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| Start date | Reporting criterion | Title | Event description | System | LER | |
|---|---|---|---|---|---|---|
| ENS 57302 | 10 July 2024 13:02:00 | 10 CFR 50.73(a)(1), Submit an LER | 60-DAY Optional Telephonic Notification of Invalid Residual Heat Removal Activation | The following information was provided by the licensee via phone and email: A 10 CFR 50.73(a)(1) invalid specified system actuation reported under 10 CFR 50.73(a)(2)(iv)(a) invalid actuation of residual heat removal (RHR). This 60-day telephone notification is being made per 10 CFR 50.73 (a)(2)(iv)(a) under the provision of 10 CFR 50.73 (a)(1) as an invalid actuation of the RHR. On July 10, 2024, while at 100 percent power, a partial train actuation of RHR was initiated by an invalid actuation signal while performing RHR valve logic testing. The cause for the RHR system logic actuation was due to improper configuration of an emergency core cooling system (ECCS) logic tester. The RHR system started and functioned as designed for the actuation signals it received from the ECCS logic tester. There was no impact on the health and safety of the public or plant personnel. The NRC resident inspector was notified. | Residual Heat Removal Emergency Core Cooling System | |
| ENS 45046 | 13 April 2009 20:46:00 | 10 CFR 50.73(a)(1), Submit an LER | Human Performance Error While Troubleshooting a Power Supply | This telephone notification, instead of a written LER is provided in accordance with 10CFR50.73(a)(1), to report an invalid actuation reportable under 10CFR50.73(a)(2)(iv)(A). On 4/13/2009, during troubleshooting activities for a control room annunciator power supply problem, a 'D' channel LOCA Level 1 Isolation Logic relay trip occurred when the relay power supply was de-energized and then re-energized. De-energization of the relays caused the 'D' Emergency Diesel Generator (EDG) to auto start, the 'B' Control Room Emergency Filtration System to auto start and the 'D' Safety Auxiliaries Cooling System pump to auto start. The other components of this logic system were properly removed from service and did not actuate. This is classified as an 'invalid' actuation reportable under 50.73(a)(2)(iv)(A). The logic system actuation was due to a human performance error and not the plant conditions. At the time, the plant was in Operational Condition 5 with the reactor cavity flooded and 'A' RHR system in shutdown cooling. In accordance with the existing plant conditions, all actions that should have occurred for this actuation did occur; no other initiations or actuations were noted. This event was entered into the HCGS (Hope Creek Generating Station) corrective action program. There was no radiological release associated with this event. The NRC Senior Resident Inspector has been notified of this report. | Emergency Diesel Generator Shutdown Cooling Control Room Emergency Filtration System |