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:
tside containment that can result in transient conditions affecting reactor coolant temperature and pressure, with resultant changes in core reactivity. The applicant's analyses of these transients in the SAR must demonstrate that reactivity, pressure, and temperature changes will not be severe enough DRAFT Rev. 2 - April 1996 15.2.8-10 to cause an unacceptable impact on the reactor coolant pressure boundary or on the capability for core cooling. The analyses must be independently reviewed by the staff in accordance with this SRP section. Meeting the requirements of GDC 27 and GDC 28 provides assurance that an AOO initiated by feedwater system pipe breaks will not result in (a) an unacceptable stress on the reactor coolant pressure boundary, (b) acceptable fuel design limits being exceeded, or (c) the incapability of the core cooling systems to cool the core or the reactivity control systems to perform their design safety functions.44 4. Compliance with GDC 31 requires that the reactor pressure boundary be designed with sufficient margin to ensure that when stressed under operating, maintenance, testing, and postulated accident conditions (a) the boundary behaves in a nonbrittle manner and (b) the probability of rapidly propagating fracture is minimized. The design shall reflect consideration of service temperatures and other conditions of the boundary material under operating, maintenance, testing, and postulated accident conditions and the uncertainties in determining (a) material properties, (b) the effects of irradiation on material properties, (c) residual, steady state, and transient stresses, and (d) size of flaws. GDC 31 is applicable to SRP Section 15.2.8 because this section involves the review of feedwater system pipe breaks inside and outside containment that could result in transient reactor coolant temperature and pressure conditions having the potential for adversely affecting the reactor coolant pressure boundary. A feedwater system pipe break could