Document: NUREG-0800
Document ID: 7ed8e5d3-fcfd-49cc-84ad-3b25caba06af
Document Type: srp
Title: STEAM SYSTEM PIPING FAILURES INSIDE AND OUTSIDE OF CONTAINMENT
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550006.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.1.5
CFR Part: 
CFR Title: 

Content:
n result in a rapid decrease in reactor coolant temperature and steam generator pressure, placing undue stress on the reactor coolant pressure boundary. This potential problem could be aggravated by a pressurization of the primary system when the emergency core cooling system is activated. The amount of stress to the reactor coolant pressure boundary depends on the severity of the transient. The severity of the transient is assessed by the applicant in the SAR and is reviewed by the staff in accordance with this SRP section. 5. Compliance with GDC 35 requires a system that will provide abundant emergency core cooling. The system safety function shall be to transfer heat from the reactor core after any loss of reactor coolant at a rate ensuring that (a) fuel and clad damage interfering with continued effective core cooling is prevented and (b) clad metal-water reaction is limited to negligible amounts. GDC 35 is applicable to this section because the reviewer evaluates steam system piping failures, both inside and outside containment, that could cause transient conditions with the potential to challenge the emergency core cooling system. During a steam system piping break, excessive steam loss will result in a rapid reduction of reactor coolant temperature and steam generator pressure. A subsequent reactor trip can further reduce the primary system pressure, producing a void within the pressure vessel and creating the need for emergency core cooling. 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 the proposed alternatives provide an acceptable method of complying with the relevant NRC requirements identified in Subsection II. 15.1.5-9 Revision 3 - March 2007 The procedures below are used during