| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
01/14/2016 - 01/15/2016 ** EVENT NUMBERS ** |
 | Power Reactor | Event Number: 51616 | Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [1] [2] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: JEFF HUMAN
HQ OPS Officer: DONG HWA PARK | Notification Date: 12/21/2015
Notification Time: 22:12 [ET]
Event Date: 12/21/2015
Event Time: 16:25 [CST]
Last Update Date: 01/14/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
MICHAEL KUNOWSKI (R3DO)
|
| 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 | N | 0 | Hot Standby | 0 | Hot Standby | Event Text UNANALYZED CONDITION DUE TO NON-COMPLIANT FIRE PROTECTION MANUAL OPERATOR ACTIONS
"As part of the License Amendment development to transition to NFPA 805, PINGP [Prairie Island Nuclear Generating Plant] Calculation ENG-ME-353, Mechanical MOV [Motor Operated Valve] Analysis to support IN-92-18 Response, revision 1, issued in 1998, was reviewed for applicability for the transition to NFPA 805. Recent consultation with an MOV engineer regarding the scope of the revision indicated ENG-ME-353 is out of date.
"On 12/21/2015, during technical review for a new weak link calculation, several MOVs were identified from the list of MOVs that are credited to be manually operated from outside the control room in the event of a fire in the control room or relay room per PINGP Procedure F5 Appendix B, Control Room Evacuation (Fire), that could be damaged if hot shorts were to bypass the torque and limit switches. There are also four other motor valves associated with the Gland Steam system of both Unit 1 and Unit 2 that were added to the procedure F5 Appendix B, Control Room Evacuation (Fire), that have not been analyzed for a weak link. This unanalyzed condition could impact the ability of plant operators to implement procedure F5 Appendix B, Control Room Evacuation (Fire).
"New hourly fire watch impairments were created for Fire Area 13 (Control Room) and Fire Area 18 (Relay and Cable Spreading Room) as compensatory measures.
"Therefore, this is an unanalyzed condition reportable under 10 CFR 50.72(b)(3)(ii)(B).
"The public health and safety is not impacted.
"The NRC Resident Inspector has been notified."
* * * UPDATE AT 0107 EST ON 01/14/16 FROM NATHAN BIBUS TO DANIEL MILLS * * *
"Reviews of the list of MOVs susceptible to hot shorts bypassing the torque and limit switches credited to be manually operated from outside the control room in the event of a fire have continued. Additional valves have been noted to be affected by this failure mechanism in areas outside of the Control Room or Relay Room. The additional MOVs affected by this unanalyzed condition could impact the ability of plant operators to implement PINGP Procedure F5 Appendix D, Impact of Fire Outside Control/Relay Room.
"As a compensatory measure, additional hourly fire watch impairments were created for the following fire areas:
Fire Area 031 ( A Train Hot Shutdown Panel & Air Compressor/Aux 695 Feedwater Room)
Fire Area 032 ( B Train Hot Shutdown Panel & Air Compressor/Aux 695 Feedwater Room)
Fire Area 058 (Aux Building Ground Floor Unit 1)
Fire Area 073 (Auxiliary Building Ground Floor Unit 2)
"The public health and safety is not impacted.
"The [NRC] Resident Inspector has been notified."
Notified R3DO (Duncan). |
| Non-Agreement State | Event Number: 51640 | Rep Org: HENRY FORD HOSPITAL
Licensee: HENRY FORD HOSPITAL
Region: 3
City: DETROIT State: MI
County:
License #: 21-04109-16
Agreement: N
Docket: 03002043
NRC Notified By: ALAN JACKSON
HQ OPS Officer: JEFF ROTTON | Notification Date: 01/07/2016
Notification Time: 15:08 [ET]
Event Date: 01/06/2016
Event Time: 10:27 [EST]
Last Update Date: 01/08/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
35.3045(a)(1) - DOSE <> PRESCRIBED DOSAGE
| Person (Organization):
KARLA STOEDTER (R3DO)
NMSS_EVENTS_NOTIFICA (EMAI)
| Event Text POTENTIALLY REPORTABLE UNDERDOSE TO PATIENT
A patient at the Henry Ford Hospital Interventional Radiology Department received a Y-90 Theraspheres treatment of 120 Gray to a portion of the left lobe of the liver via a written directive from the referring physician. The Interventional Radiologist administered the prescribed dose to the entire left lobe of the liver, and the hospital believes that will result in an underdose to the patient. The exact amount of the underdose has not determined at the time of this report. The referring physician has been notified and the licensee will inform the NRC when the patient has been notified. It is believed that this event will not result in any harm to the patient. The licensee is in the process of determining corrective action to prevent reoccurrence.
* * * UPDATE FROM ALAN JACKSON TO JEFF ROTTON AT 1543 EST ON 01/08/2016 * * *
The following update information was provided by the licensee via email:
"Providing additional materials related to a potential medical event that was reported on January 7, 2016 by Henry Ford Hospital (License 21-04109-16; Docket: 030-02043). Hospital reported an apparent deviation from the written directive of a Y-90 TheraSpheres treatment done on January 6, 2016. The written directive was prepared in tandem by a Radiation Oncologist and a Nuclear Medicine Authorized User physicians for the major portion of the left lobe of the liver, omitting segments 4A and 4B. The entire left lobe of the liver, including segments 4A and 4B, was treated by the Interventional Radiologist. The written directive called for the administration of 2.3 GBq (62.2 mCi) of Y-90. The activity delivered was 2.37 GBq (64 mCi) which properly conformed with the activity specified in the written directive. However, the dose delivered to the liver deviates from the intended dose in two important ways. First, the written directive did not include treating segments 4A and 4B of the left lobe of the liver. Secondly, the dose delivered of 94 Gy (9,400 rad) to the left lobe of the liver was lower (21.5%) than the intended dose of 120 Gy (12,000 rad). The Interventional Radiologist, who is the referring physician for this patient, originally intended to treat the entire left lobe of the liver, including segments 4A and 4B. This Interventional Radiologist, while very experienced in TheraSpheres treatments was new to the institution and proper communication of the intended treatment site did not occur.
"It is important to note that all of the physicians involved indicated that no harm resulted to the patient as a result of this deviation. According to the TheraSpheres package insert, the recommended therapeutic dose to the liver is 80 Gy to 150 Gy (8,000 rad to 15,000 rad). Thus the treatment dose of 94 Gy (9,400 rad) is well within the therapeutic range. The referring physician was notified about this case and he notified the patient about the treatment deviation."
Notified R3DO (Stoedter) and NMSS Events Notification group 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. |
| Agreement State | Event Number: 51641 | Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: MISTRAS GROUP, INC.
Region: 4
City: GEISMAR State: LA
County:
License #: LA-10986-L01
Agreement: Y
Docket:
NRC Notified By: JOSEPH NOBLE
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 01/07/2016
Notification Time: 16:45 [ET]
Event Date: 12/19/2015
Event Time: [CST]
Last Update Date: 01/07/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
VIVIAN CAMPBELL (R4DO)
NMSS_EVENTS_NOTIFICA (EMAI)
| Event Text AGREEMENT STATE REPORT - HUMAN ERROR PREVENTS A RADIOGRAPHY SOURCE FROM RETRACTING
The following report was received via e-mail:
"On December 19, 2015, a crew from Mistras was working at a temporary jobsite [Donaldsonville, LA] located at CF Industries. The crew set up 2 mR boundaries for the duration of the 'shots'/exposures. The crew cranked out the source and made the exposure. When the crew tried to retract the source into the shielded position, [the source] would not [retract] because the guide tube was improperly connected to the exposure device. The source assembly remained out of the shielded position. When it was determined the source could not be retracted, immediately the area was cleared and the boundaries were reestablished for the 2 mR/hr distance.
"The lead radiographer contacted the RSO, and received instructions on how to secure/shield the area from potential/unnecessary exposures. The unshielded source and incident duration was from 1.5 hours to 2 hours.
"The initial notice to the Department [LA Department of Environmental Quality] was made at approximately 1257 CST after the source was secured in the shielded position. The RSO did the actual retrieval and securing of the source. His time in the radiation field was approximately 30 to 40 minutes. He used the standards of time, distance and shielding to protect himself. His direct read pocket dosimeter reading was approximately 60 mR. The crew members pocket dosimeter readings were 50 mR and 20 mR.
"The exposure device and associated equipment (crank out control and source guide tube) were SPEC 150 exposure device S/N 1106 and a SPEC G-60 source. The source was 61 Ci of Ir-192. The equipment was evaluated and passed the quality assurance requirements. The radiography staff was reinstructed in the Mistras' Operation and Equipment Manual. Specifically the setup and equipment assembly, connecting and cranking out of the source and operating in potentially occupied areas."
Louisiana Report: LA-150023 |
| Power Reactor | Event Number: 51654 | Facility: SEQUOYAH
Region: 2 State: TN
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MATT JUNGELS
HQ OPS Officer: JEFF HERRERA | Notification Date: 01/14/2016
Notification Time: 16:07 [ET]
Event Date: 01/14/2016
Event Time: 11:33 [EST]
Last Update Date: 01/14/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
| Person (Organization):
DEBORAH SEYMOUR (R2DO)
FFD GROUP (EMAI)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Hot Standby | 0 | Hot Standby | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text FITNESS FOR DUTY - NON LICENSED SUPERVISORY EMPLOYEE TESTED POSITIVE
A non-licensed supervisory employee tested positive for alcohol during a random fitness for duty test. The individual's plant access has been denied.
The NRC Resident Inspector has been notified. |
| Power Reactor | Event Number: 51655 | Facility: DIABLO CANYON
Region: 4 State: CA
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOHN CLIPPERTON
HQ OPS Officer: JOHN SHOEMAKER | Notification Date: 01/14/2016
Notification Time: 18:10 [ET]
Event Date: 01/14/2016
Event Time: 14:43 [PST]
Last Update Date: 01/14/2016 | Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
RAY KELLAR (R4DO)
M DAPAS (RA)
SCOTT MORRIS (NRR)
M EVANS (NRR)
B HOLIAN (NSIR)
BERNARD STAPLETON (IRD)
DENNIS ALLSTON (ILTA)
J KOZAL (R4)
|
| 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 NOTIFICATION OF UNUSUAL EVENT - SECURITY CONDITION THAT DOES NOT INVOLVE HOSTILE ACTION
A security condition that does not involve a hostile action was reported by the Diablo Canyon security watch commander.
At 1443 PST on 1/14/16, Diablo Canyon declared an Unusual Event, due to an unauthorized person in the Owner Controlled Area. Site Security was dispatched and assistance was requested from the local Sheriff's Department. The individual was apprehended.
At 1602 PST on 1/14/16, Diablo Canyon terminated the Unusual Event after the individual was apprehended and placed in custody of local law enforcement. Diablo Canyon remained at 100 percent power for the duration of the event. No radiological release has occurred and all radiation levels are normal on both units. A press release is planned.
The licensee has notified the NRC Resident Inspector and state and local authorities.
Notified FEDS (DHS SWO, FEMA Ops, DHS NICC, and NuclearSSA via email.) | |