| | Site | Start date | Title | Description |
|---|
| IR 05000458/2024003 | River Bend | 31 October 2024 | Integrated Inspection Report 05000458/2024003 | |
| IR 05000440/2024003 | Perry
07200069 | 30 October 2024 | Integrated Inspection Report 05000440/2024003 and 07200069/2024001 | |
| ENS 57406 | Perry | 29 October 2024 15:52:00 | Inoperability of Division 3 Diesel Generator Supporting High Pressure Core Spray | The following information was provided by the licensee via phone and email:
At 1152 EDT, on 10/29/2024, the division 3 diesel generator was declared inoperable due to variations in steady state voltage during a planned monthly surveillance run. Troubleshooting of the issue is in progress. This condition could prevent the fulfillment of a safety function; therefore, this condition is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(v). All other emergency core cooling systems were operable during this time.
There was no impact on the health and safety of the public or plant personnel. The NRC resident inspector has been notified.
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
Limiting condition for operations (LCO) 3.8.1.b was entered as a result of this event. |
| ML24290A114 | Columbia | 17 October 2024 | CGS FPTI 2024011 | |
| L-24-208, License Renewal Application for the Perry Nuclear Power Plant - Responses to Request for Additional Information - Round 1 (Set 2) | Perry | 2 October 2024 | License Renewal Application for the Perry Nuclear Power Plant - Responses to Request for Additional Information - Round 1 (Set 2) | |
| ENS 57349 | Grand Gulf | 27 September 2024 23:22:00 | High Pressure Coolant Injection Inoperable | The following information was provided by the licensee via phone and email:
At 1822 CST on September 27, 2024, Grand Gulf Nuclear Station (GGNS) was conducting surveillance testing on the high pressure core spray (HPCS) division Ill diesel generator. Following initiation of the test signal, the HPCS pump room cooler start time exceeded the surveillance procedure allowance of less than or equal to 20 seconds. The HPCS pump room cooler started in 26.2 seconds. HPCS was already inoperable for performance of the surveillance testing.
The event is being reported in accordance with 10 CFR 50.72(b)(3)(v)(D) as an event or condition which could have prevented the fulfillment of a safety function.
Troubleshooting is in progress. HPCS, a single-train system, will remain inoperable until the condition is corrected.
All sources of offsite power are available. No other safety systems are inoperable. Reactor core isolation cooling was verified to be operable per GGNS Technical Specification 3.5.1.B.1.
The NRC Senior Resident Inspector has been notified. |
| ENS 57338 | Grand Gulf | 25 September 2024 03:04:00 | High Pressure Core Spray Inoperable | The following information was provided by the licensee via phone or email:
On September 24, 2024, at 2204 CDT, Grand Gulf Nuclear Station (GGNS) was conducting surveillance testing on the high pressure core spray (HPCS) division III diesel generator. During testing, the HPCS pump breaker unexpectedly tripped after the HPCS diesel generator started and powered the safety bus. The breaker performed its motor protection function and tripped due to an over-frequency indication.
The event is being reported in accordance with 10 CFR 50.72(b)(3)(v)(D) as an event or condition which could have prevented the fulfillment of a safety function.
Troubleshooting is in progress. HPCS, a single-train system, will remain inoperable until the condition is corrected.
All sources of offsite power are available. No other safety systems are inoperable. Reactor core isolation cooling was verified to be operable per GGNS Technical Specification 3.5.1.B.1.
The NRC Senior Resident has been notified. |
| 05000461/LER-2023-002-01, Reactor Core Isolation Cooling Inoperable Prior to Mode Change | Clinton | 24 September 2024 | Reactor Core Isolation Cooling Inoperable Prior to Mode Change | |
| ENS 57334 | Nine Mile Point | 23 September 2024 11:20:00 | Automatic Reactor Scram Due Turbine Trip | The following information was provided by the licensee via phone and email:
On 9/23/2024 at 0720 EDT, with Unit 2 in mode 1 at 100 percent power, the reactor automatically scrammed due to turbine stop valve closure on a turbine trip. The scram was not complex. Due to the reactor protection system (RPS) actuation while critical, this event is being reported as a four hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B). Following the scram, reactor water level dropped below level 2 (108.8 inches), starting high pressure core spray (HPCS) and reactor core isolation cooling (RCIC); both injected into the reactor. RCIC is being used with turbine bypass valves to remove decay heat. Due to the emergency core cooling systems HPCS and RCIC discharging into the reactor coolant system, this event is being reported a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(A), and an eight hour, non-emergency notification per 10 CFR 50.72(b)(3)(iv)(A). In addition, with reactor water level below level 2 (108.8 inches), primary containment isolation signals actuated resulting in group 2 recirculation sample system isolation, group 3 traveling in-core probe (TIP) isolation valve isolation, group 6 and 7 reactor water cleanup isolation, group 8 containment isolations, and group 9 containment purge isolations. This event is being reported as an eight hour, non-emergency notification per 10 CFR 50.72(b)(3)(iv)(A). Operations responded using procedure N2-EOP-RPV (1-3) and stabilized the plant in mode 3. There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector was informed. There was no impact on Unit 1.
- * * UPDATE ON 9/23/2024 AT 1550 EDT FROM RYAN LOOMIS TO IAN HOWARD * * *
On 9/23/2024 at 1156 EDT Constellation communications provided a media statement to Oswego area news media contacts summarizing the events that had occurred at Nine Mile Point Unit 2 and FitzPatrick Unit 1. This is a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(xi). The NRC Senior Resident Inspector has been notified.
Notified R1DO (Dimitriadis), NRR EO (Felts), and IR MOC (Grant). |
| GO2-24-051, Application to Revise Technical Specifications to Adopt TSTF-592, Revise Automatic Depressurization System (ADS) Instrumentation Requirements | Columbia | 23 September 2024 | Application to Revise Technical Specifications to Adopt TSTF-592, Revise Automatic Depressurization System (ADS) Instrumentation Requirements | |