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| Entered date | Event description | |
|---|---|---|
| ENS 50896 | 15 March 2015 13:29:00 | This 4 hour notification is being made pursuant to the requirements of 10 CFR 50.72(b)(2)(i), for 'The initiation of any nuclear plant shutdown required by the plant's Technical Specifications'. Salem Unit 1 has initiated a unit shutdown at 1227 (EDT) in accordance with Technical Specification Action Statement 3.6.2.3, Action A, for inoperability of the 14 Containment Fan Cooler Unit. Technical Specification 3.6.2.3, Action A requires that with one or two Containment Fan Cooler Units inoperable, operability must be restored within 7 days, or be in at least Hot Standby (Mode 3) within the next 6 hours and in Cold Shutdown (Mode 5) within the following 30 hours. The 14 Containment Fan Cooler Unit was declared inoperable on March 8, 2015, at 1158 EDT, following a trip of its low speed breaker on thermal overload during a scheduled surveillance test. 13 Chiller is tagged for scheduled maintenance. The NRC Resident Inspector has been notified. Unit 1 is proceeding to Mode 5. There is no effect on Unit 2. The licensee will notify the Lower Alloways Creek Township, the State of New Jersey, and the State of Delaware. |
| ENS 48534 | 25 November 2012 15:13:00 | This notification is being made to report that Salem Unit 2 has experienced an automatic reactor trip at 1130 EST. The reactor trip was caused by 24BF19, 24 steam generator feedwater regulation valve, not responding to demand signal that resulted in a reactor trip due to 24 steam generator lo-lo level. The cause of the 24BF19 failure to respond to demand is under investigation. 21, 22 & 23 AFW pumps all auto started as expected on the reactor trip feeding the steam generators. 23 AFW pump has been shutdown by procedure. 21 & 22 AFW pumps are maintaining steam generator levels with decay heat removal via the main steam dump system. All control & shutdown rods fully inserted on the reactor trip. Salem Unit 2 is currently in mode 3. Reactor coolant system temperature is 547 degrees F with pressure at 2235 psig. There are no shut down technical specifications action statements in effect. All ECCS and ESF systems are available. All safety related equipment responded as expected. There were no personnel injuries associated with this event. The licensee will inform the Lower Alloways Creek Township, the State of New Jersey, and the State of Delaware. The licensee has informed the NRC Resident Inspector. |
| ENS 47928 | 17 May 2012 01:05:00 | At 2210 (EDT) it was reported to the State of New Jersey that a permitted discharge exceeded Total Residual Chlorine permit level of 0.3 ppm. Actual Total Residual Chlorine discharged was 3.0 ppm. Currently the amount of the discharge is unknown and the event is under investigation. The discharge has been terminated and no personnel injury resulted form this event. The discharge originated from a tank overflow from the Chemical Treatment Building that entered the storm drain system that discharges to the Delaware River via a permitted outfall. No safety related equipment was impacted by this event. The report to the State of New Jersey Department of Environmental Protection was made in accordance with the Salem Station Spill/Discharge Reporting Plan. The licensee estimates that the discharge occurred between 2010 and 2135 EDT on 5/16/2012 and that less than 1000 gallons overflowed the clarifier. The licensee will notify the NRC Resident Inspector and has notified the State and Lower Alloways Creek Township. |
| ENS 47595 | 14 January 2012 21:37:00 | Salem Generating Station made a 15 minute notification of a chemical discharge to the State of New Jersey Department of Environmental Protection at 1806 (EST). The Salem Non-Rad Waste Chemical Treatment Building sump overflowed out of the building to a catch basin that discharges to the Delaware River. Approximately 100 gallons of chlorinated water was reported to the State of New Jersey as being discharged, which was terminated at 1806 (EST). There were no personnel injuries associated with this event. There was no impact to any Salem Station Safety-Related systems and all Safety-Related systems are available. Investigation into the cause of the event is in progress. The licensee notified the NRC Resident Inspector and Lower Alloways Township.
On 1/14/2012 Salem Generating Station made a 15 minute notification of a chemical discharge to the State of New Jersey Department of Environmental Protection at 1806. The Salem Non-Rad Waste Chemical Treatment Building sump overflowed out of the building to a catch basin that discharges to the Delaware River through DSN 488. Subsequent investigation has indicated that the spill was entirely contained within the onsite storm drainage system and that there was no discharge to the Delaware River. The storm drain system was plugged, flushed and pumped out for appropriate disposal of the waste water. Additionally, the spill to the ground was cleaned up within 24 hours. The licensee will notify the NRC Resident Inspector and has notified the New Jersey Department of Environmental Protection. |
| ENS 46992 | 26 June 2011 22:08:00 | This notification is being made to report that Salem Unit 2 has experienced an automatic reactor trip. The trip was caused by 23 Reactor Coolant (RC) loop low flow and P-8 caused by 23 reactor coolant pump trip. The cause of the 23 Reactor Coolant Pump trip is under post reactor trip investigation. Main Feedwater to the Steam Generators was isolated due to the 'Feed Water Interlock' which is expected on a reactor trip. The Auxiliary Feed Water (AFW) system auto started on low Steam Generator levels. This is also expected on a reactor trip. 21, 22 and 23 AFW pumps all automatically started and fed the Steam Generators. 23 AFW pump has been shutdown by procedure and is available. The crew entered EOP-TRIP-1, and then transitioned to EOP-TRIP-2 and stabilized the plant at no load conditions. Salem Unit 2 is currently in Mode 3. Reactor Coolant System temperature is 547 degrees F with pressure at 2235 psig NOP/NOT. 21, 22, and 24 Reactor Coolant Pumps are in service. Decay heat removal is being provided by 21 and 22 AFW pumps via the Main Steam Dump System. All shutdown and control rods fully inserted on the reactor trip. The plant is aligned with normal electrical lineup from offsite power sources. There were no personnel injuries associated with this event. The NRC Resident Inspector has been informed. |
| ENS 45647 | 21 January 2010 21:36:00 | On January 21, 2010, at 1820 hours, Salem Unit 2 had an Automatic Reactor Trip due to low steam generator (SG) water level in the 22 SG. Prior to the reactor trip, the 21 SG feedwater pump tripped due to low oil pressure. A turbine runback was in progress and SG levels failed to recover. (Also at the time of the reactor trip), the 22 SG feedwater pump tripped on overspeed. All rods fully inserted on the trip and all systems responded as designed with decay heat being removed via the Steam Dump system, with condenser vacuum maintained. All three AFW Pumps auto started due to low Steam Generator level. Following the trip, the 22 Reactor Coolant Pump (RCP) flange vibration level spiked to approximately 9 mils and returned to a normal value of 2.6 mils. 22 RCP remained in service following the trip. The 21RS12 low pressure turbine intercept valve failed to indicate closed following the turbine trip but was locally verified closed. Salem Unit 2 is currently in mode 3. The Reactor Coolant System temperature is 547 degrees F with pressure at 2235 psig (NOT and NOP). All ECCS and ESF Systems are available and no ECCS systems actuated during the event. No personnel injuries occurred as a result of the trip. There is no primary to secondary leakage. The electrical shutdown configuration is normal. There was no impact on Unit-1. The licensee notified the NRC Resident Inspector. |
| ENS 45220 | 22 July 2009 07:58:00 | On July 22, 2009, the Safety Parameter Display System (SPDS) will be removed from service at approximately 0800 hours for Salem Unit 1 to perform planned maintenance to the system. The maintenance consists of the replacement of the uninterruptable power source (UPS) to improve the reliability of the SPDS. The removal of SPDS will also affect the transmission of Salem Unit 1 data from the emergency response data system (ERDS). Appropriate compensatory measures will be in place while SPDS is out of service. SPDS is scheduled to be out of service for approximately 29 hours. Unit 2 is unaffected by this maintenance work. The NRC Resident Inspector has been notified.
The Safety Parameter Display System and the Emergency Response Data System were returned to service at 1830 EDT on 7/22/09. The licensee has notified the NRC Resident Inspector and the States of Delaware and New Jersey Emergency Management Agencies. Notified R1DO (Rogge). |
| ENS 41365 | 2 February 2005 14:25:00 | A report was made to the New Jersey Department of Environmental Protection (NJDEP) and the National Response Center (NRC) when a light sheen of oil was observed on the Delaware River at the south end of Artificial Island. Chemistry personnel first observed the sheen during a routine oil water separator system walk-down at 1034 hours on February 2, 2005. The oil water separator system was immediately shut down. The amount of oil that produced the sheen is estimated to be approximately two ounces. Site personnel responded and deployed an absorbent oil boom. At the present time, site personnel are investigating whether the oil sheen originated from the site oil water separator system or was residual from the November 2004 Delaware River oil spill. This event is being reported in accordance with 10CFR50.72(b)(2)(xi) The licensee notified the NRC Resident Inspector. |
| ENS 40350 | 23 November 2003 06:48:00 | During performance of low power physics testing for dynamic rod worth measurements, control rod bank D was being withdrawn. At control bank D position of 209 steps, control rod 1D4 dropped into the reactor core. The control room crew entered the abnormal operating procedure for a dropped (control) rod at 0507. Based upon the dropped control rod causing the reactor to go subcritical, the abnormal operating procedure directs that all (control) rods to be inserted. Based upon the control bank D not being fully withdrawn and not in the proper bank overlap due to low power physics testing, the Control Room Supervisor directed the reactor to be (manually) tripped. The crew entered the emergency operating procedure at 0519. All equipment functioned as designed and all major equipment is available. (The crew) exited the emergency operating procedures at 0538. The plant is currently stable in mode 3 at normal operating temperature and pressure. The cause of the drop rod is reported to be a blown fuse on the stationary coil. All reactor coolant pumps are in service and decay heat removal is through the steam dumps to the condenser. All control rods fully inserted when the reactor was manually tripped. Feedwater to the steam generators is being supplied by the auxiliary feedwater system. The licensee has notified the NRC Resident Inspector and will be notifying the LAC (Lower Alloways Creek) Township. |