| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
04/24/2015 - 04/27/2015 ** EVENT NUMBERS ** |
 | Non-Agreement State | Event Number: 50990 | Rep Org: KAKIVIK ASSET MANAGEMENT
Licensee: KAKIVIK ASSET MANAGEMENT
Region: 4
City: KUPARUK State: AK
County:
License #: 50-27667-01
Agreement: N
Docket:
NRC Notified By: PAT PETTIJOHN
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 04/16/2015
Notification Time: 19:26 [ET]
Event Date: 04/13/2015
Event Time: [YDT]
Last Update Date: 04/16/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
20.2202(b)(1) - PERS OVEREXPOSURE/TEDE >= 5 REM
| Person (Organization):
THOMAS FARNHOLTZ (R4DO)
ANTHONY HSIA (NMSS)
NMSS_EVENTS_NOTIFIC (EMAI)
BERNARD STAPLETON (IRD)
STEVE SUGARMAN (DOE)
| Event Text POTENTIAL OVEREXPOSURE TO RADIOGRAPHER
A radiographer dropped his film badge on the floor before his first exposure. The floor was approximately three feet below the collimator for a two minute exposure. After his second exposure, he found his film badge. The licensee's RSO had the film developed with a result of 14.069 Rem. The source was Ir-192 at 78.6 Ci. Estimated dose by the licensee and REAC/TS expected a dose of closer to one and a half Rem. The licensee is continuing his investigations because of this discrepancy. |
| Agreement State | Event Number: 50991 | Rep Org: OR DEPT OF HEALTH RAD PROTECTION
Licensee: OREGON HEALTH AND SCIENCE UNIVERSITY
Region: 4
City: PORTLAND State: OR
County:
License #: ORE-90013
Agreement: Y
Docket:
NRC Notified By: DARYL LEON
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 04/17/2015
Notification Time: 12:43 [ET]
Event Date: 04/15/2015
Event Time: [PDT]
Last Update Date: 04/17/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
THOMAS FARNHOLTZ (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)
| Event Text AGREEMENT STATE REPORT - SOURCE MOVED DURING MEDICAL TREATMENT
"On 4-15-15 the patient was to receive a fractionated dose of 4 Grays to the 'vaginal cuff' region using a 10.175 Curie Ir-192 source. The dose was to be administered using a Varian Model VariSource 200t remote HDR [High Dose Rate] afterloader, serial number 600349.
"The plan was to administer 6 radiation treatments using a cylinder applicator and holder, the treatment length intended to be 5 cm. Imaging was done after placement of the cylinder prior to treatment to verify location, however, post-treatment imaging showed that the cylinder applicator had come loose from the holder and shifted 3 cm. This was the first of the six fractions.
"Hospital staff physicists are currently working to determine the delivered dose to the target and why the shift occurred. Physician notification has not been verified at this time. The patient has been notified."
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: 50992 | Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: PCS NITROGEN FERTILIZER LP
Region: 4
City: GEISMAR State: LA
County:
License #: LA-4903-L01
Agreement: Y
Docket:
NRC Notified By: JOE NOBLE
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 04/17/2015
Notification Time: 17:10 [ET]
Event Date: 04/15/2015
Event Time: 15:50 [CDT]
Last Update Date: 04/17/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
THOMAS FARNHOLTZ (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)
| Event Text AGREEMENT STATE REPORT - FIXED GAUGE SHUTTER FAILED OPEN
The following report was received via e-mail:
"Installed fixed level gauge on a process. The shutters on a fixed level gauge would not close properly due to a breakage of a shutter pin. The situation is the result of extended usage. The gauge was purchased and put into service in 1985. The problem with the shutter function is considered equipment failure of this device. Corrective action will be to de-install this device and [dispose of it]. The gauge will be replaced with a new lower activity source device. The failure is that the shutter blades would not open and close due to a shutter pin breaking. There was no removable radiation released into the environment. The gauge/source holder was 'fixed', and the RSO tagged and posted the broken device. Additionally, all personnel working in the vicinity of the devise were informed of the problem. The RSO advised the employees the radiation exposure levels were in the normal operational range.
"The gauge was an Accuray Mfg. device, SH302, s/r HS302-S6, approximately 200 mCi of Cs-137 when installed and manufactured in 1985. The source serial number is CS11166."
Louisiana Report: LA150007, T163028 |
| Agreement State | Event Number: 50993 | Rep Org: COLORADO DEPT OF HEALTH
Licensee: VISTA RIDGE ACADEMY
Region: 4
City: ERIE State: CO
County:
License #: None
Agreement: Y
Docket:
NRC Notified By: CHERI HALL
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 04/17/2015
Notification Time: 19:34 [ET]
Event Date: 04/13/2015
Event Time: [MDT]
Last Update Date: 04/17/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
THOMAS FARNHOLTZ (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)
|
| This material event contains a "Less than Cat 3 " level of radioactive material. | Event Text AGREEMENT STATE REPORT - RADIUM SOURCE FOUND
The following report was received via e-mail:
"Reported by Weld County DPHE [Department of Public Health and Environment] on behalf of Vista Ridge Academy, Erie, Colorado on Monday April 13, 2015.
"The material was discovered in a glass vial marked 'radium dust' which was verified as Radium 226 using a portable MCA (IdentiFINDER 2, S/N 910383-80, background 0.01 mrem/hr). The readings on contact and at one foot from the vial were 2.8 mrem/hr and 0.1 mrem/hr respectively. Due to the elevated nature of the readings, it was determined shielding should be put in place to protect individuals from exposure. The material was placed in plastic bags to contain the material in the event the lid falls off or the glass is broken. Additionally, ceramic bricks were used to build a temporary storage area for the vial to reduce the exposure in the area. The exposure on the outside of the brick shielding was 0.3 mrem/hr on contact. The material is stored in a secured closet. The mass of the contents in the vial were determined to be 204.5 grams with an approximate volume of 84.78 cubic centimeters. (The mass was determined using a school scale and a similar empty vial. The volume was determined by approximation of the diameter and height of the material in the vial.)
"Surveys were performed around the work bench area, storage shelf and a removable contamination wipe was done on the vial. It was determined during the site visit no contamination was present in the lab or storage area indicating no exposures to students or staff.
"Using the information gathered and making a few assumptions about efficiency, there is an estimated 50 to 100 uCi in the vial.
"Report ID number: CO15 - I15 -12
"A provisional license will be issued until the material can be properly disposed."
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: 51008 | Facility: FARLEY
Region: 2 State: AL
Unit: [1] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: DAVID HILDEBRANDT
HQ OPS Officer: VINCE KLCO | Notification Date: 04/24/2015
Notification Time: 00:15 [ET]
Event Date: 04/23/2015
Event Time: 17:17 [CDT]
Last Update Date: 04/24/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
ALAN BLAMEY (R2DO)
WILLIAM GOTT (IRD)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text OFFSITE NOTIFICATION DUE TO WORKER FATALITY NOT RELATED TO PLANT OPERATION
"This notification is being reported to NRC in accordance with 10 CFR 50.72(b)(2)(xi) for notification of an on-site fatality of a contract employee. In addition, the contracting company plans to notify the Occupational Safety and Health Administration (OSHA) of a fatality per 29 CFR 1904.39.
"At approximately 1717 CDT on 4/23/15, a 911 call was received in the Control Room regarding a contract employee who was found unresponsive and unattended in a temporary break room set up on the Turbine Deck during the Unit 1 refueling outage. Resuscitation by first responders and paramedics from a nearby town was unsuccessful. Resuscitation efforts were suspended at 1750.
"The Houston County Sheriff's Office was notified at approximately 1800 and they responded to the site at 1822. The county coroner was notified and arrived on site at 1850.
"[Farley Nuclear Plant] received notification at approximately 2035 that the contractor company intended to notify OSHA.
"A press release is not planned at this time. The NRC Resident Inspector has been notified.
"Unit 1 remains in Mode 6 and Unit 2 remains in Mode 1 at 100% power." |
| Power Reactor | Event Number: 51010 | Facility: SUMMER
Region: 2 State: SC
Unit: [ ] [2] [3]
RX Type: [1] W-3-LP,[2] W-AP1000,[3] W-AP1000
NRC Notified By: JAMES F. SALTER
HQ OPS Officer: DONG HWA PARK | Notification Date: 04/24/2015
Notification Time: 14:14 [ET]
Event Date: 04/23/2015
Event Time: 15:32 [EDT]
Last Update Date: 04/24/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
| Person (Organization):
ALAN BLAMEY (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | N | 0 | Under Construction | 0 | Under Construction | | 3 | N | N | 0 | Under Construction | 0 | Under Construction | Event Text VIOLATION OF THE FITNESS FOR DUTY PROGRAM
A contract employee supervisor tested positive for a follow-up fitness-for-duty test. The employees access to the site has been denied.
The licensee has notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 51011 | Facility: HARRIS
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP
NRC Notified By: TIM ENGLISH
HQ OPS Officer: DONG HWA PARK | Notification Date: 04/24/2015
Notification Time: 16:13 [ET]
Event Date: 04/04/2015
Event Time: 11:20 [EDT]
Last Update Date: 04/24/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
ALAN BLAMEY (R2DO)
|
| 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 POWER LOST TO CONTROL ROOM NORMAL OUTSIDE AIR INTAKE DAMPERS DURING TESTING
"On April 4, 2015, during testing of the Control Room ventilation system while in Mode 5 at 0% power during shutdown for a refueling outage, the 1CZ-1 and 1CZ-2 Control Room Normal Outside Air Intake dampers lost power due to circuit breaker trips, preventing closure. Harris personnel immediately closed the dampers as required by Harris Nuclear Plant Technical Specifications. During subsequent evaluation, this event was determined to be reportable on April 24, 2015, at approximately 1200 EDT.
"This event is being reported under the non-emergency notification requirement of 10 CFR 50.72 (b)(3)(v)(A), 'Any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to shut down the reactor and maintain it in a safe shutdown condition,' and 50.72(b)(3)(v)(D), 'Any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident.'
"There was no adverse impact to public health and safety or to plant employees.
"The NRC Resident Inspector has been notified." |
| Power Reactor | Event Number: 51013 | Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: NATHAN BIBUS
HQ OPS Officer: DONALD NORWOOD | Notification Date: 04/25/2015
Notification Time: 04:10 [ET]
Event Date: 04/24/2015
Event Time: 21:25 [CDT]
Last Update Date: 04/25/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
NICK VALOS (R3DO)
|
| 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 LOSS OF EMERGENCY ASSESSMENT CAPABILITY DUE TO OUT-OF-SERVICE RADIATION MONITORS
"At 2125 on 4/24/15, 1R-2, Containment Vessel Area Radiation Detector failed. Previously, 1R-7, Incore Seal Table Area Radiation Detector, had failed on 4/20/15. The compensatory measure for 1R-2 out-of-service is to verify 1R-7 operating properly and the compensatory measure for 1R-7 out-of-service is to verify 1R-2 operating properly. With both monitors out-of-service and Unit 1 operating in Mode 5, no compensatory measure is available that will allow timely classification of two Emergency Action Levels (EALs) - Notification of Unusual Event (NUE) classification (RU2.2) and Alert classification (RA3.2). This results in a Loss of Emergency Assessment Capability while 1R-2 and 1R-7 are concurrently out-of-service. This is a reportable condition per 10 CFR 50.72(b)(3)(xiii).
"Monitoring of radiological conditions in Unit 1 Containment showed no indication of RCS leakage or elevated radiation levels prior to the failure of 1R-2. Unit 1 Containment also remains monitored by 1R-48, Containment Hi Range Area Radiation Detector A and 1R-49, Containment Hi Range Area Radiation Detector B, which currently indicate normal radiation levels. Unit 1 Shield Building Stack is also monitored by 1R-50, Shield Building High Range Vent Gas Radiation Detector, which also currently indicates normal radiation levels. Additionally, a temporary portable radiation monitor has been placed near the location of 1R-2 and is being continuously monitored.
"The plant remains in a safe condition and there was no effect to the health and safety of the public.
"The licensee has notified the NRC Resident Inspector." |
| Power Reactor | Event Number: 51014 | Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: RONALD FRY
HQ OPS Officer: STEVE SANDIN | Notification Date: 04/26/2015
Notification Time: 01:37 [ET]
Event Date: 04/25/2015
Event Time: 22:10 [EDT]
Last Update Date: 04/26/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xii) - OFFSITE MEDICAL
| Person (Organization):
JAMES NOGGLE (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 97 | Power Operation | 97 | Power Operation | | 2 | N | N | 0 | Refueling | 0 | Refueling | Event Text OFFSITE MEDICAL TRANSPORT FOR POTENTIALLY CONTAMINATED WORKER
"At 2125 [EDT] on 4/25/15 the control room was notified of a medical emergency in the Radiologically Controlled Area [RCA].
"The individual was considered potentially contaminated since a complete frisk could not be performed prior to transport.
"An ambulance entered the Susquehanna Owner Controlled Area and the Protected Area at 2154 and exited at 2210 to transport the individual to the hospital.
"Radiological survey performed during transport by an SSES [Susquehanna Steam Electric Station] RP [Radiation Protection] Technician verified at 2255 the individual was not contaminated. The ambulance was verified not contaminated at 2303.
"This event is reportable under 10CFR50.72(b)(3)(xii).
"An Event of Potential Public Interest (EPPI) was made to the Pennsylvania Emergency Management Agency (PEMA) due to an emergency vehicle accessing company property."
The licensee informed the NRC Resident Inspector. | |