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:
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 applicant=s proposed design criteria and design bases for these systems, analysis of the 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 GDCs 2, 4, 5, 19, and 34 and 10 CFR 50.34(f)(2)(xxvi): A. The applicant has met GDC 2 with respect to Regulatory Position C-2 of RG 1.29 concerning the seismic design of SSCs whose failure could cause an unacceptable reduction in the capability of the RHR system. B. The applicant has met GDC 4 with respect to dynamic effects associated with flow instabilities and loads (e.g., water hammer). 5.4.7-17 Revision 5 - May 2010 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 system by meeting the regulatory positions in BTP 5-4. E. The applicant has met the parameters of 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. In addition to the above criteria, the acceptability of the RHR system may be based on the degree of design similarity with previously approved plants. Deviations from these criteria for