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| Entered date | Event description | |
|---|---|---|
| ENS 53691 | 23 October 2018 19:24:00 | At 1616 EDT on 10/23/18, Salem reported to the New Jersey Department of Environmental Protection a sheen on ground water discovered during excavation in the Salem Switchyard. This discovery did not violate any NRC regulations or reporting criteria. This notification is being made solely as a four-hour, non-emergency notification for a Notification of Other Government Agency. This event is reportable in accordance with 10 CFR 50.72(b)(2)(xi). There was no impact on the health and safety of the public or plant personnel. The licensee notified the NRC Resident Inspector and will notify Lower Alloway Creek Township. |
| ENS 52129 | 28 July 2016 09:25:00 | This four and eight hour notification is being made to report that at 0541 (EDT) on 7/28/16, Salem Unit 1 initiated a shutdown to comply with Technical Specifications due to the inoperability of both source range nuclear instruments. During a reactor startup, with Unit 1 in Mode 2, both source range instruments were reading approximately one decade lower than expected compared to intermediate range and Gamma-Metric instruments and due to the proximity to the estimated critical condition. The condition could also have prevented the fulfilment of the source range instruments safety function to trip the reactor when required. Salem Unit 1 is currently stable in Mode 3. Reactor Coolant system pressure is 2235 psig and reactor coolant system temperature is 547 F with decay heat removal via the main steam dump and auxiliary feedwater systems. Unit 1 has one active shutdown tech spec action statement in effect due to the inoperability of the containment radiation monitor 1R11A. The inoperability of this radiation monitor had no effect on the event. All control rods were manually inserted to place Unit 1 in Hot Standby (Mode 3). No ECCS (emergency core cooling system) or ESF (emergency safety features) systems were required to function during this event. No major secondary equipment was tagged for maintenance prior to this event. No personnel were injured during this event. The reactor was manually shut down and a shutdown margin calculation verified sufficient margin. The licensee notified the NRC Resident Inspector and the local township.
The purpose of this notification is to retract event report number 52129 made on 7/28/2016 at 0925 (EDT). Previously PSEG reported that Salem Unit 1 initiated a shutdown to comply with Technical Specifications (TS) due to the inoperability of both source range nuclear instruments. Additionally PSEG reported that the condition could have prevented the fulfillment of the safety function needed to, 'Shut down the reactor and maintain it in a safe shutdown condition.' Subsequent review identified that the condition did not meet either reporting criteria. Maintenance and Engineering evaluation of the source range nuclear instruments determined that the instruments were fully operable at the time of the event. TS 3.3.1.1, Reactor Trip Instrumentation remained met, no TS shutdown was required and the instruments were capable of performing their required function. Therefore PSEG is retracting the notifications made under 10 CFR 50.72(b)(2)(i) and 10 CFR 50.72(b)(3)(v)(A). The NRC Resident Inspector was notified of this retraction by the licensee. Notified the R1DO (Cook). |
| ENS 51708 | 4 February 2016 13:33:00 | This 4 and 8 hour notification is being made to report that Salem Unit 2 suffered an unplanned automatic reactor trip and subsequent automatic Auxiliary Feedwater system actuation. The trip was initiated due to a Main Turbine trip above P-9 (49% power). The Main Turbine trip was caused by a Main Generator Protection signal. Salem Unit 2 is currently stable in Mode 3. Reactor Coolant system pressure is 2235 PSIG and Reactor Coolant system temperature is 547 F with decay heat removal via the Main Steam Dump and Auxiliary Feedwater Systems. Unit 2 has no active shutdown tech spec action statements in effect. All control rods inserted on the reactor trip. All ECCS and ESF systems functioned as expected. No major secondary equipment was tagged for maintenance prior to this event. The 24 Service Water pump is tagged for scheduled preventive maintenance and did not affect post trip plant response. No personnel were injured during this event. The licensee has notified the NRC Resident Inspector and will notify the Lower Alloway Creek Township. |
| ENS 50092 | 7 May 2014 07:45:00 | This 4 and 8 hour notification is being made to report that Salem Unit 1 experienced an unplanned automatic reactor trip and subsequent Auxiliary Feedwater System actuation. The automatic trip was initiated from a generator protection relay. A troubleshooting team is being assembled to determine the exact cause for the generator protection actuation. 11, 12 and 13 Aux Feedwater Pumps automatically started as expected on low Steam Generator water level following the reactor trip. All control rods inserted on the reactor trip. All ECCS and ESF systems functioned as expected. Salem Unit 1 is currently in Mode 3. Reactor Coolant system pressure is at 2235 PSIG and temperature is 547 F with decay heat removal via the Main Steam Dumps and Auxiliary Feedwater Systems. Condenser vacuum was available for the duration of the event. The 12 Chiller was tagged for maintenance prior to this event and had no adverse impact on the post trip plant response or stabilization. No personnel were injured during this event. The licensee notified the NRC Resident Inspector |
| ENS 50039 | 16 April 2014 10:48:00 | At 0908 EDT on April 16th, 2014, approximately one pint of hydraulic fluid was spilled into the Delaware River in front of the Unit One Circulating Water System (CWS) Intake trash racks at the Salem Generating Station. The spill of hydraulic fluid was caused by a leak from the crane used to rake debris from the Unit One trash racks. The crane was stopped and the leak terminated at the time of discovery. The oil was cleaned up by onsite personnel at 0930 EDT. Nuclear Environmental Affairs Department determined a 4 hr report to the NRC under RAL 11.8.2.a. was warranted due to the 15 minute notification to the New Jersey Department of Environmental Protection at 0922 EDT. Additionally, a report of the spill was made to the National Response Center at 1034 EDT. The licensee informed the NRC Resident Inspector. |
| ENS 49780 | 31 January 2014 11:44:00 | This 4-hour notification is being made to report that Salem Unit 2 has performed an unplanned manual reactor trip. The trip was initiated due to reactor coolant temperature approaching the minimum temperature for criticality, 543 degree F, due to boration to achieve shutdown margin requirements following identification of a misaligned control rod. All control rods inserted on the reactor trip. All ECCS (Emergency Core Cooling System) and ESF (Engineered Safety Features) systems functioned as expected with no equipment actuated. The 21 safety injection pump was out of service for scheduled maintenance during the event as was the 2R41 plant vent radiation monitor. Salem Unit 2 is currently in Mode 3. Reactor coolant system pressure is at 2235 psig and temperature is 547 degrees F with decay heat removal via the main steam dump and auxiliary feedwater systems. Unit 2 has no active shutdown technical specification action statements in effect. There was no major secondary equipment tagged for maintenance prior to the event. Prior to the event, the licensee was conducting their monthly control rod surveillance. No primary or secondary relief valves lifted during the transient. The electrical grid is stable and the plant is in its normal shutdown electrical lineup. There was no effect on Unit 1. The licensee notified the NRC Resident Inspector, the State of New Jersey, the State of Delaware and the Lower Alloways Creek Township. |
| ENS 46075 | 7 July 2010 13:22:00 | Salem Unit 1 experienced an automatic reactor trip at 1117 hours due to a trip of the main generator and turbine. The main generator tripped as a result of a fault on the B Main Power Transformer (MPT). The B MPT fire protection deluge system automatically actuated and extinguished a small fire that occurred on the B MPT. The fire existed for approximately 5 minutes prior to being extinguished. All control 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 (Auxiliary Feed Water) Pumps auto started as expected due to low Steam Generator level. Following the trip, the Reactor Coolant Pump (RCP) thermal barrier supply valve 1CC131 automatically closed and was subsequently reopened with no issue. Salem Unit 1 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 (Emergency Core Cooling System) systems actuated during the event. The 13 AFW pump has not yet been reset following the trip, per the Emergency Operating Procedures and is unavailable. No personnel injuries occurred as a result of the trip. There is no primary to secondary leakage. There was no impact on Unit 2. The licensee has notified the NRC Resident Inspector.
Based on additional reviews, the reactor trip occurred at 1118 hours following actuation of the B Main Power Transformer (MPT) fire protection deluge system at 1116 hours. Personnel in the area stated that an arc flash occurred on the high voltage bushing of the B MPT following the deluge system actuation and there was no fire present when the deluge system actuated. Notified the R1DO (Dimitriadis). |
| ENS 45847 | 16 April 2010 17:07:00 | At 1649 (EDT), on April 16, 2010, Salem Unit 2 notified the New Jersey Department of Environmental Protection (NJDEP) via the NJDEP hotline of the discovery of fuel oil from a sample well. At 1645 (EDT), a sample was pulled from a monitoring well on the north east side of the Unit 2 Auxiliary Building which contained approximately 1 pint of diesel fuel oil. This notification to the State of New Jersey is reportable in accordance with 10 CFR 50.72(b)(2)(xi). The source of the diesel fuel oil is under investigation by the licensee. The licensee notified the NRC Resident Inspector and will notify the State of Delaware. |
| ENS 43873 | 28 December 2007 19:58:00 | This 4 hour notification is being made in accordance with 10 CFR 50.72(b)(2)(iv)(B) to report that Salem Unit 1 has experienced an automatic reactor trip. The trip was initiated by failure of 12 Station Power Transformer (SPT). The cause of the trip was the loss of two Reactor Coolant Pumps (RCP) (13 and 14). These RCPs were powered from 'F' and 'G' group busses (non safeguards), which were powered by 12 SPT. Post trip the following occurred: 11, 12 & 13 Auxiliary Feed Water (AFW) Pumps (automatically) started after the trip due to valid steam generator low levels (14%) as expected. The automatic start of the Auxiliary Feedwater System due to a valid steam generator low level is an ESF actuation and is an 8 hour report in accordance with 10 CFR 50.72 (b)(3)(iv)(B). 13 AFW pump was tripped (in accordance with) the Emergency Operating Procedure and will be returned to an operable condition following recovery of steam generator levels. All control rods fully inserted following the trip. No ECCS actuation occurred. There was no major equipment out of service prior to the event. No injuries resulted from this event. Salem Unit 1 is currently in Mode 3. Reactor Coolant System pressure is at 2235 PSIG and temperature is at 547 degrees with decay heat removal via the Main Steam Dump System. Unit 1 has no active shutdown (Technical Specification) action statements in effect. The NRC Resident Inspector has been notified. |
| ENS 42343 | 16 February 2006 06:38:00 | This is an 8-hour notification being made to report exceeding the design basis for reactor coolant leakage outside of containment. The normal daily RCS leakrate was completed at 2345 on 2/15/06. This leakrate indicated a step change in unidentified leakrate to .8 gpm from .09 gpm. This leakage value is within the 1 gpm allowed by Technical Specifications. Investigation is on going, and the source of the leak has not been determined at this time, however preliminary conclusion is that the leakage is outside of containment and related to the centrifugal charging pumps. The design requirement ECCS leakage outside of containment is 3840 cc/hour ( .1 gpm) to support GDC-19 limits for control room habilitability. No safety system actuation occurred or were required. No injuries have occurred due to this event. The licensee has performed troubleshooting to identify the source of the leak and to narrow down the portion of the charging system where they believe the leak to be located. The licensee believes the leak is in a relief valve or hard pipe system to the waste tanks, and that the leak is not external to the system. The licensee notified the NRC Resident Inspector.
On February 16, 2006, PSEG made an 8-hour report (event number 42343) in accordance with 10CFR50.72(b)(3)(v) because of exceeding the design basis limits for ECCS leakage outside containment. The leakage was determined to be approximately 0.8 gpm with a limit of 3840 cc/hour. Further investigation into this event determined that the leakage was not in the ECCS recirculation flow path. The cause of the elevated RCS unidentified leakrate was the failure of the automatic three-way high level divert valve (2CV35), which prevents a high level from occurring in the Volume Control Tank (VCT). This valve failed to fully isolate flow to the Chemical Volume Control (CVC) Hold-Up Tanks (HUTs) after VCT level dropped below the divert setpoint of 77% . This conclusion is based on the VCT level being at the divert setpoint a number of times during the shift, the increased use of the valve to control level, and valve performance to fully isolate flow to the CVC HUT'S. Because this flow path is automatically isolated on a Safety Injection signal by other means (valves), the leakage through this valve is not considered part of the ECCS recirculation flow path and therefore is not included in the calculation for ECCS leakage outside containment. The event is being withdrawn. The licensee will notify the NRC Resident Inspector. R1DO(Finney) notified. |
| ENS 41942 | 24 August 2005 15:47:00 | This is a 4-hour notification to report a notification made to the New Jersey Department of Environmental Protection (NJDEP) for a chemical spill to the ground that could not be cleaned up within 24 hours. The spill was discovered at 1545 on 8/23/05, when water containing approximately 30 ppm hydrazine was discovered north of the condensate polisher building. The source of the spill was secured. Efforts to clean-up the affected soil commenced in parallel but could not be completed within 24-hours therefore necessitating notification of NJDEP per NJAC 7: 1E. The full volume of the discharge is unknown, however approximately 500 gallons of water have been removed. The operations shift manager made a report to the state of New Jersey to report the discharge at 1530 (on 08/24/05) when it was realized that the clean up could not be fully completed in less then 24 hours. There was no effect on plant operation. There was no one injured during the event. The licensee notified the NRC Resident Inspector. |
| ENS 41679 | 7 May 2005 14:03:00 | An undetermined quantity of water containing 40 (parts per billion) hydrazine was discharged into the Delaware River through a state permitted outfall. The discharge was stopped at 1130 on 5/7/05 and confirmed by chemistry sample at 1150. Clean-up efforts are in progress. This event had no impact on plant safety or operation. No one was injured as a result of this event. No safety systems actuated or were required to activate as a result of this event. All systems operated as required. The cause is under investigation by the licensee. The licensee notified Lower Alloway Creek Township and the state of New Jersey. The licensee will notify the NRC Resident Inspector. |
| ENS 41245 | 5 December 2004 15:54:00 | This is an 8-hour notification being made to report exceeding the design basis for the reactor coolant leakage outside of containment. The event is being reported under paragraph (b)(3)(v) of 10CFR50.72. On 12/05/04 at 1015 the control room was notified of leakage from a gasketed flange area on the 11 Residual Heat Removal Heat Exchanger. The leak rate has been conservatively quantified at 0.68 gpm, which is greater than the UFSAR limit of 2100 cc/hr (0.009 gpm) for ECCS leakage outside containment. With leakage greater than the UFSAR allowed limits, GDC-19 limits for control room habitability cannot be assured. Actions are in progress to torque the flange bolts to reduce the leakage. The licensee has notified the NRC Resident inspector of this event. Salem Unit One is in Mode 4 with the Residual Heat Removal system in service removing reactor decay heat. No ECCS system actuations occurred. No one was injured as a result of the leak. |