Residual Heat Removal (RHR) aka residual heat removal system (RHS) is a mode of Low Pressure Injection System which is meant to cool the reactor core after its shutdown. Since fuel will still be reactive to some degree it will continue to give off heat. The RHR prevents the water covering the pool from getting hot and boiling off.
Modes
Shutdown Cooling
The shutdown cooling (SDC) mode of RHR is meant for long term reactor vessel to RHRSW heat exchangers.
Low Pressure Cooling Injection
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| | Site | Start date | Title | Description |
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| ML25155A058 | | 5 June 2025 | NRC Presentation for Performance Indicator Workshop 1 | | | 05000263/LER-2024-002-01, Low Pressure Coolant Injection Inoperable Due to Motor Valve Failure | Monticello | 30 May 2025 | Low Pressure Coolant Injection Inoperable Due to Motor Valve Failure | | | ML25122A101 | Vogtle | 30 May 2025 | Issuance of Amendment to Regarding the Adoption of Technical Specifications, Revision 1 | | | ML25149A224 | South Texas | 29 May 2025 | Final ASP Analysis - South Texas Project 1, Condition Prohibited by TS and Potential Loss of Safety Function of Pressurizer PORV (LER 498-2024-006) - Precursor | | | IR 05000298/2024003 | Cooper | 29 May 2025 | Integrated Inspection Report 05000298/2024003, Disputed Non-Cited Violation Revised | | | ENS 57731 | River Bend | 23 May 2025 04:58:00 | Degraded RHR Check Valve | The following information was provided by the licensee via phone and email:
On May 22, 2025, at 2358 CDT, River Bend Station determined that a degraded condition existed following the performance of a VT-3 examination of E12-AOVF041A, Residual Heat Removal (RHR) 'A' injection line testable check valve. The cause of this event is currently being investigated. This examination was conducted following the plant shutdown, which was reported in Event Notification (EN) 57725.
This event is being reported as an 8-hour reportable condition in accordance with 10 CFR 50.72(b)(3)(ii)(A) for the degraded condition of the pressure boundary.
The NRC Resident Inspector has been notified."
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
This degraded condition resulted in a leakage rate of approximately 3.6 gallons per minute when at pressure. The plant is shutdown and depressurized which has caused the leakage to stop. No release is occurring or expected and possible corrective actions are being evaluated. | | ML25143A104 | | 23 May 2025 | FOIA-2025-000420 - Resp 2 - Released Set | | | ML25085A417 | 05200050 | 22 May 2025 | SDAA - FSER Chapter 11 - Radioactive Waste Management | | | ML25094A152 | 05200050 | 22 May 2025 | SDAA - FSER Chapter 4 - Reactor | | | ML25094A183 | 05200050 | 22 May 2025 | SDAA - FSER Appendix C - Abbreviations | |
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