| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
06/08/2016 - 06/09/2016 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 51970 | Rep Org: NEW YORK STATE DEPT. OF HEALTH
Licensee: NOT PROVIDED
Region: 1
City: State: NY
County:
License #:
Agreement: Y
Docket:
NRC Notified By: JANAKI KRISHNAMOORTHY
HQ OPS Officer: JEFF HERRERA | Notification Date: 06/01/2016
Notification Time: 15:17 [ET]
Event Date: 05/24/2016
Event Time: [EDT]
Last Update Date: 06/01/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
DAN SCHROEDER (R1DO)
NMSS_EVENTS_NOTIFIC (EMAI)
| Event Text AGREEMENT STATE REPORT - MEDICAL UNDERDOSE TO THE LEFT LOBE OF LIVER
The following report was received from the New York State Department of Health, Bureau of Environmental Radiation Protection via facsimile:
"Radiation safety staff from a hospital called on 5/24/2016 to report a medical event that meets the reportability criterion on the borderline. 79.5 percent of intended dose is believed to have been delivered to the left lobe of the liver of a patient receiving Y90 treatment. The patient had received treatment to the right lobe a month ago. The left lobe was smaller with small vessels. The waste measured after the procedure showed that only about 79 .5 percent had been delivered. The licensee usually is able to administer 95 percent of intended dose in this procedure. We were informed that since the amount retained in the device is about the same, smaller doses tend to show a greater percent in retained in the device. They will send a report within 7 days."
NYS NRC Event Report ID No.: NYDOH-16-02
NY State Incident No.: 1146
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. |
| Agreement State | Event Number: 51971 | Rep Org: TEXAS DEPT OF STATE HEALTH SERVICES
Licensee: CARDINAL HEALTH
Region: 4
City: DALLAS State: TX
County:
License #: 02048
Agreement: Y
Docket:
NRC Notified By: IRENE CASARES
HQ OPS Officer: JEFF HERRERA | Notification Date: 06/01/2016
Notification Time: 15:46 [ET]
Event Date: 06/01/2016
Event Time: [CDT]
Last Update Date: 06/01/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
RICK DEESE (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)
CNSNS (MEXICO) (EMAI)
|
| This material event contains a "Less than Cat 3 " level of radioactive material. | Event Text AGREEMENT STATE REPORT - TWO RADIOACTIVE MATERIALS PACKAGES NOT LOCATED AFTER CARRIER ACCIDENT
The following report was received from the Texas Department of State Health Services via facsimile:
"On June 1, 2016, the licensee notified the Agency [Texas Department of State Health Services] that one of its shipments was involved in a transportation accident. A carrier was transporting two type A packages, each containing a vial of fluorodeoxyglucose (F-18), 10 mCi, when it was involved in an accident on an unreported freeway. Emergency responders arrived at the scene, the driver was taken to a hospital. The vehicle was cleared from the roadway. It is uncertain at this time where the vehicle or the packages are located. The licensee is obtaining information to recover the radioactive materials. Additional information will be provided as it is received in accordance with SA-300."
Texas Incident #: I 9408
* * * UPDATE AT 1703 EDT ON 6/1/16 FROM ART TUCKER TO JEFF HERRERA * * *
The following report was received from the Texas Department of State Health Services via email:
"Agency [Texas Department of State Health Services] received call 1529 CDT from licensee. He informed us [Texas] that the packages were intact, not damaged, and recovered from the accident vehicle. The packages are currently located at the original pharmacy location in Dallas. The vial activity amount was 15 mCi each instead of the reported 10 mCi. The licensee stated that since the driver was not his employee he could not obtain information on the driver.
"The packages were intact and no exposures occurred."
Notified the R4DO (Deese), NMSS Events, and 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 |
| Power Reactor | Event Number: 51987 | Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: LONNIE CRAWFORD
HQ OPS Officer: HOWIE CROUCH | Notification Date: 06/08/2016
Notification Time: 07:01 [ET]
Event Date: 06/08/2016
Event Time: 02:26 [EDT]
Last Update Date: 06/08/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
| Person (Organization):
FRANK ARNER (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown | Event Text DISCOVERY OF UNISOLABLE REACTOR PRESSURE BOUNDARY LEAKAGE
"Susquehanna Unit 1 identified RPV [reactor pressure vessel] pressure boundary leakage from [local power range monitor] LPRM 24-09 housing above the flange during an under vessel leak inspection on 06/08/2016 at 0226 EDT. The leakage point is a through wall indication on the ASME Class 1 LPRM stub tube. The leakage is not isolable from the reactor vessel. The reactor was in Mode 4 at the time of discovery.
"This event is being reported as a degraded condition pursuant to 10CFR50.72(b)(3)(ii)(A)."
A repair plan is being formulated.
The licensee has notified the NRC Resident Inspector. |
| Part 21 | Event Number: 51988 | Rep Org: CURTISS WRIGHT
Licensee: STRUTHERS-DUNN
Region: 3
City: CINCINNATI State: OH
County:
License #:
Agreement: Y
Docket:
NRC Notified By: TIMOTHY FRANCHUK
HQ OPS Officer: JEFF HERRERA | Notification Date: 06/08/2016
Notification Time: 09:27 [ET]
Event Date: 06/08/2016
Event Time: [EDT]
Last Update Date: 06/08/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(a)(2) - INTERIM EVAL OF DEVIATION
| Person (Organization):
BILLY DICKSON (R3DO)
FRANK ARNER (R1DO)
ANTHONY MASTERS (R2DO)
JOHN KRAMER (R4DO)
PART 21/50.55 REACT (EMAI)
| Event Text PART-21 REPORT - NONCONFORMANCE ON STRUTHERS-DUNN RELAY FOR PSEG NUCLEAR LLC
"This letter serves as an interim report in accordance with 10 CFR 21.21 pertaining to a potential deviation associated with Struthers-Dunn relays P/N B255XCXPFHSC125V supplied to PSEG Nuclear LLC. Based upon information obtained from PSEG, a defect may exist with the reset coil of the Struthers-Dunn relay listed above. Preliminary observations indicate the reset coil had shorted (opened) during operation, and that no other sub-components of the relay are believed to be associated with this failure. PSEG is aware of Curtiss-Wright's investigation into this failure.
"Evaluation of reportability in accordance with 10 CFR Part 21 is not able to be completed within the 60-day evaluation period due to the need for additional time to collect and evaluate the necessary information. It is currently expected that the evaluation of this defect will be completed by July 22, 2016."
POC: Timothy Franchuk
Director, Quality Assurance
4600 East Tech Drive
Cincinnati, Ohio 45245
(513) 528-7900
The licensee indicated that the current list of affected plants are being evaluated. |
| Power Reactor | Event Number: 51994 | Facility: SEQUOYAH
Region: 2 State: TN
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ROBERT URBANSKI
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 06/08/2016
Notification Time: 17:10 [ET]
Event Date: 06/08/2016
Event Time: 15:26 [EDT]
Last Update Date: 06/08/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
ANTHONY MASTERS (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text UNANALYZED CONDITION THAT COULD POTENTIALLY DEGRADE PLANT SAFETY
"At 1526 Eastern Daylight Time on 6/8/2016, a determination was made involving the potential impact of a tornado on the Emergency Diesel Generators (EDGs). The EDGs are required to be operable to provide power to ensure that acceptable fuel design limits, reactor coolant system pressure boundary limits, and containment integrity are not exceeded during abnormal transients. Further, the EDGs are designed with a crankcase pressure trip (setpoint = 1 inch water), which is bypassed during an emergency start. Engineering has determined that a tornado could potentially cause actuation of the crankcase pressure trip due to a low barometric condition. If an emergency start signal has NOT previously occurred, then during a tornado, actuation of the crankcase pressure trip would energize the shutdown relay causing an EDG lockout condition. The EDG lockout condition prevents subsequent EDG starts (normal or emergency) until operators manually reset the lockout condition locally at the EDG. This condition could potentially affect all four EDGs simultaneously.
"The EDGs are operable but degraded. All EDGs have successfully passed their required surveillances within the appropriate frequency. No severe weather warnings or watches are forecast in the local areas, which could challenge the crankcase pressure trip.
"This condition places both units in an unanalyzed condition that potentially significantly degrades plant safety, 10 CFR 50.72 (b)(3)(ii)(B).
"A compensatory measure has been established, that upon notification of a Tornado Warning, the EDGs would be 'emergency started' and run during the time the Tornado Warning was in effect. This action bypasses the crankcase pressure trip function and allows the EDGs to perform their required safety function.
"The NRC Senior Resident Inspector has been notified." |
| Power Reactor | Event Number: 51995 | Facility: WATTS BAR
Region: 2 State: TN
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MICHAEL BOTTORFF
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 06/08/2016
Notification Time: 17:23 [ET]
Event Date: 06/08/2016
Event Time: 15:26 [EDT]
Last Update Date: 06/08/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
ANTHONY MASTERS (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | | 2 | N | Y | 8 | Power Operation | 8 | Power Operation | Event Text UNANALYZED CONDITION THAT COULD POTENTIALLY DEGRADE PLANT SAFETY
"At 1526 Eastern Daylight Time on 6/8/2016, a determination was made involving the potential impact of a tornado on the Emergency Diesel Generators (EDGs). The EDGs are required to be operable to provide power to ensure that acceptable fuel design limits, reactor coolant system pressure boundary limits, and containment integrity are not exceeded during abnormal transients. Further, the EDGs are designed with a crankcase pressure trip (setpoint = 1 inch water), which is bypassed during an emergency start. Engineering has determined that a tornado could potentially cause actuation of the crankcase pressure trip due to a low barometric condition. If an emergency start signal has NOT previously occurred, then during a tornado, actuation of the crankcase pressure trip would energize the shutdown relay causing an EDG lockout condition. The EDG lockout condition prevents subsequent EDG starts (normal or emergency) until operators manually reset the lockout condition locally at the EDG. This condition could potentially affect all four EDGs simultaneously.
"The EDGs are operable but degraded. All EDGs have successfully passed their required surveillances within the appropriate frequency. No severe weather warnings or watches are forecast in the local areas, which could challenge the crankcase pressure trip.
"This condition places both units in an unanalyzed condition that potentially significantly degrades plant safety, 10 CFR 50.72 (b)(3)(ii)(B).
"A compensatory measure has been established, that upon notification of a Tornado Warning, the EDGs would be 'emergency started' and run during the time the Tornado Warning was in effect. This action bypasses the crankcase pressure trip function and allows the EDGs to perform their required safety function.
"The NRC Senior Resident Inspector has been notified." |
| Power Reactor | Event Number: 51996 | Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [ ] [ ] [3]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: TODD CHRISTENSEN
HQ OPS Officer: DANIEL MILLS | Notification Date: 06/08/2016
Notification Time: 17:51 [ET]
Event Date: 06/08/2016
Event Time: 10:37 [CDT]
Last Update Date: 06/08/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
ANTHONY MASTERS (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text HIGH PRESSURE COOLANT INJECTION INOPERABLE
"At 0800 CDT on 6/8/2016, 3-SR-3.5.1.7, 'HPCI [High Pressure Coolant Injection] Main and Booster Pump Set Developed Head and Flow Rate Test at Rated Reactor Pressure' periodic surveillance was being performed. As part of the surveillance procedure, HPCI was declared inoperable per Technical Specification (TS) Limiting Condition for Operation (LCO) 3.5.1 Emergency Core Cooling Systems (ECCS) - Operating, Condition C at 0925. At 1037, the HPCI turbine was started and a turbine trip alarm was received as well as large swings observed on the suction pressure indicator and slow turbine response. The control room operator then manually tripped the HPCI turbine due to the abnormal indications received.
"HPCl 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 Resident Inspector has been notified." | |