Event Notification Report for July 22, 2020
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U.S. Nuclear Regulatory Commission Event Reports For ** EVENT NUMBERS ** |
| 54757 | 54760 | 54777 | 54795 | 54796 |
| Agreement State | Event Number: 54757 |
| Rep Org: OK DEQ RAD MANAGEMENT Licensee: OU Medicine, Inc. Region: 4 City: Oklahoma City State: OK County: License #: OK-21035-01 Agreement: Y Docket: NRC Notified By: Kevin Sampson HQ OPS Officer: Bethany Cecere |
Notification Date: 06/24/2020 Notification Time: 16:31 [ET] Event Date: 06/23/2020 Event Time: 00:00 [CDT] Last Update Date: 07/21/2020 |
| Emergency Class: Non Emergency 10 CFR Section: Agreement State |
Person (Organization): JEFFREY JOSEY (R4DO) NMSS_EVENTS_NOTIFICATION (EMAIL) |
Event Text
EN Revision Imported Date : 7/22/2020 EN Revision Text: AGREEMENT STATE REPORT - SUSPECTED DOSE TO WRONG ORGAN The following is a summary of email received from the Oklahoma Department of Environmental Quality (OK DEQ): OK DEQ was just informed that yesterday, June 23, 2020, a medical event may have occurred involving a patient undergoing radiation therapy to the vagina. The treatment plan called for three (3) fractions delivered by a High Dose Rate (HDR) afterloader. After the first fraction was administered, the therapist noted the presence of fecal matter on the applicator. The licensee is assuming that the applicator was placed in the patient's rectum instead of the vagina. The treatment plan estimated a dose of 0.85 Sv to the rectum due to the procedure. The licensee estimates the actual dose delivered, assuming the applicator was in the rectum, to be 1.5 Sv. The licensee is the University of Oklahoma Health Science Center, OK-03176-01. This is a Type A medical broadscope license. OK DEQ will provide more information as it becomes available. * * * UPDATE ON 07/21/2020 AT 1549 EDT FROM LIBBY MCCASKILL TO OSSY FONT * * * The following update was received from the OK DEQ via email: OK DEQ is correcting the licensee name and license number. Initially, they were reported as the University of Oklahoma Health Science Center, OK-03176-01. The correct licensee is OU Medicine, Inc., License No. OK-21035-01. Notified R4DO (Drake) and NMSS Event Notification via 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. |
| Part 21 | Event Number: 54760 |
| Rep Org: PARAGON ENERGY SOLUTIONS Licensee: Paragon Energy Solutions Region: 4 City: Fort Worth State: TX County: License #: Agreement: Y Docket: NRC Notified By: Tracy Bolt HQ OPS Officer: Brian Lin |
Notification Date: 06/30/2020 Notification Time: 17:41 [ET] Event Date: 06/01/2020 Event Time: 00:00 [CDT] Last Update Date: 07/21/2020 |
| Emergency Class: Non Emergency 10 CFR Section: 21.21(d)(3)(i) - Defects And Noncompliance |
Person (Organization): DAVE WERKHEISER (R1DO) MARK MILLER (R2DO) PATRICIA SILVA (R4DO) - PART 21/50.55 REACTORS (EMAIL) |
Event Text
EN Revision Imported Date : 7/22/2020 EN Revision Text: PART 21 - FAILURE OF SIZE 1 AND 2 FREEDOM SERIES AUXILIARY CONTACTS The following is a summary of information received from Paragon Energy Solutions: DUKE Harris Nuclear Plant (HNP) has identified instances where Size 1 and 2 Eaton Freedom Series starters have failed to function as expected in assemblies that were originally supplied by NLI. The auxiliary contacts have degraded prematurely and have failed to change state when the starter was energized which has affected indication and other controlling actions within the circuit. The premature degradation of the auxiliary contacts with the old model NLI special coil, part number: 057018-COIL-1/2, has occurred on size 1 and 2 contactors that were continuously energized with significant run time after approximately 3 to 5 years of service time. HNP has provided information to manage the known degradation. The auxiliary contacts should be replaced at an increased frequency until new auxiliary contacts are installed along with the new design NLI special coil, part number: 057018-COIL-1/2-M. The nature of the defect is the pre-mature aging of the component within the auxiliary contact mechanism that is adjacent to the operating coil. The starter coil is potentially being subjected to voltages of a nature that elevates the temperature within the starter adjacent to the auxiliary contacts. It is recommended that the starters and coils be replaced in the applications where the units are being operated in a continuous duty application. It is also recommended that the control transformer be replaced with a true 4:1 ratio transformer. Paragon/NLI has developed a true 4:1 ratio transformer that will provide additional mitigation of this potential over-voltage condition. Replacing the transformer with a true 4:1 ratio reduces the control voltage that is being applied to the control circuit in a manner that will not prevent the unit from providing a sufficient voltage during a degraded voltage condition, and also will not subject the components to a voltage above the ratings when the supply voltage is operated above the nominal 480 VAC bus voltage. Paragon has no other recommendations as the accelerated aging of the components and the expected life based on the additional heat the units have been subjected to is unknown. Affected plants: Sharon Harris Oconee Turkey Point Columbia North Anna Waterford River Bend Beaver Valley Should you have any questions regarding this matter, please contact: Tracy Bolt Chief Nuclear Officer Paragon Energy Solutions 817-284-0077 tbolt@paragones.com * * * UPDATE ON 7/21/20 AT 1241 EDT FROM TRACY BOLT TO ANDREW WAUGH * * * The following is the summary of an email received from Paragon Energy Solutions: The root cause of the degraded component is due to the increased voltage and the overall temperature of the starter coil at the elevated voltage. This elevated voltage and temperature has degraded the mechanism of the auxiliary contact operator to a point to which it has become separated from the parent component. Paragon/NLI has developed a new version of the special coil (part number: 057018-COIL-1/2-M) that operates at a lower temperature than the original special coil that is currently in use at HNP. When the new version of the special coil is subjected to the same voltages, the temperature is lower. The affected plants have been revised to: Sharon Harris Oconee Turkey Point Columbia North Anna Notified R1DO (Carfang), R2DO (Miller), R4DO (Drake), and Part 21 Reactors Group (email). |
| Fuel Cycle Facility | Event Number: 54777 |
| Facility: Global Nuclear Fuel - Americas RX Type: Uranium Fuel Fabrication Comments: Leu Conversion (Uf6 To Uo2) Leu Fabrication Lwr Commerical Fuel Region: 2 City: Wilmington State: NC County: New Hanover License #: SNM-1097 Docket: 07001113 NRC Notified By: Mr. Phillip Ollis HQ OPS Officer: Thomas Herrity |
Notification Date: 07/14/2020 Notification Time: 10:13 [ET] Event Date: 07/13/2020 Event Time: 10:15 [EDT] Last Update Date: 07/14/2020 |
| Emergency Class: Non Emergency 10 CFR Section: PART 70 APP A (c) - Offsite Notification/News Rel |
Person (Organization): MARK MILLER (R2DO) NMSS_EVENTS_NOTIFICATION (EMAIL) |
Event Text
| CONCURRENT REPORT FOR FIRE SUPPRESSION OUT OF SERVICE "At 1015 EST on July 13, 2020, the New Hanover County Deputy Fire Marshall was notified per State code requirements that the fire suppression system for various Fuel Manufacturing Operation Shop Areas was taken offline for planned maintenance to conduct a NFPA [(National Fire Protection Association)] required 5-year inspection. These inspections will be ongoing throughout the week. Compensatory measures were enacted and communicated to the Deputy Fire Marshall. Because the New Hanover County Deputy Fire Marshall was notified, a concurrent notification to the NRC Operations Center is being made per 10 CFR 70, Appendix A(c)." Licensee will notify Region 2. |
| Power Reactor | Event Number: 54795 |
| Facility: Browns Ferry Region: 2 State: AL Unit: [1] [] [] RX Type: [1] GE-4,[2] GE-4,[3] GE-4 NRC Notified By: Todd Christensen HQ OPS Officer: Thomas Herrity |
Notification Date: 07/21/2020 Notification Time: 08:58 [ET] Event Date: 07/21/2020 Event Time: 04:35 [CDT] Last Update Date: 07/21/2020 |
| Emergency Class: Non Emergency 10 CFR Section: 50.72(b)(2)(iv)(B) - RPS Actuation - Critical 50.72(b)(3)(iv)(A) - Valid Specif Sys Actuation |
Person (Organization): MARK MILLER (R2DO) |
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | |||||||
| 1 | M/R | Y | 40 | Power Operation | 0 | Hot Shutdown |
Event Text
| BIOFOULING OF INTAKE STRUCTURE LEADS TO MANUAL REACTOR SCRAM OF UNIT 1 The following was received from TVA - Brown's Ferry at 0858, 21 July 20. "On July 21, 2020, at 0435 hours Central Daylight Time, Browns Ferry Unit 1 inserted a manual reactor scram due to degrading main condenser vacuum from marine biofouling at the intake structure. Browns Ferry Unit 2 is in Mode 4 and Browns Ferry Unit 3 is at approximately 76% rated thermal power and stable. "Primary Containment Isolation Systems received an actuation signal for groups 2, 3, 6, 8 on reactor water level below +2". All Primary Containment Isolation System groups that received an actuation signal performed as designed. Additionally, all other systems functioned as designed. "This event is reportable within 4 hours per 10CFR50.72(b)(2)(iv)(B) - Any event or condition that results in actuation of the reactor protection system (RPS) when the reactor is critical except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation. "This event also requires an 8 hour report per 10CFR50.72(b )(3)(iv)(A), Any event or condition that results in valid actuation of any of the systems listed in paragraph (b)(3)(iv)(B), (1) Reactor protection system (RPS) including: reactor scram or reactor trip, except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation and (2) General containment isolation signals affecting containment isolation valves in more than one system or multiple main steam isolation valves (MSIVs). "The NRC Resident Inspector has been notified." The plant is stable in Mode 3 and will remain shutdown until marine growth clogging the intake structure abates. |
| Power Reactor | Event Number: 54796 |
| Facility: Robinson Region: 2 State: SC Unit: [2] [] [] RX Type: [2] W-3-LP NRC Notified By: Kirk Schauer HQ OPS Officer: Ossy Font |
Notification Date: 07/21/2020 Notification Time: 12:42 [ET] Event Date: 07/21/2020 Event Time: 08:51 [EDT] Last Update Date: 07/21/2020 |
| Emergency Class: Non Emergency 10 CFR Section: 50.72(b)(2)(i) - Plant S/D Reqd By Ts |
Person (Organization): MARK MILLER (R2DO) |
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | |||||||
| 2 | N | Y | 100 | Power Operation | 99 | Power Operation |
Event Text
| TECHNICAL SPECIFICATION REQUIRED SHUTDOWN "At 0851 EDT on July 21, 2020, a Technical Specification required shutdown was initiated at Robinson Unit 2. Technical Specification LCO 3.0.3 was entered due to LCO 3.1.7 not being met as a result of indication loss on Control Rod positions with more than one position indication inoperable for a group. LCO 3.0.3 was entered at 0752 EDT to initiate action within 1 hour to place the unit in MODE 3 within 7 hours. Since a Technical Specification required shutdown was initiated, this event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(i). "Technical Specification LCO 3.0.3 was exited at 1003 EDT on July 21, 2020. "There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified." Shutdown was initiated and power was reduced approximately 3 percent. Reactor power was back to 98.5 percent at the time of notification. |
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021