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:
rimary reactor responsibility for SRP Sections 7.1 through 7.7. HICB also reviews the credit taken for a reactor trip signal or for actuation of ESS to determine the ability of the instrumentation and control systems to respond as assumed under accident conditions.30 g. The Materials and Chemical Engineering Branch (EMCB) reviews the fracture toughness properties of the reactor coolant pressure boundary and reactor vessel as part of its primary review responsibility for SRP Sections 5.2.3 and 5.3.1.31 For those areas of review identified above as being reviewed as part of the primary review responsibility of other branches, the acceptance criteria necessary for the review and their methods of application are contained in the referenced SRP sections of the corresponding primary branch. DRAFT Rev. 2 - April 1996 15.2.8-6 II. ACCEPTANCE CRITERIA The basic objective of the review of feedwater system pipe break events is to confirm that the reactor primary system is maintained in a safe status for a range of feedwater line breaks, up to and including a break equivalent in area to the double-ended rupture of the largest feedwater line. RSBSRXB acceptance criteria are based on meeting the relevant requirements of the following regulations: A. General Design Criterion 17 (GDC 17) as it relates to providing onsite and offsite electric power systems to ensure that structures, systems, and components important to safety will function. The safety function for each system (assuming the other system is not functioning) shall be to provide sufficient capacity and capability to ensure that design conditions of the reactor coolant pressure boundary are not exceeded and the core is cooled in the event of postulated accidents.32 B. General Design Criteria 27 (GDC 27) and 28 (GDC 28), as they relate to the reactor 33 coolant system being designed with appropriate margin to assureensure that acceptable fuel design limits are not exceeded, and that the capability to cool the core is