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| Entered date | Event description | |
|---|---|---|
| ENS 56095 | 7 September 2022 15:06:00 | A licensed employee had a confirmed positive for alcohol during a random fitness-for-duty test. Unescorted access for the individual has been denied at all Dominion Energy sites. |
| ENS 55299 | 9 June 2021 15:02:00 | At 1115 EDT on June 9, 2021, during a siren activation test, a loss of the capability to activate the sirens from both Surry local activation sites was identified. The Virginia EOC was participating in the activation test and is aware of the issue and notified the local government authorities in the Surry EPZ of the situation. The NRC Resident has been notified of this issue. The station telecommunications department has been contacted and is aware of the issue. In the event that a radiological emergency should occur at the Surry Power Station, Primary Route Alerting procedures will be put in use by the local jurisdictions. This report is being made in accordance with 10 CFR 50.72(b)(2)(xi) and 10 CFR 50.72(b)(3)(xiii) due to notification of other state and local government agencies of the failure of the Alert & Notification system for Surry.
Surry Power Station Event Notification 55299 is being retracted based upon further evaluation. Surry has three localities (State SAU, James City, and Surry County) with access to the redundant activation trains (primary and backup systems). The actuation tests only one primary and one backup activation panel at two localities, only primary at the State SAU (Situational Awareness Unit) and back up at James City County were tested. Follow-up telecom and vendor investigation revealed that the primary server was functional from James City County that would have actuated all 71 sirens; Consequently, it was concluded that all of the sirens were fully functional from the James City primary system and there was no loss of all sirens as originally reported on 6/9/2021 (EN 55299). EN 55299 also contained a 4-hour Offsite Notification per 10 CFR 50.72(b)(2)(xi) that is unaffected. The NRC Resident Inspector has been notified. Notified R2DO (Miller). |
| ENS 54727 | 26 May 2020 15:55:00 | A contract foreman had a confirmed positive for alcohol during a random fitness-for-duty test. The employee's access to the plant has been terminated. The licensee notified the NRC Resident Inspector. |
| ENS 54437 | 11 December 2019 15:06:00 | On December 11, 2019, at 1356 EST, it was concluded that certain safety-related equipment is vulnerable to design basis tornado missiles which could render the equipment inoperable and not able to perform its design function. This applies to the following Technical Specification equipment: 1. Component cooling water piping for the 'A' spent fuel cooling water system heat exchanger. This heat exchanger is vulnerable to a horizontal missile traveling through the roll-up door, which would challenge operability of the Technical Specification required component cooling system equipment. 2. All three (3) emergency service water pumps and their diesel fuel oil supply tank. The emergency service water pumps and diesel fuel oil tank are vulnerable to a horizontal missile penetrating the missile screens. 3. Certain component cooling water system pump discharge piping is vulnerable from a vertical missile penetrating the auxiliary building roof. 4. The Unit 1 auxiliary feedwater (AFW) system pumps and the pump suction and discharge piping are vulnerable to a missile traveling through the screens on the sides and roof of the main steam valve house. This vulnerability also exists for the Unit 2 AFW. This condition puts Unit 1 and 2 into Technical Specification 3.01 which requires the units to be in hot shutdown within 6 hours and in cold shutdown within the following 30 hours. The NRC Resident Inspector has been notified. |
| ENS 52894 | 9 August 2017 17:35:00 | On 8/9/17, a Unit 1 containment entry was made in order to investigate increased Reactor Coolant System (RCS) unidentified leakage. The team noted a through-wall leak from the tubing/socket weld area of 'C' Hot Leg Sample Valve. The sample valve and RCS pressure boundary were declared inoperable, and a 6-hour action statement to place Unit 1 in Hot Shutdown was entered at 1338 (EDT) hours as required by Technical Specification 3.1.C.3. At 1606 (EDT) hours on 8/9/17, Unit 1 shutdown was commenced, and at 1637 (EDT), Unit 1 was at Hot Shutdown. This report is being submitted pursuant to 10CFR50.72(b)(2)(i) as a result of power reduction required by Technical Specifications. Further, this report is being submitted pursuant to 10CFR50.72(b)(3)(ii)(A) for any event or condition that results in the condition of the nuclear power plant, including its principle safety barriers, being seriously degraded. The NRC Resident (Inspector) has been notified of this event and is on site. There was no radiation release associated with this event, nor were there any personnel injuries or contamination events. |
| ENS 52292 | 9 October 2016 06:09:00 | Surry Unit 2 reactor automatically tripped at 0254 hours on 10/09/2016, due to a Main Generator Differential Lockout Turbine Trip. The cause of the generator differential lockout is under investigation at this time. Reactor Coolant System temperature is currently being maintained at 547 degrees Fahrenheit on the main steam dump valves. All three Auxiliary Feedwater Pumps automatically started as designed on Low-Low Steam Generator Water Level following the trip. Auxiliary feedwater pumps have since been secured and Main Feedwater is in use. All systems operated as required. The source range nuclear instruments had to be manually reinstated following the reactor trip due to indications of undercompensation on Intermediate Range Nuclear Instrument channel N-36. Off site power remains available. There is no impact on Surry Unit 1. This notification is being made pursuant to 10CFR50.72(b)(2)(iv)(B) for 4-hour notification of Reactor Protection System activation and 10CFR50.72(b)(3)(iv)(A) for 8-hour notification of automatic actuation of the Auxiliary Feedwater System. The NRC Resident Inspector has been notified and is responding to the site. There were no radiation releases, personnel injuries, or contamination events due to this event. All control rods fully inserted. Secondary reliefs lifted and reseated as expected following a reactor trip from 100% power. |
| ENS 48194 | 15 August 2012 16:21:00 | At 1000 hours (EDT) on 8/14/12, Surry Power Station personnel confirmed the presence of tritium at a level of 1,250 picoCuries/liter (pCi/l) in the #3 Turbine Building sump. The sump water had been tested upon discovery of a degraded drain line on the sump discharge that resulted in a leak to the environment. The exact volume could not be determined, but it is estimated to be greater than the 100 gallon reporting criteria. The location of the leak is within the Protected Area of Surry Power Station. To prevent additional releases, water from the #3 Turbine Building sump has been redirected to another turbine building sump. There is no Indication that this water has migrated offsite. Because there was a detectable amount of licensed material in the water, Surry has implemented our voluntary communication protocols to the state and Surry County as per our commitment to the Nuclear Energy Institute (NEI) Ground Water Protection Initiative. An adjacent ground water monitoring well was sampled, and no tritium activity was detected in the well water. There has been no tritium detected in any monitoring wells in the vicinity of the drain line, nor in any monitoring wells outside the Protected Area. The activity of the leak was approximately 6% of the criteria for reporting actual ground water activity (20,000 pCi/l). Because the leak remained on site, no offsite impact to ground water is expected. Furthermore, the leak posed no threat to employees or the public. The degraded drain pipe is currently being repaired. This notification Is being transmitted due to Notification of Other Government Agencies under 10CFR50.72(b)(2)(xi). The Virginia Department of Environmental Quality, Virginia Department of Health, and Virginia Department of Emergency Management were notified. The NRC Senior Resident (Inspector) and Surry County Administrator will be notified. |
| ENS 45986 | 8 June 2010 12:00:00 | At 0948 hours (EDT) on 6/8/10, a Unit 1 vital AC bus was lost when the uninterruptible power supply inverter failed while the alternate AC source was out of service for scheduled maintenance. The loss of the vital bus inverter caused a loss of 120 VAC vital bus 1-III. The loss of this vital bus caused the 'A' main feed pump recirculation valve to fail open and also caused 2 of the 3 main feedwater regulating valves to fail to automatic-hold mode of operation. This combination of as designed failures resulted in a reduction in main feedwater flow and resulted in an automatic reactor trip due to a feed flow steam flow mismatch in conjunction with low steam generator level. The loss of vital bus 1-III also resulted in initiation of safety injection due to loss of vital bus 1-III instrumentation in conjunction with the expected momentary RCS cooldown below 543 DEG-F. The safety injection resulted from the high steam flow in conjunction with low RCS T-ave actuation signal. The safety injection actuation also resulted in automatic start of the #1 Emergency Diesel and the #3 Emergency Diesel Generators. Neither EDG was required to load since off-site power remained operable. The loss of vital bus 1-III also resulted in loss of numerous field inputs to the Plant Computer System (PCS) and resulted in non-functionality of the SPDS (Safety Parameter Display System). The PCS itself remains functional along with MCR (Main Control Room) annunciators and sufficient MCR instrumentation to monitor critical safety functions. All three auxiliary feedwater pumps automatically initiated as designed on low-low steam generator level following the trip. Currently, RCS temperature is being maintained stable at 547 degrees. All systems functioned as required following the reactor trip. During the post-trip transient, pressurizer PORV (Power Operated Relief Valve), PCV-1455C, cycled as required to maintain RCS pressure due to the safety injection and the loss of normal letdown. There were no radiation releases due to this event, nor were there any personnel injuries or contamination events. This event is being reported in accordance with 10CFR50.72(b)(2)(iv)(B), 10CFR50.72(b)(2)(iv)(A), 10CFR50.72(b)(3)(iv)(A), and 10CFR50.72(b)(3)(xiii). The NRC Resident Inspector was notified of this event. During the trip, all rods inserted into the core. In addition to the pressurizer PORV lifting, a secondary main steam relief valve lifted. All relief valves properly reseated and there is no known primary to secondary leakage. The plant is in its normal shutdown electrical lineup. Main steam trip valves were isolated during the transient. Decay heat is being removed via main steam bypasses to the condenser and steam generator power operated relief valves. |