|Entered date||Site||Region||Reactor type||Event description|
|ENS 54740||6 June 2020 12:25:00||Seabrook||NRC Region 1|
At 0920 (EDT), with the unit in Mode 1 and 100 percent power, the reactor was manually tripped due to group 1 of control rod bank 'B' fully inserting into the core. All systems responded normally post trip. Operations has stabilized the plant in mode 3 at NOP/NOT (normal operating pressure and temperature). Decay heat removal is being accomplished via the steam dumps in the steam pressure mode to the main condenser.
Emergency feedwater actuated due to low low steam generator level as expected.
This event is being reported pursuant to 10CFR50.72(b)(2)(iv)(B) and 10CFR50.72(b)(3)(iv)(A)
The senior NRC Resident Inspector has been notified. The plant response to the trip was uncomplicated. All safe shutdown equipment is available. There were no reliefs or safeties actuated during the transient. The licensee manually tripped eight days ago for the same condition. See EN #54731.
|ENS 54731||29 May 2020 16:41:00||Seabrook||NRC Region 1||At 1403 EDT, with the unit in Mode 1 and 100 percent power, the reactor was manually tripped due to Group 1 of Control Rod Bank 'B' unexpectedly inserting. All systems responded normally post-trip. Operations stabilized the plant in Mode 3 at 557 degrees Fahrenheit. Decay heat removal is being accomplished via the steam dumps in the steam pressure mode to the main condenser. Emergency feedwater actuated due to low low steam generator level as expected. This event is being reported pursuant to 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR (b)(3)(iv)(A). The NRC Senior Resident Inspector has been notified.|
|ENS 54569||5 March 2020 21:14:00||Seabrook||NRC Region 1|
On March 05, 2020, at 2100 EST, the site commenced a planned upgrade of the main plant computer system (MPCS). During this upgrade, the normal computer data will not be available to the emergency response facilities, but compensatory capabilities will be in place. The scheduled duration for the MPCS upgrade is 96 hours. Since the compensatory measures will be in place in excess of 72 hours, this condition is being reported pursuant to 10 CFR 50.72(b)(3)(xiii).
The NRC Resident Inspector has been notified.
|ENS 53897||25 February 2019 11:59:00||Seabrook||NRC Region 1||A non-licensed, licensee supervisory employee failed a for-cause FFD test for alcohol. The individual's authorization for site access has been denied. The NRC Resident Inspector has been notified.|
|ENS 53854||31 January 2019 17:06:00||Seabrook||NRC Region 1||On 1/31/2019, the Medical Review Officer for Seabrook was notified of an error made by the HHS (Health and Human Services) certified lab resulting in a false negative Fitness for Duty quality assurance test result. The test lab, Quest Diagnostics-Norristown, was provided an adulterated sample specimen that was part of a blind performance test, which tested negative. This false negative test result will be investigated and the results reported as required. This event is being reported in accordance with 10 CFR 26.719(c)(3). NRC Resident Inspector has been notified.|
|ENS 53760||29 November 2018 12:56:00||Seabrook||NRC Region 1||This 60-day telephone notification is being made under reporting requirements specified by 10 CFR 50.73(a)(2)(iv)(A) to describe an invalid actuation of the Reactor Protection System (RPS). At 0147 (EST) on October 1, 2018, Seabrook Unit 1 was in Mode 3 shutdown, when an invalid Reactor Protection System actuation occurred due to a high Source Range detector. All equipment responded in accordance with the plant design. Specifically, all actuations were complete and successful. There were no safety consequences or impacts on the health and safety of the public. The event was entered into Seabrook's corrective action program for resolution. The NRC Resident Inspector has been notified. The Source Range detector which gave the invalid input has been replaced.|
|ENS 52718||29 April 2017 21:19:00||Seabrook||NRC Region 1||Westinghouse PWR 4-Loop||At 1844 (EDT) on 04/29/2017, while the unit was in a low power condition exiting from a refueling outage, the reactor was manually tripped following a P-14 signal (Steam Generator Hi-Hi Level) and a resulting feedwater isolation signal. All control rods were verified to be fully inserted. The cause of the ('B') steam generator high level is currently being investigated. Emergency feedwater actuated at 1845 due to a low-low water level in steam generator 'D'. Plant equipment response is being evaluated and the plant is stabilized in Mode 3 with decay heat removal through the steam dump system to the condensers. There was no release and the emergency feedwater system has been restored to standby. The event description is based on information currently available. If through subsequent reviews of this event, additional information is identified that is pertinent to this event or alters the information being provided at this time, a follow up notification will be made via the ENS or under the reporting requirements of 10 CFR 50.73. The licensee notified the NRC Resident Inspector.|
|ENS 52288||7 October 2016 18:28:00||Seabrook||NRC Region 1||Westinghouse PWR 4-Loop||This report is being made pursuant to 10 CFR 26.719(b). At 1620 EDT today, a prohibited substance (marijuana) was identified inside the protected area. The substance was obviously very old, so is surmised to be from a preoperational period. The item (a small remainder, or butt, of a marijuana joint) is currently under the control of the site security department and will be turned over to local law enforcement for disposal. The licensee notified the NRC Resident Inspector.|
|ENS 51932||16 May 2016 02:02:00||Seabrook||NRC Region 1||Westinghouse PWR 4-Loop|
At 0300 EDT on May 16, 2016, Seabrook Station's seismic monitoring instrumentation will be removed from service for a planned upgrade to the Seismic Monitoring Control Panel and its accelerometers. Modifications are expected to be complete on May 27, 2016. Proceduralized compensatory measures are in place and have been communicated to applicable emergency response decision makers. This preplanned action is being reported in accordance with 10 CFR 50.72(b)(xiii). The NRC Resident Inspector has been notified.
At 2045 EDT on 5/26/16, the seismic monitoring system was returned to service. The licensee notified the NRC Resident Inspector. Notified R1DO (Lilliendahl).
|ENS 51765||2 March 2016 18:13:00||Seabrook||NRC Region 1||Westinghouse PWR 4-Loop||On 3/2/2016, (at) 1312 hours EST, while in the process of a plant cooldown, a valid actuation of the emergency feedwater system (EFW) occurred when B steam generator levels were reduced to 20 (percent). The lowering level was a result of the unanticipated tripping of the start up feed pump on low condensate storage level while it was the feed source to the steam generators. The start up feed pump was restarted and feed flow had been restored when the actuation took place. The EFW flow was secured per procedure and the start up feed pump remains the feed source to the steam generators. This is reportable under 50.72(b)(3)(iv)(A). The licensee notified the NRC Resident Inspector.|
|ENS 51762||2 March 2016 04:27:00||Seabrook||NRC Region 1||Westinghouse PWR 4-Loop|
The turbine tripped for an unknown cause followed by a reactor trip. All systems are functioning as designed. Operators have transitioned out of the EOP (Emergency Operating Procedure) network into normal operating procedures. The plant is stable in mode 3. All control rods fully inserted during the trip and no safety or relief valves lifted. The plant is in its normal shutdown electrical lineup. Emergency Feedwater actuation occurred to restore steam generator levels. The plant expects to make a press release. The licensee notified the NRC Resident Inspector.
The licensee will not issue a press release for this event. The licensee will inform the NRC Resident Inspector. Notified R1DO (Cook).
|ENS 50817||13 February 2015 08:31:00||Seabrook||NRC Region 1||Westinghouse PWR 4-Loop||This event is being reported pursuant to the requirements of 10 CFR 26.719 because a non-licensed licensee supervisor violated the fitness for duty policy. The individual's access has been terminated. The Licensee has notified the NRC Resident Inspectors.|
|ENS 50513||7 October 2014 15:40:00||Seabrook||NRC Region 1||Westinghouse PWR 4-Loop||At approximately 1230 EDT on October 7, 2014, Seabrook Station was notified by Rockingham County Dispatch that an inadvertent activation of the Public Alert Notification System (PANS) sirens in Newtown, NH occurred at 1220 EDT. The activation was caused by an apparent human error during procedure review by a town of Newton employee. The sirens sounded, reset, and are functional. This event is being reported as it may generate media interest. No press release is planned at this time. The NRC Senior Resident Inspector and Region I have been notified.|
|ENS 49979||1 April 2014 02:44:00||Seabrook||NRC Region 1||Westinghouse PWR 4-Loop||At 0026 on 04/01/2014, following the turbine shutdown and removal of the main generator from service in preparation for refueling outage 16, Seabrook had a reactor trip and all control rods were fully inserted. The trip was caused by an electrical issue that caused 345 KV bus 6 to deenergize and power was lost to the Unit Auxiliary Transformers (UATs). The in-house busses transferred to the Reserve Auxiliary Transformer (RAT) supplies and the momentary loss of power to in-house Bus 1 caused 2 reactor coolant pumps to trip, generating a 2 loop loss of flow reactor trip signal. The exact cause of the initiating electrical issue is being investigated. The NRC Resident Inspector has been notified. Emergency feedwater actuated at 0035 due to a low low water level in steam generator 'C'. Plant equipment response is being evaluated and the plant is stabilized in Mode 3 with decay heat removal through the steam dump system to the condensers. There was no release and the emergency feedwater system is being restored to standby. The event description is based on information currently available. If through subsequent reviews of this event, additional information is identified that is pertinent to this event or alters the information being provided at this time, a follow-up notification will be made via the ENS or under the reporting requirements of 10CFR50.73.|
|ENS 48413||16 October 2012 19:56:00||Seabrook||NRC Region 1||Westinghouse PWR 4-Loop|
An Unusual Event was declared at 1920 EDT, HU1 - Earthquake felt in the plant (Control Room), and confirmed by calling the Manchester Dispatch Office. Post event walkdowns indicate no reports of damage at the station. Walkdowns of station structures and systems continue. Plant is stable in Mode 5 planned refueling outage. No adverse impacts to shutdown cooling. The station seismic monitor is currently out of service for a scheduled calibration. The licensee is exiting a refueling outage. The earthquake was felt by the site at 1914 EDT. The United States Geological Survey website indicates that an earthquake of magnitude 4.0 centered 3 miles west of Hollis Center, Maine occurred at this time. The licensee is currently in a Train 'B' system outage. All Train 'A' systems are functioning as required. The licensee has notified the NRC Resident Inspector and State authorities. No media or press release is anticipated at this time. The Headquarters Operations Officer has notified other FEDS (FEMA, DHS, DHS NICC and Nuclear SSA via email).
* * * UPDATE FROM SEAN RILEY TO PETE SNYDER AT 0212 ON 10/17/12 * * *
The Unusual Event was terminated at 0149 EDT. Initiating condition was HU-1 due to the earthquake felt at the plant and confirmed by calling Manchester Dispatch Office. Information obtained by seismic monitoring system confirmed no additional escalation warranted. Site walkdown of key systems revealed no damage from the earthquake. All systems required for the current mode of operation were not adversely affected and remain in operation. The licensee will notify the NRC Resident Inspector. Notified R1DO (Welling), NRR (Bahadur), IRD (Grant) and other FEDS (FEMA, DHS, DHS NICC and Nuclear SSA via email).
|ENS 48363||1 October 2012 12:06:00||Seabrook||NRC Region 1||Westinghouse PWR 4-Loop|
Seabrook personnel determined that the Emergency Response Data System (ERDS) is unavailable due to a malfunction of its process computer. The condition occurred around 0430 EDT today after a plant electrical bus was de-energized and subsequently reenergized during a maintenance activity. The plant is presently in a refueling outage with the reactor vessel defueled. Following repair of the process computer, Seabrook expects to return ERDS to service later today. This event is being reported in accordance with 10 CFR50.72(b)(3)(xiii), loss of emergency preparedness capabilities, for loss of the ERDS function. The NRC Resident Inspector has been notified of this event.
The ERDS system has been returned to service. The licensee will be notifying the NRC Resident Inspector. Notified R1DO (Schmidt).
|ENS 48310||14 September 2012 22:05:00||Seabrook||NRC Region 1||Westinghouse PWR 4-Loop||(At) 2025 (EDT) reactor tripped on 'C' Steam Generator Low Low Level due to feed water regulating valve failing closed due to a 7300 process cabinet card failure. Control Room entered E-0, Reactor Trip or Safety Injection, then transitioned to ES-0.1, Reactor Trip Response. Emergency Feedwater actuated due to the Low Low Steam Generator Level. All other plant equipment functioned as expected. Plant is being stabilized in mode 3. Emergency News Manager will update the states and local media. NRC Resident Inspector was notified at 2045 (EDT). The trip was uncomplicated and all rods fully inserted. Decay heat is being removed to the condenser via the turbine bypass valves. Electrical buses are powered by offsite power.|
|ENS 48021||13 June 2012 14:22:00||Seabrook||NRC Region 1||Westinghouse PWR 4-Loop|
Seabrook declared an Unusual Event (HU3 - hazard or other conditions affecting plant safety) due to a spill of one gallon of ammonium hydroxide in the stockroom area of the Administration Building. No reports of injured individuals (were received) at this time. No plant or equipment damage occurred. The lower level of the Administration Building is evacuated. Personnel in SCBAs (Self Contained Breathing Apparatus) are mitigating the spill. The Administration Building is in the Protected Area adjacent to the Turbine Building. The licensee notified the NRC Resident Inspector and the State. Notified DHS, FEMA, NICC, DOE, USDA, and HHS.
At 1343 (EDT) on 6/13/12 an Unusual Event was declared due to a reported Ammonium Hydroxide spill in a storeroom on the first floor of the Administration Building. At 1357 (EDT) the State of NH was notified and at 1401 the State of Massachusetts was notified of the Unusual Event using the State Notification Fact Sheet. The delay to the State of Massachusetts notification was due to issues with the dedicated phone system. At 1422 the NRC was notified of the Unusual Event using the Event Notification Worksheet. This initial notification reported a one gallon spill of Ammonium Hydroxide. Additionally there were no reported injuries and no impact to plant equipment. Further investigation revealed that the spill amount is 1-2 pints out of a 1 gallon container and the initial report of no injuries was validated. The concentration of the Ammonium Hydroxide is 25.5%. The spill was confined to a small area of the store room on the first floor of the Administration Building. The spill had no impact on plant equipment used for normal operation. Initial cleanup by plant personnel is complete and external services have been notified to complete the final spill cleanup. Seabrook Station is terminating the Unusual Event. Seabrook Station will continue to investigate and resolve the issues with the dedicated state notification phone system. Currently we have a troubleshooting team which has verified backup communications via the commercial phone lines is available. The Unusual Event was terminated at 1730 EDT. The licensee notified the NRC Resident Inspector and State. Notified R1DO (Gray), NRR ((Howe), IRD (Grant), DHS, FEMA, NICC, DOE, USDA, and HHS.
|ENS 47917||11 May 2012 09:20:00||Seabrook||NRC Region 1||Westinghouse PWR 4-Loop||At approximately 0515 EDT today, Seabrook experienced a brief loss of the Emergency Notification System (ENS). The ENS was inoperable for approximately four minutes due to an unknown cause. During this time, commercial telephone lines were available as a means of communication with the NRC. A subsequent communications check using the ENS phone was satisfactory. This event is being reported as an eight-hour notification in accordance with 10CFR50.72(b)(3)(xiii) for a loss of offsite ENS communications capability. Investigation into the cause continues and will be documented via the corrective action process. The licensee has notified the NRC Resident Inspector.|
|ENS 47395||1 November 2011 09:38:00||Seabrook||NRC Region 1||Westinghouse PWR 4-Loop||On October 31, 2011, NextEra Energy Seabrook, LLC completed a 10 CFR 21 evaluation of a condition associated with General Electric (GE)-CR-120B relays supplied by National Technical Systems, Inc. and intended for use at Seabrook. Six (6) Quality Level 1 GE-CR-120B relays failed bench testing. During bench testing, the subject relays failed to reset when de-energized. An evaluation was performed to determine the applications where these relays could have been and were installed and to determine if the failure of the subject relays could result in a Substantial Safety Hazard as defined in 10 CFR 21.3. The evaluation concluded that there is one safety significant application relative to the failure of the GE-CR-120B relays to reset in the Seabrook Diesel Air Handling System (DAH). Each DAH system train (includes one supply fan and one exhaust fan per train) has one relay that provides a start permissive for the ventilation fans. An analysis of the failure of a GE-CR-120B relay in the DAH system determined that, if the relays were installed, the condition could create a substantial safety hazard due to a subsequent loss of the emergency power function. Therefore, this report is being submitted pursuant to the requirements of 10 CFR 21.21(d)(3)(i). A written notification will be made to the NRC within 30 days pursuant to 10 CFR 21.21(d)(3)(ii). No actual safety consequences resulted from this condition because the GE-CR-120B relays were not installed in the plant in this safety significant application. The licensee notified the NRC Resident Inspector.|