| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
12/02/2013 - 12/03/2013 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 49507 | Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [1] [2] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: STEVE INGALLS
HQ OPS Officer: PETE SNYDER | Notification Date: 11/06/2013
Notification Time: 03:26 [ET]
Event Date: 11/06/2013
Event Time: 00:58 [CST]
Last Update Date: 12/02/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
CHRISTINE LIPA (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 | N | 0 | Defueled | 0 | Defueled | Event Text R-21 CIRCULATING WATER DISCHARGE RADIATION MONITOR PLANNED OUTAGE
"When transferring power supplies to a non-safety related cooling tower bus for planned outage maintenance, R-21, the Circulating Water Discharge Radiation Monitor was removed from service at 0058 [CST] and returned to service at 0111 [CST]. There is no installed backup for R-21 which has an emergency response function to provide indication of gaseous liquid effluent release to the environment. This monitor has no compensatory measure that will allow timely classification of two NUE (Notification of Unusual Event) and Alert classifications when out of service. This resulted in a loss of emergency assessment capability while R-21 was out of service.
"There are no radioactive leaks that impact the Circulating Water System.
"The licensee notified the NRC Resident Inspector."
* * * RETRACTION AT 1155 EST ON 12/2/13 FROM WAYNE EPPEN TO DANIEL MILLS * * *
"Based on further reviews of plant drawings and discussion with the Radiation Monitor System Engineer, R-21 was not inoperable when power supplies were transferred to the non-safety related Cooling Tower Bus. While R-21 was logged out of service during the transfer on November 6, 2013, it did not lose power and was not out of service. R-21 did not lose the ability to provide continuous monitoring of discharge canal effluent or monitoring in the event of an unplanned radiological release. Our defense in depth strategies are relied upon to take actions to protect the health and safety of the public.
"The licensee has notified the NRC Resident Inspector."
Notified the R3DO (Duncan). |
| Agreement State | Event Number: 49572 | Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: QUALSPEC SERVICES LLC
Region: 4
City: CORPUS CHRISTI State: TX
County:
License #: 06351
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: STEVE SANDIN | Notification Date: 11/22/2013
Notification Time: 14:40 [ET]
Event Date: 11/20/2013
Event Time: [CST]
Last Update Date: 11/22/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
DAVID PROULX (R4DO)
FSME EVENTS RESOURCE (EMAI)
| Event Text AGREEMENT STATE REPORT - STUCK RADIOGRAPHY SOURCE
The following information was received from the State of Texas via email:
"On November 22, 2013, the Agency [Texas Department of State Health Services] was notified by the licensee that on November 20, 2013, one of their crews performing radiography work was unable to retract the iridium-192 source into a QSA 880D camera. The radiography crew was performing radiography work on a job that required the use of an extension tube sold by the manufacturer for use with the guide tube. On the fifth of five shots, the source was cranked out of the camera, but when they attempted to retract it, it would not move. The radiographers contacted the licensee's Radiation Safety Officer who responded to the location. The RSO attempted to retract the source and he could not get the source to move. The source was stuck inside the collimator. The RSO dismantled the crank out device and pulled on the drive cable to move the source, but it would not move. The RSO removed the guide tube from its location and placed it on the grating of the platform they were working from. The source was covered with lead to reduce exposures. The barricade was extended and other licensee personnel who were also working at the plant were used to control access to the area. The RSO removed the drive cable housing from the back of the camera and attempted to pull on the cable and retract the source. It did not move. The RSO stated he inspected the locking device and it appeared to be fine. The RSO loosened the clamp that was being used to hold the guide tube extension in place while they were shooting. The source could then be retracted and was returned to the fully shielded position. The RSO believes that over time the extension guide tube walls had weakened and collapsed to a point where the source/drive cable could not pass through it. The RSO stated no one had exceeded any limits. He stated his 0-200 millirem self-reading dosimeter (SRD) had gone off scale, but his assistant's SRD only read 140 millirem. The RSO stated he would send both his and his assistant's dosimetry to their processors for reading. No other individuals received any exposure due to this event. Additional information will be provided as it is received in accordance with SA-300."
Texas Incident #: I-9137 |
| Agreement State | Event Number: 49577 | Rep Org: VIRGINIA RAD MATERIALS PROGRAM
Licensee: NORFOLK DREDGING
Region: 1
City: FIRE ISLAND State: NY
County:
License #: GL-1290
Agreement: Y
Docket:
NRC Notified By: MIKE WELLING
HQ OPS Officer: CHARLES TEAL | Notification Date: 11/25/2013
Notification Time: 13:53 [ET]
Event Date: 11/25/2013
Event Time: [EST]
Last Update Date: 11/25/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
DAN SCHROEDER (R1DO)
FSME EVENT RESOURCE (EMAI)
| Event Text AGREEMENT STATE REPORT - MEMBER OF PUBLIC EXPOSURE EXCEEDING LIMITS
The following was received from the Commonwealth of Virginia via email:
"An individual (non-radiation worker) performing a pipe inspection on a Norfolk Dredging barge received a dose from a Vega America Model SR-2 fixed gauge source while crawling through the pipe. Initial dose estimates to the individual are that he received 146 mrem. Norfolk Dredging sent an e-mail to the Virginia Radioactive Materials Program on Saturday the 23rd and discussions were held on Monday the 25th. Norfolk Dredging is working on an event report to submit, and the RMP will perform an investigation with the licensee. Virginia is providing the event report as the barge is home based in Virginia and is registered as a General License. The barge was operating at a temporary jobsite in New York. The New York State Program and NRC Region 1 was notified of the event."
Virginia Report Number: VA-13-10 |
| Agreement State | Event Number: 49578 | Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: MISTRAS GROUP INC
Region: 4
City: LA PORTE State: TX
County:
License #: 06369
Agreement: Y
Docket:
NRC Notified By: KAREN BLANCHARD
HQ OPS Officer: CHARLES TEAL | Notification Date: 11/25/2013
Notification Time: 14:48 [ET]
Event Date: 11/22/2013
Event Time: [CST]
Last Update Date: 11/25/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
GREG PICK (R4DO)
FSME EVENT RESOURCE (EMAI)
| Event Text AGREEMENT STATE REPORT - RADIOGRAPHY TRUCK INVOLVED IN ACCIDENT
"On November 22, 2013, the Agency [Texas Department of State Health Services] received information from the Odessa, Texas, Emergency Management that an accident involving an industrial radiography truck carrying two radiography cameras had occurred near Andrews, Texas. The Agency contacted the licensee and they reported that the driver had hit a patch of ice on the road, lost control, and the truck turned over. Both of the cameras remained secured inside the transportation box in the truck's darkroom. Another of the licensee's radiographers was following the truck and maintained control of the cameras until the licensee's staff came from Midland to pick them up. There were no exposures to any individual as a result of this event.
"On November 25, 2013, an Agency investigator learned from the licensee that the driver had been taken by ambulance to a local hospital's emergency department following the accident. The driver was examined and released after approximately 5 hours. More information will be provided as it obtained in accordance with SA-300."
Texas Incident Number: I-9138 |
| Power Reactor | Event Number: 49593 | Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [ ] [2] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: RYAN C. HAMILTON
HQ OPS Officer: PETE SNYDER | Notification Date: 12/02/2013
Notification Time: 11:03 [ET]
Event Date: 12/02/2013
Event Time: 09:04 [EST]
Last Update Date: 12/02/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
| Person (Organization):
WILLIAM COOK (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | M/R | Y | 40 | Power Operation | 0 | Hot Shutdown | Event Text MANUAL SCRAM FOLLOWING TRIP OF BOTH REACTOR RECIRCULATION PUMPS
"At 0904 [EST] on Monday, December 2, 2013, Nine Mile Point Unit 2 was manually scrammed from approximately 40% thermal power due to the loss of both reactor recirculation pumps during a planned downpower evolution. Manual scram of the unit is procedurally required upon loss of both recirculation pumps to avoid potential power/flow oscillations. The reactor recirculation pumps failed to transfer to the low frequency motor generators when downshifted from fast speed. The cause of the loss of both reactor recirculation pumps is not known at this time. [Nine Mile Point Unit 2] NMP2 has commenced cooldown in preparation for the forced outage to investigate and commence repairs.
"10 CFR 50.72(b)(2)(iv)(B) requires reporting within 4 hours of any event or condition that results in actuation of the reactor protection system (RPS) when the reactor is critical."
All control rods fully inserted. No safety systems actuated. Decay heat is being removed via the main condenser. The "A" recirculation pump was restarted in low speed at 1045 EST. Unit 2 is in a normal shutdown electrical lineup.
The licensee informed the NRC Resident Inspector and will inform the New York State Public Services Commission. |
| Power Reactor | Event Number: 49595 | Facility: VOGTLE
Region: 2 State: GA
Unit: [3] [4] [ ]
RX Type: [3] W-AP1000,[4] W-AP1000
NRC Notified By: HOWARD MAHAN
HQ OPS Officer: VINCE KLCO | Notification Date: 12/02/2013
Notification Time: 13:52 [ET]
Event Date: 09/24/2013
Event Time: 08:00 [EST]
Last Update Date: 12/02/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.55(e) - CONSTRUCT DEFICIENCY
| Person (Organization):
BRIAN BONSER (R2DO)
OMID TABATABAI (NRO)
PART 21 GROUP (EMAI)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | N | 0 | Under Construction | 0 | Under Construction | | 4 | N | N | 0 | Under Construction | 0 | Under Construction | Event Text DEFICIENCY IDENTIFIED IN QUALITY ASSURANCE PROGRAM
"This is a 10 CFR 50.55(e) initial notification for a significant breakdown in the Quality Assurance (QA) Program of Chicago Bridge & Iron (CB&I) Lake Charles facility, a sub-supplier of CB&I. CB&I Lake Charles supplies safety-related structural sub-modules for the Vogtle 3 & 4 construction project.
"In September 2013, CB&I Lake Charles issued a root cause analysis report for deviations associated with sub-modules being supplied to domestic AP1000 construction projects. An evaluation of the root cause analysis results concluded that a significant QA program breakdown had occurred that could have produced a defect. No defect has been identified.
"This initial notification is being made in accordance with 10 CFR 50.55(e)(4)(iii) and 10 CFR 50.55(e)(5)(i)."
The licensee will notify the NRC Resident Inspector.
Reference similar Summer Event (EN#49582). |
| Power Reactor | Event Number: 49596 | Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [1] [2] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: RYAN C. HAMILTON
HQ OPS Officer: STEVE SANDIN | Notification Date: 12/02/2013
Notification Time: 16:52 [ET]
Event Date: 12/02/2013
Event Time: 08:53 [EST]
Last Update Date: 12/02/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
| Person (Organization):
WILLIAM COOK (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 | | 2 | N | Y | 41 | Power Operation | 41 | Power Operation | Event Text FITNESS-FOR-DUTY - CONFIRMED POSITIVE TEST FOR ALCOHOL
A non-licensed employee supervisor had a confirmed positive for alcohol during a for-cause fitness-for-duty test. The employee's unescorted access to the plant has been terminated.
The NRC Resident Inspector has been notified. |
| Power Reactor | Event Number: 49599 | Facility: BYRON
Region: 3 State: IL
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: LEO WREDE
HQ OPS Officer: STEVE SANDIN | Notification Date: 12/02/2013
Notification Time: 22:01 [ET]
Event Date: 12/02/2013
Event Time: 22:00 [CST]
Last Update Date: 12/02/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
ERIC DUNCAN (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 TECHNICAL SUPPORT CENTER (TSC) NON-FUNCTIONAL DUE TO PLANNED MAINTENANCE
"On December 2, 2013, activities are scheduled that will render the Technical Support Center (TSC) non-functional by removing the normal and emergency ventilation system from service. These activities are being performed in support of planned preventive maintenance. In preparation for these normal and emergency ventilation system outages, the TSC emergency responders were notified that if an emergency occurred during this outage the Emergency Coordinator and the TSC staff involved with classification, notification and PARS should report to the Work Execution Center. All other TSC personnel should report to the Operational Support Center. The duration of this TSC outage is expected to be less than 36 hours. The NRC Operations Center will be provided an update to this notification when the TSC normal and emergency ventilation is restored. This 8 hour notification in accordance with 10 CFR 50.72(b)(3)(xiii).
"The licensee notified the NRC Resident Inspector." |
| Power Reactor | Event Number: 49600 | Facility: PALO VERDE
Region: 4 State: AZ
Unit: [ ] [2] [ ]
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: ALLAN BRIESE
HQ OPS Officer: STEVE SANDIN | Notification Date: 12/02/2013
Notification Time: 23:26 [ET]
Event Date: 12/02/2013
Event Time: 17:58 [MST]
Last Update Date: 12/02/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
| Person (Organization):
MICHAEL VASQUEZ (R4DO)
|
| 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 FOLLOWING THE LOSS OF THE 1A REACTOR COOLANT PUMP
"The following event description is based on information currently available. If through subsequent reviews of this event, additional information is identified that is pertinent to this event or alters the information being provided at this time, a follow-up notification will be made via the ENS or under the reporting requirements of 10CFR50.73.
"On December 2, 2013, at approximately 1758 Mountain Standard Time (MST), the Palo Verde Nuclear Generating Station (PVNGS) Unit 2 control room received reactor protection system alarms for low departure from nucleate boiling ratio and an automatic reactor trip occurred. Prior to the reactor trip, Unit 2 was operating normally at 100% power. Plant operators entered the emergency operations procedures and diagnosed an uncomplicated reactor trip but noted the 1A reactor coolant pump (RCP) was not running. All CEAs fully inserted into the core. Following the reactor trip, indications on the train A logarithmic (log) power nuclear instrument initially responded normally but then did not trend as expected. All other nuclear instruments responded normally and the train A log power channel was declared inoperable and technical specification limiting conditions for operation 3.3.10 and 3.3.11 were entered. No emergency classification was required per the PVNGS Emergency Plan.
"The Unit 2 safety related electrical busses remained energized from normal offsite power during the event. Due to planned maintenance on one switchyard breaker, the Ruud offsite power line was disconnected from the PVNGS switchyard when the Unit 2 main generator output breakers opened. There was no impact to the required circuits between the offsite transmission network and the onsite Class 1E Electrical Power Distribution System; the offsite power grid is stable.
"No major equipment was inoperable prior to the event that contributed to the event or complicated operator response. Unit 2 is currently stable in Mode 3 with the reactor coolant system at normal operating temperature and pressure. Preliminary information indicates the reactor trip resulted from an electrical protection trip of the power supply circuit breaker for the 1A RCP.
"The event did not result in any challenges to fission product barriers and there were no adverse safety consequences as a result of this event. The event did not adversely affect the safe operation of the plant or the health and safety of the public.
"The NRC Resident Inspector has been informed of the Unit 2 reactor trip."
There was no impact on either Unit 1 or Unit 3. |
| Power Reactor | Event Number: 49601 | Facility: PALO VERDE
Region: 4 State: AZ
Unit: [ ] [ ] [3]
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: DAVID KELSEY
HQ OPS Officer: DANIEL MILLS | Notification Date: 12/03/2013
Notification Time: 04:05 [ET]
Event Date: 12/02/2013
Event Time: 23:24 [MST]
Last Update Date: 12/03/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
| Person (Organization):
MICHAEL VASQUEZ (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | Y | 78 | Power Operation | 48 | Power Operation | Event Text TECH SPEC REQUIRED SHUTDOWN DUE TO DROPPED CONTROL ELEMENT ASSEMBLY
"The following event description is based on information currently available. If through subsequent reviews of this event additional information is identified that is pertinent to this event or alters the information being provided at this time a follow-up notification will be made via the ENS or under the reporting requirements of 10 CFR 50.73.
"All times described are approximate Mountain Standard Time.
"At 2324 on December 2, 2013, Palo Verde Nuclear Generating Station (PVNGS) Unit 3 commenced a reactor shutdown required by Technical Specification (TS) 3.1.5, Control Element Assembly (CEA) Alignment. TS Limiting Condition for Operation (LCO) 3.1.5, requires 'All full strength CEAs shall be OPERABLE, and all full strength and part strength CEAs shall be aligned to within 6.6 inches (indicated position) of all other CEAs in their respective groups.'
"Regulating CEA number 69 dropped to the fully inserted position at 1830 on December 2, 2013, when the circuit breaker for CEA 69 tripped open. The other 88 CEAs in the reactor were unaffected and remained fully withdrawn. Unit 3 entered LCO 3.1.5 Condition A for one misaligned CEA and reduced power to 78% within one hour in accordance with Required Action A.1.
"The CEA was unable to be restored to its required position within two hours in accordance with Required Action A.2 to restore CEA alignment.
"At 2030, Unit 3 entered Condition C of LCO 3.1.5 because of the inability to restore CEA alignment. Condition C requires the unit to be in Mode 3 in 6 hours.
"At 0033 on December 3, 2013 the Power Switch Assembly was replaced and tested satisfactorily. The shutdown was terminated at this time while at approximately 48% power. At 0039, Unit 3 began to withdraw CEA 69. CEA 69 was realigned with its group at 0143 and LCO 3.1.5 conditions A and C were exited.
"The event did not result in the unplanned release of radioactivity to the environment and did not adversely affect the safe operation of the plant or health and safety of the public.
"The NRC Resident Inspector has been notified." | |