Document: NUREG-0800
Document ID: 0b17303b-e5cc-4091-b22c-056b0c78eb34
Document Type: srp
Title: – 15.3.4
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070707.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.3.3
CFR Part: 
CFR Title: 

Content:
fety functions.41 3. Compliance with GDC 31 requires that, under the stress of operating, maintenance, testing, and postulated accident conditions, 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 15.3.3-7 DRAFT Rev. 3 - April 1996 shall reflect consideration of service temperatures and other boundary material variables under operating, maintenance, testing, and postulated accident 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 two events (RCP rotor seizure and shaft break) that could result in transient conditions having the potential for adversely affecting the reactor coolant pressure boundary. Loss of a reactor cooling pump will cause a rapid reduction in coolant flow through the core and, consequently, an increase in temperature and pressure. The amount of stress to which the reactor coolant pressure boundary is subjected depends on the severity of the transient. The severity of the transient is assessed by the applicant in the SAR and reviewed by the staff in accordance with this SRP section. Meeting the requirements of GDC 31 provides a level of assurance that a transient initiated by an RCP rotor seizure or shaft break will not result in an unacceptable stress on the reactor coolant pressure boundary or on the ability to cool the reactor core.42 4. To establish the suitability of a nuclear power plant site, 10 CFR Part 100 specifies how the exclusion area, low population zone, and population center distance should be determined. Further, radiation exposure criteria stipulated in 10 CFR Part 100 provide reference values to be used in the site