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:
k 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 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 potentially initiate the ECCS to reduce the core coolant temperature to an acceptable level so that fuel and clad damage that could interfere with continued effective core cooling is prevented and that fuel clad metal-water reaction is limited to negligible amounts. The severity of this 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 35 provides assurance that a system will be available for providing abundant emergency core cooling, thus preventing fuel and clad damage that could interfere with continued effective core cooling and limiting any clad metal-water reaction to negligible amounts in the event of an AOO initiated by a feedwater system pipe break.46 III. REVIEW PROCEDURES The procedures below are used during reviews of both construction permit (CP), and operating license (OL), and combined license (COL) applications. During the CP review the values of 47 system parameters and setpoints used in the analysis will be preliminary in nature and subject to change. At the OL or COL review stage, final values should be used in the analysis, and the reviewer should compare these to the limiting safety system settings included in the proposed technical specifications. The values of system parameters and initial core and system conditions used as input to the model are reviewed by RSBSRXB and are compared to the initial conditions listed in subsection II of this SRP section. Of particular importance are the reactivity coefficients and control rod worths used in the applicant's analysis and the variation of