Document: NUREG-0800
Document ID: c5cd8519-169f-4fec-9d25-9ddb3ba73f52
Document Type: srp
Title: RESIDUAL HEAT REMOVAL (RHR) SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550002.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.4.7
CFR Part: 
CFR Title: 

Content:
e adequacy of those criteria and bases, and conformance of the design to those criteria and bases. Based on the following, the staff concludes that the design of the RHR system is acceptable and meets the requirements of General Design Criteria 2, 4, 5, 19, and 34 and 10 CFR 50.34(f)(2)(xxvi): A. The applicant has met General Design Criterion 2 with respect to Regulatory Position C-2 of Regulatory Guide 1.29 concerning the seismic design of structures, systems, and components (SSCs) whose failure could cause an unacceptable reduction in the capability of the RHR system. B. The applicant has met General Design Criterion 4 with respect to dynamic effects associated with flow instabilities and loads (e.g., water hammer). C. The applicant has met the requirements of General Design Criterion 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 General Design Criterion 19, with respect to the main control room requirements for normal operations and shutdown, and General Design Criterion 34, which specifies requirements for the RHR by meeting the regulatory positions in Branch Technical Position 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 residual heat removal (RHR) function is accomplished in two phases—the 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 reactor core isolation cooling (RCIC) system and