| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
05/01/2014 - 05/02/2014 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 50050 | Rep Org: KANSAS DEPT OF HEALTH & ENVIRONMENT
Licensee: IRISNDT
Region: 4
City: McPherson State: KS
County:
License #: 21-B982
Agreement: Y
Docket:
NRC Notified By: TOM CONLEY
HQ OPS Officer: DANIEL MILLS | Notification Date: 04/23/2014
Notification Time: 09:46 [ET]
Event Date: 04/22/2014
Event Time: [CDT]
Last Update Date: 04/23/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
RAY AZUA (R4DO)
FSME EVENTS RESOURCE (EMAI)
| Event Text AGREEMENT STATE REPORT - RADIOGRAPHY SOURCE HANG-UP
The following was received from the State of Kansas via fax:
"Today [on] 4/22/14, [the] x-ray radiography crew had a source hang-up, at the NCRA plant in McPherson, Kansas, at approximately 0930 CDT. [The] radiography crew performed their operational and emergency procedures very well. A 35 curie Ir-192 source hung up in the source guide tube. [The crew] made the necessary adjustments to their boundaries, kept watch over them, allowed no one to enter, notified [the crew supervisor] and the Kansas RSO. They re-adjusted the crankouts and pulled them to straighten out the cranks and guide tube, and were able to retract the source into the device with one attempt, and were successful. There was no disconnect or anyone exposed to radiation levels above regulatory limits.
"Notification of the incident was given to the plant safety coordinators at the time of the incident, and they remained at distance to avoid exposure, the full time of the incident lasted approximately 10-15 minutes from the initial determination of a stuck source to retraction of the source into the device."
Three monitored IRISNDT staff were onsite and they watched over the boundaries while the retraction was completed. After the incident, all IRISNDT staff read their Instadose film badges and got readings from their personal dosimeters ranging from 1.2 to 3.8 mRem.
Kansas incident # KS140007 |
| Agreement State | Event Number: 50053 | Rep Org: ARIZONA RADIATION REGULATORY AGENCY
Licensee: ALPHA GEOTECHNICAL AND MATERIALS
Region: 4
City: TEMPE State: AZ
County:
License #: AZ 7-444
Agreement: Y
Docket:
NRC Notified By: AUBREY GODWIN
HQ OPS Officer: CHARLES TEAL | Notification Date: 04/23/2014
Notification Time: 16:46 [ET]
Event Date: 04/22/2014
Event Time: 14:00 [MST]
Last Update Date: 04/23/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
RAY AZUA (R4DO)
FSME EVENT RESOURCE (EMAI)
|
| This material event contains a "Less than Cat 3 " level of radioactive material. | Event Text AGREEMENT STATE REPORT - LOST AND FOUND MOISTURE DENSITY GAUGE
The following was received from the State of Arizona via email:
"The Agency [State of Arizona] was informed by the Licensee at approximately 2:45 PM [MDT], April 22, 2014 that at approximately 2:00 PM a worker had lost a Campbell-Pacific Model MC-1, SN MD41007631 moisture density gauge off a pickup truck. The worker forgot to close the tailgate. The gauge contained 10 millicuries of Cesium 137 and 50 millicuries of Americium 241. At approximately 3:15 PM, the Mesa Fire Department reported they had possession of a gauge found on a freeway near the work site.
"A review of the situation confirmed that this was the lost source by the Licensee. The Agency [State of Arizona] has released the gauge to the Licensee for leak testing.
"The NRC, FBI and Governor's Offices are being notified of this event.
"The Agency continues to investigate this event."
First Notice: 14-008
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 |
| Agreement State | Event Number: 50057 | Rep Org: COLORADO DEPT OF HEALTH
Licensee: ANALYTICAL INSTRUMENT RECYCLE, INC.
Region: 4
City: GOLDEN State: CO
County:
License #: CO License No
Agreement: Y
Docket:
NRC Notified By: JAMES JARVIS
HQ OPS Officer: JOHN SHOEMAKER | Notification Date: 04/24/2014
Notification Time: 16:38 [ET]
Event Date: 02/05/2014
Event Time: [MDT]
Last Update Date: 04/24/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
RAY AZUA (R4DO)
FSME EVENTS RESOURCE (EMAI)
| Event Text AGREEMENT STATE REPORT - LEAKING GENERALLY LICENSED SOURCES
The following was received from the state of Colorado via email:
"On or after February 05, 2014, while working on a license renewal action, the Colorado Radiation Program was informed by the licensee that it had three (3) generally licensed electron capture detectors (ECDs), containing ~15-18 mCi of Ni-63 (each), that [leak tests] indicated contamination in excess of regulatory limits. The devices were determined to be manufactured by Hewlett-Packard and Agilent Technologies (model number verification is pending).
"The licensee reported that upon discovery, the devices were contained to minimize potential contamination spread. The area where gauges were used/handled was surveyed and determined to be free of contamination. The licensee indicated that the manufacturer was notified and the devices have been returned to the manufacturer for disposal.
"Further investigation by the Colorado Radiation Program is pending." |
| Power Reactor | Event Number: 50077 | Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: JOHN LAUDENBACH
HQ OPS Officer: CHARLES TEAL | Notification Date: 05/01/2014
Notification Time: 09:54 [ET]
Event Date: 05/01/2014
Event Time: 08:40 [CDT]
Last Update Date: 05/01/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
LAURA KOZAK (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 89 | Power Operation | 89 | Power Operation | Event Text SERVICE WATER RADIATION MONITOR TAKEN OUT OF SERVICE FOR PLANNED MAINTENANCE
"The Service Water Radiation Monitor will be removed from service to facilitate planned preventative maintenance. As a result, this represents a loss of emergency assessment capability under NUREG 1022 revision 3 specific to RU 1.2 and RA 1.2. The planned maintenance is expected to last 7 hours. During this time, the site Chemistry Department will perform sampling every thirty minutes per procedure. As a result of the sampling, reasonable assurance exists to monitor and detect rising radiation levels in order to protect the health and safety of the public.
"The NRC Resident Inspector has been informed." |
| Power Reactor | Event Number: 50078 | Facility: CALVERT CLIFFS
Region: 1 State: MD
Unit: [1] [ ] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: BOB MARTIN
HQ OPS Officer: JEFF ROTTON | Notification Date: 05/01/2014
Notification Time: 11:50 [ET]
Event Date: 05/01/2014
Event Time: 10:16 [EDT]
Last Update Date: 05/01/2014 | 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):
WILLIAM COOK (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | A/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text AUTOMATIC REACTOR TRIP
"At 1016 [EDT] CCNPP [Calvert Cliffs Nuclear Power Plant] Unit 1 automatically tripped due to an RPS actuation. Cause is under investigation. All safety functions are met with normal heat removal. Electric plant is in a normal lineup. No ESFAS [Engineered Safety Feature Actuation System] actuations have occurred."
Steam Generator atmospheric dump valves momentarily opened and then closed. There is no known steam generator tube leakage. All control rods fully inserted on the trip.
There was no impact on Unit 2 from this event.
The licensee notified the NRC Resident Inspector and provided a courtesy notification to the Calvert County Control Center. |
| Power Reactor | Event Number: 50079 | Facility: BEAVER VALLEY
Region: 1 State: PA
Unit: [ ] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: MATT ENOS
HQ OPS Officer: JEFF ROTTON | Notification Date: 05/01/2014
Notification Time: 18:12 [ET]
Event Date: 05/01/2014
Event Time: 16:10 [EDT]
Last Update Date: 05/01/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
| Person (Organization):
WILLIAM COOK (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | N | 0 | Defueled | 0 | Defueled | Event Text DEGRADED CONDITION DISCOVERED ON REACTOR VESSEL HEAD CONTROL ROD DRIVE PENETRATION
"On 5/01/2014 during the Beaver Valley Power Station Unit No. 2 (BVPS-2) refueling outage, it was determined that the results of planned ultrasonic (UT) examinations performed on one of the 66 penetrations of the reactor vessel head would not meet the applicable acceptance criteria. This penetration will require repair prior to returning the vessel head to service. The indication was not through wall and there was no evidence of leakage based on inspections performed on the top of the reactor vessel head. The examinations were being performed to meet the requirements of 10CFR50.55a(g)(6)(ii)(D) and ASME Code Case N-729-1, to find potential flaws/indications well before they grow to a size that could potentially jeopardize the structural integrity of the reactor vessel head pressure boundary. Currently 52 of 66 penetrations have been examined, with 51 satisfactory. All of the penetrations will be examined during the current refueling outage.
"The plant is currently shutdown and in a mode undefined [Defueled] and the reactor vessel head is not currently installed. Repairs are currently being planned and will be completed prior to startup.
"This is reportable pursuant to 10CFR50.72(b)(3)(ii)(A) since the as found indications did not meet the applicable acceptance criteria referenced in ASME Code Case N-729-1 to remain in-service without repair.
"The NRC Resident Inspector has been notified." |
| Power Reactor | Event Number: 50080 | Facility: HATCH
Region: 2 State: GA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: JOHN SELLERS
HQ OPS Officer: JEFF ROTTON | Notification Date: 05/01/2014
Notification Time: 22:33 [ET]
Event Date: 05/01/2014
Event Time: 20:45 [EDT]
Last Update Date: 05/02/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
DAVID AYRES (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 LOSS OF HPCI OPERABILITY DUE TO WATER ACCUMULATION IN THE HPCI TURBINE
"While investigating a Unit 1 high pressure coolant injection (HPCI) room instrument sump level high alarm, condensation was observed dripping out around the HPCI turbine shaft gland seals. A steady stream of water was also observed coming out of the governor end gland seal along with a slight leak coming from the coupling end. Observation revealed that leakage through the 'closed' steam admission valve (1E41-F001) was apparently resulting in water accumulation in the HPCI turbine. A blown fuse that prevented the associated HPCI exhaust drain pot from draining in conjunction with the leakage by the steam admission valve was determined to be sufficient to impact HPCI operability. Required actions were taken in accordance with the Technical Specifications.
"Efforts are underway to determine the actions needed to restore the HPCI system to operable status."
The licensee has notified the NRC Resident Inspector.
* * * UPDATE FROM JOHN SELLERS TO CHARLES TEAL AT 0154 EDT ON 5/2/14 * * *
"HPCI has been restored to an Operable but degraded nonconforming condition. Fuses replaced and automatic functions restored. Leakage confirmed to not be excessive for this condition. Compensatory actions established. Restoration time 2345 EDT 5/1/14."
The licensee will notify the NRC Resident Inspector.
Notified R2DO (Ayers). | |