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:
tor. Heat-up of the reactor coolant by reduced feedwater flow to the affected steam generator and by the subsequent 15.2.8-9 Revision 2 - March 2007 addition of decay heat could result in undue stress on the RCS pressure boundary. The amount of stress to which the reactor coolant pressure boundary is subjected depends upon AOO severity, which is assessed in the SAR and reviewed by the staff in accordance with this SRP section. 6. GDC 35 requires a system for abundant emergency core cooling. The system safety function is to transfer heat from the reactor core following any loss of reactor coolant at a rate to prevent fuel and clad damage that could interfere with continued effective core cooling and limit fuel clad metal-water reaction to negligible amounts. GDC 35 applies because this SRP section is for the review of feedwater system pipe breaks both inside and outside containment that could result in transient reactor coolant temperature conditions that could challenge the ECCS. A feedwater system pipe break could result in either an RCS cool-down by excessive energy discharge through the break or an RCS heat-up by reduced feedwater flow to the affected steam generator. Heat-up of the reactor coolant by reduced feedwater flow to the affected steam generator and by the subsequent addition of decay heat could initiate ECCS reduction of the core coolant temperature to an acceptable level to prevent fuel and clad damage that could interfere with continued effective core cooling and limit fuel clad metal-water reaction to negligible amounts. The severity of this AOO is assessed in the SAR and reviewed by the staff in accordance with this SRP section. III. REVIEW PROCEDURES The reviewer will select material from the procedures described below, as may be appropriate for a particular case. These review procedures are based on the identified SRP acceptance criteria. For deviations from these acceptance criteria, the staff should review the applicant’s evaluation of how