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:
ith that reviewer. For the purposes of the cooldown review of both PWRs and BWRs, the reviewer should only assume the operation of safety-grade equipment. For PWRs, if the PORVs are relied upon in the performance of a safety-related function such as plant cooldown for compliance with Branch Technical Position BTP 5-4, the PORVs must meet the guidance contained in Generic Letter 90-06 (see also NUREG-1316), as reviewed under SRP Section 6.8. For new PWRs that use PORVs, the valves should be safety related. 7. The staff reviews the cooldown function to determine whether it can be performed from the control room assuming a single failure of an active component, with only either onsite or offsite electric power available. The applicant must justify any operation required outside of the control room. As with item 6 above, the organization responsible for the review of steam and feedwater systems will evaluate the initial cooldown for PWRs. 8. By reviewing the system description and the P&IDs, the reviewer confirms that the RHR system satisfies the pressure relief requirements of Branch Technical Position BTP 5-4. 9. By reviewing the piping arrangement and system description of the RHR system, the reviewer confirms that the RHR system meets the requirements of GDC 5 concerning shared systems. 10. The reviewer of reactor thermal hydraulic systems contacts the reviewer of steam and feedwater systems in conjunction with the review of the RHR system heat sink and refueling system interaction to exchange information and ensure that the reviews consider the interfacing parameters consistently. For example, the organization responsible for the review of cooling water systems associated with balance of plant review determines the maximum service or component cooling water temperature. The reviewer of reactor thermal hydraulic systems then evaluates the RHR system description to determine that the RHR system design allows for this maximum temperature. 5.4.7-11 Revision 4 - March