| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
03/22/2016 - 03/23/2016 ** EVENT NUMBERS ** |
 | Part 21 | Event Number: 50935 | Rep Org: UNITED CONTROLS INTERNATIONAL
Licensee: UNITED CONTROLS INTERNATIONAL
Region: 1
City: NORCROSS State: GA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: LUIS SANCHEZ
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 03/27/2015
Notification Time: 17:33 [ET]
Event Date: 01/30/2015
Event Time: [EDT]
Last Update Date: 03/22/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(a)(2) - INTERIM EVAL OF DEVIATION
| Person (Organization):
TODD JACKSON (R1DO)
PART 21/50.55 REACT (EMAI)
| Event Text PART-21 NOTIFICATION - SENSE AND TRANSFER MODULE RESISTIVE SHORT
The following excerpted report was received via e-mail:
"Sense & Transfer Module (part number 41-09-339904) was provided to PSEG under purchase order 4500726553. The customer identified an abnormal curve trace (resistive short) on the integrated circuit installed at location IC825 pin 6 on this printed circuit board. The customer performed an evaluation which included dissection of the subject IC [integrated circuit] however, this dissection provided inconclusive results as to the cause of the IC anomaly.
"At this time, UCI requires additional time to evaluate the results provided by PSEG and to work with the manufacturer in identifying the root cause. UCI currently considers this issue to be an isolated event as no previous instances of this failure have been observed by UCI to date. PSEG has returned the item to UCI for evaluation and rework [received by UCI on 3/25/2015].
"If you have any questions or wish to discuss this matter or this report, please contact:
Wesley Hickle
Procurement Engineer
whickle@unitedcontrols.com
770-496-1406 x 165"
Potentially affected plants are Salem and Hope Creek.
* * * UPDATE ON 3/22/16 AT 1511 EDT FROM KORINA LOOFT TO DONG PARK * * *
The following excerpted report was received via e-mail:
"Follow up to previously reported by United Controls International (UCI) as requiring additional evaluation time and to correct purchase order information previously reported to the NRC with a report in general conformity of the requirements of 10 CFR Part 21.21."
Notified R1DO (McKinley) and Part 21 group via email. |
| Agreement State | Event Number: 51790 | Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: FOOTHILLS GEOTECHNICAL SERVICES
Region: 4
City: PLACERVILLE State: CA
County:
License #: 7448-09
Agreement: Y
Docket:
NRC Notified By: NIKA HEWADIKARAM
HQ OPS Officer: HOWIE CROUCH | Notification Date: 03/14/2016
Notification Time: 16:05 [ET]
Event Date: 03/12/2016
Event Time: [PDT]
Last Update Date: 03/14/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
GREG WARNICK (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)
CNSNS (MEXICO) (FAX)
ILTAB (EMAI)
| Event Text CALIFORNIA AGREEMENT STATE REPORT - STOLEN MOISTURE DENSITY GAUGE
The following information was obtained from the State of California via email:
"On 03/14/16, RHB [California Department of Public Health - Radiologic Health Branch] was contacted via email by the California Office of Emergency Services (OES) to report a stolen moisture density gauge. This is a Troxler Model 3440, S/N T34436628, gauge containing 9 mCi of Cesium -137 and 44 mCi of Americium - 241. This gauge was stolen from the licensee's storage facility located in Placerville, CA on 03/12/16. [The licensee radiation safety officer] RSO had filed a report with the El Dorado County Sheriff's office. There is no report of damage to the device, however, the whereabouts of the gauge is unknown. RHB will be following up with this investigation."
California Report Number: 5010-031416 |
| Agreement State | Event Number: 51791 | Rep Org: TEXAS DEPT OF STATE HEALTH SERVICES
Licensee: GEOTEST ENGINEERING, INC.
Region: 4
City: HOUSTON State: TX
County:
License #: L02735
Agreement: Y
Docket:
NRC Notified By: KAREN BLANCHARD
HQ OPS Officer: STEVEN VITTO | Notification Date: 03/15/2016
Notification Time: 10:36 [ET]
Event Date: 03/15/2016
Event Time: [CDT]
Last Update Date: 03/15/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
GREG WARNICK (R4DO)
NMSS_EVENTS_NOTIFICA (EMAI)
CNSNS (MEXICO) (FAX)
ILTAB (EMAI)
|
| This material event contains a "Less than Cat 3 " level of radioactive material. | Event Text AGREEMENT STATE - STOLEN MOISTURE DENSITY GAUGE
The following information was obtained from the State of Texas via email:
"On March 15, 2016, the licensee notified the Agency [Texas Department of State Health Services] that one of its technicians had stopped by an apartment complex on his way to a temporary job site and had left a Troxler model 3430 moisture/density gauge (SN: 63944) secured with 2 chains in the back of the company truck while he went inside an apartment. When he returned to his vehicle, he found that the chains had been cut, the transport case was on the ground near the vehicle, and the gauge had been removed. The licensee's radiation safety officer reported that the insertion rod on the gauge was locked and the technician had the key. The RSO notified local law enforcement and searched the immediate area. They will continue and expand their search for the gauge. The gauge contained a 40 milliCurie americium-241 source and an 8 milliCurie cesium-137 source. An investigation into this event is ongoing. Further information will be provided as it is obtained in accordance with SA-300."
Texas Incident #: I-9386
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: 51793 | Rep Org: FLORIDA BUREAU OF RADIATION CONTROL
Licensee: ECS-FLORIDA, LLC
Region: 1
City: TAMPA State: FL
County:
License #: 3440-3
Agreement: Y
Docket:
NRC Notified By: MARK SEIDENSTICKER
HQ OPS Officer: HOWIE CROUCH | Notification Date: 03/15/2016
Notification Time: 19:43 [ET]
Event Date: 03/15/2016
Event Time: 07:25 [EDT]
Last Update Date: 03/15/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
JAMES NOGGLE (R1DO)
NMSS_EVENTS_NOTIFIC (EMAI)
|
| This material event contains a "Less than Cat 3 " level of radioactive material. | Event Text FLORIDA AGREEMENT STATE REPORT - LOST MOISTURE DENSITY GAUGE
The following information was obtained from the State of Florida via email:
"[A licensee] employee left the shop this morning at 7:25 a.m. [EDT] in a pick up truck. The soil moisture density gauge was locked but not chained and locked to bed of pick up truck. [The] employee drove about one mile to [the] job site and upon arrival realized the gauge was missing. Multiple employees retraced the route to try and find the gauge but could not find it. The RSO [Radiation Safety Officer] notified local law enforcement and fire department. The RSO noted the gauge is an InstroTek 1955 Explorer 3500, sources serial number is CZ6000; 267-14 and estimated current activity is 40 mCi of Am241 and 10 mCi of Cs137. Incident report from RSO to follow."
Florida Incident Number: FL16-040
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: 51808 | Facility: ARKANSAS NUCLEAR
Region: 4 State: AR
Unit: [1] [2] [ ]
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: RODRICK JOHNSON
HQ OPS Officer: STEVEN VITTO | Notification Date: 03/19/2016
Notification Time: 22:51 [ET]
Event Date: 03/19/2016
Event Time: 17:10 [CDT]
Last Update Date: 03/22/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
50.72(b)(3)(v)(B) - POT RHR INOP
| Person (Organization):
MARK HAIRE (R4DO)
|
| 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 UNANALYZED CONDITION THAT COULD CHALLENGE RHR EQUIPMENT DURING FLOOD CONDITIONS
"Two (2) potentially degraded flood barriers at penetrations 0073-01-0034 and 0073-01-0063 were identified in the area between the Unit 1 Turbine Building and Auxiliary Building. The deficient barriers are a 'blockout section' of the floor designed to house multiple penetrations that transition from the Turbine Building to the Auxiliary Building. Attempts have been made to investigate the status of the flood barrier with no definitive results. Investigations and additional evaluations are continuing, however, it is currently unknown if the aggregate of these two flood barriers could potentially overwhelm and flood the Auxiliary Building which would challenge equipment necessary to remove residual heat and constitute an unanalyzed condition.
"Based on current conditions (i.e., no forecast flooding conditions), this condition does not present an immediate safety concern.
"This condition has been determined to be reportable per 10 CFR 50.72(b)(3)(ii)(B) and 10 CFR 50.72(b)(3)(v)(B). This condition is a non-emergency condition. This condition has been entered into the Corrective Action Program.
"Compensatory measures have been prepared to allow placement of a seal over the identified deficient barriers. If required these seals can be installed well in advance of forecast flood conditions. Permanent repairs are currently being designed for installation."
The NRC Resident Inspector has been notified.
* * * UPDATE AT 0044 EDT ON 3/22/2016 FROM KEITH LEDBETTER TO MARK ABRAMOVITZ * * *
"This is an 8 hour non-emergency supplemental notification to previously issued Event Notification number 51808. In EN 51808, two non-functional barriers were identified and reported, and during an extent of condition review, a third barrier has been identified that does not conform to expected flood barrier standards
"A potentially degraded flood barrier at 'blockout' penetration 0073-01-9018 was identified in the area between the Unit 1 Turbine Building and Auxiliary Building. The deficient barrier is a 'blockout section' of the floor designed to house multiple penetrations that transition from the Turbine Building to the Auxiliary Building. Attempts have been made to investigate the status of the flood barrier with no definitive results. Investigations and additional evaluations are continuing; however, it is currently unknown if this flood barrier could potentially be overwhelmed and flood the Auxiliary Building which would challenge equipment necessary to remove residual heat and constitute an unanalyzed condition.
"Based on current conditions (i.e., no forecast flooding conditions), this condition does not present an immediate safety concern.
"This condition has been determined to be reportable per 10 CFR 50.72(b)(3)(ii)(B) and 10 CFR 50.72(b)(3)(v)(B). This condition is a non-emergency condition. This condition has been entered into the Corrective Action Program.
"Compensatory measures have been prepared to allow placement of a seal over the identified deficient barrier. If required this seal can be installed well in advance of forecast flood conditions. Permanent repairs are currently being designed for installation."
The NRC Resident Inspector was notified earlier in the evening that this event would be updated.
Notified the R4DO (Haire). |
| Power Reactor | Event Number: 51812 | Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: RANDY SAND
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 03/22/2016
Notification Time: 06:38 [ET]
Event Date: 03/22/2016
Event Time: 01:04 [CDT]
Last Update Date: 03/22/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
ROBERT DALEY (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 | Event Text HIGH PRESSURE COOLANT INJECTION (HPCI) OIL LEAK
"On 3/22/2016 during performance of HPCI FLOW CONTROL SYSTEM DYNAMIC TEST PROCEDURE, an oil leak was discovered on the hydraulic control oil piping. HPCI had previously been declared INOPERABLE due to planned maintenance, however as a result of the oil leak HPCI remains INOPERABLE. This oil leak would have cause HPCI to be declared INOPERABLE had it been found outside of the planned maintenance. The plant remains at 100% power with no challenges to the health and safety of the public."
HPCI is in a 14 day technical specification to repair the oil leak.
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 51814 | Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: JIM SOUTHERTON
HQ OPS Officer: DONG HWA PARK | Notification Date: 03/22/2016
Notification Time: 12:43 [ET]
Event Date: 03/22/2016
Event Time: 09:14 [EDT]
Last Update Date: 03/22/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
| Person (Organization):
RAY MCKINLEY (R1DO)
FFD GROUP (EMAI)
|
| 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 FITNESS FOR DUTY - NON-LICENSED SUPERVISOR TESTED POSITIVE DURING RANDOM TESTING
"A non-licensed supervisor tested positive for alcohol during a random fitness for duty test. The individual's access to the facility has been denied.
"The licensee has notified the NRC Resident Inspector." |
| Power Reactor | Event Number: 51815 | Facility: WATTS BAR
Region: 2 State: TN
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MATTHEW ROBERTSON
HQ OPS Officer: KARL DIEDERICH | Notification Date: 03/22/2016
Notification Time: 13:59 [ET]
Event Date: 03/22/2016
Event Time: 11:31 [EDT]
Last Update Date: 03/22/2016 | 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):
DAVID AYRES (R2DO)
|
| 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 WATTS BAR AUTOMATIC REACTOR TRIP
"On March 22, 2016, at 1131 EDT, the Watts Bar Nuclear Plant Unit 1 (WBN1) reactor tripped due to the actuation of the Over Temperature Delta Temperature bistables. Concurrent with the reactor trip, the Auxiliary Feedwater (AFW) system actuated. All control rods inserted upon the reactor trip. Engineered Safety Function systems functioned as expected.
"WBN1 is currently stable in Mode 3. The Reactor Coolant system is being maintained at normal operating pressure and no-load temperature with decay heat removal via the Main Condenser steam dumps and the AFW system. The station is in a normal shutdown electrical alignment. Watts Bar Unit 2 is in mode 4 preparing for power ascension testing and was unaffected by the WBN1 event.
"The cause of the event is under investigation. This event is being reported pursuant to 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A)."
The NRC Resident Inspector has been notified. |
| Part 21 | Event Number: 51816 | Rep Org: UNITED CONTROLS INTERNATIONAL
Licensee: MERSEN
Region: 1
City: NORCROSS State: GA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: KORINA LOOFT
HQ OPS Officer: DONG HWA PARK | Notification Date: 03/22/2016
Notification Time: 15:11 [ET]
Event Date: 02/20/2016
Event Time: [EDT]
Last Update Date: 03/22/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
| Person (Organization):
ROBERT DALEY (R3DO)
PART 21/50.55 REACT (EMAI)
| Event Text PART 21 REPORT - DEFECTIVE FUSES
The following information is a synopsis of information received via E-mail:
"On February 20, 2016 United Controls International issued a Return Material Authorization (RMA) request to First Energy - Perry Nuclear Power Plant. The RMA was issued to request the return of general purpose fuses of part number OT15 that were provided to First Energy - Perry Nuclear Power Plant under purchase order 45225736. The customer identified a fuse that had intermittent electrical continuity during resistance checks. The customer performed an evaluation which included dissection of the subject fuse and the cause of the issue was identified as being due to a lack of or inadequate solder connection of the fuse element to the fuse ferrules.
"If you have any questions or wish to discuss this matter or this report, please contact:
Wesley Hickle
Engineering Manager
whickle@unitedcontrols.com
770-496-1406 x 165" |
| Power Reactor | Event Number: 51817 | Facility: MCGUIRE
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: TOM BERNARD
HQ OPS Officer: DONG HWA PARK | Notification Date: 03/22/2016
Notification Time: 23:33 [ET]
Event Date: 03/22/2016
Event Time: 19:34 [EDT]
Last Update Date: 03/22/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
| Person (Organization):
DAVID AYRES (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown | Event Text DEGRADED CONDITION FOUND IN REACTOR COOLANT SYSTEM PIPING
"On Tuesday, March 22, 2016, while performing planned inspections of Unit 1 Reactor Coolant System piping welds, a flaw indication was identified on a 3 inch Charging Line connection to the Reactor Coolant System piping.
"NDE [Non-Destructive Evaluation] results showed a change in the flaw since the previous outage inspection and the condition is now determined as not meeting the acceptance criteria specified in ASME Code Section XI. As such, this indication is reportable under 10 CFR 50.72(b)(3)(ii)(A) as a degraded condition.
"An action plan is being developed. There is no impact on current Unit 1 refueling operations. This condition and the action plan have no impact to the health and safety of the public or employees.
"The NRC Resident [Inspector] has been notified." | |