(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Reactor Core Isolation Cooling (RCIC) is a system which injects cooling water at high pressure. Not as much water as HPCI
System |
|---|
|
|
| | Site | Start date | Title | Description |
|---|
| ENS 58036 | Fermi | 12 November 2025 17:50:00 | High Pressure Coolant Injection Inoperable | The following information was provided by the licensee via phone and email:
On November 12, 2025, at approximately 1250 EST, during surveillance testing of the high-pressure coolant injection (HPCI) system the HPCI minimum flow valve (E4150F012) would not open during stroke testing. HPCI had been removed from service for quarterly surveillance testing at 0957, November 12, 2025. The unplanned inoperability condition began at 1250 when a stroke time test was attempted, and the valve did not reposition. Since HPCI is a single-train safety system, this meets the criterion for event notification per 10CFR50.72(b)(3)(v)(D) as a condition that, at the time of discovery, could have prevented the fulfillment of a safety function needed to mitigate the consequences of an accident, based on loss of a single train safety system. Reactor core isolation cooling was and has remained operable. The Senior NRC Resident Inspector has been notified. The failure is currently under investigation.
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
Limiting conditions for operation 3.5.1 and 3.6.1.3 were entered to address HPCI inoperable. The site remains on normal offsite power, and all emergency diesel generators remain available. | | 05000296/LER-2025-002, Reactor Core Isolation Cooling Inoperable Due to Failed Ramp Generating Signal Converter | Browns Ferry | 20 October 2025 | Reactor Core Isolation Cooling Inoperable Due to Failed Ramp Generating Signal Converter | | | LG-25-132, License Amendment and Alternative Request Related to One-Time Exception of Primary Containment Isolation Valve Testing | Limerick | 9 October 2025 | License Amendment and Alternative Request Related to One-Time Exception of Primary Containment Isolation Valve Testing | | | ML25265A018 | Limerick | 29 September 2025 | Pre-Application Meeting: Limerick LAR for a One-Time Exception to Appendix J, Type C Tests and Relief Request for ASME Inservice Tests (Slides/Presentation) | | | ML25268A175 | Hatch | 26 September 2025 | Authorization of Alternative Request RR-V-4 - Sixth Inservice Testing Interval | | | L-MT-25-031, Site Specific Emergency Action Level Technical Basis Documents Change | Monticello | 24 September 2025 | Site Specific Emergency Action Level Technical Basis Documents Change | | | IR 05000387/2025010 | Susquehanna | 22 September 2025 | Comprehensive Engineering Team Inspection (CETI) Inspection Report 05000387/2025010 and 05000388/2025010 | | | PLA-8189, Supplement to License Amendment Requesting Revision to Technical Specifications for Reactor Vessel Water Level 3 and Level 8 Allowable Values - PLA-8189 | Susquehanna | 10 September 2025 | Supplement to License Amendment Requesting Revision to Technical Specifications for Reactor Vessel Water Level 3 and Level 8 Allowable Values - PLA-8189 | | | ENS 57905 | Quad Cities | 5 September 2025 06:30:00 | High Pressure Coolant Injection Inoperable | The following information was provided by the licensee via phone and email:
At 0130 CDT on September 5, 2025, it was discovered that the single train high pressure coolant injection (HPCI) system was inoperable. Due to this inoperability, the system was in a condition that could have prevented the fulfilment of a safety function. Therefore, this condition is being reported as an 8-hour, non-emergency notification per 10 CFR 50.72(b)(3)(v)(D).
Unit 1 reactor core isolation cooling was operable during this time period. There was no impact on the health and safety of the public or plant personnel.
The NRC Resident Inspector has been notified. The Illinois Emergency Management Agency has been notified.
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
The inoperability was caused by a malfunctioning turbine steam admission valve during a surveillance. Unit 1 is in a 14-day limiting condition for operations. | | JAFP-25-0046, License Amendment Request - Proposed Change to the Technical Specifications to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment Isolation | FitzPatrick | 5 September 2025 | License Amendment Request - Proposed Change to the Technical Specifications to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment Isolation | |
|