Semantic search
| Entered date | Event description | |
|---|---|---|
| ENS 57146 | 26 May 2024 13:52:00 | The following information was provided by the licensee by phone and email: At 0210 CDT 5/24/24, essential chiller A train and cascading equipment was declared inoperable for maintenance to correct a temperature control malfunction. At 0720 CDT 5/26/24, essential cooling water B train and cascading equipment (including B train essential chiller) was declared inoperable due to a through wall leak discovered on the essential cooling water return header temperature element thermal well. This condition resulted in an inoperable condition on two out of three safety trains for the accident mitigating function, including the train A and train B high head safety injection, low head safety injection, containment spray, electrical auxiliary building heating ventilation and air conditioning (HVAC), and essential chilled water. All C train safety related equipment remains operable. This was determined to be reportable within 8 hours as required by 10CFR50.72(b)(3)(v)(D). NRC Resident Inspector has been notified. |
| ENS 57145 | 25 May 2024 15:26:00 | The following information was provided by the licensee by phone and email: A 50 ml bottle of vodka was found in the Unit 3 debris basket on the exterior of the intake structure. The bottle likely came from the ultimate heat sink (Niantic Bay) during normal backwash operations by the system that collects debris. Security has discarded the contraband. The NRC Resident Inspector has been notified. The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers report guidance: The bottle was found unsealed. |
| ENS 57144 | 24 May 2024 16:39:00 | The following information was provided by Arizona Department of Health Services (the Department) via email: On May 23, 2024, the Department received notification from the licensee about a medical event involving Y-90 TheraSpheres that occurred on May 22, 2024. A patient was prescribed a dose of 1.304 GBq but was delivered 0.931 GBq, a percent dose delivered of 71.4 percent. The Department has requested additional information and continues to investigate the event. Additional information will be provided as it is received in accordance with SA-300. Arizona incident number: 24-007 A Medical Event may indicate potential problems in a medical facilitys use of radioactive materials. It does not necessarily result in harm to the patient. |
| ENS 57120 | 9 May 2024 21:10:00 | The following information was provided by the licensee via phone and email: At 1629 EDT on 05/09/2024, the high pressure coolant injection (HPCI) system was declared inoperable due to a pinhole through-wall leak identified on the seal drain line for 23HOV-1 (HPCI trip throttle valve) downstream of the restricting orifice 23RO-137A. The location of the defect is in the class 2 safety related piping. HPCI is a single train safety system and this notification is being made in accordance with 10 CFR 50.72(b)(3)(v)(D). The NRC Senior Resident Inspector has been notified. The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance: This pinhole leak was discovered during normal operator rounds. Although HPCI is inoperable and in a 14 day limited condition of operation, the system function remains available. In addition, all other ECCS systems are currently operable. Compensatory measures (walkdowns) have been implemented to ensure the leak rate does not significantly increase. |
| ENS 57118 | 9 May 2024 17:21:00 | The following synopsis was received via phone and email from the New Mexico Radiation Control Bureau: At 1230 MDT on 05/09/2024, a Delta 880 industrial radiography camera containing an activity of 74 curies of iridium (Ir-192) has been determined to be lost on a closed non-public road on an oil field lease. The camera serial number is D15729. The sealed source serial number is 93189M. Local law enforcement has been informed, details to follow. NM Event number: ENTS 18002 Notified the following external agencies: DHS Senior Watch Officer, FEMA Operations Center, USDA Operations Center, HHS Operations Center, DOE Operations Center, CISA Central, EPA Emergency Operations Center, FDA Emergency Operations Center, Nuclear SSA (email), FEMA National Watch Center (email), CWMD Watch Desk (email)
The following is a summary of information received from the New Mexico Radiation Control Bureau via phone and email: The Delta 880 camera has been found by a member of the public and is in process of being transferred to a representative of the Department of Energy (DOE) Radiological Assistance Program for inspection and transfer to a DOE facility. The device has an automatic locking mechanism and there is no indication of public exposure at this time. Notified R4DO (Josey), NMSS Regional Coordinator (Williams), IRMOC (Grant), ILTAB (MacDonald), INES National Officer (email), NMSS Events Notification (email), NMSS INES Coordinator (email). Notified the following external agencies: DHS Senior Watch Officer, FEMA Operations Center, USDA Operations Center, HHS Operations Center, DOE Operations Center, CISA Central, EPA Emergency Operations Center, FDA Emergency Operations Center (email), Nuclear SSA (email), FEMA National Watch Center (email), CWMD Watch Desk (email), CNSNS-Mexico (email). THIS MATERIAL EVENT CONTAINS A Category 2 LEVEL OF RADIOACTIVE MATERIAL Category 2 sources, if not safely managed or securely protected, could cause permanent injury to a person who handled them, or were otherwise in contact with them, for a short time (minutes to hours). It could possibly be fatal to be close to this amount of unshielded radioactive material for a period of hours to days. These sources are typically used in practices such as industrial gamma radiography, high dose rate brachytherapy and medium dose rate brachytherapy. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf |
| ENS 57143 | 24 May 2024 15:47:00 | The following information was provided by Paragon Energy Solutions, LLC via email: Paragon has identified a defect in one voltage regulator supplied to AEP DC Cook with serial number NLI-3S7950GR751A1-1007. Pursuant to 10CFR Part 21 � 21.21(d)(3)(i), Paragon is providing initial notification of a defect associated with the emergency diesel generator (EDG) voltage regulator. The voltage regulator was refurbished under the client purchase order 01600229, project number 351030025. Part of the refurbishment involved complete replacement of the units wiring, physical inspection and testing of the unit to Paragon approved acceptance testing instructions. The refurbished unit was supplied to the customer in December 2023. Prior to installation (March 2024), the unit successfully passed bench testing at the plant. During post installation testing, the EDG was started, and the output voltage pegged high and was not controllable. DC Cook subsequently removed the voltage regulator and documented the non-conformance. DC Cook troubleshooting determined the unit was mis-wired. The unit (voltage regulator) was returned to Paragon, and inspection confirmed the plants diagnosis. The identified mis-wire affects the system circuitry by placing silicon controlled rectifier 5CD in a reverse biased position. The reversed biased rectifier blocks the flow of current which creates an open circuit condition. This open circuit condition causes the output voltage to max out, and does not allow the output voltage to be adjusted. This condition, if left uncorrected, could contribute to a substantial safety hazard and is reportable in accordance with 10CFR Part 21. Date of Discovery: May 9, 2024 Reportability Determined: May 23, 2024 Paragon has entered this condition in our corrective action program, and we have custody of the effected unit. The extent of condition is limited to this unit supplied to DC Cook. Paragon has determined there is no action necessary for DC Cook at this time. Affected plant: DC Cook |
| ENS 57116 | 9 May 2024 12:57:00 | The following information was provided by the licensee via phone and email: In accordance with 10 CFR 70, Appendix A(c) concurrent reporting, this notification is being made because a plant condition required reporting to the Washington State Department of Health (WDOH). At approximately 1015 PDT on 5/7/2024, three items were found in a storage area. Those items were: 1. A metal table that had been used in contaminated areas. 2. A cart that had been used in contaminated areas to transport material, with an additional weight standard stored on it. 3. An out-of-service overpack, designed to transport pellet sintering boats between buildings. The items were removed and sent to an outside waste area for gamma spectrometry measurement. The gamma spectrometry results at 1445 PDT on 5/7/2024, indicated that less than 8 grams of uranium were present in the transfer vault. This is more than the annual portion quantity of the building containing the storage area. The limit per stack license for Emission Unit 1511 is 1 gram of uranium. The other items were found to not be contaminated. There was no removable contamination on the items as measured by health and safety technicians. |
| ENS 57114 | 8 May 2024 17:00:00 | The following was provided by the Illinois Emergency Management Agency (the Agency) via email: The radiation safety officer for Endeavor Health Clinical Operations (IL-01248-02) contacted the Agency at 1115 CDT on 5/8/2024 to report a medical underdose. The patient had been prescribed two administrations of Y-90 TheraSpheres. The first administration was completed without incident. The second administration (a separate written directive) resulted in only 14 percent of the dose being delivered (17.1 Gy of 122.14 Gy prescribed). The administering physician reported initial resistance due to a kinked catheter at the distal end. Both the patient and the referring physician were notified. The licensee met the reporting requirements. A reactive inspection is scheduled to be performed on 5/16/2024. IL Event Number: IL240012 A Medical Event may indicate potential problems in a medical facilitys use of radioactive materials. It does not necessarily result in harm to the patient. |
| ENS 57053 | 26 March 2024 16:21:00 | The following information was provided by the licensee via phone and email: On March 26, 2024 at 1115 CDT, Grand Gulf Nuclear Station experienced an actuation of the reactor protection system (RPS) due to high reactor coolant system pressure. The plant was in Mode 4 at zero percent power and performing scram time testing. All rods were fully inserted at the time of the RPS actuation, and all required equipment responded as designed. This actuation is being reported in accordance with 10 CFR 50.72(b)(3)(iv)(A). The cause of the event is under investigation. The NRC resident inspector has been notified. |
| ENS 57052 | 26 March 2024 14:15:00 | The following was received from the Texas Department of State Health Services (the Department) via phone and email: On March 26, 2024, the Department was notified by the licensees radiation safety office (RSO) that earlier this day a radiography crew had a source disconnect while using a SPEC 150 exposure device. The device contained a 23 curie, iridium-192 source. The disconnect occurred on the first shot of the day. The RSO reported that the radiographers had completed set up for the first shot but had failed to properly connect the guide tube to the camera. When the radiographers cranked the source out and it hit the collimator, the guide tube popped loose from the camera. The radiographer immediately attempted to crank the source back into the camera but when the source reached the end of the guide tube the source pigtail disconnected from the drive cable. The radiographers set up new boundaries and contacted the RSO. An RSO from a nearby office responded to the location. The RSO was wearing a self-reading dosimeter (SRD), alarming rate meter, and TLD (thermoluminescent dosimeter) exposure badge. The RSO placed the camera on the source for shielding, attached the source back to the drive cable, and retracted the source into the camera. The responding RSOs SRD was reading off scale after retracting the source. The badge has been sent to the licensees dosimetry processor for emergency processing. The licensee does not believe any individual exceeded any limit due to this event. Additional information will be provided as it is received in accordance with SA-300. Texas Incident # 10095 |
| ENS 57054 | 26 March 2024 17:51:00 | The following is a summary of information received from the Colorado Department of Public Health and Environment via email: Three SRB Technologies exit signs, model SLXTU1GB10, containing 7.09 curies each of tritium (21.27 curies total) were determined to be lost. Colorado event number CO240008 THIS MATERIAL EVENT CONTAINS A Less than Cat 3 LEVEL OF RADIOACTIVE MATERIAL Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf |
| ENS 57057 | 27 March 2024 19:00:00 | The following is a summary of information received from the Colorado Department of Public Health and Environment via email: Two Best Lighting Products, Inc. exit signs, model SLXTU1GB10, containing 14.18 curies each, of tritium (26.36 curies total) were determined to be lost. Colorado event number CO240009 THIS MATERIAL EVENT CONTAINS A Less than Cat 3 LEVEL OF RADIOACTIVE MATERIAL Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf |
| ENS 57055 | 26 March 2024 18:00:00 | The following is a summary of information received from the Colorado Department of Public Health and Environment via email: Seven Isolite Corporation exit signs, model 2040, containing 11.5 curies each, of tritium (80.5 curies total) were determined to be lost. Colorado event number CO240007 THIS MATERIAL EVENT CONTAINS A Less than Cat 3 LEVEL OF RADIOACTIVE MATERIAL Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf |
| ENS 57056 | 27 March 2024 14:10:00 | The following is a summary of information received from the licensee via phone: Licensee discovered three electron capture detectors (ECD) were missing on 03/18/2024. Each ECD contained 15 millicuries of nickel-63 (45 millicuries total). The last known accountability of these ECDs occurred at a leak test performed in 08/25/2020. The licensee suspects the ECDs may have been disposed of improperly. THIS MATERIAL EVENT CONTAINS A Less than Cat 3 LEVEL OF RADIOACTIVE MATERIAL Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf |
| ENS 57014 | 7 March 2024 16:20:00 | The following information was provided by the licensee via phone and email: On March 7, 2024, at 1142 PST, an operator trainee operating the reactor under the direction of a licensed operator initiated a planned manual scram. Following the planned manual scram, the licensed operator did not switch the console switch to 'off' or remove the key from the console. The reactor did not meet the definition of 'reactor secured' and thus the staffing requirements of technical specification 6.1.3 were still required to be met. The licensed operator then left the control room, securing the door on their way out. At 1200 PST, a licensed senior reactor operator (SRO) entered the control room and found the key in the console with the switch in the 'operate' position. This SRO placed the switch in the 'off' position, secured the key, logged the action, and notified the Director. Throughout the duration of the event, all control rods were fully inserted. Project Manager (Wertz) will be contacted. Oregon Department of Energy and the Oregon Radiation Protection Services will be notified. |
| ENS 56966 | 14 February 2024 13:53:00 | The following is a summary of information provided by the New Mexico Radiation Control Bureau via email: On February 14, 2024, a routine inspection discovered that a densitometer (Berthold LB8010, serial number 10377, 20 mCi of cesium-137) was missing the handle that actuates the shutter. The shutter was in the open position. The radiation safety officer packed the defective densitometer in lead pending disposal. There were no excessive exposures due to this event. |
| ENS 56965 | 14 February 2024 16:17:00 | The following is a summary of information provided by the licensee via phone: At 1110 EST on February 14, 2024, a patient was administered the wrong radiopharmaceutical. The prescribed dose was 25 mCi Tc-99m pyrophosphate, and the administered dose was 25 mCi Tc-99m sestamibi. The patient and referring physician were informed. There were no adverse effects to the patient. The total effective dose equivalent for this study was estimated to be 1,200 mrem.
After further review, the dose to the patient was below reporting threshold. The radiopharmaceutical was a diagnostic tracer and non-therapeutic. Notified R1DO (Bickett), NMSS (Rivera-Capella), and NMSS Events (email). A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient |
| ENS 56963 | 13 February 2024 17:10:00 | The following is a synopsis of information provided by the licensee via email: On February 13, 2024, a non-licensed supervisor violated the station's FFD policy. The employee's access at Sequoyah Nuclear Plant has been terminated. The NRC resident inspector has been notified. |
| ENS 56959 | 11 February 2024 11:38:00 | The following information was provided by the licensee via email: At 1011 EST on 02/11/2024, during a refueling outage at 0 percent power, while performing local leakage rate testing (LLRT) of the feedwater check valves (part of the containment boundary), it was determined that the Unit 1 primary containment leakage rate did not meet 10 CFR 50 Appendix J requirements specified in Technical Specification 5.5.12. This event is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(ii)(A). There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. |
| ENS 56961 | 12 February 2024 17:26:00 | The following synopsis of information was provided the State of New Mexico via phone: Sometime during the overnight hours between 02/10/24 and 02/11/24, a rollover accident occurred on Interstate 25 within Albuquerque, NM. Following the accident, an Instrotek moisture density gauge (serial number 4578) containing 11 mCi of cesium (Cs-137) and 44 mCi of americium-beryllium (Am-241Be) could not be located at the scene. Local law enforcement responded to the accident and filed a report. The driver was transported to a hospital and was in stable condition. More information will be provided as it is obtained.
The licensee provided a follow-up report on this incident. The driver of the vehicle is still in the hospital and was unable to confirm the presence of the gauge in the truck prior to the accident. Based on the gauge and other test equipment missing at the crash site, the licensee suspects that it may have been stolen prior to the accident. The last confirmed location of the gauge was at Isleta Resort and Casino (Pueblo of Isleta, Federal Reservation). Notified R4DO (Vossmar), ILTAB (email), NMSS Events (email), and CNSNS (email)
The following update was provided by the New Mexico Radiation Control Bureau (the Bureau) via email: The licensee reported on 02/13/24 at 1603 MST, the density moisture gauge was recovered. The licensee will provide a written report to the Bureau at their earliest opportunity. The damage was to the transportation box, the gauge is being leak tested, and the gauge handle was still in the locked (safe) position. Notified R4DO (Vossmar), and NMSS Events Notification, ILTAB (MacDonald), CNSNS (Mexico) via email. THIS MATERIAL EVENT CONTAINS A 'Less than Cat 3' LEVEL OF RADIOACTIVE MATERIAL Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf |
| ENS 56953 | 8 February 2024 15:07:00 | The following was received from the Texas Department of State Health Services (the Department) via email: On February 8, 2024, the Department was notified by the licensee that, while testing the shutter of a Vega SH-F2B nuclear gauge containing a 200 millicurie (original activity) cesium-137 source, the shutter failed to close. Open is the normal position of the shutter. The license stated there is no risk of exposure to members of the general public or their workers. The licensee may have the repair parts for the shutter already in hand. Additional information will be provided as it is received in accordance with SA-300. Texas Incident Number: 10087 Texas NMED Number: TX240004 |
| ENS 56952 | 8 February 2024 12:40:00 | The following information was provided by the licensee via email: A programmatic vulnerability, failure, or degradation was discovered within the fitness for duty (FFD) program that may permit undetected drug or alcohol use or abuse by individuals within the protected area, or by individuals who are assigned to perform duties that require them to be subject to the FFD program. Public and plant safety have not been affected. The NRC Resident Inspector was notified. |
| ENS 56949 | 6 February 2024 18:23:00 | The following information was provided by the Virginia Office of Radiological Health via email: At approximately 0730 EST on 2/06/24, VA Office of Radiological Health was notified by phone of a traffic incident involving a portable nuclear gauge. This was reported by the Assistant Chief of the Spotsylvania County Hazmat, the on-scene incident command, who had secured the scene and gauge. Earlier this morning (exact time unknown at this point), a Troxler gauge Model 3440 Plus, in its transportation box, containing an 8 mCi Cs-137 source, reportedly fell from a truck, presumably unknown to the driver, and was struck by a tractor trailer truck and possibly other vehicles. This occurred at or near the intersection of Plank Road and Eley Ford Road in Spotsylvania, VA. There was damage to the transport box and plastic housing of the gauge. VA Department of Emergency Management Division 7 arrived on scene and conducted radiation surveys. Per the Assistant Chief of the Spotsylvania County Hazmat, there were no readings above background indicating the source was most likely still in its shielded position; so, no radiation exposures occurred. He also reported there had been no injuries to any individuals during the incident, only vehicle damage. The licensee/owner of the gauge was contacted, and they retrieved the gauge. The licensee contacted the VA Office of Radiological Health at 0830 EST indicating they were en route to acquire the gauge. The licensee later confirmed the damaged gauge was secure at the storage location, the source was in the shielded position, and all survey readings were at background. The licensee indicated that the gauge electronics were damaged, and it will be sent to the manufacture for evaluation. The Radioactive Materials Program will follow up with an investigation. Virginia Event Report ID: VA240001 |
| ENS 56942 | 1 February 2024 15:35:00 | The following is a summary of information received by email from the Illinois Office of Nuclear Safety: On January 31, 2024, a medical administration of Y-90 microspheres at Rush University Medical Center failed to deliver the intended dose. A patient had been prescribed 34.99 mCi (500 Gy) of yttrium-90 (Y-90) Theraspheres intended for a liver treatment. The post-administration survey indicated a delivered dose of only 23.05 mCi (330 Gy), which was a 34 percent underdose. The patient and physician were notified the day of the treatment. There was no adverse impact on the patient and the patient will not need to be retreated. The administering physician reported significant resistance in the initial and subsequent flushes. IL NMED Item Number: IL240003 A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient. |
| ENS 56940 | 30 January 2024 19:48:00 | The following is a summary of information that was provided by the California Department of Public Health, Radiological Health Branch via email: On January 30, 2024, at 1450 PST, the radiation safety officer of Cedars Sinai Medical Center contacted the Los Angeles County Radiation Management office to report a medical underdose event. The underdose occurred during a treatment of Y-90 (yttrium-90) TheraSpheres microspheres for a radioembolization treatment for liver cancer. The prescribed activity was 480 Gy and the administered activity was 227.6 Gy (about 47 percent of the prescription). The underdose was due to an obstruction of the microcatheter used to deliver the Y-90. The patient has been notified. Cedars Sinai Medical Center will conduct an investigation to gain a better understanding of the details of the event. CA event ID number: 013024 A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient. |
| ENS 56936 | 29 January 2024 13:32:00 | The following information was provided by the licensee via email: At approximately 1202 EST on 01/29/24, unit 2 experienced a reactor scram caused by a main turbine trip. Investigation is still ongoing. The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance: All control rods were fully inserted. The licensee indicated that the turbine trip may have been caused by a power load imbalance, however the cause of the incident is under investigation. The scram was not complex. Decay heat is currently being removed thru bypass valves dumping to the main condenser. Initially unit 2 lost the use of the bypass valves due to lack of condenser vacuum. Unit 2 used the high pressure coolant injection (HPCI) system in the condenser storage tank (CST) to CST mode to remove decay heat. Residual heat removal was used to keep the torus cool. Condenser vacuum was regained and unit 2 is back to removing decay heat with the turbine bypass valves. There was no impact to unit 3. The licensee confirmed there was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.
The following information was provided by the licensee via email: Licensee adds 8-hour non-emergency 10 CFR 50.72(b)(3)(iv)(A) specified system actuation report to original 4-hour non-emergency 10 CFR 50.72(b)(2)(iv)(B) RPS Actuation report. At approximately 1202 EST on 01/29/24, unit 2 experienced a reactor scram by a main turbine trip. All control rods inserted. Reactor core isolation cooling system (RCIC) was manually initiated for level control. HPCI was manually initiated for pressure control. Primary containment isolation system (PCIS) Group II and III isolations occurred (specified system actuation). Investigation is ongoing. The NRC Resident Inspector has been notified. |
| ENS 56938 | 29 January 2024 16:56:00 | The following information was provided by the licensee via email: At 1005 CST on January 29, 2024, Grand Gulf Nuclear Station was conducting surveillance testing on the high pressure core spray system. During testing, the 1E22F012 minimum flow valve failed to return to the full closed position. The valve went from full open indication to dual indication. The event is being reported in accordance with 10 CFR 50.72(b)(3)(v)(D) as an event or condition which could have prevented the fulfillment of a safety function. Troubleshooting is in progress. The NRC Senior Resident has been notified. The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance: All off-site power is available. No other systems are out of service and there are no compensatory measures taken. There is no increase to plant risk. |
| ENS 56899 | 19 December 2023 17:34:00 | The following is a synopsis of information was provided by the licensee via phone and email: Pursuant to 10 CFR 21.21(d)(3)(i), Paragon provided initial notification of a defect associated with the auxiliary feedwater pump diesel engine fuel injectors supplied to Constellation. The injectors were provided to Paragon for refurbishment. Constellation provided Paragon with root cause report # 4703982 on November 12, 2023. The associated failure analysis report documented potential defects with some fuel injectors supplied to Braidwood. These reported deficiencies allowed excessive fuel oil leakage which resulted in diesel lubricating oil system contamination above specified limits. Paragon concluded their evaluation on December 18, 2023, which determined that this condition, if left uncorrected, could contribute to a substantial safety hazard and is reportable in accordance with 10 CFR Part 21. The extent of condition is limited to the Constellation Braidwood and Byron plants. Paragon has entered this condition in their corrective action program. Affected injectors at Braidwood have been removed from service and returned to Paragon. Paragon is coordinating with Byron on recommended actions and will follow up with a final notification on or before 1/17/2024.
Paragon Energy Solutions submitted a final report for this event. Notified R3DO (Orlikowski), R4DO (Josey), and Part 21 (email). |
| ENS 56898 | 19 December 2023 16:15:00 | The following information was provided by the licensee via phone and email: At approximately 1100 CST on December 15, 2023, the facility was discovered to be in violation of a Limiting Condition of Operation (LCO) according to Technical Specification 3.3.2.2, which requires that the static pressure measurement in the confinement exhaust system measure -0.1 inches of water or less during operation. It was discovered that this plant variable was not tied to the PANALARM trip for 'Building Pressure', nor was the sensor output value available in the control room to be checked by operators. The PANALARM trip for 'Building Pressure' was set to a different variable not related to the LCO required value. This condition has existed since 2006. The reactor was not in operation at the time of the discovery, and the situation creating this LCO violation is being corrected prior to the next reactor startup. The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance: The issue was discovered by the vendor when a controller board was being replaced after damage from a power outage. |