| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
05/23/2013 - 05/24/2013 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 49035 | Rep Org: COLORADO DEPT OF HEALTH
Licensee: UNKNOWN
Region: 4
City: GRAND JUNCTION State: CO
County:
License #:
Agreement: Y
Docket:
NRC Notified By: ED STROUD
HQ OPS Officer: PETE SNYDER | Notification Date: 05/15/2013
Notification Time: 13:49 [ET]
Event Date: 04/24/2013
Event Time: [MDT]
Last Update Date: 05/15/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
MICHAEL HAY (R4DO)
FSME EVENT RESOURCE (EMAI)
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text AGREEMENT STATE REPORT - FOUND RADIUM 226 SOURCE
"On April 24, 2013, The Colorado Department of Public Health and Environment [Department] received notification from the Mesa County Landfill located in Grand Junction, Colorado, that a load of trash had alarmed the gate monitor. The roll-off in question came from a residential spring clean-up event sponsored by the city of Grand Junction.
"That same day, a member of the Department responded to the alarm and the roll-off was moved to a secure location after an initial radiation survey on the outside of the roll-off had been completed.
"On May 7, 2013, members of the Department examined the contents or the roll-off and a small section of plastic pipe (1 foot length) and a small source bound with tape were identified. It appeared that the source had been taped to the side of the plastic pipe at one time, and the word 'source' was written on the pipe. Using an Identifinder multi-channel analyzer, the isotope was identified as Ra-226.
"Dose rates were measured at greater than 200 millirem per hour on contact with the source (the limit of the inspector's instrument), and 10 millirem per hour at 1 foot. The dimensions of the source appeared to be approximately 3 mm by 2 cm. The source is currently stored in a secured location.
"The Department is conducting an investigation, and a press release is being issued to encourage anyone with information about the source to contact the Department."
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: 49036 | Facility: CATAWBA
Region: 2 State: SC
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: AARON MICHALSKI
HQ OPS Officer: VINCE KLCO | Notification Date: 05/15/2013
Notification Time: 15:00 [ET]
Event Date: 05/15/2013
Event Time: [EDT]
Last Update Date: 05/15/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(ii) - LOST/STOLEN LNM>10X
| Person (Organization):
JONATHAN BARTLEY (R2DO)
FSME RESOURCES (EMAI)
HAROLD CHERNOFF (NRR)
| | This material event contains a "Less than Cat 3" level of radioactive material. |
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text MISSING LICENSED MATERIAL
This is a non-emergency 30 day notification for missing licensed material. This event is reportable in accordance with 10CFR20.2201(a)(1)(ii).
On April 16, 2013, while performing the required semi-annual source leak check and inventory, Radiation Protection personnel could not locate the source label tag or cable for source RMC-0169 on radiation monitor 1EMF44H (This monitor has not been in use since 1995). The monitor's pre-amplifier box had been removed as well. 1EMH44H was inspected and the source was not found within the housing. A search was conducted for this missing source, however it could not be located. During the previous source leak check and inventory on October 4, 2012, the source was in its expected location.
Source RMC-0169 is a 200 milligram depleted uranium source. The total original activity of the source was 9.998E-02 microCuries (3.03E-02 micro curies; U-234; 1.98E-03 microCuries; U-235, 6.77E-02 microCuries; U-238). The reportable limit for U-234 (the shortest-lived isotope in the source is U-234 with a half-live of 2.46E+05 years) is 0.01 microCuries per 10CFR20, Appendix C. Based on the activity of U-234 present in the source of 0.03 microCuries, this 30 day phone notification to the NRC is being provided pursuant to 10CFR22.2201(a)(1)(ii).
The external dose to an individual from this source is negligible due to the small quantity and the type of material involved. Therefore, this event has no adverse effect upon the health and safety of employees or the public.
The required written report pursuant to 10CFR20.2201(b)(1) will be provided to the NRC within 30 days of the telephone notification.
The NRC Resident Inspector has been notified.
The licensee with notify State and local authorities.
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 |
| !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Agreement State | Event Number: 49037 | Rep Org: NV DIV OF RAD HEALTH
Licensee: ST. MARY'S REGIONAL MEDICAL CENTER
Region: 4
City: RENO State: NV
County:
License #: 16-12-0244-02
Agreement: Y
Docket:
NRC Notified By: SNEHA RAVIKUMAR
HQ OPS Officer: PETE SNYDER | Notification Date: 05/15/2013
Notification Time: 16:54 [ET]
Event Date: 05/14/2013
Event Time: 09:45 [PDT]
Last Update Date: 05/16/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
MICHAEL HAY (R4DO)
FSME EVENTS RESOURCE (EMAI)
| Event Text AGREEMENT STATE REPORT - WRONG DOSE ADMINISTERED TO PATIENT
The following information was obtained from the State of Nevada via email:
"The patient was to undergo a HIDA [hepatobiliary] scan for abdominal pain (Tc-99m; 5mCi, abdomen), but given syringe for MDP [bone scan] (Tc-99m; 30mCi; bone). A wrong dose of Tc-99m (600% the prescribed dose) was administered to the patient due to human error.
"Corrective action: Better training in cross-checking and confirming patient identity with prescribed dose information."
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.
Item Number: NV130006
* * * RETRACTION FROM SNEHA RAVIKUMAR VIA E-MAIL ON 5/16/13 AT 1329 EDT * * *
"This is with regard to the wrong dose administration that was reported yesterday. [The State of Nevada] heard back from the RSO regarding the Effective Dose Equivalent:
"What should have been administered was 5 mCi of HIDA (Mebrofenin) = (3E-02) x 5 rem = 0.15 rem.
"What was administered was 30 mCi of MDP = (2E-02) x 30 rem = 0.60 rem.
"So, this would not be reportable."
Notified R4DO (Walker) and FSME Events Resource via E-mail. |
| Agreement State | Event Number: 49040 | Rep Org: VIRGINIA RAD MATERIALS PROGRAM
Licensee: HONEYWELL RESINS & CHEMICALS LLC
Region: 1
City: CHESTER State: VA
County:
License #: 041-344-2
Agreement: Y
Docket:
NRC Notified By: ASFAW FENTA
HQ OPS Officer: DONALD NORWOOD | Notification Date: 05/16/2013
Notification Time: 10:28 [ET]
Event Date: 05/15/2013
Event Time: [EDT]
Last Update Date: 05/16/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
DAN SCHROEDER (R1DO)
FSME EVENTS RESOURCE (E-MA)
| Event Text FIXED GAUGE SHUTTER HARD TO OPEN
The following information was submitted by the Commonwealth of Virginia via fax:
"On May 15, 2013, the licensee reported that the shutter of one of its fixed gauges was not 'functioning per the design.' The problem was detected during the periodic shutter checks on May 15, 2013. The shutter could be closed but needed strong force to open it. The gauge is a Ronan Engineering Company, Model SA1-F37, Serial number M-2232. The gauge contains 50 mCi of Cs-137 as of the manufacturing date (remaining activity as of the incident date is 34.3 mCi).
"Ronan Engineering Company was contacted and a schedule has been arranged for shutter repair.
"A radiation survey was performed by the licensee and found to be within design parameters and regulatory limits. There are no public health or safety issues involved. The Virginia Radioactive Material Program will follow up with the licensee."
Virginia Event Report ID: VA-13-005 |
| Agreement State | Event Number: 49041 | Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: NON-DESTRUCTIVE INSPECTION CORPORATION
Region: 4
City: LAKE JACKSON State: TX
County:
License #: 02712
Agreement: Y
Docket:
NRC Notified By: KAREN BLANCHARD
HQ OPS Officer: HOWIE CROUCH | Notification Date: 05/16/2013
Notification Time: 12:50 [ET]
Event Date: 05/15/2013
Event Time: [CDT]
Last Update Date: 05/16/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
WAYNE WALKER (R4DO)
FSME EVENTS RESOURCE (EMAI)
| Event Text TEXAS AGREEMENT STATE REPORT - BROKEN RADIOGRAPHY CAMERA DRIVE CABLE
The following information was obtained from the State of Texas via email:
"On May 15, 2013, the licensee reported that one of its radiography teams had been unable to retract an iridium-192 source back into a QSA Model 880 radiography camera at a temporary field site in Galena Park, Texas. The licensee's RSO and a supervisor responded to the site.
"The RSO covered the collimator containing the source with lead shot bags then an individual authorized to perform source retrieval responded and secured the source. The pocket dosimeter readings for the three were: RSO received 60 millirem; the supervisor received 50 millirem; and the individual performing source retrieval received 40 millirem.
"The licensee reported that the drive cable had broken right behind the ball. No member of the public received any exposure as a result of this event. The source, camera, and equipment will be taken to the licensee's facility and the licensee will contact the manufacturer.
"Further information will be provided as it is obtained in accordance with SA-300.
"Radiography camera: QSA Model 880, SN: 2735. Source SN: 91360B"
Texas Incident # I-9078 |
| Agreement State | Event Number: 49044 | Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: MISTRAS GROUP INC
Region: 4
City: DEER PARK State: TX
County:
License #: 06369
Agreement: Y
Docket:
NRC Notified By: KAREN BLANCHARD
HQ OPS Officer: JOHN SHOEMAKER | Notification Date: 05/16/2013
Notification Time: 16:47 [ET]
Event Date: 05/14/2013
Event Time: [CDT]
Last Update Date: 05/16/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
WAYNE WALKER (R4DO)
FSME EVENTS RESOURCE (EMAI)
| Event Text AGREEMENT STATE REPORT - UNABLE TO RETRACT SOURCE INTO RADIOGRAPHY CAMERA
The following information was obtained from the State of Texas via E-mail:
"On May 15, 2013, the licensee's Radiation Safety Officer (RSO) reported to the Agency [Texas Department of State Health Services] that on May 14, 2013, one of its radiography crews had been unable to retract the source back into the QSA Model 880 camera they were using. The radiography crew had dropped and damaged the crank assembly when it was moving the equipment between shots. The crew apparently failed to thoroughly check the crank assembly prior to the next shot. Following the next shot, the source could not be retracted. The RSO was notified and he and another licensee employee, with assistance from the radiographers, performed the source retrieval (the camera and equipment had to be lowered to the ground from 40 feet inside a tank where the radiography was being performed in order to retrieve the source). The RSO reported that the connector at the end of the cable, which connects the cable to the pigtail, had come off of the cable. [The connector] was apparently damaged in the crank assembly accident. Readings from the pocket dosimeters were: RSO received 240 mrem; other employee performing source retrieval received 40 mrem; and, the 3 [other] radiography crew members received 300 mrem, 110 mrem, and 80 mrem, respectively. No member of the public received any exposure from this event. Further information will be provided as it is obtained, per SA-300.
"Radiography Camera: QSA Model 880, SN: D11097, Source: SN: 93674B"
Texas Incident #: I-9079 |
| Agreement State | Event Number: 49046 | Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: THERMO PROCESS INSTRUMENTS LP
Region: 4
City: SUGAR LAND State: TX
County:
License #: 03524
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: JOHN SHOEMAKER | Notification Date: 05/16/2013
Notification Time: 17:56 [ET]
Event Date: 05/16/2013
Event Time: 15:25 [CDT]
Last Update Date: 05/16/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
WAYNE WALKER (R4DO)
FSME EVENTS RESOURCE (EMAI)
DAN SCHROEDER (R1DO)
| Event Text AGREEMENT STATE REPORT - CONTAMINATION EVENT REQUIRES AREA TO BE RESTRICTED FOR GREATER THAN 24 HOURS
The following information was obtained from the State of Texas via E-mail:
"On May 16, 2013 at 1525 [CDT], the licensee contacted the Agency [Texas Department of State Health Services] to report a contamination event which required access to an area to be restricted for more than 24 hours due to an unplanned contamination event. The licensee had received a drum containing 18 nuclear gauges from a facility licensed in the State of North Carolina (NC). The Texas licensee was to dismantle the gauges and dispose of the sources. The Texas licensee stated the gauges had been leak tested by the NC licensee and the leak test results were below regulatory levels. The Texas licensee stated they performed a contamination survey of the drum before they began removing the gauges. A licensee's worker removed the first gauge in preparation to remove the source. The gauge was a Berthold model LB 7400 gauge containing a Cs-137 source. When the worker opened the shutter of the gauge to remove the source, they found a piece of lead inside the gauge cavity between the gauge shutter and the source. As the worker removed the piece of lead they noted the background radiation readings where increasing. The worker stopped work and notified his supervisor. A contamination survey found that the workers hands, shirt sleeves, the table top, the floor in the immediate work area, and the worker's personal dosimetry were contaminated. The workers contaminated shirt and dosimetry were removed and his hands were decontaminated. The worker's face was surveyed for contamination, none was detected. The licensee's Radiation Safety Officer (RSO) stated that worker was decontaminated within 15 minutes of the event occurring. The RSO stated that the individual had not exceeded any exposure limits based on their electronic dosimeter reading. The licensee attempted to decontaminate the table top and the floor in the work area, but some areas remain contaminated. Access to the area remains restricted. The Texas licensee has contacted the NC licensee and notified them of the event. Additional information will be provided as it is received in accordance with SA-300."
Texas Incident #: I-9080 |
| !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 49047 | Facility: MILLSTONE
Region: 1 State: CT
Unit: [ ] [ ] [3]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: GERALD BAKER
HQ OPS Officer: HOWIE CROUCH | Notification Date: 05/17/2013
Notification Time: 12:05 [ET]
Event Date: 05/17/2013
Event Time: 04:39 [EDT]
Last Update Date: 05/23/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
DAN SCHROEDER (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | N | 0 | Hot Standby | 0 | Hot Standby | Event Text UNANALYZED CONDITION FOR REACTOR COOLANT SYSTEM TEMPERATURE BELOW REQUIRED VALUE
"On May 17, 2013 at 0439 EDT, with the unit in Mode 3, operators identified RCS temperature decreased below 551 deg. F with the reactor trip breakers closed. The condition existed for approximately one hour after which operators identified this was below the procedurally required value identified to support power range nuclear instrumentation trip operability. The condition was then immediately corrected.
"The plant remains stable in Mode 3.
"This condition is reportable pursuant to 10 CFR 50.72(b)(3)(ii)(B) for an unanalyzed condition. The NRC Senior Resident Inspector has been notified."
The reactor trip breakers were closed to support rod testing at the time this event occurred. RCS temperature was decreasing due to Terry turbine testing which was being performed at the same time. The reactor trip breakers were opened when the operators identified RCS temperature below 551 degrees. The RCS temperature was returned to above 551 degrees. This temperature limit is specified in Millstone 3 FSAR section 15.4.1, "Uncontrolled rod cluster control assembly bank withdrawal from a subcritical or low power startup condition".
The licensee notified state and local authorities.
* * * RETRACTION FROM WILLIAM BARTRON TO DONALD NORWOOD AT 1053 EDT ON 5/23/2013 * * *
"The purpose of this call is to retract the report made on May 17, 2013, Event Number 49047.
"Upon further review, the condition in which Reactor Coolant System (RCS) temperature decreased below a procedural limit while in Mode 3 did not result in an unanalyzed condition. Engineers verified that RCS boron concentration was sufficiently high that criticality could not have occurred during any inadvertent control rod withdrawal. The details of the engineering review have been provided to the NRC Senior Resident Inspector."
Notified R1DO (Gray). |
| Power Reactor | Event Number: 49061 | Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: DAVID NOYES
HQ OPS Officer: DONG HWA PARK | Notification Date: 05/23/2013
Notification Time: 12:42 [ET]
Event Date: 05/23/2013
Event Time: 04:55 [EDT]
Last Update Date: 05/23/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
MEL GRAY (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 2 | Startup | 2 | Startup | Event Text PRIMARY CONTAINMENT DECLARED INOPERABLE DURING HPCI TESTING
"At 0455 hours on Thursday, May 23, 2013, with Pilgrim Station in the Startup/Hot Standby Mode and reactor coolant pressure approximately 550 psig, primary containment was declared inoperable due to a leak on the High Pressure Coolant Injection system (HPCI) turbine exhaust line while performing the HPCI system flow rate test. Power ascension was suspended pending investigation and repair. Repair plans to restore system integrity are in progress.
"The plant is in a safe condition and plant personnel are investigating the cause. The Resident Inspector has been informed of this notification. This notification is being made in accordance with 10 CFR 50.72(b)(3)(v)(C) and (D). The licensee will notify the Massachusetts Emergency Management Agency (MEMA)."
The licensee has entered Technical Specification 3.7.A.2 to be in cold shutdown within 24 hours. |
| Power Reactor | Event Number: 49062 | Facility: COOPER
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: NATHAN L. BEGER
HQ OPS Officer: CHARLES TEAL | Notification Date: 05/23/2013
Notification Time: 15:45 [ET]
Event Date: 05/23/2013
Event Time: 10:19 [CDT]
Last Update Date: 05/23/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
NEIL OKEEFE (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 TEMPORARY LOSS OF METEOROLOGICAL MONITORING SYSTEM DURING PLANNED MAINTENANCE
"At 1019 CDT, AC power was removed from the site meteorological monitoring system (MET) equipment for planned maintenance in order to remove abandoned equipment left in place since installing the new meteorological system in October 2012. Removing AC power was not expected to have an effect since all MET information would continue to be available due to an 8-hour battery backup system installed at the meteorological tower. However, when power was removed, all onsite meteorological data was lost to the control room via the Plant Management Information System (PMIS). PMIS is the only display of local direct meteorological conditions available. Subsequently, [Cooper Nuclear Station] CNS determined the interface between MET system and PMIS was not powered from the 8 hour MET battery backup system which accounted for the lost MET indication. CNS corrected the condition and restored meteorological data to the control room via the PMIS system at 1219 CDT.
"Site backup assessment capability relies on Meteorological model estimates from the National Weather Service out of Valley, Nebraska or on default values derived from historical local weather patterns. Since there was no direct information of site meteorological conditions during the period of lost power, CNS considered this to be a major loss of assessment capability and reportable under 10CFR50.72(b)(3)(xiii)."
The NRC Resident Inspector has been informed. |
| Power Reactor | Event Number: 49064 | Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: DAVID NOYES
HQ OPS Officer: CHARLES TEAL | Notification Date: 05/23/2013
Notification Time: 18:07 [ET]
Event Date: 05/23/2013
Event Time: 10:50 [EDT]
Last Update Date: 05/23/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
MEL GRAY (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 2 | Startup | 2 | Startup | Event Text HPCI DECLARED INOPERABLE DURING POST MAINTENANCE TESTING
"At 1050 hours on Thursday, May 23, 2013, with Pilgrim Station in the Startup/Hot Standby Mode and with the reactor coolant pressure at approximately 525 psig, the High Pressure Coolant Injection (HPCI) system was declared inoperable. The HPCI system was being operated in accordance with plant procedures to complete post maintenance test requirements. The flow controller could not achieve required system flow rates with the flow controller in the automatic mode. Plans to restore the automatic flow control capability are in progress.
"The plant is in a safe condition and plant personnel are investigating the cause.
"The [NRC] Resident Inspector has been informed of this notification.
"The licensee will notify the Massachusetts Emergency Management Agency (MEMA)." |
| Power Reactor | Event Number: 49065 | Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: MARK JENKINS
HQ OPS Officer: DONG HWA PARK | Notification Date: 05/23/2013
Notification Time: 18:25 [ET]
Event Date: 05/23/2013
Event Time: 14:16 [CDT]
Last Update Date: 05/23/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
| Person (Organization):
NEIL OKEEFE (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 FITNESS-FOR-DUTY REPORT INVOLVING A NON-LICENSED SUPERVISOR TESTING POSITIVE FOR ALCOHOL
A non-licensed, supervisory employee had a confirmed positive for alcohol during a random fitness-for-duty test. The employee's access to the plant has been terminated.
The licensee has notified the NRC Resident Inspector. | |