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:
at 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 cause either a reactor coolant system cooldown by excessive energy discharge through the break or a reactor coolant system heatup by reducing feedwater flow to the affected steam generator. Heat-up of the reactor coolant by reducing feedwater flow to the affected steam generator and subsequently by the addition of decay heat, could cause undue stress on the reactor coolant system pressure boundary. The amount of stress to which the reactor coolant pressure boundary is subjected is dependent upon the severity of the AOO. The severity of the AOO is assessed by the applicant in their SAR and reviewed by the staff in accordance with this SRP section. Meeting the requirements of GDC 31 provides assurance that (a) the reactor coolant pressure boundary behaves in a nonbrittle manner and (b) the probability of rapidly propagating fracture is minimized.45 5. Compliance with GDC 35 requires that a system be supplied that will provide abundant emergency core cooling. The system safety function shall be to transfer heat from the reactor core following any loss of reactor coolant at a rate that (a) fuel and clad damage that could interfere with continued effective core cooling is prevented and (b) fuel clad metal-water reaction is limited to negligible amounts. GDC 35 is applicable to SRP Section 15.2.8 because this section involves the review of feedwater system pipe breaks both inside and outside containment that could result in transient reactor coolant temperature conditions having the potential for challenging the emergency core cooling system (ECCS). A feedwater system pipe break could cause either a reactor coolant system cooldown by excessive energy discharge through the 15.2.8-11 DRAFT Rev. 2 - April 1996 break or a reactor coolant system heatup by reducing feedwater flow