| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
04/08/2014 - 04/09/2014 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 49976 | Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: UT SOUTHWEST MEDICAL CENTER
Region: 4
City: DALLAS State: TX
County:
License #: L00384
Agreement: Y
Docket:
NRC Notified By: ROBERT FREE
HQ OPS Officer: STEVE SANDIN | Notification Date: 03/31/2014
Notification Time: 16:40 [ET]
Event Date: 03/18/2014
Event Time: [CDT]
Last Update Date: 04/03/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
HEATHER GEPFORD (R4DO)
FSME_EVENTS RESOURCE (EMAI)
ILTAB (EMAI)
|
| This material event contains a "Less than Cat 3 " level of radioactive material. | Event Text AGREEMENT STATE - DISCOVERED I-125 SOURCE MISSING FOLLOWING SURGERY
The following information was received from the State of Texas via email:
"UT Southwestern, RSO called to report that an I-125 seed implant [135 mCi] had been lost during a breast implant procedure on 03/18/14. The treatment staff did not notify Radiation Safety until 03/26/14. The room had been cleaned before Radiation Safety had a chance to search. [The] RSO will provide more details in his written report."
Texas Incident #: I-9173
* * * UPDATE ON 4/3/14 AT 1529 EDT FROM ARTHUR TUCKER TO DONG PARK * * *
The following information was received from the State of Texas via email:
"On April 3, 2014, the Agency [Texas Department of Health] contacted the licensee to confirm the activity of the missing I-125 seed. The licensee's Radiation Safety Officer stated the activity was 135 microcuries. Additional information will be provided as it is received in accordance with SA-300."
Notified R4DO (Gepford), FSME Events Resource, and ILTAB via email.
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: 49981 | Rep Org: PATRIOT ENGINEERING AND ENVIRONMENT
Licensee: PATRIOT ENGINEERING AND ENVIRONMENT
Region: 3
City: TERRE HAUTE State: IN
County:
License #: 13-32725-01
Agreement: N
Docket:
NRC Notified By: KENNETH SULLIVAN
HQ OPS Officer: JEFF ROTTON | Notification Date: 04/01/2014
Notification Time: 11:50 [ET]
Event Date: 04/01/2014
Event Time: 07:30 [EDT]
Last Update Date: 04/01/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
| Person (Organization):
DAVE PASSEHL (R3DO)
FSME EVENTS RESOURE (EMAI)
ILTAB (EMAI)
|
| This material event contains a "Less than Cat 3 " level of radioactive material. | Event Text THEFT OF SEAMAN MODEL C-200 NUCLEAR DENSITY GAUGE
A technician for Patriot Engineering and Environmental, Inc. took possession of a Seaman Model C-200 (Serial # L-102) nuclear density gauge on the evening of 3/31/2014 for use at a jobsite the next day. He secured the gauge in the back of his pickup truck with a chain and 3 padlocks. Two of the padlocks secured the gauge to the bed of the pickup truck and the third padlock secured the wrapped chain to the device. Between 0100 EDT and 0730 EDT on the morning of 4/1/2014, the gauge was stolen from the back of the pickup truck. Indianapolis Metro Police Department was contacted and they are investigating. The gauge contains 4.5 mCi of Radium 226 (Source Serial # B8633)
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: 49983 | Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: BIG STATE X-RAY
Region: 4
City: ODESSA State: TX
County:
License #: L02693
Agreement: Y
Docket:
NRC Notified By: GENTRY HEARN
HQ OPS Officer: JEFF ROTTON | Notification Date: 04/01/2014
Notification Time: 15:47 [ET]
Event Date: 11/12/2013
Event Time: 09:30 [CDT]
Last Update Date: 04/01/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
HEATHER GEPFORD (R4DO)
FSME_EVENTS RESOURCE (EMAI)
| Event Text AGREEMENT STATE REPORT - CAMERA FAILED TO RETRACT SOURCE PROPERLY
The following information was received from the State of Texas via email:
"On March 26, 2014, the Agency [State of Texas - Department of State Health Services] received information that a source disconnect had occurred in November of the previous year. A subsequent report from the licensee received April 1, 2014 indicates that the disconnect occurred on November 12, 2013 at a temporary field site just west of Wink, Texas. The drive cable had become worn, allowing the source to be pushed out without being fully engaged with the pigtail. The source was pushed out of the guide tube but did not retract when the drive cable was cranked in. The camera was a QSA Model 880D S/N D6125, source QSA Global model A424-9 Ir-192 at 66.7 Ci, S/N 99589B. The source was recovered without further incident by attaching another drive cable. No exposure to the public resulted form this event. Additional information will be supplied as it is received in accordance with SA-300."
Texas Incident Number: I-9174 |
| Fuel Cycle Facility | Event Number: 49998 | Facility: NUCLEAR FUEL SERVICES INC.
RX Type: URANIUM FUEL FABRICATION
Comments: HEU CONVERSION & SCRAP RECOVERY
NAVAL REACTOR FUEL CYCLE
LEU SCRAP RECOVERY
Region: 2
City: ERWIN State: TN
County: UNICOI
License #: SNM-124
Agreement: Y
Docket: 07000143
NRC Notified By: RANDY SHACKELFORD
HQ OPS Officer: HOWIE CROUCH | Notification Date: 04/04/2014
Notification Time: 16:34 [ET]
Event Date: 04/04/2014
Event Time: 13:15 [EDT]
Last Update Date: 04/04/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
70.50(b)(2) - SAFETY EQUIPMENT FAILURE
| Person (Organization):
STEVEN VIAS (R2DO)
MARK LOMBARD (NMSS)
FUELS GROUP (EMAI)
| Event Text CRITICALITY ACCIDENT EVACUATION ALARM NOT AUDIBLE IN CERTAIN AREAS OUTSIDE THE MATERIAL HANDLING AREA
"At approximately 1315 hours (Eastern Daylight Time) on April 4, 2014, while testing the audibility of the criticality accident evacuation alarm in the Building locker room, a report was made that the alarm could not be heard in an office trailer restroom. Subsequent testing confirmed the evacuation alarm could not be heard in the office trailer restroom when the fan was running. Safety management personnel were notified of the problem and other restrooms were tested. Testing revealed that the alarm was not able to be heard in three (3) additional office trailer restrooms. All affected restrooms were posted with signs indicating the areas are not to be occupied pending resolution of the audibility issue. It should be noted that the restrooms are located outside of the material processing areas.
"The licensee notified the NRC Resident Inspector."
See similar event EN #49848. |
| Power Reactor | Event Number: 50006 | Facility: VOGTLE
Region: 2 State: GA
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DAN MONAHON
HQ OPS Officer: DANIEL MILLS | Notification Date: 04/08/2014
Notification Time: 05:21 [ET]
Event Date: 04/08/2014
Event Time: 04:28 [EDT]
Last Update Date: 04/08/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
| Person (Organization):
STEVEN VIAS (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | A/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text AUTOMATIC REACTOR TRIP DUE TO LOW STEAM GENERATOR LEVEL
"VEGP Unit 2 was at 100% power, normal activities, when digital feedwater trouble alarms were received on all 4 steam generators (SG) with level stable in all generators. Operating crew entered abnormal operating procedure for feedwater malfunction when SG #3 level began rapidly lowering. Operators attempted to take manual control of SG #3 main feedwater regulating valve and were unable to raise SG #3 level. SG #3 level lowered to the Lo-Lo Level setpoint causing an automatic reactor trip. All control rods fully inserted and SG #3 level remained off scale low on narrow range indications. Auxiliary feedwater and feedwater isolation actuated as expected. [Unit 2] is currently stable in Mode 3 at normal operating temperature and pressure. A forced outage response team has been formed to determine the cause of the low SG water level and determine restart criteria and time of restart."
All control rods fully inserted on the trip. Decay heat is being removed via auxiliary feedwater to steam generators steaming to the condenser steam dumps.
The licensee has notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 50007 | Facility: LIMERICK
Region: 1 State: PA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: DAN WILLIAMSON
HQ OPS Officer: PETE SNYDER | Notification Date: 04/08/2014
Notification Time: 09:45 [ET]
Event Date: 04/08/2014
Event Time: 06:18 [EDT]
Last Update Date: 04/08/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
| Person (Organization):
RAY POWELL (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 17 | Power Operation | 17 | Power Operation | Event Text SHUTDOWN ACTION INITIATED BECAUSE HPCI AND RCIC WERE SIMULTANEOUSLY INOPERABLE
"U1 entered Technical Specification 3.0.3, and initiated actions to reduce power via control rod insertion in preparations to enter startup within the following 6 hours. Entry into Tech Spec 3.0.3 was a result of both HPCI and RCIC injection systems being inoperable at the same time.
"During startup from the U1 refueling outage, RCIC and HPCI full flow testing was unable to be completed at rated reactor pressure prior to the expiration of the 12 hour allowance per Tech Spec Surveillances 4.7.3.b* and 4.5.1.b.3** respectively. This occurred due to testing issues encountered while attempting to perform the rated pressure pump valve and flow tests.
"U1 HPCI testing was completed satisfactorily at 0830, and HPCI was restored to operable. Plant shutdown was terminated at 0830 [EDT] as conditions for 3.0.3 no longer existed."
The licensee will notify the NRC Resident Inspector. |
| Research Reactor | Event Number: 50009 | Facility: U. S. GEOLOGICAL SURVEY
RX Type: 1000 KW TRIGA MARK I
Comments:
Region: 4
City: DENVER State: CO
County: DENVER
License #: R-113
Agreement: Y
Docket: 05000274
NRC Notified By: TIM DeBEY
HQ OPS Officer: STEVE SANDIN | Notification Date: 04/08/2014
Notification Time: 13:56 [ET]
Event Date: 04/08/2014
Event Time: 10:27 [MDT]
Last Update Date: 04/08/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
NON-POWER REACTOR EVENT
| Person (Organization):
LAWRENCE KOKAJKO (NRR)
| Event Text REPORT OF TECHNICAL SPECIFICATION VIOLATION
"Event details:
"While performing a routine reactor pulse for surveillance purposes, the signal input cable to one of the power monitoring safety channels was disconnected, making the associated high power scram not functional. The pulsing procedure requires disconnecting this cable for preoperational testing, but states that the instrument input be returned to its normal operating status prior to actually performing the operation. Contrary to the procedure, this was not done and the reactor was operated at 2 watts for 7 minutes without that required safety channel operating. A second safety channel was fully operational during that time. The high power scrams are not required during pulse mode operations. The disconnected cable was subsequently discovered and reconnected."
The licensee informed the NRR Program Manager (Morlang). |
| Power Reactor | Event Number: 50010 | Facility: MILLSTONE
Region: 1 State: CT
Unit: [ ] [2] [ ]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: TODD STRINGFELLOW
HQ OPS Officer: STEVE SANDIN | Notification Date: 04/08/2014
Notification Time: 14:14 [ET]
Event Date: 04/08/2014
Event Time: 09:51 [EDT]
Last Update Date: 04/08/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
RAY POWELL (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown | Event Text LOSS OF STACK GAS EFFLUENT RADIATION MONITOR
At 0951 EDT Operators discovered that RM-8168 (Stack Gas Effluent Radiation Monitor) was inoperable due to a temporary loss of power to the motor. This resulted in a loss of assessment capability. The licensee followed the required steps in the Alarm Response Procedure and restored the Radiation Monitor to service at 1310 EDT.
The licensee informed State/local agencies and the NRC Resident Inspector. |
| Power Reactor | Event Number: 50012 | Facility: SALEM
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: WILLIAM MUFFLEY
HQ OPS Officer: STEVE SANDIN | Notification Date: 04/08/2014
Notification Time: 23:13 [ET]
Event Date: 04/08/2014
Event Time: 21:14 [EDT]
Last Update Date: 04/08/2014 | 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):
RAY POWELL (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | M/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text UNIT 1 MANUALLY TRIPPED FOLLOWING THE LOSS OF AN OPERATING STEAM GENERATOR FEED PUMP (SGFP)
"This 4 and 8 hour notification is being made to report that Salem Unit 1 has performed an unplanned manual reactor trip and subsequent Auxiliary Feedwater system actuation. The trip was initiated due to loss of Steam Generator water level [SGWL] following the loss of one of the running SGFPs (#11 Steam Generator Feed Pump). The reactor was manually tripped prior to reaching the automatic SGWL low setpoints. #11/12/13 Aux Feedwater Pumps automatically started following the reactor trip on low Steam Generator water level.
"Salem Unit 1 is currently in Mode 3. Reactor Coolant system pressure is at 2235 PSIG and temperature is 547 degrees Fahrenheit with decay heat removal via the Main Steam Dumps and Auxiliary Feedwater Systems. Unit 1 has no active shutdown technical specification action statements in effect. All control rods inserted on the reactor trip. All ECCS [Emergency Core Cooling System] and ESF [Engineered Safety Feature] systems functioned as expected.
"There was no major primary or secondary equipment tagged for maintenance prior to this event. No personnel were injured during this event."
The licensee will inform the Lower Alloways Creek Township and the NRC Resident Inspector. | |