Document: NUREG-0800
Document ID: 243e1ce7-857c-48e4-9eb7-6125311da9be
Document Type: srp
Title: RESIDUAL HEAT REMOVAL (RHR) SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070437.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.4.7
CFR Part: 
CFR Title: 

Content:
an Requirements." 24. NUREG-1316, “Technical Findings and Regulatory Analysis Related to Generic Issue 70 - Evaluation of Power-Operated Relief Valve and Block Valve Reliability in PWR Nuclear Power Plants.”168 5.4.7-21 DRAFT Rev. 4 - April 1996 25. NUREG-1449, “Shutdown and Low-Power Operation at Nuclear Power Plants in the United States.”169 26. NUREG-0927, Revision 1, "Evaluation of Water Hammer Occurrences in Nuclear Power Plants," March 1984.170 Processes involved in cooldown are heat removal, depressurization, flow circulation, and 1 reactivity control. The cold shutdown condition, as described in the Standard Technical Specifications, refers to a sub critical reactor with a reactor coolant temperature no greater than 93.3 C (200 F) for a PWR and 100 C (212 F) for a BWR. DRAFT Rev. 4 - April 1996 5.4.7-22 BRANCH TECHNICAL POSITION RSB 5-1 (CURRENTLY THE RESPONSIBILITY OF REACTOR SYSTEMS BRANCH - SRXB)171 DESIGN REQUIREMENTS OF THE RESIDUAL HEAT REMOVAL SYSTEM BACKGROUND GDC 19 states that, "A control room shall be provided from which actions can be taken to operate the nuclear power unit under normal conditions..." Normal operating conditions includeing the shutting down of a reactor; therefore, since the 172 residual heat removal (RHR) system is one of several systems involved in the normal shutdown of all reactors, this system must be operable from the control room. GDC 34 states that "Suitable redundance...shall be provided to assure that for onsite electrical power system operation (assuming offsite power is not available) and for offsite electrical power system operation (assuming onsite power is not available), the system safety function can be accomplished, assuming a single failure." In most current plant designs the RHR system has a lower design pressure than the reactor coolant system (RCS), is located outside of containment and is part of the emergency core cooling system (ECCS). However, it is possible for the RHR system to have different