| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
09/10/2014 - 09/11/2014 ** EVENT NUMBERS ** |
 | Power Reactor | Event Number: 49471 | Facility: OCONEE
Region: 2 State: SC
Unit: [ ] [ ] [3]
RX Type: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP
NRC Notified By: MIKE TATE
HQ OPS Officer: BILL HUFFMAN | Notification Date: 10/24/2013
Notification Time: 09:45 [ET]
Event Date: 10/24/2013
Event Time: 05:53 [EDT]
Last Update Date: 09/10/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
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 | | 3 | M/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text MANUAL REACTOR TRIP FROM FULL POWER DUE TO FEEDWATER SYSTEM OSCILLATIONS
"At 0553 EDT on 10/24/2013, Oconee Unit 3 was manually tripped due to oscillations in the feedwater system in anticipation of an automatic reactor trip. At 0549 EDT, Unit 3 began experiencing small feedwater oscillations. The feedwater control system was placed in manual in an attempt to stabilize feedwater flows. Feedwater oscillations continued to grow in magnitude and at 0553 EDT, a manual trip was directed to prevent an automatic reactor trip.
"Due to an RPS actuation, this event is being reported as a 4 and 8 hour Non-Emergency per 10 CFR 50.72 (b)(2)(iv)(B) and 10 CFR 50.72 (b)(3)
"Following the reactor trip, four main steam relief valves failed to reseat. Procedure guidance was utilized to reduce main steam system pressure by approximately 30 psig to reseat the main steam relief valves. All main stream relief valves are now reseated. All other post trip conditions were normal and all other systems performed as expected. Unit 3 is currently in Mode 3 and stable.
"Operations have been stabilized on Unit 3. A post-trip investigation is in progress, per site procedures and directives."
The licensee has notified the NRC Resident Inspector.
* * * UPDATE FROM BOB MEIXELL TO DONALD NORWOOD AT 1439 ON 9/10/14 * * *
"Duke Energy reviewed NRC Event Number 49471 against NUREG 1022, Rev 3, section 3.2.6, "System Actuation" and determined this event should have been reported only per 10 CFR 50.72 (b)(2)(iv)(B), RPS Actuation (while critical). Thus, Duke Energy is revising NRC Event Number 49471 to remove the 8-hour report criteria 10 CFR 50.72 (b)(2)(iv)(A). The NRC Resident Inspector was notified of this revised report.
"This update has no effect on safety significance."
Notified R2DO (Shaeffer). |
| Agreement State | Event Number: 50421 | Rep Org: MARYLAND DEPT OF THE ENVIRONMENT
Licensee: FROEHLING & ROBERTSON
Region: 1
City: JESSUP State: MD
County:
License #: MD-27-083-01
Agreement: Y
Docket:
NRC Notified By: RAY MANLEY
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 09/02/2014
Notification Time: 16:40 [ET]
Event Date: 08/27/2014
Event Time: [EDT]
Last Update Date: 09/02/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
MARC FERDAS (R1DO)
FSME EVENTS RESOURCE (EMAI)
| Event Text AGREEMENT STATE REPORT - MOISTURE DENSITY GAUGE DAMAGED AT CONSTRUCTION SITE
"Our [Froehling & Robertson] technician was using the gauge to test compaction of soils placed for wall backfill. [The technician] placed the nuclear gauge on the sloped hill next to the backfill area and stepped away from the gauge to check on the concrete pour that was happening at the top of the hill. As she was walking away, the backfill crew started using the two drum walk-behind roller. The roller was in vibratory mode and, as it approached the area near the nuclear gauge, the gauge slid down the slope into the path of the roller. The gauge was hit with the roller on the end opposite the rod, damaging the casing and the instrument panel. [The technician] and the roller operator moved the gauge to assess the damage and, when they realized it was damaged, [the technician] cordoned off the area.
"Exposure Readings and Visual Damage Assessment:
"[The RSO] arrived on-site with the survey meter (CD V-700 calibrated 5/9/2014) and checked the area for radiation exposure. No significant readings were recorded (less than 0.1 mrem/hr 5 feet from the gauge). The source rod was fully retracted into the casing and did not appear to be damaged other than the handle was twisted. The gauge appeared to be intact in the vicinity of the Americium source. The gauge was packed and secured in its storage case and transported to Northeast Technical Services for a leak test and damage evaluation.
"Assessment of Cause:
"[The RSO] interviewed the client and [technician] to try to assess a cause for the incident. The client had asked [the technician] to go check on the concrete pour before performing another density test and, instead of properly securing the gauge in the truck or keeping it within arm's reach, [the technician] left the gauge unattended while she walked up the slope. In talking with [the technician], she was aware of the proper procedures for securing the gauge and maintaining control of the gauge but failed to do so in this case.
"Corrective Measures:
"As this is a first offense for [the technician], she will be issued a written warning stating that if involved in another incident like this, she will be terminated. Additionally, she will be asked to take another refresher course on using and transporting nuclear density gauges. [The RSO] will also be holding a safety meeting with all technicians to review this incident and review the F&R Nuclear Gauge Safety material regarding maintaining control of gauges."
Sources: 0.37 GBq Cs-137 and 1.48 GBq Am-241:Be
Make/Model: Troxler 3400
Serial #: 23898 |
| Agreement State | Event Number: 50422 | Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: SKYWORKS SOLUTIONS
Region: 1
City: WOBURN State: MA
County:
License #: G0516
Agreement: Y
Docket:
NRC Notified By: ANTHONY CARPENITO
HQ OPS Officer: CHARLES TEAL | Notification Date: 09/03/2014
Notification Time: 11:25 [ET]
Event Date: 06/06/2014
Event Time: [EDT]
Last Update Date: 09/03/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
MARC FERDAS (R1DO)
FSME EVENTS RESOURCE (EMAI)
BARRY WRAY (ILTA)
|
| This material event contains a "Less than Cat 3 " level of radioactive material. | Event Text AGREEMENT STATE REPORT - ELEVEN MISSING PO-210 SOURCES
The following was received from the Commonwealth of Massachusetts via email:
"On 9/3/14, Agency [Commonwealth of Massachusetts] determined, through inventory reconciliation, the general licensee is missing eleven Model 2021 Nuclecel Ionizers each originally containing up to 10 mCi Po-210. Agency further determined that six devices contained material with calculated current activity well below the immediate report level (0.1 mCi for Po-210), three devices contained material with calculated current activity of 0.12 mCi, and two devices contained material with calculated current activity of 0.77 mCi. The Agency did not receive specific lost source notification from the licensee. No other details from the licensee at this time. The devices are designed to be rugged, require no special handling procedures, and intended for use in neutralization of static charge in environmental tests. The current exposure rate for each device is expected to be considerably less than the initial maximum exposure rate of less than 0.2 mR/hr.
"Agency inspector to conduct site visit.
"Agency considers this event to still be OPEN and Agency review is ONGOING"
The devices were manufactured by NRD Inc., Model P-2021, three were manufactured 4/13/12, and two were manufactured 4/10/13. The serial numbers are A2JB491, A2JB496, A2JB500, A2JM622, and A2JM624.
The sources were Po-210 10 mCi each.
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: 50423 | Rep Org: FLORIDA BUREAU OF RADIATION CONTROL
Licensee: JACKSONVILLE BAPTIST MEDICAL CENTER
Region: 1
City: JACKSONVILLE State: FL
County:
License #: 2213-1
Agreement: Y
Docket:
NRC Notified By: KELLIE ANDERSON
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 09/03/2014
Notification Time: 15:16 [ET]
Event Date: 08/20/2014
Event Time: [EDT]
Last Update Date: 09/04/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
MARC FERDAS (R1DO)
FSME EVENTS RESOURCE (EMAI)
BARRY WRAY (E-MAIL) (ILTA)
|
| This material event contains a "Less than Cat 3 " level of radioactive material. | Event Text AGREEMENT STATE REPORT - LOST FLOOD SOURCE
"A Co-57, 4 mCi flood source was reported missing. The source was first noticed missing two weeks ago. It was possible source was shipped back to vendor with another flood source that was mailed recently. They are currently checking with their vendor Eckert & Ziegler Isotope Products, Inc. to verify their shipment. Jacksonville inspection office contacted to perform site inspection."
Florida incident: FL14-075
* * *UPDATE PROVIDED BY KELLIE ANDERSON TO JEFF ROTTON AT 1313 EDT ON 09/04/2014 * * *
The following is a summary of information provided by the State of Florida via email:
The State of Florida was notified today by the [licensee's] RSO, who made the initial report, that the licensee had found the source and it had been accidently mailed back to their supplier along with another source. The State of Florida will still send an investigator to look into the matter and provide recommendations, otherwise the State of Florida is considering this incident closed.
Notified R1DO (Ferdas), ILTAB (Wray) and FSME Events Resource group 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 |
| Power Reactor | Event Number: 50440 | Facility: TURKEY POINT
Region: 2 State: FL
Unit: [ ] [4] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: ROBERT PELL
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 09/10/2014
Notification Time: 10:24 [ET]
Event Date: 09/09/2014
Event Time: 19:36 [EDT]
Last Update Date: 09/10/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
SCOTT SHAEFFER (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 4 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text FAILURE OF THE AUTO-START FEATURE ON TWO CONTAINMENT COOLERS
"This is a non-emergency notification in accordance with 10 CFR 50.72(b)(3)(v)(D) which requires a report when any event or condition at time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident.
"On 9/9/14, FPL discovered the automatic feature associated with the swing 4A emergency containment cooling (ECC) unit was inoperable due to a design change inadequacy. During breaker replacement activities performed on 9/3/14, a one hour shutdown action statement pursuant to TS 3.6.2.2.b was exceeded due to two ECC's being unable to automatically start on an SI [Safety Injection] signal. [This was not known until the 4A was declared inoperable on 9/9/14 at 1936 EDT].
"The 4A ECC was declared inoperable at 1936 EDT on 9/9/14, and in accordance with TS 3.6.2.2.a, must be returned to OPERABLE status within 72 hours from the time of discovery."
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 50441 | Facility: VOGTLE
Region: 2 State: GA
Unit: [3] [4] [ ]
RX Type: [3] W-AP1000,[4] W-AP1000
NRC Notified By: MICHAEL YOX
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 09/10/2014
Notification Time: 11:24 [ET]
Event Date: 03/13/2014
Event Time: 08:00 [EDT]
Last Update Date: 09/10/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.55(e) - CONSTRUCT DEFICIENCY
| Person (Organization):
SCOTT SHAEFFER (R2DO)
|
| 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 WELDING PROGRAM DEVIATIONS DURING CONSTRUCTION
"This is a 10CFR50.55(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 and 4 construction project.
"In March, 2014, CB&I Lake Charles issued a root cause analysis report for welding program deviations associated with the fabrication of 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 10CFR50.55(e)(4)(iii) and 10CFR50.55(e)(5)(i)."
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 50442 | Facility: SUMMER
Region: 2 State: SC
Unit: [ ] [2] [3]
RX Type: [1] W-3-LP,[2] W-AP1000,[3] W-AP1000
NRC Notified By: FINDLAY SALTER
HQ OPS Officer: DONALD NORWOOD | Notification Date: 09/10/2014
Notification Time: 11:51 [ET]
Event Date: 03/13/2014
Event Time: 08:00 [EDT]
Last Update Date: 09/10/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.55(e) - CONSTRUCT DEFICIENCY
| Person (Organization):
SCOTT SHAEFFER (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | N | 0 | | 0 | | | 3 | N | N | 0 | | 0 | | Event Text WELDING PROGRAM DEVIATIONS DURING CONSTRUCTION
"This is a 10CFR50.55(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 Virgil C. Summer Units 2 and 3 construction project.
"In March, 2014, CB&I Lake Charles issued a root cause analysis report for welding program deviations associated with the fabrication of 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 10CFR50.55(e)(4)(iii) and 10CFR50.55(e)(5)(i)."
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 50443 | Facility: HARRIS
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP
NRC Notified By: MARK LEE
HQ OPS Officer: VINCE KLCO | Notification Date: 09/10/2014
Notification Time: 11:55 [ET]
Event Date: 09/10/2014
Event Time: 04:53 [EDT]
Last Update Date: 09/10/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
SCOTT SHAEFFER (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 TECHNICAL SUPPORT CENTER VENTILATION SYSTEM OUT OF SERVICE DUE TO FIRE ALARM
"This is a non-emergency eight hour notification for a loss of Emergency Preparedness Capabilities. This event is reportable in accordance with 10 CFR50.72(b)(3)(xiii) as the condition affects the functionality of an emergency response facility.
"At approximately 0453 EDT on September 10, 2014, a fire alarm in an area near the primary Technical Support Center (TSC) triggered an automatic shutdown of the TSC ventilation system. The system was restored at 0755 EDT. The alternate TSC was available at all times.
"This condition does not affect the health and safety of the public or station employees.
"The NRC Resident Inspector has been notified." |
| Power Reactor | Event Number: 50444 | Facility: MILLSTONE
Region: 1 State: CT
Unit: [ ] [ ] [3]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: RICHARD VIGNEAU
HQ OPS Officer: DONALD NORWOOD | Notification Date: 09/10/2014
Notification Time: 14:20 [ET]
Event Date: 09/10/2014
Event Time: 11:06 [EDT]
Last Update Date: 09/10/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
TODD JACKSON (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text RADIATION MONITOR OUT OF SERVICE
"Loss of assessment capability due to pre-planned maintenance affecting a radiation monitor for supplementary leakage collection and release system. [Monitor] (3HVR*RE19A/B) will be out of service. The condition is reportable per 10CFR50.72(b)(3)(xiii). The equipment is expected to be restored within 48 hours."
The licensee notified the NRC Resident Inspector. | |