Event Notification Report for December 19, 2016

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
12/16/2016 - 12/19/2016

** EVENT NUMBERS **


47818 52417 52420 52421 52422 52424 52440 52441 52442

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Part 21 Event Number: 47818
Rep Org: ABB INC
Licensee: ABB INC
Region: 1
City: FLORENCE State: SC
County:
License #:
Agreement: Y
Docket:
NRC Notified By: DAVID BROWN
HQ OPS Officer: CHARLES TEAL
Notification Date: 04/09/2012
Notification Time: 17:06 [ET]
Event Date: 04/09/2012
Event Time: [EDT]
Last Update Date: 12/16/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
Person (Organization):
BLAKE WELLING (R1DO)
GERALD MCCOY (R2DO)
DAVID HILLS (R3DO)
VINCENT GADDY (R4DO)
PART 21 GROUP (EMAI)

Event Text

PART 21 REPORT - HK CIRCUIT BREAKER STUDS FAILED TO MEET SPECIFICATION

"This letter is submitted in accordance with 10 C.F.R. 21.21(d)(3)(ii) with respect to a failure to comply with the specifications associated with two studs P/N 163392A00 and 192247A00 used in medium voltage HK circuit breakers that may be subject to failure due to hydrogen embrittlement due to incorrect processing during plating. These studs were manufactured at the ABB Medium Voltage Service facility in Florence, SC from steel rod, heat treated in-house, and then sent to Surtronics for zinc plating with chromate treatment, including hydrogen embrittlement relief baking immediately following plating. A total of 51 pieces of P/N 163392A00 and 104 pieces of P/N 192247A00 were plated by Surtronics."

* * * UPDATE FROM DAVID BROWN VIA FAX AT 1309 EDT on 4/27/12 * * *

The vendor has notified the affected licensees, removed all remaining studs from inventory and will be auditing Surtronics established process during the next finishing production run.

The licensees affected include EFH/Luminant, Progress Energy and TVA.

Notified R1DO (Jackson), R2DO (Musser), R3DO (Lara) and R4DO (Proulx).

* * * UPDATE FROM DAVID BROWN TO DONG PARK VIA FAX AT 1318 EST on 12/16/16 * * *

"This [update] amends the previous 10CFR Part 21 Notification of 27 April 2012 that reported failed studs on 7.5 and 15 kV HK circuit breakers. This amendment is required to encompass a wider time period during which the stud (PIN: 163392A00) was sold for use in medium voltage HK circuit breakers. The previous report addressed orders between September 2011 and March 2012, but based upon a recent notification reported by TVA, our notification should have extended further in the past. Further research indicates that a shift in plating vendors in November 2010 is the likely starting point for this issue."

Notified R1DO (Schroeder), R2DO (Michel), R3DO (Dickson), R4DO (Kellar), and Part 21 group via email.

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Non-Agreement State Event Number: 52417
Rep Org: COMMUNITY MEDICAL CENTER
Licensee: COMMUNITY MEDICAL CENTER
Region: 4
City: MISSOULA State: MT
County: MISSOULA
License #: 503-620-6617
Agreement: N
Docket:
NRC Notified By: DAN DUGAN
HQ OPS Officer: KARL DIEDERICH
Notification Date: 12/08/2016
Notification Time: 10:51 [ET]
Event Date: 12/07/2016
Event Time: 10:30 [MST]
Last Update Date: 12/08/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
20.1906(d)(1) - SURFACE CONTAM LEVELS > LIMITS
Person (Organization):
VINCENT GADDY (R4DO)
NMSS_EVENTS_NOTIFICA (EMAI)

Event Text

SURFACE CONTAMINATION INSIDE HIGH DOSE RATE AFTERLOADER

On 12/7/16 at approximately 1030 MST, surface contamination was discovered on the interior of a High Dose Rate (HDR) afterloader. The contamination is limited to the inside of the housing and the interior portions of the transfer cables. The contamination was discovered by the manufacturer when the manufacturer was replacing the Ir-192 seeds used by the afterloader. Direct radiation readings could not be taken due to the proximity to the sources. Wipes were observed at 200 to 4000 counts per minute. There was no observed damage to the sources. There was no contamination of personnel. The room has been secured. The resolution planned is for the manufacturer to replace the afterloader.

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Agreement State Event Number: 52420
Rep Org: OHIO BUREAU OF RADIATION PROTECTION
Licensee: UNIV OF CINCINNATTI MEDICAL CTR
Region: 3
City: CINCINNATTI State: OH
County: HAMILTON
License #: 02110-31-0001
Agreement: Y
Docket:
NRC Notified By: MICHAEL SNEE
HQ OPS Officer: KARL DIEDERICH
Notification Date: 12/09/2016
Notification Time: 10:54 [ET]
Event Date: 12/07/2016
Event Time: [EST]
Last Update Date: 12/09/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
ANN MARIE STONE (R3DO)
NMSS_EVENTS_NOTIFICA (EMAI)

Event Text

AGREEMENT STATE REPORT - CANCER TREATMENT DOSE LESS THAN PRESCRIBED

The following was received from the state of Ohio via e-mail:

"On 12/9/16, the licensee reported a medical event that occurred on 12/7/16 and was discovered on 12/8/16. During a prostate seed implant procedure, the patient received a dose that was 30.57% less than the prescribed dose. The patient was informed and the physician is evaluating if a boost will be administered. The patient is not expected to have any adverse affects."

Ohio report: OH160010.

A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.

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Non-Agreement State Event Number: 52421
Rep Org: ANS CONSULTANTS
Licensee: ANS CONSULTANTS
Region: 1
City: CEDAR GROVE State: NJ
County:
License #: 29-30183-01 /
Agreement: Y
Docket:
NRC Notified By: ATUL SHAH
HQ OPS Officer: HOWIE CROUCH
Notification Date: 12/09/2016
Notification Time: 17:02 [ET]
Event Date: 12/08/2016
Event Time: 16:30 [EST]
Last Update Date: 12/12/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
Person (Organization):
ART BURRITT (R1DO)
NMSS_EVENTS_NOTIFICA (EMAI)

Event Text

TROXLER MOISTURE DENSITY GAUGE DAMAGED BY PAVING EQUIPMENT

While preparing to conduct a measurement, the gauge operator placed the gauge on the asphalt. A paving roller operator did not see the gauge and ran it over.

At the time of the accident, the source was in its shielded and locked position. While the case and controls of the gauge were damaged, there was no damage to the source or the shield. As a precaution, the Radiation Safety Officer contacted the local hazmat team to confirm the source was not damaged. A leak check swipe was performed by the gauge owner and it was sent to Troxler for evaluation. There were no overexposures to the workers or members of the public.

The gauge is a Troxler model 3430 (serial number 37669). It contains a 9 mCi Cs-137 source (serial number 77-4904) and a 44 mCi AmBe source (serial number 78-2427). The gauge will be returned to Troxler for disposal.

* * * UPDATE FROM THE STATE OF NEW JERSEY (DANIEL RICE) TO HOWIE CROUCH AT 1544 EST ON 12/12/16 * * *

The licensee also reported the event to the New Jersey Department of Environmental Protection (NJDEP) at 1630 EST on 12/9/16. Additional information included:

"The license reported the gauge user was nearby, but not in direct observation of the device, at the time of the incident.

"NJDEP will be investigating further. The incident is reportable within 24-hours under N.J.A.C. 7:28-51.1 (10 CFR 30.50(b)2). NJDEP is tracking this incident internally as incident ID# C62454. NMED Report No. to be assigned."

Notified R1DO (Schroeder) and NMSS_EVENTS_NOTIFICATION Resource, both via email.

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Non-Agreement State Event Number: 52422
Rep Org: JANX INTEGRITY GROUP
Licensee: JANX INTEGRITY GROUP
Region: 3
City: DANVILLE State: IN
County:
License #: 21-16560-01
Agreement: N
Docket:
NRC Notified By: STEVE FLICKINGER
HQ OPS Officer: HOWIE CROUCH
Notification Date: 12/09/2016
Notification Time: 17:21 [ET]
Event Date: 12/09/2016
Event Time: 09:00 [EST]
Last Update Date: 12/09/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
Person (Organization):
ANN MARIE STONE (R3DO)
NMSS_EVENTS_NOTIFICA (EMAI)

Event Text

RADIOGRAPHY SOURCE BECAME TEMPORARILY STUCK OUTSIDE OF SHIELD

While preparing to perform his first exposure of the day, the radiographer determined that the source became stuck near the camera and guide tube connection. He notified the client, verified his boundaries, and contacted the Radiation Safety Officer (RSO).

After discussion with the radiographer, the RSO believed the source was lodged due to freezing temperatures and a small amount of ice within the guide tube. The radiographer was able to obtain a heater and, after about an hour of warming the guide tube, was able to retrieve the source into the camera normally.

No overexposures occurred due to this event.

The camera is a SPEC-150 that contains 47 Ci of Ir-192.

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Agreement State Event Number: 52424
Rep Org: TEXAS DEPT OF STATE HEALTH SERVICES
Licensee: ACUREN INSPECTION INC
Region: 4
City: LA PORTE State: TX
County:
License #: 01774
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 12/10/2016
Notification Time: 11:12 [ET]
Event Date: 12/09/2016
Event Time: [CST]
Last Update Date: 12/10/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
VINCENT GADDY (R4DO)
NMSS_EVENTS_NOTIFICA (EMAI)

Event Text

AGREEMENT STATE REPORT - RADIOGRAPHY SOURCE COULD NOT BE RETRACTED

The following was received from the State of Texas via email:

"On December 10, 2016, the Agency [Texas Department of State Health Services] was notified that on December 9, 2016, the licensee [while working at Exxon Mobil in Beaumont, Texas] was required to perform a source retrieval of a 74.9 curie iridium-192 source. The exposure device associated with the source is a QSA 880 exposure device. The licensee reported the exposure device fell on the guide tube and crimped it to a point where the source could not pass by. The radiographers verified their boundaries and contacted their radiation safety officer. The licensee sent a qualified recovery team to the location. The recovery team cut the guide tube and was able to retract the source. No individual received an exposure that exceeded any limits. No member of the general public was exposed as a result of this event. The licensee stated the camera would be sent to the manufacturer for inspection. The licensee stated they would provide additional information on December 13, 2016. Additional information will be provided as it is received in accordance with SA-300."

Texas Incident #: I - 9447

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Fuel Cycle Facility Event Number: 52440
Facility: WESTINGHOUSE ELECTRIC CORPORATION
RX Type: URANIUM FUEL FABRICATION
Comments: LEU CONVERSION (UF6 to UO2)
                   COMMERCIAL LWR FUEL
Region: 2
City: COLUMBIA State: SC
County: RICHLAND
License #: SNM-1107
Agreement: Y
Docket: 07001151
NRC Notified By: NANCY PARR
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 12/16/2016
Notification Time: 09:27 [ET]
Event Date: 12/16/2016
Event Time: 07:00 [EST]
Last Update Date: 12/16/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
PART 70 APP A (c) - OFFSITE NOTIFICATION/NEWS REL
Person (Organization):
ERIC MICHEL (R2DO)
NMSS_EVENTS_NOTIFICA (EMAI)

Event Text

OFFSITE NOTIFICATION OF AN INDUSTRIAL SAFETY INCIDENT

"On December 15, 2016, a grid area employee was moving containers in the plating room, where his finger was pinched between two containers. He was taken to the emergency room where he was treated for an injury to the tip of his left ring finger. The event did not involve special nuclear material or contamination and is classified as an industrial safety incident.

"This concurrent report is being made under Paragraph (c) of 10 CFR 70, Appendix A because a 24 hour report was made to the South Carolina Department of Labor [at 0700 EST on 12/16/16] per 29CFR1904.39."

The employee was not admitted to a hospital and was sent home after treatment.

The licensee has notified NRC Region II.

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Power Reactor Event Number: 52441
Facility: ARKANSAS NUCLEAR
Region: 4 State: AR
Unit: [1] [ ] [ ]
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: STEVEN KIRSHBERGER
HQ OPS Officer: BETHANY CECERE
Notification Date: 12/17/2016
Notification Time: 05:43 [ET]
Event Date: 12/16/2016
Event Time: 14:00 [CST]
Last Update Date: 12/17/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
RAY KELLAR (R4DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 33 Power Operation 33 Power Operation

Event Text

VENTILATION SYSTEM INOPERABLE

"At approximately 1400 CST on 12/16/16, during the performance of VEF-38A Lead Penetration Room Ventilation System (PRVS) Exhaust Fan Monthly Test, flow was found to be at 2000 SCFM with an operability limit of 1620 to 1980 SCFM. VEF-38A was declared inoperable. Unit 1 entered Technical Specification Limiting Condition for Operation (LCO) 3.7.11 Condition C for both trains of PRVS inoperable. With VEF-38A aligned as the lead fan and capable of auto-start, the operable standby fan (VEF-38B) would not have started.

"During the time that VEF-38A was inoperable and capable of auto-starting, the Unit 1 PRVS was in a condition that could have prevented the control of the release of radioactive material.

"At 1546 CST on 12/16/16, Unit 1 rendered VEF-38A incapable of auto starting by placing its hand switch in PULL-TO-LOCK. Unit 1 Entered LCO 3.7.11 condition A for one PRVS train inoperable and Exited LCO 3.7.11 Condition C.

"This is a notification per 10 CFR 50.72(b)(3)(v) for a condition that could have prevented the control of the release of radioactive material."

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 52442
Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: JEFFERY KUETHER-ULBERG
HQ OPS Officer: JEFF HERRERA
Notification Date: 12/18/2016
Notification Time: 18:13 [ET]
Event Date: 12/18/2016
Event Time: 11:24 [PST]
Last Update Date: 12/18/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(A) - ECCS INJECTION
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
RAY KELLAR (R4DO)
MIKE KING (NRR)
BERNARD STAPLETON (IRD)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 A/R Y 100 Power Operation 0 Hot Shutdown

Event Text

AUTOMATIC SCRAM DUE TO LOAD REJECT FROM SUBSTATION

"On December 18, 2016 at time 1124 PST the plant experienced a full reactor scram. Preliminary investigations indicate that the scram was caused by a load reject from the Bonneville Power Administration (BPA) Ashe substation. Further investigations continue. The following conditions have occurred:

"Turbine Governor valve closure
Reactor high pressure trip
+13 inches reactor water level activations
E-TR-B (backup transformer) supplying E-SM-7/SM-8 (vital power electrical busses)
Complete loss of Reactor Closed Cooling (RCC)
E-TR-S (Startup transformer) supplying SM-1/2/3 (non-vital power electrical busses)
E-DG-1/2/3 (emergency diesel generators) auto start
Low Pressure Core Spray (LPCS) and Residual Heat Removal (RHR) A/B/C initiation signals
Main Steam Isolation Valves (MSIV) are closed

"Reactor Core Isolation Cooling (RCIC) RCIC and High Pressure Core Spray (HPCS) were manually activated and utilized to inject and maintain reactor water level. Pressure control is with Safety Relief Valves (SRV) in, manual. Level control is with RCIC and Control Rod Drive (CRD). RCIC has experienced an over speed trip that was reset so that level control could be maintained by RCIC.

"This event is being reported under the following:
10 CFR 50.72(b)(2)(iv)(A) which requires a 4 hour notification for Emergency Core Cooling System (ECCS) discharge into the reactor coolant system.
10 CFR 50.72(b)(2)(iv)(B) which requires a 4 hour notification for any event or condition that results in actuation of the Reactor Protection System (RPS) when the reactor is critical.
10 CFR 50.72(b)(3)(iv)(A) which requires an 8 hours notification for actuation of ECCS systems.

"All control rods fully inserted.

"The NRC Resident Inspector has been informed."

The licensee indicated that no increase in radiation levels were detected.

Page Last Reviewed/Updated Wednesday, March 24, 2021