| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
09/14/2015 - 09/15/2015 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 51370 | Rep Org: NC DIV OF RADIATION PROTECTION
Licensee: NASCO PRODUCTS, INC.
Region: 1
City: MOCKSVILLE State: NC
County:
License #: 030-1338-1
Agreement: Y
Docket:
NRC Notified By: DAVID CROWLEY
HQ OPS Officer: JEFF ROTTON | Notification Date: 09/04/2015
Notification Time: 13:00 [ET]
Event Date: 08/31/2015
Event Time: 13:00 [EDT]
Last Update Date: 09/04/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
JOHNATHAN LILLIENDAH (R1DO)
NMSS_EVENTS_NOTIFIC (EMAI)
| Event Text NORTH CAROLINA AGREEMENT STATE REPORT - NUCLEAR GAUGE WITH STUCK CLOSED SHUTTER
The following information was provided by the State on North Carolina via email:
"On 8/31/15, at approximately 1300 EDT, a NASCO worker operating the #4 Protos cigarette making machine noticed that the nuclear gauge seemed to be malfunctioning. The worker immediately reported this observation to the NASCO RSO. The RSO performed a shutter test and determined that the shutter would not open. [RSO] then turned #4 Protos off and established a no-entry cordoned area around the gauge, the radius of the restricted area was and still is about 20 feet. The RSO next contacted Little Creek Electronics, a North Carolina licensee, for assistance in repairing the shutter.
"The RSO of Little Creek contacted a health physicist inspector with the NC Radiation Protection Section, on 9/2/15 to ask whether they are authorized to perform this repair. This is how the Agency [North Carolina Radiation Protection Section] learned of this incident. [Little Creek] was not authorized and instructions were given not to perform work on the gauge; the Agency decided to investigate first thing in the morning on 9/3/2015 to get the details straight from NASCO.
"State inspector visited site on 9/3/15 to perform a health and safety assessment. State inspector determined that licensee had confirmed that shutter is closed and that the associated machinery had been deactivated. Furthermore, the licensee had established a cordoned, do-not-enter area of approximately twenty feet in radius around the affected gauge. The inspector's surveys were consistent with the surveys during the last regular inspection (8/6/15) of this license.
"NASCO arranged with Automated Control Technologies (ACT), a reciprocal license which handles manufacturing and repair of fixed nuclear gauges. [ACT] should be in to the facility before close of this week."
The licensee address and location of the event is 321 Farmington Road, Mocksville, NC 27028.
Nuclear gauge is a Accuray TG-5 fixed gauge, model number: S-18, serial number S-4086-H containing a Sr-90 25 milliCi source (assay date 04/2001), and last leak test on 4/23/15 was negative.
Report identification number: NMED NC150024 |
| Agreement State | Event Number: 51372 | Rep Org: TENNESSEE DIV OF RAD HEALTH
Licensee: CHOO CHOO CUSTOMS GROUP
Region: 1
City: HIXSON State: TN
County:
License #: GL# 890
Agreement: Y
Docket:
NRC Notified By: SABRINA ROBERTSON
HQ OPS Officer: JEFF ROTTON | Notification Date: 09/04/2015
Notification Time: 15:06 [ET]
Event Date: 09/03/2015
Event Time: 13:20 [EDT]
Last Update Date: 09/04/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
JOHNATHAN LILLIENDAH (R1DO)
NMSS_EVENTS_NOTIFIC (EMAI)
ILTAB (EMAI)
|
| This material event contains a "Less than Cat 3 " level of radioactive material. | Event Text TENNESSEE AGREEMENT STATE REPORT - LOST STATIC ELIMINATOR
The following information was provided by the State of Tennessee via email:
"A General Licensed (GL) facility called Choo Choo Customs Group possessed a Po-210 static eliminator GL device with approximately 10 mCi of activity. [Choo Choo Customs Group] has been inactive or dissolved. The [State of Tennessee - Division of Radiological Health] has been trying for a number of years to get them to reply. The [Division] has had our field office staff go by the last known and suspected addresses this year (2015) to run them down but to no avail. The collections company for the [Tennessee Department of Environment and Conservation - Division of Fiscal Services] has also had no success. This would be a lost source that the [Division] would report but were hoping to get some resolution or locate the individuals who had owned the company. The [Division] has now exhausted all our leads and are proceeding with reporting it as a lost source/device."
Manufacturer: AEA Technology/USA Inc. Static Eliminator
Model: PDV1420 (PDM.1002Hn series)
Serial#: 8139KB
Isotope: Po-210 (10 mCi)
Shipped date: 6/25/1999
State Event Report ID NO.: TN-15-132
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: 51373 | Rep Org: COLORADO DEPT OF HEALTH
Licensee: PREMIER NDT
Region: 4
City: GRAND JUNCTION State: CO
County:
License #: CO 1162-01
Agreement: Y
Docket:
NRC Notified By: CHERI HALL
HQ OPS Officer: JEFF ROTTON | Notification Date: 09/04/2015
Notification Time: 22:46 [ET]
Event Date: 09/04/2015
Event Time: [MDT]
Last Update Date: 09/04/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
GREG WARNICK (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)
| Event Text COLORADO AGREEMENT STATE REPORT - BROKEN DRIVE CABLE ON RADIOGRAPHY CAMERA
The following information was provided by the State of Colorado via email:
"A radiography source stuck outside the shielded position on Friday, September 4, 2015 [at a temporary job site near Rangely, CO]. The source did not return to the shielded position after an exposure and was quickly discovered by the radiographer. Neither the radiographer nor assistant approached the source. [Both individuals] set up a 2 mR/hr boundary and ensured no person entered the area; then called the RSO for support at approximately 1400 MDT. The RSO arrived on scene and notified the State around 1700 MDT. The licensee is authorized for retrieval and verbally verified all necessary emergency equipment was available and there were no elevated exposures suspected at the time. The licensee began retrieval and contacted the State at 2000 MDT to verify the source was successfully returned to the shielded position. A full report on the cause and recovery efforts to follow.
"Cause and corrective action: broken drive cable, corrected by replacing drive cable and returning [source] to the shielded position.
"Camera/device information: QSA Global Delta 880; SN D8543
Source information: QSA Global A424-9; SN 20273G; current activity 97.7 Ci
assayed 8/26/2015 - 106.3 Ci - leak tested by manufacturer at that time
"Doses from pocket dosimeters: RSO - 110 mRem; Radiographer - 21 mRem; assistant - 4 mRem (this was the total from previous exposures during the day, he did not assist with retrieval but was tasked with maintaining surveillance of the boundaries)"
Incident identification: CO15-I15-24 |
| Power Reactor | Event Number: 51391 | Facility: FERMI
Region: 3 State: MI
Unit: [2] [ ] [ ]
RX Type: [2] GE-4
NRC Notified By: CHRIS ROBINSON
HQ OPS Officer: JEFF HERRERA | Notification Date: 09/14/2015
Notification Time: 02:46 [ET]
Event Date: 09/13/2015
Event Time: 23:05 [EDT]
Last Update Date: 09/14/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
PATTY PELKE (R3DO)
SCOTT MORRIS (NRR)
JEFFERY GRANT (IRD)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | M/R | Y | 100 | Power Operation | 0 | Hot Shutdown | Event Text MANUAL SCRAM DUE TO LOSS OF TURBINE BUILDING CLOSED COOLING WATER
"At 2305 EDT on September 13, 2015, a manual scram was initiated in response to a loss of all Turbine Building Closed Cooling Water (TBCCW). All control rods fully inserted. The lowest Reactor Water Level (RWL) reached was 137 inches. All isolations and actuations for RWL 3 occurred as expected. Decay heat was initially being removed through the Main Turbine Bypass System to the Main Condenser, however, as a result of the loss of TBCCW, the Main Feed Pumps lost cooling and had to be secured. At 2310, Standby Feedwater was initiated and Main Feedwater was secured.
"The loss of TBCCW also caused all Station Air Compressors (SACs) to trip on loss of cooling. The loss of SACs caused the Instrument Air header pressure to degrade to the point at which the Secondary Containment isolation dampers drifted closed. This resulted in the Reactor Building vacuum exceeding the Technical Specification limit. At 2325, operators started the Standby Gas Treatment system and manually initiated a Secondary Containment isolation signal. Secondary Containment vacuum was promptly restored to within Technical Specification limits. Additionally, Operators were monitoring for expected MSIV drift due to the degraded Instrument Air header pressure. When outboard MSIVs were observed to be drifting, Operators closed the outboard and inboard MSIVs at 2345. At 2352, Safety Relief Valves (SRVs) reached the Low-Low Setpoint and began cycling to control reactor pressure.
"RWL is currently being maintained in the normal level band with the Standby Feedwater and Control Rod Drive systems. Reactor Pressure is being controlled with Safety Relief Valves. Operators are currently in the Emergency Operating Procedure for Reactor Pressure Vessel control. Investigation into the loss of TBCCW continues.
"No safety-related equipment was out of service at the time of the event. All offsite power sources were adequate and available throughout the duration of the event.
"The NRC resident inspector has been notified."
* * * UPDATE AT 0555 EDT AT 09/14/15 FROM CHRIS ROBINSON TO JEFF HERRERA * * *
"At 0409 EDT the Reactor Core Isolation Cooling (RCIC) system was placed in service due to identification of an unisolable leak in the Standby Feedwater System. Reactor water level and pressure is now being controlled though the RCIC system and Safety Relief Valves. This event update is reportable as a valid manual initiation of a specified safety system under 10CFR50.72(b)(3)(iv)(A).
"The NRC resident inspector has been notified."
The leak rate was reported as approximately 5-10 gallons per minute from a weld on the standby feedwater pump header drain valve F326. The licensee reported the leak stopped once RCIC was placed into service. The licensee is still investigating the issue.
Notified the R3DO (Pelke), IRD Manager (Grant), NRR EO (Morris).
* * * UPDATE PROVIDED BY CHRIS ROBINSON TO JEFF ROTTON AT 2135 EDT ON 09/14/2015 * * *
"At 1847 EDT on September 14, 2015, a valid automatic Reactor Protection System (RPS) actuation occurred due to Reactor Water Level 3 while shutdown in MODE 3. Operators were manually controlling Reactor Pressure Vessel (RPV) level and pressure with Reactor Core Isolation Cooling (RCIC) and Safety Relief Valves (SRV). While operators were cycling SRVs, the RPV level went below the Level 3 setpoint. Operators promptly restored RPV level by manual operation of RCIC. The Level 3 actuation and associated isolations were verified to operate properly.
"The scram signal has been reset. Fermi 2 remains in MODE 3 controlling RPV Level and Pressure through manual operation of RCIC and SRVs.
"This is the second occurrence of a valid specified safety system actuation reportable under 10CFR50.72(b)(3)(iv)(A) for this ongoing event.
"The NRC Resident Inspector has been notified."
Notified R3DO (Riemer), IRD Manager (Grant), and NRR EO (Morris) |
| Power Reactor | Event Number: 51392 | Facility: SEQUOYAH
Region: 2 State: TN
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: STEVE TUTHILL
HQ OPS Officer: JEFF HERRERA | Notification Date: 09/14/2015
Notification Time: 08:12 [ET]
Event Date: 09/14/2015
Event Time: 04:26 [EDT]
Last Update Date: 09/14/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
| Person (Organization):
SCOTT SHAEFFER (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | M/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text MANUAL REACTOR TRIP DUE TO LOSS OF POWER TO VITAL INSTRUMENT BOARD
"At 0426 EDT on 9/14/2015, Sequoyah Unit 1 was at 100% power when the Vital Instrument Power Board (VIPB) 1-II deenergized. A manual reactor trip was initiated in accordance with the Abnormal Operating Procedure for the loss of VIPB 1-II.
"Following the reactor trip, all safety-related equipment operated as designed. Auxiliary Feedwater automatically initiated as expected from the Feedwater Isolation Signal.
"Unit 1 is currently being maintained in Mode 3 at NOT/NOP [Normal Operating Temperature/Normal Operating Pressure], approximately 547 degrees F and 2235 psig, with auxiliary feedwater supplying the steam generators and decay heat removal via the condenser steam dumps.
"Current Temperature and Pressure - Reactor Coolant System (RCS) temperature is 547 degrees F and stable and RCS pressure is 2235 psig and stable. There is no indication of any primary to secondary leakage. All rods fully inserted on the reactor trip and remain inserted. The electrical alignment is normal with shutdown power supplied from off-site power. There is no operational impact to Unit 2. Unit 2 continues to operate in Mode 1 at 100 [percent].
"There was no impact on public health and safety. Post-trip investigation is in progress and planned restart timeline has not yet been determined.
"The licensee notified the NRC Resident Inspector. " | |