Semantic search
| Entered date | Event description | |
|---|---|---|
| ENS 54075 | 21 May 2019 17:14:00 | At approximately 1833 EDT on 5/20/2019, VC Summer Nuclear Station identified a potential missed surveillance of the Spent Fuel Storage Canister Heat Removal System Surveillance Requirement (SR) 3.1.2. This is a surveillance requirement in the Holtec CoC No. 1032 Amendment 0, Revision 1 for the HI-STORM FW. It was identified that the station suspended verifying all overpack inlets and outlets were free of blockage from solid debris or floodwater every 24 hours and began utilizing the alternate surveillance method of installed temperature monitoring equipment. However, this monitoring equipment had not been declared operable from the completion of the Dry Cask Storage Campaign on April 11, 2019. This surveillance was last performed satisfactorily on May 15, 2019. The station has documented this missed surveillance in the Corrective Action Program under CR-19-01866. The NRC Senior Resident has been notified. The licensee stated that the temperature monitoring equipment while not operable, was functional. The licensee successfully performed the surveillance requirement on 5/21/2019.
ENS Event Number 54075, made on May 21, 2019, is being retracted. NRC Notification 54075 was made to ensure the 24-Hour Non-Emergency reporting requirement of 10 CFR 72.75(d)(1)(i) was met for a potential missed surveillance of the Spent Fuel Storage Canister Heat Removal System Surveillance Requirement (SR) 3.1.2. On June 4, 2019, a Past Operability Evaluation determined the temperature monitoring equipment, utilized to complete the Technical Specification Surveillance 3.1.2, was operable during the time period of 5/16/2019-5/21/2019. The station performed satisfactory calibration checks on the temperature monitoring equipment and had not experienced any significant weather events capable of producing vent blockage (i.e. flood, tornado, snow storm, etc.). Therefore, utilizing the installed temperature monitoring equipment is not considered a missed surveillance of SR 3.1.2 and renders this event not reportable under 10 CFR 72.75(d)(1)(i). VCSNS's evaluation of this event is documented in the Corrective Action Program in Condition Report (CR-19-01866). The licensee has notified the NRC Resident Inspector. Notified R2DO (Rose) and NMSS Events Notification (email). |
| ENS 52833 | 29 June 2017 12:43:00 | On 6/29/2017 at 0857 (EDT), VC Summer Nuclear Station automatically tripped due to a loss of normal feed water flow to the B Steam Generator. There were no complications with the trip. All control rods fully inserted. All emergency feedwater pumps automatically started and recovered steam generator levels. The plant is stable in Mode 3. Station personnel are investigating the cause of the loss of normal feedwater to the B Steam Generator. This is reportable per 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A). The NRC Resident Inspector has been notified. The licensee notified the State of South Carolina as well as Fairfield, Lexington, Richland and Newberry Counties regarding the event. |