| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
9/13/2018 - 9/14/2018 ** EVENT NUMBERS ** |
| Part 21 | Event Number: 53464 | Rep Org: AAF FLANDERS
Licensee: AAF FLANDERS
Region: 1
City: WASHINGTON State: NC
County:
License #:
Agreement: Y
Docket:
NRC Notified By: SHAWN WINDLEY
HQ OPS Officer: RICHARD SMITH | Notification Date: 06/20/2018
Notification Time: 20:55 [ET]
Event Date: 05/02/2018
Event Time: 00:00 [EDT]
Last Update Date: 09/14/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(a)(2) - INTERIM EVAL OF DEVIATION
| Person (Organization):
KENNETH RIEMER (R3DO)
PART 21/50.55 REACTORS () | Event Text PART 21 - INTERIM REPORT NOTIFICATION
The following was received via phone call and email:
This report provides notification and interim information concerning an evaluation being performed by AAF Flanders for an unapproved design change in a High Efficiency Particulate Air Filter.
"An evaluation is underway for filters that underwent a non-approved design change. AAF Flanders has determined that an evaluation cannot be completed within the 60 day period. Discovery of the potential deviation was May 2, 2018.
"The information required for the 60-Day Interim Report Notification 21.21(a)(2) was provided. We anticipate that the evaluation will be completed by Sept 15, 2018.
"AAF Flanders is evaluating a potential nonconforming condition associated with filters (model number 0-007-C-42-03-NU-11-13-GG FU5) supplied to Prairie Island Nuclear Generating Plant (PINGP) / Xcel Energy."
AAF Flanders notified Prairie Island Nuclear Plant of this potential defect.
* * * UPDATE ON 9/14/2108 AT 1129 EDT FROM SHAWN WINDLEY TO ANDREW WAUGH * * *
The following information was received via email:
"A notification was submitted to the Commission with the subject matter of, 'Unapproved Design Change in a High Efficiency Particulate Air Filter.' At this time, the evaluation is pending third part qualification testing of the product. Information obtained from the qualification will be used in the determination of a defect. AAF Flanders had anticipated this process to have been completed by Sept 15, 2018 but because it is still on-going, we request an extension until October 31, 2018 to submit a final report to the Commission.
"The subject filters (model number 0-007-C-42-03-NU-11-13-GG FU5) supplied to Prairie Island Nuclear Generating Plant (PINGP)/ Xcel Energy had not been installed. AAF Flanders has recalled the subject filters and currently have them segregated and stored at our facility. They pose no threat public safety."
Notified R3DO (Hanna) and Part 21/50.55 Reactors Group (email). |
| !!!!! THIS EVENT HAS BEEN RETRACTED.THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 53562 | Facility: FERMI
Region: 3 State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: GREG MILLER
HQ OPS Officer: DONG HWA PARK | Notification Date: 08/24/2018
Notification Time: 15:01 [ET]
Event Date: 08/24/2018
Event Time: 00:00 [EDT]
Last Update Date: 09/13/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
HIRONORI PETERSON (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 INOPERABLE SEISMIC MONITORING SYSTEM
"At 0745 EDT on August 24, 2018, the Active Seismic Monitoring System failed a planned surveillance test and was declared inoperable. Compensatory measures to provide alternative methods for event classification of a seismic event have been implemented in accordance with the Fermi 2 Emergency Plan procedures. The compensatory measures include the use of information provided by the United States Geological Survey (USGS) to confirm if an earthquake has occurred within a 100 mile radius.
"The loss of the Active Seismic Monitoring System is reportable to the NRC within 8 hours of discovery in accordance with 10CFR50.72(b)(3)(xiii).
"No seismic activity has been felt onsite and the USGS recorded no seismic activity in the area.
"The NRC Resident Inspector bas been notified."
* * * RETRACTION FROM JEFF GROFF TO VINCE KLCO ON SEPTEMBER 13, 2018 AT 1524 EDT * * *
"After further review the Active Seismic Monitoring system was removed from service for planned maintenance for a duration less than 72 hours with appropriate compensatory measures established. Therefore, no major loss of emergency assessment capability occurred. In addition, the surveillance tests were re-performed and the Active Seismic Monitoring System was declared Operable. Therefore, no reportable condition existed and EN 53562 reported on August 24, 20I8 is being retracted.
"The NRC Resident Inspector has been notified."
Notified the R3DO (Hanna). |
| Agreement State | Event Number: 53581 | Rep Org: NEW YORK STATE DEPT. OF HEALTH
Licensee: COLUMBIA UNIVERSITY
Region: 1
City: PALISADES State: NY
County: ROCKLAND
License #: 537-2
Agreement: Y
Docket:
NRC Notified By: DANIEL SAMSON
HQ OPS Officer: RYAN ALEXANDER | Notification Date: 09/05/2018
Notification Time: 14:39 [ET]
Event Date: 08/02/2018
Event Time: 00:00 [EDT]
Last Update Date: 09/05/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
CHRISTOPHER LALLY (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL) | | This material event contains a "Less than Cat 3" level of radioactive material. | Event Text AGREEMENT STATE REPORT - REMOVABLE CONTAMINATION ON A SEALED SOURCE
The following information was obtained from the State of New York via fax:
"Columbia University notified the New York State Department of Health (NYSDOH) on August 7, 2018 [regarding an August 2, 2018 event] of the detection of 592 Becquerel (0.016 microCurie) of removable radioactive material on a 10 milliCurie Ni-63 sealed source contained in a Shimadzu GC-8A II gas chromatography mass spectroscopy unit. The manufacturer and model number of the source were not available. The licensee immediately suspended the operation of the unit and placed the unit in storage. The source will be disposed of as radioactive waste and the equipment will be decontaminated prior to proper disposal by an authorized waste broker."
New York Report Number NYDOH-18-02
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: 53582 | Rep Org: TILDEN MINING COMPANY L.C.
Licensee: TILDEN MINING COMPANY L.C.
Region: 3
City: ISHPEMING State: MI
County:
License #: 21-26748-01
Agreement: N
Docket:
NRC Notified By: LAWRENCE GRAY
HQ OPS Officer: ANDREW WAUGH | Notification Date: 09/06/2018
Notification Time: 12:45 [ET]
Event Date: 08/12/2017
Event Time: 00:00 [EDT]
Last Update Date: 09/14/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
| Person (Organization):
ROBERT DALEY (R3DO)
NMSS_EVENTS_NOTIFICATION (EMAIL) | Event Text GAUGE STUCK SHUTTER
On August 12, 2017, the Tilden Mining Company experienced a stuck open shutter on a gauge in the Tilden Unit 1 Cooler Chunk Tunnel. The licensee determined that the shutter lever was jammed with debris preventing the shutter from closing. The gauge was repaired on August 15, 2017. The Ronan RLL 1 source contains 0.9 milliCurie of Cesium-137 (serial number 317287A).
There were no overexposures as a result of this event.
* * * UPDATE FROM LAWRENCE GRAY TO HOWIE CROUCH AT 1151 EDT ON 9/14/18 * * *
The licensee reported that the gauge was not repaired on August 15, 2017 as previously reported but was repaired on September 13, 2017.
Notified R3DO (Hanna) and NMSS Events Notification (email). |
| Agreement State | Event Number: 53583 | Rep Org: TENNESSEE DIV OF RAD HEALTH
Licensee: ADVANCED MEASUREMENT TECHNOLOGIES (AMETEK)
Region: 1
City: OAK RIDGE State: TN
County:
License #: R-01003-J18
Agreement: Y
Docket:
NRC Notified By: ANTHONY HOGAN
HQ OPS Officer: ANDREW WAUGH | Notification Date: 09/06/2018
Notification Time: 16:46 [ET]
Event Date: 09/06/2018
Event Time: 00:00 [EDT]
Last Update Date: 09/06/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
CHRISTOPHER LALLY (R1DO)
ILTAB (EMAIL)
NMSS_EVENTS_NOTIFICATION (EMAIL) | | This material event contains a "Less than Cat 3" level of radioactive material. | Event Text AGREEMENT STATE REPORT - LOST OR STOLEN SOURCES
The following was received state of Tennessee via email:
"AMETEK conducted an inventory of their sources and found 4 sealed sources that were unaccounted for and possibly lost or stolen. The total amount of all four of the sources was 8.76 microCi. They are as follows:
"Mixed gamma, 133 kBq, serial number 1249
Am-241, 2,200 Bq, serial number SS6712
Am-241, 3.873 kBq, serial number 1868
Sr-90, 5 microCuries"
State Event Report ID NO.: TN-18-151
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: 53601 | Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [3] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: ERIK SILKO
HQ OPS Officer: OSSY FONT | Notification Date: 09/13/2018
Notification Time: 08:24 [ET]
Event Date: 09/13/2018
Event Time: 00:00 [EDT]
Last Update Date: 09/13/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
| Person (Organization):
RAY MCKINLEY (R1DO)
WILLIAM GOTT (IRD) | | Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | | 3 | N | N | 0 | Hot Shutdown | 0 | Hot Shutdown | Event Text HURRICANE NOTIFICATION PER TECHNICAL REQUIREMENT FOR HURRICANE FLORENCE
"A hurricane is within 500 nautical miles from Indian Point Energy Center with wind speed in excess of 87 knots. The National Weather Service has issued a hurricane warning for a hurricane with wind in excess of 87 knots (approximately 100 mph) within 500 nautical miles of the facility. Per the Technical Requirement Manual a prompt report shall be made to the NRC Incident Response Center within 1 hour of receipt of that hurricane warning.
"The licensee has notified the NRC Resident Inspector." |
| Fuel Cycle Facility | Event Number: 53604 | Facility: LOUISIANA ENERGY SERVICES
RX Type:
Comments: URANIUM ENRICHMENT FACILITY
GAS CENTRIFUGE FACILITY
Region: 2
City: EUNICE State: NM
County: LEA
License #: SNM-2010
Docket: 70-3103
NRC Notified By: WYATT PADGETT
HQ OPS Officer: THOMAS KENDZIA
| Notification Date: 09/14/2018
Notification Time: 11:29 [ET]
Event Date: 09/15/2018
Event Time: 00:00 [MDT]
Last Update Date: 09/15/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
INFORMATION ONLY
70.50(b)(2) - SAFETY EQUIPMENT FAILURE | Person (Organization):
MIKE ERNSTES (R2DO)
NMSS_EVENTS_NOTIFICATION (EMAIL) | Event Text PREPLANNED OUTAGE OF A REQUIRED SAFETY MONITORING SYSTEM
"The UUSA [URENCO USA] facility CAAS [Criticality Accident and Alarm System] exists to detect and alarm in the unlikely event of a criticality accident, as required by 10 CFR 70.24, Criticality accident requirements. This monitoring system will be temporarily disabled during planned corrective maintenance activities for approximately thirty minutes, commencing at approximately 0730 MDT, on Saturday, September 15th, 2018. This activity will affect the CAAS in the Separations Building Module (SBM) 1001/1002 and the Cylinder Receipt and Dispatch Building (CRDB). The CAAS in the remaining portions of the facility will be unaffected.
"Essential personnel will remain inside the controlled access area during the maintenance activities. The populated areas of the facility will be limited to the Security Alarm Station, Operations Control Room, and the Maintenance Area housing the CAAS control cabinets in the Technical Services Building (TSB) where technicians will be needed for this work evolution. CAAS coverage of these populated areas will be provided during the maintenance activity by temporary criticality detection equipment.
"Compensatory measures will be implemented in accordance with section 3.1.5 of the UUSA Integrated Safety Analysis (ISA) Summary. These measures including evacuation of non-essential personnel from the areas of concern and the Immediate Evacuation Zone (IEZ) before removing the equipment from service, limiting access into facility, and restricting Special Nuclear Material (SNM) movement will be implemented until CAAS coverage is verified operational.
"UUSA will notify the NRC when CAAS coverage is returned to normal operation. Radiation surveys will be conducted prior to re-entry to confirm acceptable conditions in the area."
The licensee has notified the NRC Project Manager.
* * * UPDATE FROM WYATT PADGETT TO HOWIE CROUCH AT 1139 EDT ON 9/15/18 * * *
The Criticality Accident and Alarm System was returned to service at 0930 MDT after the completion of the scheduled maintenance. During the maintenance period, no abnormal radiation readings were observed.
Notified R2DO (Ernstes). |
| Independent Spent Fuel Storage Installation | Event Number: 53605 | Rep Org: SAN ONOFRE
Licensee: SOUTHERN CALIFORNIA EDISON COMPANY
Region: 4
City: SAN CLEMENTE State: CA
County: SAN DIEGO
License #: GL
Agreement: Y
Docket: 72-41
NRC Notified By: CHRIS DIMENTO
HQ OPS Officer: PHIL NATIVIDAD | Notification Date: 09/14/2018
Notification Time: 16:00 [ET]
Event Date: 08/03/2018
Event Time: 00:00 [PST]
Last Update Date: 09/14/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
72.75(d)(1) - SFTY EQUIP. DISABLED OR FAILS TO FUNCTION
| Person (Organization):
MARK HAIRE (R4DO)
WILLIAM GOTT (IRD) | Event Text SPENT FUEL CANISTER BECAME BOUND DURING DOWNLOAD INTO DRY STORAGE
"On Friday, August 3, [2018,] at approximately 1245 PST, Holtec International (a contractor for Southern California Edison (SCE)) was lowering a Multi-Purpose Canister (MPC) loaded with spent fuel into the Cavity Enclosure Container (CEC) of the SONGS Holtec UMAX Independent Spent Fuel Storage Installation (ISFSI) for purposes of dry storage. The canister was suspended from a Holtec Vertical Cask Transporter (VCT). During the download, the canister encountered an interference with the CEC divider shell and became bound in place. As a result, the downloader slings of the VCT became slack while the MPC was resting partially inside the CEC.
"Once Holtec became aware of the situation, the VCT towers were raised in order to restore tension in the rigging and to raise the MPC. The VCT was then adjusted, and the MPC was then safely lowered into the CEC and the rigging was disengaged.
"There was no effect on the integrity of the canister or release of radioactive material as a result of this event.
"This event meets the reporting criteria of 10CFR72.75(d)(1) in that the VCT, which is an important-to-safety component, was placed in a configuration which defeated its ability to perform its safety function. The VCT and associated rigging are described in Certificate of Compliance 1040, Technical Specification 5.2.c.3, which requires that lifting equipment shall have redundant drop protection features which prevent uncontrolled lowering of the load. By placing the VCT in the configuration of this event, the single-failure proof nature of the lifting devices was defeated. The VCT was no longer capable of mitigating the consequence of an accident, and there was no redundant equipment available and operable to perform the required safety function.
"SCE made an original determination that the event did not require a report. However, SCE contacted the NRC [Region IV] on Monday August 6th and again on Tuesday August 7th to provide details of the event.
"It has now been determined that the event is reportable under 10CFR72.75(d)(1) and this late report is being made."
Licensee notified RIV (Simpson). |
| Power Reactor | Event Number: 53606 | Facility: SALEM
Region: 1 State: NJ
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JUSTIN HARGRAVE
HQ OPS Officer: BRIAN LIN | Notification Date: 09/14/2018
Notification Time: 16:28 [ET]
Event Date: 09/14/2018
Event Time: 00:00 [EDT]
Last Update Date: 09/14/2018 | 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 MCKINLEY (R1DO) | | Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | A/R | Y | 90 | Power Operation | 0 | Hot Standby | Event Text AUTOMATIC REACTOR TRIP DUE TO A FAILURE OF THE STEAM GENERATOR FEED REGULATING VALVE
"At 1323 [EDT] on 9/14/18, with Unit 2 in Mode 1 at 90% power, the reactor automatically tripped due to a failure of 23BF19, 23 Steam Generator (SG) Feed Regulating Valve. The trip was not complex, with all systems responding normally post-trip. No equipment was inoperable prior to the event. An actuation of the auxiliary feedwater system occurred following the automatic reactor trip. The reason for the auxiliary feed water system auto-start was due to low level in the steam generator. Operations responded and stabilized the plant. Decay heat is being removed by the main steam dumps and auxiliary feedwater system. Unit 1 is not affected.
"Due to the Reactor Protection System actuation while critical, this event is being reported as a four-hour, non- emergency notification per 10 CFR 50.72(b)(2)(iv)(B). This event is being reported in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of the auxiliary feed water system.
"There was no impact on the health and safety of the public or plant personnel.
"The NRC Resident Inspector has been notified. The Lower Alloways Creek Township will be notified." |
| Power Reactor | Event Number: 53608 | Facility: GRAND GULF
Region: 4 State: MS
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: GERRY ELLIS
HQ OPS Officer: ANDREW WAUGH | Notification Date: 09/14/2018
Notification Time: 21:09 [ET]
Event Date: 09/14/2018
Event Time: 00:00 [CDT]
Last Update Date: 09/14/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
| Person (Organization):
MARK HAIRE (R4DO) | | Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | M/R | Y | 100 | Power Operation | 0 | Hot Shutdown | Event Text MANUAL REACTOR SCRAM
"At 1644 [CDT] a manual reactor scram was inserted by placing the Reactor Mode Switch to Shutdown. At 1643 [CDT] the Condensate Booster Pump A tripped on low suction pressure. At 1644 [CDT] the Reactor Feed Pump A tripped on low suction pressure. A Recirculation Flow Control Valve runback occurred as designed. Reactor Water level was approaching the Automatic Low Water Level 3 (11.4 inches) scram set point and manual actions were taken by placing the Mode Switch to Shutdown before the low level set point was reached. All systems responded as expected following the manual scram. The plant is stable in mode 3. This event is being reported under 10CFR 50.72(b)(2)(iv)(B), as any event or condition that results in actuation of the Reactor Protection System (RPS), when the reactor is critical.
"The NRC Senior Resident Inspector has been notified."
All control rods fully inserted, and decay heat is being removed through the turbine bypass valves to the main condenser. The licensee is investigating the cause of the event. | |