE BREAKS INSIDE AND OUTSIDE CONTAINMENT
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070704.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.2.8
CFR Part: 
CFR Title: 

Content:
III regarding loss of offsite power and assumed single failures. This new position will be applied to new applications (for a Construction Permit, a manufacturing license, or design certification). 68 VI. REFERENCES 1. 10 CFR Part 100, "Reactor Site Criteria." 2. Regulatory Guide 1.70, "Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants." 3. ASME Boiler and Pressure Vessel Code, Section III, "Nuclear Power Plant Components," Article NB-7000, "Protection Against Overpressure," American Society of Mechanical Engineers. 4. 10 CFR Part 50, Appendix A, "General Design Criteria for Nuclear Power Plants." a. General Design Criterion 17, "Electric Power Systems."69 a.b. General Design Criterion 27, "Combined Reactivity Control System Capability." b.c. General Design Criterion 28, "Reactivity Limits." c.d. General Design Criterion 31, "Fracture Prevention of Reactor Coolant Pressure Boundary." b.e. General Design Criterion 35, "Emergency Core Cooling." 5. Branch Technical Positions ASB 3-1, "Protection Against Postulated Piping Failures in Fluid Systems Outside Containment," attached to SRP Section 3.6.1; and MEB 3-1, "Postulated Break and Leakage Locations in Fluid System Piping Outside Containment," attached to SRP Section 3.6.2. 6. NUREG-0718, "Licensing Requirements for Pending Applications for Construction Permits and Manufacturing Licenses." 7. NUREG-07367, "Clarification of TMI Action Plan Requirements." 70 8. NUREG/CR-4945, "Summary of the Semi Scale Program 1985 - 1986."71 9. Generic Letter 83-10A - 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. DRAFT Rev. 2 - April 1996 15.2.8-16 10. Generic Letter 83-10B - 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