|
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
02/06/2015 - 02/09/2015
** EVENT NUMBERS **
|
| Agreement State |
Event Number: 50779 |
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: GILES ENGINEERING ASSOCIATES
Region: 4
City: ORANGE State: CA
County:
License #: 4592-30
Agreement: Y
Docket:
NRC Notified By: DONALD OESTERLE
HQ OPS Officer: CHARLES TEAL |
Notification Date: 01/30/2015
Notification Time: 15:42 [ET]
Event Date: 01/30/2015
Event Time: [PST]
Last Update Date: 01/30/2015 |
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE |
Person (Organization):
GEOFFREY MILLER (R4DO)
NMSS EVENTS NOTIFICA (EMAI)
MEXICO (FAX)
DARYL JOHNSON (ILTA) |
| This material event contains a "Less than Cat 3 " level of radioactive material. |
Event Text
AGREEMENT STATE REPORT - STOLEN MOISTURE DENSITY GAUGE
The following was received from the State of California via email:
"On January 30, 2015, a telephone report was made to the [California Department of Public Health] CDPH Director's office that a gauge had been stolen. The person making the report was difficult to understand, but the Director's office was able to ascertain the contact telephone number. Upon receiving notice of the call, a representative from [Radiologic Health Branch] (RHB) immediately called that telephone number (at approximately 1100 PST on January 30, 2015), and spoke with the RSO of Giles Engineering Associates, RML #4592-30. [The RSO] stated that a moisture/density gauge (CPN, MC-1DRP, serial #MD20506575 containing 0.370 GBq of Cs-137 and 1.85 GBq of Am-241) had been stolen from a transport vehicle in front of a Comfort Inn at 1185 Admiral Callahan Lane, Vallejo, CA. The authorized gauge user had left the radioactive gauge chained and locked in the back of his vehicle at approximately 0600 PST and went back inside the Comfort Inn to complete some paper work. When he returned to his vehicle at approximately 0625 PST to go to the worksite, [the authorized gauge user] noticed that the chains had been cut through and that the radioactive gauge had been removed from his vehicle. [The authorized gauge user] contacted the RSO of Giles Engineering Associates, who stated he had attempted to notify Local Law Enforcement officials in Vallejo to report the theft. [The RSO] was directed to fill out a report online as that was the policy of the Vallejo Police Department in regards to all theft cases not involving immediate threats to persons. When [the RSO] receives [the authorized user's] written report and the police report, he will forward them to RHB Brea. [The RSO] will utilize local papers in the Vallejo area to attempt to retrieve the stolen gauge. Additionally he will notify local vendors who service radioactive gauges to be alert for the serial number of the stolen gauge in case it turns up at any of their facilities."
CA 5010 #: 013015
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: 50780 |
Rep Org: NE DIV OF RADIOACTIVE MATERIALS
Licensee: OMAHA PUBLIC POWER DISTRICT
Region: 4
City: OMAHA State: NE
County:
License #: 01-39-04
Agreement: Y
Docket:
NRC Notified By: BRYAN MILLER
HQ OPS Officer: JEFF ROTTON |
Notification Date: 01/30/2015
Notification Time: 16:31 [ET]
Event Date: 01/30/2015
Event Time: 08:20 [CST]
Last Update Date: 02/05/2015 |
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE |
Person (Organization):
MICHAEL VASQUEZ (R4DO)
NMSS EVENTS NOTIFICA (EMAI) |
Event Text
AGREEMENT STATE REPORT - FIXED GAUGE SHUTTER FAILED TO CLOSE
While attempting to close the shutter on a Kay-Ray fixed gauge at a coal fired power plant located at 24th and Craig Street in Omaha, NE, the cable operating the shutter mechanism broke. The gauge contained 50 mCi of Cs-137. Plant operators manually closed the gauge shutter. There were no exposures to workers in the area.
The state will provide additional information when it is available.
* * * UPDATE FROM BRYAN MILLER TO JOHN SHOEMAKER AT 0908 EST ON 2/5/15 * * *
The following event update was received from the State of Nebraska via email:
"The Nebraska Department of Health and Human Services, Radioactive Materials Program, was notified at 1455 hours [CST] on 01/30/2015 by the Tech. Supervisor, at Omaha Public Power District that a Kay Ray fixed gauge Model Number 7080, housing serial number 16784Y, source shutter failed to close. The device originally installed in 1984 with approximately 50 millicuries Cesium 137 now contains approximately 25 millicuries. The gauge which is part of a hopper level sensor is mounted between two fly ash hoppers approximately 20 feet off of the floor. The source closure mechanism on the gauge is connected to a handle located at floor level by a flexible cable. The closure cable are secured so that when the floor handle is operated, the control cable slides inside of the sheath thus opening/closing the shutter. One of the station's chemists was restoring the source to service following a maintenance outage. The 'external' source closure mechanism for Unit 4 precipitator was being placed in the open position when a metallic snap was heard when opening the source shutter. The source handle was half way to the open position when this noise was heard. The operator then proceeded to check the cables function by trying to move the shutter to the closed position . The source shutter did not move. Scaffolding was erected and an inspection of the device showed the source shutter was in the open position and that the cable was not connected to the gauge operating mechanism. The source shutter mechanism was moved manually to the closed position and the cable reattached and tested several times using the remote actuator. All functions were noted to be in working condition.
"No personnel were unintentionally exposed to radiation during this event.
"Cause: Defective or Failed Part.
"Corrective Action Information: Equipment maintenance and repairs made without engineering change to the system."
Device/Associated Equipment: Kay-Ray/Sensall/Fixed Gauge, Model Number 7080, Serial Number 16784Y.
Source of Radiation: Amersham, Sealed Source Gauge, Model CDC 800, Serial Number 15112-V, with a CS-137 .025 Ci source
Nebraska Item Number: NE150001
Notified the R4DO (Miller) and NMSS Events Notification via email. |
| Part 21 |
Event Number: 50791 |
Rep Org: THERMO GAMMA-METRICS LLC
Licensee: THERMO GAMMA-METRICS LLC
Region: 4
City: SAN DIEGO State: CA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: CLARK ARTAUD
HQ OPS Officer: DANIEL MILLS |
Notification Date: 02/06/2015
Notification Time: 13:17 [ET]
Event Date: 02/06/2015
Event Time: [PST]
Last Update Date: 02/06/2015 |
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE |
Person (Organization):
ANNE DeFRANCISCO (R1DO)
ROBERT HAAG (R2DO)
LAURA KOZAK (R3DO)
GEOFFREY MILLER (R4DO)
PART 21/50.55 REACT (EMAI) |
Event Text
PART 21 REPORT - SHUTDOWN MARGIN MONITOR ENVIRONMENTAL QUALIFICATION NONCOMPLIANCE
The following is an excerpt of a report received from the vendor via email:
"A deviation has been identified in the SDMM supplied by Thermo Gamma-Metrics LLC. The SDMM will fail during conditions of simultaneous high temperature and high humidity less than the values reported in Qualification Test Report (QTR) 010. Testing has indicated the SDMM would not properly operate above a certain value of moisture content corresponding to a dew point of around 128øF. QTR 010 listed qualified temperature and humidity conditions corresponding to a dew point of around 136øF."
The vendor has issued a revised qualification test report which documents the revised qualified conditions for the affected SDMMs.
The following plants are potentially affected: ANO U2; Millstone U3; Prairie Island U1 & U2; Seabrook U1 & U2; South Texas U1 & U2; St. Lucie U1; Catawba U1 & U2; McGuire U1 & U2; Salem U1 & U2; Calvert Cliffs U1 & U2; Almaraz U1 & U2; Sequoyah U1 & U2; Watts Bar U1 & U2; Vogtle U1 & U2; Byron U1 & U2; Ringhals U2, U3 & U4. |
| Power Reactor |
Event Number: 50792 |
Facility: DRESDEN
Region: 3 State: IL
Unit: [ ] [2] [ ]
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: RYAN SEARS
HQ OPS Officer: DANIEL MILLS |
Notification Date: 02/06/2015
Notification Time: 16:53 [ET]
Event Date: 02/06/2015
Event Time: 12:27 [CST]
Last Update Date: 02/06/2015 |
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(A) - ECCS INJECTION
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION |
Person (Organization):
LAURA KOZAK (R3DO) |
| Unit |
SCRAM Code |
RX CRIT |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
| 2 |
A/R |
Y |
100 |
Power Operation |
0 |
Hot Shutdown |
Event Text
AUTOMATIC REACTOR SCRAM DUE TO LOSS OF FEEDWATER
"At 1227 CST on 06 Feb 2015, Dresden Unit 2 automatically scrammed due to a Reactor Water Level transient. Set up activities for weekend maintenance were being performed on the feedwater system at the time of the event.
"All rods inserted to their full-in positions.
"Systems operated as expected.
"Reactor vessel inventory and pressure are being maintained in normal control bands. The ultimate heat sink was maintained.
"The source of the transient was a loss of Feedwater Level Control and the reactor automatically scrammed on low reactor water level. Cause of the failure is under investigation. All three feed pumps tripped as a result of the transient. The 2B reactor feed pump was restored following the transient in accordance with station operating procedures. Level is being maintained with normal feedwater.
"High Pressure Coolant Injection initiated on a valid low-low reactor water level. Manual operator action was taken to prevent unneeded injection into the reactor coolant system.
"Group 2 Primary Containment and Group 3 Shutdown Cooling and Reactor Water Clean-up system isolations occurred as expected.
"Unit 2 and 2/3 [swing diesel] EDGs started as expected, but did not load onto their associated busses as offsite power was maintained."
The licensee has notified the NRC Resident Inspector. |
| Power Reactor |
Event Number: 50794 |
Facility: CLINTON
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: RICHARD CHAMPLEY
HQ OPS Officer: VINCE KLCO |
Notification Date: 02/07/2015
Notification Time: 07:37 [ET]
Event Date: 02/06/2015
Event Time: 23:55 [CST]
Last Update Date: 02/07/2015 |
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL |
Person (Organization):
LAURA KOZAK (R3DO) |
| Unit |
SCRAM Code |
RX CRIT |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
| 1 |
N |
Y |
98 |
Power Operation |
98 |
Power Operation |
Event Text
LEAKAGE DETECTION SYSTEM INOPERABLE
"On 2/6/15 at 2300 (CST) the Division 1 Reactor Water Cleanup (RT) system differential flow instrument was declared inoperable due to erratic indication. The Division 1 RT differential flow instrument was declared inoperable in accordance with Technical Specification 3.3.6.1 Action D.1. At time 2355 Division 2 RT differential flow instrument failed downscale and was declared inoperable in accordance with Technical Specification 3.3.6.1 Action D.1 and also Technical Specification 3.3.6.1 Action E.1 (entered due to Division 1 RT differential flow already inoperable). Since this condition renders the Leakage Detection System incapable of performing its safety function, it is reportable under 10CFR50.72(b)(3)(v)(C). Division 1 RT differential flow was declared Operable at time 0036 on 2/7/15. Division 2 RT differential flow was restored to Operable at time 0225 on 2/07/2015.
"The NRC Resident [Inspector] has been notified." |
| Power Reactor |
Event Number: 50795 |
Facility: GRAND GULF
Region: 4 State: MS
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: DAVID BURRUS
HQ OPS Officer: DANIEL MILLS |
Notification Date: 02/07/2015
Notification Time: 21:47 [ET]
Event Date: 02/07/2015
Event Time: 18:56 [CST]
Last Update Date: 02/07/2015 |
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL |
Person (Organization):
GEOFFREY MILLER (R4DO) |
| Unit |
SCRAM Code |
RX CRIT |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
| 1 |
A/R |
Y |
100 |
Power Operation |
0 |
Hot Shutdown |
Event Text
AUTOMATIC REACTOR SCRAM
"A reactor SCRAM occurred at 1856 CST on 2/7/15 from 100 percent core thermal power. The cause of the SCRAM appears to be a Generator/Turbine trip, but it is still under investigation.
"Appropriate off-normal event procedures were entered to mitigate the transient with all systems responding as designed. No loss of offsite or ESF power occurred. No ECCS initiation signals were reached, and no ECCS or Emergency Diesel Generator initiations occurred.
"Main Steam Isolation Valves remained open and Safety Relief Valves lifted and reseated as designed. Currently, reactor water level is being maintained by the Condensate and Feedwater system in normal band, and reactor pressure is being controlled via turbine bypass valves to the main condenser."
Following the reactor SCRAM, all rods fully inserted and all systems functioned as expected. The plant is in a normal electrical lineup.
The licensee has notified the NRC Resident Inspector. |
| 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: 02/08/2015 |
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." |
|