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:
he 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 moderator temperature, void, and Doppler coefficients of reactivity with core life. The justification provided by the applicant to show that he has selected the core burnup that yields the minimum margins is evaluated. CPB is consulted regardingSRXB also reviews the values of reactivity parameters used in the applicant's analysis.48 Analytical models should be of sufficient detail to simulate the reactor coolant (primary), steam generator (secondary), and auxiliary systems. The equations, sensitivity studies, and models proposed by the applicant, and justification that the methods used are conservative in comparison with the semi-scale test data from NUREG/CR-4945 are reviewed by RSBSRXB. 49 Credit taken for a reactor trip signal or for actuation of engineered safety featuresESS should be reviewed by ICSBHICB to determine the ability of the instrumentation and control systems to respond as assumed under accident conditions. The ability of the auxiliary feedwater systemAFWS to supply adequate feedwater flow to the unaffected steam generators during the accident and subsequent shutdown is evaluated by ASBSPLB as to availability and by RSBSRXB as to capability to effect an orderly shutdown. 50 Since auxiliary feedwater systemAFWS designs are diverse and may require both automatic and DRAFT Rev. 2 - April 1996 15.2.8-12 manual actuation, preoperational tests should be specified to identify any necessary operator actions and to determine the maximum times permitted for their completion. To the extent considered necessary, the RSBSRXB reviewer evaluates the effect of single active failures of systems and components that may alter the course of the accident. For new applications, the LOOP is not considered a single active failure, but considered in addition to a single active