| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
02/13/2015 - 02/17/2015 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 50786 | Facility: GRAND GULF
Region: 4 State: MS
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: RYAN MEYER
HQ OPS Officer: DANIEL MILLS | Notification Date: 02/04/2015
Notification Time: 17:57 [ET]
Event Date: 02/04/2015
Event Time: 09:34 [CST]
Last Update Date: 02/13/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
GEOFFREY MILLER (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text CONTROL ROOM VENTILATION INOPERABLE DUE TO MISPOSITIONED VENTILATION INSPECTION PORT
"At 0934 CST hours on Wednesday, February 4, 2015 during a housekeeping inspection, an inspection port (18x18 inch opening) on the Control Room Fresh Air (CRFA) System was discovered open. The opening of the inspection port resulted in the loss of safety function for both trains of CRFA as a loss of control room envelope boundary.
"The cause of the inspection port being open is currently unknown and is under investigation. The Control Room was notified and an operator immediately secured the inspection port returning both trains of CRFA to operable status.
"The reactor was at approximately 100 percent power at the time of the discovery of the event. The Limiting Condition for Operation (LCO) Technical Specification 3.7.3, Control Room Fresh Air (CRFA) System, is two CRFA subsystems shall be OPERABLE. This Technical Specification is applicable in MODES 1, 2, and 3, and during operations with a potential for draining the reactor vessel.
"This condition is reportable as an 8 hour call in accordance with 10 CFR 50.72(b)(3)(v)."
The licensee has notified the NRC Resident Inspector.
* * * RETRACTION AT 1520 EST ON 02/13/15 FROM PAUL SALGADO TO S. SANDIN * * *
"Grand Gulf Nuclear Station is retracting this event notification based on the following: Regulatory Guidance in NUREG-1022, Revision 3, Event Reporting Guidelines 10 CFR 50.72 and 50.73, Sections 2.8 Retraction and Cancellation of Event Reporting and 4.2.3 ENS Notification Retraction.
"Once the inspection port was discovered open, the control room was notified and an operator immediately secured the inspection port. After the port was secured, detailed engineering calculations were initiated to analyze the situation. Due to the time needed to perform the detailed calculations versus the time required for notification (8 hours) a conservative decision was made to report the event based on knowledge at the time of the event and rough calculations. Subsequently detailed calculations were performed to evaluate and support system operability evaluation. The calculations evaluated dose sensitivity analysis for the increased Control Room in-leakage due to the open inspection port. A test determined the control building in-leakage to be 585 cfm, the in-leakage from other sources to be 15 cfm, and the calculation determined the flow rate through the opening to be 1245 cfm. This total in-leakage rate of 1845 cfm is below the maximum allowable control building in-leakage of 2000 cfm. The calculation performed a sensitivity analysis with recent ILRT results applied and concluded that 4200 cfm in-leakage is permissible to maintain within the limits of 10CFR50.67. By subtracting the measured in-leakage assuming all ports closed ( 585+15= 600 cfm) from the in-leakage permissible to maintain within the limits of 10CFR50.67 (4200 cfm), there Is a resulting margin of 3600 cfm.
"Technical Specification 3.7.3, Control Room Fresh Air (CRFA) System, requires TWO CRFA subsystems shall be OPERABLE, and the calculations show that the CFRA was OPERABLE. The calculations lead to the conclusion that the system would have fulfilled its safety function needed to mitigate the consequences of an accident.
"Therefore, this event is not an 8-hour notification under 50.72(b)(3)(v)."
The licensee informed the NRC Resident Inspector. Notified R4DO (Allen). |
| Non-Agreement State | Event Number: 50788 | Rep Org: HELLER AND JOHNSEN
Licensee: HELLER AND JOHNSEN
Region: 1
City: STRATFORD State: CT
County:
License #: 06-30033-01
Agreement: N
Docket:
NRC Notified By: JUAN BEDOYA
HQ OPS Officer: DANIEL MILLS | Notification Date: 02/05/2015
Notification Time: 14:00 [ET]
Event Date: 01/16/2015
Event Time: 12:00 [EST]
Last Update Date: 02/05/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
| Person (Organization):
ANNE DeFRANCISCO (R1DO)
DENNIS ALLSTON (ILTA)
NMSS_EVENTS_NOTIFICA (EMAI)
|
| This material event contains a "Less than Cat 3 " level of radioactive material. | Event Text MOISTURE DENSITY GAUGE IN TRUNK OF STOLEN CAR
The licensee reported that a technician had a Troxler moisture/density gauge, Model #3430 (Serial #19531), locked in the trunk of his car. The technician's brother took the car for a "joy ride" and the car was reported to the Fairfield police as stolen. The brother was pulled over by the police roughly 1/2 hour later. The gauge was recovered undamaged and still locked in the trunk of the car. The licensee reported that they lost possession of the gauge for no more than 1/2 hour and that the brother probably did not intend to steal the gauge. The gauge contains 27mCi of Cesium 137 and 132 mCi of Americium 241. The Fairfield police, bomb squad, and the local FBI responded to the event.
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 |
| Non-Agreement State | Event Number: 50793 | Rep Org: MCLAREN MEDICAL CENTER - BAY REGION
Licensee: MCLAREN MEDICAL CENTER - BAY REGION
Region: 3
City: BAY CITY State: MI
County:
License #: 21-18585-01
Agreement: N
Docket:
NRC Notified By: MATT BUCZEK
HQ OPS Officer: DANIEL MILLS | Notification Date: 02/06/2015
Notification Time: 18:39 [ET]
Event Date: 02/06/2015
Event Time: 08:00 [EST]
Last Update Date: 02/06/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
35.3045(a)(1) - DOSE <> PRESCRIBED DOSAGE
| Person (Organization):
LAURA KOZAK (R3DO)
NMSS_EVENTS_NOTIFIC (EMAI)
JAMES RUBENSTONE (NMSS)
| Event Text MEDICAL MISADMINISTRATION DURING BRACHYTHERAPY
A patient underwent brachytherapy utilizing a vaginal cylinder. The prescribed dose was 5.5 Gray (550 rem) to the target volume, but due to mispositioning of the source, the target volume received only a negligible dose. The source was positioned such that the skin received a dose of up to 2.5 Gray (250 rem). The patient and prescribing physician have been notified. The patient is unlikely to suffer any permanent effects, but could experience mild erythema. The patient has been scheduled for an additional treatment. The hospital will take steps to prevent a future recurrence before the next patient is treated.
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. |
| Power Reactor | Event Number: 50796 | Facility: SUMMER
Region: 2 State: SC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP,[2] W-AP1000,[3] W-AP1000
NRC Notified By: WILLIAM TAYLOR
HQ OPS Officer: JEFF ROTTON | Notification Date: 02/08/2015
Notification Time: 08:12 [ET]
Event Date: 02/07/2015
Event Time: 08:48 [EST]
Last Update Date: 02/16/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
ROBERT HAAG (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 | Event Text OFFSITE NOTIFICATION TO OCCUPATIONAL SAFETY AND HEALTH ADMINISTRATION (OSHA)
"At approximately 0848 [EST] on February 7, 2015, a contract employee was found unresponsive at a VC Summer Unit 1 facility outside the Owner Controlled Area. The VC Summer Medical Emergency Response Team responded to the scene and provided assistance until offsite medical personnel arrived. Emergency Medical Services arrived on the scene and transported the individual to a local area hospital. VC Summer has reported this to OSHA and is reporting this to the NRC in accordance with 10 CFR 50.72 (b)(2)(xi).
"The NRC Resident Inspector has been notified."
* * * UPDATE AT 1300 EST ON 02/16/15 FROM MICHAEL MOORE TO S. SANDIN * * *
"At 0935 EST, on February 16, 2015 SCE&G notified OSHA that the contract employee had passed away. This update also corrects the second sentence of the initial notification that station personnel versus the Medical Emergency Response Team responded to the scene.
"The NRC Resident Inspector has been notified."
Notified R2DO (Nease). |
| Power Reactor | Event Number: 50817 | Facility: SEABROOK
Region: 1 State: NH
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: SHAWN MILLER
HQ OPS Officer: HOWIE CROUCH | Notification Date: 02/13/2015
Notification Time: 08:31 [ET]
Event Date: 02/12/2015
Event Time: 13:30 [EST]
Last Update Date: 02/13/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
| Person (Organization):
RAY POWELL (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text VIOLATION OF FITNESS FOR DUTY POLICY
"This event is being reported pursuant to the requirements of 10 CFR 26.719 because a non-licensed licensee supervisor violated the fitness for duty policy. The individual's access has been terminated.
"The Licensee has notified the NRC Resident Inspectors." |
| Power Reactor | Event Number: 50822 | Facility: COOK
Region: 3 State: MI
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: RICHARD HARRIS
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 02/13/2015
Notification Time: 15:55 [ET]
Event Date: 02/13/2015
Event Time: 13:15 [EST]
Last Update Date: 02/13/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
PATTY PELKE (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 | Y | 100 | Power Operation | 100 | Power Operation | Event Text OFFSITE NOTIFICATION TO MICHIGAN OSHA
"At 1123 EST on 2/13/2015, an emergency medical report was received in both unit's Control Rooms that an individual was having a personal medical issue outside the protected area. Onsite Emergency Medical personnel were dispatched to the scene. Off-site medical assistance was immediately requested. CPR was administered and the individual was transferred by off-site medical ambulance service to a local hospital.
"The Operations Shift Manager received confirmation of a fatality at 1315 EST on 2/13/2015. Notification was made to the Michigan Occupational Safety and Health Administration (MIOSHA).
"Both Units remain at 100% power. This Event Notification is being made due to the fatality and notification to a government agency.
"The NRC Resident Inspector has been notified."
The individual was at the workout facility when this incident occurred. |
| Power Reactor | Event Number: 50826 | Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [1] [2] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: BRIAN JOHNSON
HQ OPS Officer: JOHN SHOEMAKER | Notification Date: 02/17/2015
Notification Time: 00:13 [ET]
Event Date: 02/16/2015
Event Time: 16:44 [CST]
Last Update Date: 02/17/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
PATTY PELKE (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 | Y | 100 | Power Operation | 100 | Power Operation | Event Text CONTROL ROOM SPECIAL VENT BOUNDARY INOPERABLE
"On February 16, 2015, at 1644 [CST], Prairie Island Nuclear Generating Plant (PINGP) Unit 1 and Unit 2 Control Room Envelope Boundary was declared inoperable when it was discovered that Door 158, Auxiliary Building to 122 Control Room Chiller Room, would not latch. Both trains of Control Room Special Ventilation were declared inoperable and Tech Spec LCO 3.7.10 Condition B was entered. In addition, with the Control Room Envelope Boundary inoperable, Tech Spec 3.7.11 Condition E was required to be entered due to both Control Room Chillers inoperable. The required actions of Tech Spec 3.7.11 Condition E required both Units to enter Tech Spec LCO 3.0.3. As a mitigating action, station personnel were dispatched to secure Door 158. This condition was corrected on February 16, 2015, at 1709 [CST] when the deadbolt was engaged to maintain Door 158 closed. Tech Specs 3.7.10 Condition B, 3.7.11 Condition E, and 3.0.3 were all exited at 1709 [CST] February 16, 2015.
"This condition is reportable under 10 CFR 50.72 (b)(3)(v)(D), Event or Condition that Could Have Prevented Fulfillment of a Safety Function to Mitigate the Consequences of an Accident.
"Based on immediate implementation of mitigating actions and restoration of the Control Room Envelope, the protection of the health and safety of the public was not affected by this issue.
"This event has been entered into the sites Corrective Action Program.
"The licensee has notified the NRC Senior Resident Inspector." | |