Document: NUREG-0800
Document ID: c755e557-3a72-423f-92bc-0f0270936e27
Document Type: srp
Title: RESIDUAL HEAT REMOVAL (RHR) SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1006/ML100680577.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.4.7
CFR Part: 
CFR Title: 

Content:
G 1.29 concerning the seismic design of SSCs whose failure could cause an unacceptable reduction in the capability of the RHR system. 5.4.7-16 Revision 5 - May 2010 B. The applicant has met GDC 4 with respect to dynamic effects associated with flow instabilities and loads (e.g., water hammer). C. The applicant has met the requirements of GDC 5 with respect to the sharing of SSCs by demonstrating that such sharing does not significantly impair the ability of the RHR system to perform its safety function, including, in the event of an accident to one unit, an orderly shutdown and cooldown of the remaining units. D. The applicant has met GDC 19, with respect to the main control room requirements for normal operations and shutdown, and GDC 34, which specifies requirements for the RHR by meeting the regulatory positions in BTP 5-4. E. The applicant has met the parameters in Item III.D.1.1 of NUREG-0737, equivalent to 10 CFR 50.34(f)(2)(xxvi) for applicants subject to 10 CFR 50.34(f), with respect to leakage detection and control in the design of RHR systems outside containment that contain (or may contain) radioactive material following an accident. 2. For BWRs The RHR function is accomplished in two phasesCthe initial cooldown phase and a low pressure-temperature operation phase. In the event of a loss of offsite electrical power, the initial cooldown phase is accomplished through the RCIC system and the safety/relief valves. The RHR system usually supports the low pressure-temperature mode of operation. However, certain single failures can render the RHR system inoperative. In that event, two alternate systems that use components of the RCIC and RHR system are available to bring the reactor to cold shutdown conditions. The scope of review of these systems for the plant included piping and instrumentation diagrams, equipment layout drawings, failure modes and effects analysis, and design performance specifications for essential components. The review has included the