Document: NUREG-0800
Document ID: ed948426-dd77-4047-be5e-2b7ab22de3f5
Document Type: srp
Title: FEEDWATER SYSTEM PIPE BREAK INSIDE AND OUTSIDE CONTAINMENT (PWR)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550009.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.2.8
CFR Part: 
CFR Title: 

Content:
ral Design Criteria for Nuclear Power Plants." A. GDC 13, “Instrumentation and Control.” B. GDC 17, "Electric Power Systems." C. GDC 27, "Combined Reactivity Control System Capability." D. GDC 28, "Reactivity Limits." E. GDC 31, "Fracture Prevention of Reactor Coolant Pressure Boundary." F. GDC 35, "Emergency Core Cooling." 2. 10 CFR Part 100, "Reactor Site Criteria." 3. Regulatory Guide 1.70, "Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants." 4. Branch Technical Position 3-3, "Protection Against Postulated Piping Failures in Fluid Systems Outside Containment." 5. Branch Technical Position 3-4, "Postulated Rupture Locations in Fluid System Piping Inside and Outside Containment." 6. ASME Boiler and Pressure Vessel Code, Section III, "Nuclear Power Plant Components," Article NB-7000, "Protection Against Over pressure," American Society of Mechanical Engineers. PAPERWORK REDUCTION ACT STATEMENT The information collections contained in the Standard Review Plan are covered by the requirements of 10 CFR Part 50 and 10 CFR Part 52, and were approved by the Office of Management and Budget, approval number 3150-0011 and 3150-0151. PUBLIC PROTECTION NOTIFICATION The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid OMB control number.