| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
05/16/2016 - 05/17/2016 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 51807 | Facility: FORT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: (1) CE
NRC Notified By: JUSTIN WIEMER
HQ OPS Officer: DANIEL MILLS | Notification Date: 03/18/2016
Notification Time: 18:43 [ET]
Event Date: 03/18/2016
Event Time: 11:28 [CDT]
Last Update Date: 05/16/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
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 | Event Text SHUTDOWN COOLING PIPE VOID
"During a scheduled surveillance test on 3/18/2016 at 1128 [CDT], Fort Calhoun ultrasonic testing technicians discovered a void on the common shutdown cooling heat exchanger discharge piping. This piping is normally isolated during power operation, and the void does not adversely affect the Containment Spray function, Low Pressure Safety Injection function, or High Pressure Safety Injection function.
"This isolated piping with the void is placed in service only during shutdown cooling operation. The fluid height measured was 10.8 inches, compared to the required height of 11.7 inches for the surveillance test. The void could potentially complicate the initiation of shutdown cooling in the required mode of operation.
"This piping was last tested satisfactory on 12/31/2015. The source of the void is still under investigation.
"Fort Calhoun maintenance was successful in venting the void on 3/18/2016 at 1704 CDT."
The NRC Resident Inspector has been notified.
* * * RETRACTION AT 1701 EDT ON 05/16/16 FROM JAKE WALKER TO KARL DIEDERICH * * *
"Following the 8-hour 10 CFR 50.72 notification made on 3/18/16 (EN 51807), further engineering analysis has determined that the ensuing water hammer transient would not have prevented the shutdown cooling system from performing its required safety functions. Specifically, it was found that the resulting system pressure transient would not cause any relief valves to lift and that piping and supports would not be significantly challenged.
"Therefore, the common shutdown cooling heat exchanger discharge piping remained operable by the detailed analysis. As such, the safety function was not lost and the event notification is being retracted as it is not reportable pursuant to 10 CFR 50.72(b)(3)(v)(B)."
Notified the R4DO (G Miller). |
| Agreement State | Event Number: 51911 | Rep Org: ALABAMA RADIATION CONTROL
Licensee: MILLENNIUM RESOURCES, LLC
Region: 1
City: GRAYSVILLE State: AL
County:
License #: G/L
Agreement: Y
Docket:
NRC Notified By: MYRON K. RILEY
HQ OPS Officer: HOWIE CROUCH | Notification Date: 05/06/2016
Notification Time: 10:24 [ET]
Event Date: 05/06/2016
Event Time: 09:15 [CDT]
Last Update Date: 05/06/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
FRED BOWER (R1DO)
NMSS_EVENTS_NOTIFIC (EMAI)
|
| This material event contains a "Less than Cat 3 " level of radioactive material. | Event Text ALABAMA AGREEMENT STATE REPORT - LOST GENERALLY LICENSED PROCESS GAUGE
The following information was obtained from the State of Alabama via facsimile:
"On May 5, 2016, it was determined that Millennium Resources, LLC, Graysville, Alabama had lost control and possession of a generally licensed device (Ronan SA1-C5 #2255GO containing 5 mCi of Cs-137).
"During a requested visit by the new owner Cane Creek, LLC on April 7, 2016, it was determined that they possessed a new generally licensed device. The new owners only knew that the site once contained a similar plant which contained a device with radioactive material. The old plant was constructed in 1997, and our [Alabama Department of Public Health - Office of Radiation Control] records show that device being received by Millennium Resources, LLC on November 14, 1997. The plant was torn down and sold for scrap during the year of 2006. The new owners had no information in regards to whom the scrap was sold or the whereabouts of the device.
"On April 7, 2016, the Agency [Alabama Department of Public Health - Office of Radiation Control] contacted Ronan and their records indicated no transfer for disposal. During the next few weeks, several calls were made to the Alabama Department of Environmental Management and the Alabama Surface Mining Commission to determine if any new information could be obtained. None of the representatives could provide any additional information.
"As of today [5/6/16], 0915 CDT, the device containing radioactive material has not been recovered. This incident remains open until further investigation can be completed."
Alabama Incident 16-15
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: 51932 | Facility: SEABROOK
Region: 1 State: NH
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: MATTHEW LARRABEE
HQ OPS Officer: DAN LIVERMORE | Notification Date: 05/16/2016
Notification Time: 02:02 [ET]
Event Date: 05/16/2016
Event Time: 03:00 [EDT]
Last Update Date: 05/16/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
ART BURRITT (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 | Event Text SEISMIC MONITORING SYSTEM OUT OF SERVICE FOR PLANNED UPGRADE
"At 0300 EDT on May 16, 2016, Seabrook Station's seismic monitoring instrumentation will be removed from service for a planned upgrade to the Seismic Monitoring Control Panel and its accelerometers. Modifications are expected to be complete on May 27, 2016. Proceduralized compensatory measures are in place and have been communicated to applicable emergency response decision makers. This preplanned action is being reported in accordance with 10 CFR 50.72(b)(xiii)."
The NRC Resident Inspector has been notified. |
| Power Reactor | Event Number: 51934 | Facility: DRESDEN
Region: 3 State: IL
Unit: [ ] [2] [ ]
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: DANIEL MURPHY
HQ OPS Officer: KARL DIEDERICH | Notification Date: 05/16/2016
Notification Time: 19:56 [ET]
Event Date: 05/16/2016
Event Time: 14:57 [CDT]
Last Update Date: 05/16/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
ANN MARIE STONE (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text ACCIDENT MITIGATION - HPCI DECLARED INOPERABLE
"At 1457 [CDT] on 5-16-16, U-2 [Unit 2] High Pressure Coolant Injection (HPCI) system was declared inoperable after isolation of the system due to a steam leak on the HPCI steam inlet drain pot drain line.
"The event is reportable per 10CFR50.72(b)(3)(v)(D), Any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences an accident. This is an eight hour report requirement.
"The Dresden NRC Resident Inspector has been notified." |
| Power Reactor | Event Number: 51935 | Facility: SEQUOYAH
Region: 2 State: TN
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ROBERT URBANSKI
HQ OPS Officer: KARL DIEDERICH | Notification Date: 05/16/2016
Notification Time: 21:17 [ET]
Event Date: 05/16/2016
Event Time: 21:05 [EDT]
Last Update Date: 05/16/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
JAMIE HEISSERER (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 | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text UNANALYZED CONDITION THAT SIGNIFICANTLY DEGRADES PLANT SAFETY
"On May 16, 2016 at 2105, Sequoyah Nuclear Power Plant identified a nonconforming condition involving the Emergency Diesel Generator (EDG) fire dampers installed in Units 1 and 2. Specifically, it has been identified that if a tornado causes a differential pressure across the east and west sides of the EDG Building, this could create a high airflow rate through the EDG Building ventilation path. The fire dampers for each EDG bay (required to isolate the space for CO2 fire suppression per SQN Fire Protection Report) have not been analyzed to withstand high air flows resulting from a tornado and could possibly fail in a way that impedes airflow for EDG cooling. This is an unanalyzed condition that could prevent all EDGs from supplying electrical power as designed during a tornado or other similar weather events.
"All 4 EDGs are required to be operable by both units' Technical Specifications to provide electrical power to safe shutdown/safety related equipment following accident conditions coincident with a loss of offsite power. The Current Licensing Basis (CLB) requires that tornado effects be considered in the design of safety related SSCs [Systems, Structures, and Components], and it cannot be demonstrated at this time that the described SSCs will withstand the design basis tornado. It has been determined that the CLB may not adequately address possible design basis tornado scenarios.
"The EDGs are located inside the power plant structure and are currently capable of performing their safety function. The occurrence of such an event is highly unlikely and there is no imminent concern regarding severe weather involving tornadoes. Compensatory measures have been developed to address the associated nonconformance.
"The condition described above is being reported as an unanalyzed condition that significantly degrades plant safety per 10 CFR 50.72(b)(3)(ii)(B)."
The NRC Resident Inspector has been notified. |
| Part 21 | Event Number: 51936 | Rep Org: UNITED CONTROLS INTERNATIONAL
Licensee: THOMAS AND BETTS AND CYBEREX PRINTED CIRCUIT BOARDS
Region: 1
City: Norcross State: GA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: KORINA LOOFT
HQ OPS Officer: RICHARD SMITH | Notification Date: 05/16/2016
Notification Time: 22:39 [ET]
Event Date: 05/16/2016
Event Time: [EDT]
Last Update Date: 05/16/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(a)(2) - INTERIM EVAL OF DEVIATION
| Person (Organization):
ANNE DeFRANCISCO (R1DO)
PART 21/50.55 REACT (EMAI)
| Event Text PART 21 NOTIFICATION - FOR PRINTED CIRCUIT BOARDS
The following was received by email:
"Required information as per 10CFR Part 21.21(d)(4) follows:
"(i) Name and Address of the individual or individuals informing the Commission
"Luis Sanchez, Vice President
United Controls International
205 Scientific Drive
NORCROSS, GA 30092
"(ii) Identification of the facility, the activity, or the basic component supplied for such facility or such activity within the United States which fails to comply or contains a defect.
"Thomas & Betts Power Solutions/Cyberex Printed Circuit Boards (Gate Drive Assemblies P/Ns: 41-01-229677 & 41-01-229678, Reference Oscillator Module P/N: 41-01-808901) & Mersen (formerly Ferraz Shawmut) Fuses P/N: A30QS400-4 items were installed in PSEG [Public Service Enterprise Group] inverter unit and resulted in opening of P/N: A30QS400-4 fuses. When the original equipment was installed this issue was not present.
"(iii) Identification of the firm constructing the facility or supplying the basic component which fails to comply or contains a defect.
"United Controls International
205 Scientific Drive
Norcross, GA 30092
"(iv) Nature of the defect or failure to comply and the safety hazard which is created or could be created by such defect or failure to comply.
"Opening of the subject fuses prevents operation of the host inverter unit.
"(v) The date on which the information of such defect or failure to comply was obtained.
"March 17,2016
"(vi) In the case of a basic component which contains a defect or fails to comply, the number and location of these components in use at, supplied for, being supplied for, or may be supplied for, manufactured or being manufactured for one or more facilities or activities subject to the regulations in this Part.
"The following is a compilation of UCI supplied items with like part numbers as the subject components. Only the printed circuit boards identified by the end-user [supplied under purchase orders 4500576271 (Qty. 1), 4500728702 (Qty. 1), and 4500625591 (Qty. 1)] along with the subject fuses supplied under purchase orders 4500810474 (Qty. 10) and 4500772093 (Qty. 6) are considered to possibly be affected by the end-user's reported issue.
"(vii) The corrective action which has been, is being, or will be taken; the name of the individual or organization responsible for the action; and the length of time that has been or will be taken to complete the action.
"UCI is not capable of performing additional evaluation of the subject printed circuit boards because UCI does not have the capability to simulate the in-service condition of these items. UCI suggests that the end-user perform additional evaluations with the subject printed circuit boards installed in their training inverter unit. UCI has requested that the end-user supply additional fuses supplied under purchase orders 4500810474 and 4500772093 for evaluation of current carrying performance since the fuses already provided were open.
"(viii) Any Advice related to the defect or failure to comply about the facility, activity, or basic component that has been, is being, or will be given to purchasers or licensees.
"None
"(ix) In the case of an early site permit, the entities to whom an early site permit was transferred.
"Not Applicable." | |