| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
07/06/2016 - 07/07/2016 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 52050 | Rep Org: KENTUCKY DEPT OF RADIATION CONTROL
Licensee: UNIVERSITY OF LOUISVILLE
Region: 1
City: LOUISVILLE State: KY
County:
License #: 202-029-22
Agreement: Y
Docket:
NRC Notified By: MARISSA VEGA VELEZ
HQ OPS Officer: JEFF HERRERA | Notification Date: 06/29/2016
Notification Time: 10:15 [ET]
Event Date: 05/18/2016
Event Time: [CDT]
Last Update Date: 06/29/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
HAROLD GRAY (R1DO)
NMSS_EVENTS_NOTIFIC (EMAI)
| Event Text AGREEMENT STATE REPORT - PATIENT OVERDOSE OF IODINE-125 DURING MEDICAL TREATMENT
The following report was received from the Kentucky Department of Public Health and Safety, Radiation Health Branch via email:
"The KY Radiation Health Branch [RHB] was notified on 6/28/16 by the RSO at the University of Louisville that a patient received 297.7 cGy (rad), instead of the prescribed 31 cGy (rad). The patient was implanted with a 7.4 MBq (200 uCi) I-125 localization seed for treatment of non-palpable breast cancer on 3/18/16. The seed was to be removed within five days after implant. However, shortly after induction of anesthesia on the day of removal the patient became unstable, surgery was cancelled, the patient was placed in ICU, and the seed wasn't removed until 5/18/16. The dose was calculated by the radiation oncologist with a reference point of 1 cm around the seed. KY RHB has been in contact with the licensee and expects additional information to be provided by the licensee."
KY Event Report ID No.: KY160006
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: 52052 | Rep Org: COLORADO DEPT OF HEALTH
Licensee: EXTENDED STAY AMERICA
Region: 4
City: AURORA State: CO
County:
License #: GL
Agreement: Y
Docket:
NRC Notified By: LINDA BARTISH
HQ OPS Officer: STEVE SANDIN | Notification Date: 06/29/2016
Notification Time: 13:01 [ET]
Event Date: 06/29/2016
Event Time: [MDT]
Last Update Date: 06/29/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
GREG WERNER (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)
|
| This material event contains a "Less than Cat 3 " level of radioactive material. | Event Text AGREEMENT STATE REPORT - MISSING TRITIUM EXIT SIGNS
The following information was received from the State of Colorado via email:
"Details: The corporate office of Extended Stay America responded to the 2016 General License Annual reports. In their letter, it is stated, after a full investigation of the property, the exit signs were not found. There were 17, B100 Series, SN 625444 to 625460, with 9.2 Ci and 9 BXU10WS, SN 631179 to 631186, with 9.2 Ci not located. The total lost exit signs being reported are 26. Due to employee turnover from date reported shipped 4-23-1998 and 7-20-1998 to 2016 no records were maintained as the company had no knowledge of the status of Tritium Exit Signs associated with the site.
"Event Description: The Company will be conducting a special project to determine if Tritium Exit Signs exist at any of their facilities in Colorado when fire inspections are completed. Should they locate any Tritium Exit Signs the signs will be properly disposed. The company will notify the Radioactive Materials Unit [State of Colorado] that the signs were removed and properly disposed."
CO Event Report ID No.: CO16-I16-10
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: 52065 | Facility: COOK
Region: 3 State: MI
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BRANDY WARK
HQ OPS Officer: DONG HWA PARK | Notification Date: 07/06/2016
Notification Time: 01:02 [ET]
Event Date: 07/06/2016
Event Time: 00:38 [EDT]
Last Update Date: 07/06/2016 | Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
PATTY PELKE (R3DO)
CHRIS MILLER (NRR)
BILL GOTT (IRD)
CYNTHIA PEDERSON (R3RA)
BILL DEAN (NRR)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | M/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text MANUAL REACTOR TRIP AND UNUSUAL EVENT DECLARATION DUE TO STEAM LEAK IN TURBINE BUILDING
"On July 6, 2016, at 0038 [EDT], DC Cook Unit 2 Reactor was manually tripped and at 0050 [EDT] an Unusual Event (N-7 'Unanticipated Explosion') Emergency Declaration was made due to steam leak and associated damage to the turbine building.
"In accordance with Emergency Plan procedures, notifications of Berrien County and State of Michigan were completed. The licensee has notified the NRC Senior Resident Inspector. The Unusual Event was terminated at 0207 [EDT].
"This notification is being made in accordance with 10 CFR 50.72 (a)(1)(i) due to declaration of an emergency class. Original notification to NRC made at 0100 EDT via ENS. This event is reportable under 10 CFR 50.72(b)(2)(iv)(B), Reactor Protection System (RPS) actuation and 10 CFR 50.72(b)(2)(xi) Offsite Notification, as a four (4) hour report, and under 10 CFR 50.72(b)(3)(iv)(A), specified system actuation of the Auxiliary Feedwater System, as an eight (8) hour report. The DC Cook NRC Resident Inspector has been notified. A press release is planned.
"Unit 2 is being supplied by offsite power. All control rods fully inserted. Decay heat is being removed via Steam Generator PORVs [Power Operated Relief Valve]. Preliminary evaluation indicates all plant systems functioned normally following the reactor trip. DC Cook Unit 2 remains stable in Mode 3 while conducting the Post Trip Review. No radioactive release is in progress as a result of this event."
Notified DHS SWO, FEMA Ops Center, DHS NICC. Notified FEMA National Watch and Nuclear SSA via email. |
| Power Reactor | Event Number: 52067 | Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [ ] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: JOHN DIGNAM
HQ OPS Officer: JEFF HERRERA | Notification Date: 07/06/2016
Notification Time: 13:16 [ET]
Event Date: 07/06/2016
Event Time: 09:38 [EDT]
Last Update Date: 07/06/2016 | 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):
FRED BOWER (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | A/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text AUTOMATIC REACTOR TRIP WHILE PERFORMING TESTING
"On July 6, 2016 at 0938 EDT Indian Point Unit 2 experienced a trip from 100% steady state power during the performance of reactor protection testing. The cause of the trip is under investigation.
"All control rods fully inserted and all systems responded as expected. The auxiliary feedwater system actuated as expected on a low level in the steam generators which occurs as a result of a trip from full power. Auxiliary feedwater is maintaining steam generator levels and decay heat removal is via the steam generators to the main condenser.
"Offsite power and plant electrical line ups are normal with the exception of 13.8kV feeder 33332 which remains out of service during the replacement of breaker BT4-5.
"No primary or secondary code safety relief valves lifted. The reactor is in Mode 3 and stable.
"Indian Point Unit 3 was unaffected and remains at 100% steady state power.
"The NRC Resident Inspector has been notified."
The licensee notified the New York Public Service Commission and the New York Independent System Operator. Indian Point indicated they have issued a press release regarding the event. |
| Power Reactor | Event Number: 52069 | Facility: BRUNSWICK
Region: 2 State: NC
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: MIKE NAYLOR
HQ OPS Officer: VINCE KLCO | Notification Date: 07/06/2016
Notification Time: 21:33 [ET]
Event Date: 07/06/2016
Event Time: 18:07 [EDT]
Last Update Date: 07/06/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
FRED BOWER (R1DO)
DEBORAH SEYMOUR (R2DO)
NMSS_EVENTS_NOTIFICA (EMAI)
|
| 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 OFFSITE NOTIFICATION TO THE UNITED STATES DEPARTMENT OF TRANSPORTATION
"In accordance with 10 CFR 50.72(b)(2)(xi), Duke Energy is notifying the NRC of a report made to the Department of Transportation concerning the identification of removable contamination in excess of 49 CFR 173.443(a) limits. This report was made at 1807 Eastern Daylight Time (EDT).
"On July 6, 2016, an EnergySolutions 3-60B Transportation Package was received onsite. As a result of receipt surveys, Brunswick Health Physics personnel confirmed removable surface contamination on the transportation package in excess of 49 CFR 173.443(a) limits. The package was shipped as UN2910, Radioactive material, excepted package-limited quantity of material, 7, and was consigned as a non-exclusive use shipment.
"Surveys identified mixed beta/gamma contamination ranging from approximately 2500 to 4500 dpm/100 sq cm on the surface of the transportation package. All other smears taken on the cask raincover, trailer bed and tires were less than minimum detectable activity for removable contamination.
"The transportation package is located in a radiological controlled area and access is controlled by Radiation Protection. Surveys have confirmed that the contamination is limited to the surface of the cask. In addition, no personnel contamination events have been attributed to the contamination found on the transportation package.
"This event did not result in any adverse impact to the health and safety of the public.
"The NRC Resident [Inspector] has been notified.
"The safety significance of this condition is minimal. There is no indication of onsite or personnel contamination as a result of this event.
"The transportation package is controlled in a radiological controlled area and access is controlled by Radiation Protection."
The originator of the empty cask arriving at the site (Westinghouse-Pittsburgh) was notified of the contamination. The cask is used for control rod blades and local power range neutron monitoring string shipping. | |