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:
stemAFWS to confirm that the flow provided is acceptable for controlling the transient following a feedwater line break. SCSB reviews the methodology which evaluates the response of the containment to breaks of feedwater lines with regard to the effects of pressure and temperature on the containment functional capabilities as part of its primary review responsibility for SRP Section 6.2.1. d. A secondary review is performed by the Accident Evaluation Branch (AEB)PERB and the results are used by ASBSPLB to complete the overall evaluation of the break analysis. e. The AEBPERB evaluates the fission product release assumptions used in deter- mining any offsite releases and verifies that the radiological consequences resulting from a feedwater pipe break are within acceptable limits as part of its primarysecondary review responsibility for SRP Section 15.6.5. The result of 27 AEB'sPERB's analysis is transmitted to RSBSRXB for use in the SER writeup. 28 f. The ICSBHICB reviewer concentrates on the instrumentation and control aspects of the sequence described in the SAR to evaluate whether the reactor and plant protection and safeguards controls and instrumentation systems will function as assumed in the safety analysis with regard to automatic actuation, remote sensing, indication, control, and interlocks with auxiliary or shared systems. The HICB review includes an evaluation of the instrumentation and controls required to ensure automatic and manual auxiliary feedwater system initiation and flow indication in the control room in accordance with the requirements of 10 CFR 50.34(f)(2)(xii), as part of its primary review responsibility for SRP Section 7.1. ICSBHICB also evaluates potential bypass modes and the 29 possibility of manual control by the operator as part of its primary 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