Document: NUREG-0800
Document ID: 5d88f9f1-c708-4a51-8593-a2aa484a15f3
Document Type: srp
Title: Revision 4 - March 2007
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0708/ML070850123.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5
CFR Part: 
CFR Title: 

Content:
lear Regulatory Commission, Washington, DC 20555, Attention: Reproduction and Distribution Services Section, or by fax to (301) 415-2289; or by email to DISTRIBUTION@nrc.gov. Electronic copies of this section are available through the NRC's public Web site at http://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr0800/, or in the NRC's Agencywide Documents Access and Management System (ADAMS), at http://www.nrc.gov/reading-rm/adams.html, under Accession # ML070850123. NUREG-0800 U.S. NUCLEAR REGULATORY COMMISSION STANDARD REVIEW PLAN BRANCH TECHNICAL POSITION 5-4 DESIGN REQUIREMENTS OF THE RESIDUAL HEAT REMOVAL SYSTEM REVIEW RESPONSIBILITIES Primary - Organization responsible for review of reactor thermal hydraulic systems in PWRs and BWRs Secondary - None A. BACKGROUND General Design Criterion (GDC) 19 in Appendix A to 10 CFR Part 50 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 include the shutting down of a reactor; therefore, since the 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.” 1 Processes involved in cooldown are heat removal, depressurization, flow circulation, and reactivity control. The cold shutdown condition, as described in the Standard Technical Specifications, refers to a subcritical reactor with a reactor coolant temperature no greater than 93.3EC (200EF) for a pressurized-water reactor (PWR) and 100EC (212EF) for a boiling-water reactor. BTP 5-4-2 Revision 4 - March 2007 In