Semantic search
| Entered date | Event description | |
|---|---|---|
| ENS 49294 | 22 August 2013 01:11:00 | On 08/21/2013, the Kewaunee Power Station was notified by Kewaunee County Emergency Management of the inadvertent actuation of siren K-005 at 2100 (CDT). At the time of the actuation, there was severe weather in the area. The siren stopped actuating at 2125. Kewaunee Power Station requested maintenance crews remove power from the siren to prevent additional actuation until repairs can be made. The resulting loss of siren coverage is 4%. Siren K-005 is a shared siren with Point Beach Nuclear Power Plant. Point Beach control room has been notified. The licensee has notified the NRC Resident Inspector. |
| ENS 49247 | 7 August 2013 09:05:00 | On August 7, 2013, at 0345 (CDT), Kewaunee Power Station was notified that a loss of alert sirens impacting greater than 50% of the Emergency Planning Zone population are non-functional due to a loss of power. The sirens are used to provide a public prompt notification. The sirens lost are those that Point Beach Nuclear Power Plant takes primary responsibility. Power was lost to them during a severe thunderstorm and the expected out of service time is unknown at this time. This condition is being reported in accordance with 10CFR50.72(b)(3)(xiii) as an event that results in a major loss of emergency assessment capability. The NRC Resident Inspector has been notified. See related EN #49246 * * * UPDATE FROM SCOTT CIESLEWICZ TO PETE SNYDER AT 1652 EDT ON 8/7/13 * * * Most emergency sirens have been returned to service such that the lost coverage is now only 24%. The licensee notified the NRC Resident Inspector. Notified R3DO (Lara). |
| ENS 48830 | 19 March 2013 10:00:00 | On March 19, 2013, at 0830 hours (CDT), the Kewaunee Power Station Technical Support Center (TSC) ventilation system was removed from service for planned TSC ventilation system maintenance. The removal of the ventilation system potentially affects the TSC habitability during a declared emergency requiring activation. The Emergency Response Organization (ERO) team has been notified of the maintenance and the possible need to relocate during an emergency. If an emergency is declared and TSC ERO activation is required, the TSC will be staffed and activated unless the TSC becomes uninhabitable due to ambient temperatures, radiological, or other conditions. If relocation of the TSC staff becomes necessary, the Station Emergency Director will relocate the staff to an alternate TSC location. The ventilation system is expected to be out of service for approximately 5 hours. This condition is being reported in accordance with 10CFR50.72(b)(3)(xiii) as an event that results in a major loss of emergency assessment capability. The NRC Resident Inspector has been notified. |
| ENS 46666 | 10 March 2011 18:29:00 | At 1549 on 03/10/2011 with the plant shut down and the reactor defueled, power was lost to Safeguards 4160 Volt Bus 6. Diesel Generator B started and re-energized Bus 6. At the time of the event, Bus 6 was energized from the Main Auxiliary Transformer (MAT) on backfeed. The event was caused by opening of substation breaker TA2066 as the result of an error by technicians working In the substation. All equipment operated as expected for the voltage restoration to Safeguards Bus 6. Safeguards Bus 5 remained energized from offsite power through the Tertiary Auxiliary Transformer during the event. Spent Fuel Pool Cooling Train A remained In operation during the event. Spent Fuel Cooling Train B was restarted following restoration of power to Bus 6. The loss of the MAT also resulted in the loss of non-safeguards 4160 V Buses 1-4. In response to the loss of power to Bus 4, the Technical Support Center (TSC) / Station Blackout (SBO) Diesel started and failed to load onto 480 Volt Bus 46. This resulted in a loss of power to the Technical Support Center. The loss of power to the TSC is being reported as a loss of Emergency Assessment Capability. At 1632, the TSC/SBO Diesel Generator tripped due to the failure of the output breaker to close and provide power to its support equipment. The cause of the failure of the TSC/SBO output breaker to close is unknown at this time. The licensee is investigating the cause of the breaker being opened and failure of the TSC/SBO diesel to load. One Spent Fuel Pool cooling train was in service throughout the event and no pool heatup occurred. The licensee notified the NRC Resident Inspector. |
| ENS 42589 | 18 May 2006 21:22:00 | At 1323 the Shift Manger was notified of a flooding concern that could impact both trains of the Residual Heat Removal (RHR) System. At this time both trains of RHR were declared inoperable and actions were taken to isolate the lines that could flood the RHR Pump Pits, The lines in question were from the Spent Fuel Pool Cleanup system specifically associated with the Spent Fuel Pool Dernineralizers and the Pre-filters and Post-filters. These lines were Isolated at 1345. Spent Fuel Pool cooling remained in service following isolation of the Spent Fuel Pool Cleanup system. Both RHR trains were returned to service at 1345. Initial piping analysis determined that these lines would have remained intact during and following a seismic event. The final evaluation s expected to be completed within two weeks. The NRC Resident Inspector was notified of this event by the licensee. |
| ENS 42152 | 17 November 2005 20:53:00 | At 1651 on 11/17/2005 both trains of Shield Building Ventilation were declared out-of-service because it was identified that Shield Building penetrations 31 and 36NW flexible boot seals were not clamped per the design drawing. Since there is no documentation to show that Shield Building Ventilation would be able to perform its function during a design basis event with no clamps installed, Shield Building Vent was declared inoperable. Clamps have been installed and the penetrations were returned to the design configuration. At 1810 CST Shield Building Ventilation was declared Operable. The licensee notified the NRC Resident Inspector.
The licensee has performed an engineering review and determined that the boot seals would have been capable of performing their design basis function without the clamps installed. Consequently, this event is no longer considered reportable and is being retracted. The NRC Resident Inspector has been notified by the licensee. R3DO (O'Brien) has also been notified. |
| ENS 41423 | 20 February 2005 00:47:00 | During continuing evaluation of the operability of the Auxiliary Feedwater (AFW) Pump discharge pressure switches, engineering determined that a high energy line break had the potential to affect the AFW Pump Suction line from the Condensate Storage Tank (CST) due to the inability of the discharge pressure switches to protect the AFW pumps from a loss of suction from the CST. At 1910 CST on 02/19/2005 it was determined that all three AFW Pumps were inoperable as a result of the condition discovered by engineering. Due to the high energy line break, there is the potential for damage to the CST supply line to the AFW Pumps (due to pipe whip resulting from a feedwater line circumferential break). Damage to the CST supply line may result in air entrainment in the AFW Pump supply and potential AFW pump damage following an automatic AFW Pump Start. Technical Specification 3.4.b.7 allows AFW Pumps to be placed in "pull-out" at less than 15% power because analysis shows that there is at least 10 minutes available for an operator to manually initiate AFW flow if needed. At 2003 CST a power reduction to <15% power was initiated to restore the operability of an AFW Pump. When power is less than 15%, the Turbine Driven AFW Pump will be placed in "pull-out" and Service Water will be aligned to the suction of the Turbine Driven AFW Pump to restore Operability of the Turbine Driven AFW Pump. When operability is restored to one AFW pump, the plant will enter a 4 hour LCO as a result of two AFW Pumps remaining out of service. Since operability of the two motor driven pumps will not be restored within the 4 hour LCO time, plant cooldown to less than 350 deg F will continue in accordance with Technical Specification 3.4.b.6. The licensee notified the NRC Resident Inspector. |