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:
(unless prevented by positive means), rod dropout, steam line rupture, changes in reactor temperature and pressure, and addition of cold water. GDC 27 and GDC 28 are applicable to this section because the reviewer evaluates steam system piping failures, both inside and outside containment, that could cause transient conditions affecting reactor coolant temperature and pressure, including complex 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 to cause an unacceptable impact on the reactor coolant pressure boundary or on the capability for cooling the core. These analyses must be independently reviewed by the staff in accordance with this SRP section. Meeting the requirements of GDC 27 and 28 provides assurance that a transient initiated by a steam system pipe break will not result in (a) an unacceptable stress on the reactor coolant pressure boundary, (b) acceptable fuel design limits being exceeded, or (c) loss of capability of the core cooling systems or the reactivity control systems to perform their design safety functions.43 3. Compliance with GDC 31 requires that, under the stress of operation, maintenance, testing, and postulated accidents, the reactor pressure boundary shall be designed with sufficient margin to ensure that (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 boundary material variables under a full range of conditions. The design will also address such issues as the uncertainties of determining material properties; the effects of irradiation on material properties; residual, steady state, and transient stresses; and the sizes of flaws. GDC 31 is applicable to this section because the reviewer evaluates steam system piping failures, both inside and outside containment, that