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Event Notification Report for January 20, 2016

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
01/19/2016 - 01/20/2016

** EVENT NUMBERS **


51547 51645 51647 51648 51662 51663 51664

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Power Reactor Event Number: 51547
Facility: TURKEY POINT
Region: 2 State: FL
Unit: [3] [ ] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: NICHOLAS DESANTIS
HQ OPS Officer: STEVEN VITTO
Notification Date: 11/18/2015
Notification Time: 09:53 [ET]
Event Date: 11/18/2015
Event Time: 03:26 [EST]
Last Update Date: 01/19/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
MIKE ERNSTES (R2DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
3 N N 0 Cold Shutdown 0 Cold Shutdown

Event Text

INVALID ACTUATION OF 3A EMERGENCY DIESEL GENERATOR (EDG)

"This is a non-emergency eight hour notification in accordance with 10 CFR 50.72(b)(3)(iv)(A), for an automatic actuation of the 3A Emergency Diesel Generator (EDG).

"On 11/18/15 at approximately 0326 [EST] a loss of power was experienced on the 3A 4KV Bus. The redundant 3B 4KV bus did not experience a loss of power. All systems operated as expected following the loss of power with the 3A EDG automatically sequencing onto the 3A 4KV bus and the load sequencer loading as designed. At the time of the actuation, Unit 3 was in a refueling outage in MODE 5. Investigation into the cause of the loss of power is in progress. There was no impact on Unit 4 operation during this time."

The NRC Resident Inspector has been informed.

* * * UPDATE AT 2100 EST ON 01/19/16 FROM JIM SPEICHER TO S. SANDIN * * *

The licensee is retracting the original notification of a valid actuation and has re-categorized this as a 60-day optional report based on the following:

"This 60-day telephone notification is being made under the reporting requirements specified by 10 CFR 50.73(a)(2)(iv)(A) and 10 CFR 50.73(a)(1) to describe an invalid actuation of the 3A EDG. The 3A EDG start resulted from an unexpected actuation of the 3A load sequencer during setup activities for the 3A Engineered Safeguards Integrated Test (ESIT) loss of offsite power (LOOP) sequence.

"On November 18, 2015, at approximately 0330 EST with Unit 3 in Mode 5 during a refueling outage, an unexpected LOOP occurred on the 3A 4160 V bus. At the time, an Instrument and Control (I&C) specialist was working in sequencer cabinet 3C23A verifying proper placement of flags in preparation for the installation of a local test switch that would be used to initiate the 3A ESIT LOOP signal. The 3A EDG started and functioned as designed. Initial troubleshooting determined that there were no actual plant conditions or parameters (e.g., undervoltage, degraded voltage, manual initiation) involved in the actuation.

"The root cause investigation revealed that individuals working in the room near the open cabinet did not have their mobile phones in airplane mode as required and two computer tablets being used adjacent to the sequencer cabinet were not in airplane mode as required prior to entering the 3A sequencer room. The cause of the actuation was determined to be an unintended human interaction in the form of electromagnetic or radio frequency interference at the proximity of the 3C23A cabinet.

"The licensee notified the NRC Resident Inspector."

Notified R2DO (McCoy).

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Agreement State Event Number: 51645
Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: CENTRAL TESTING CO., INC.
Region: 4
City: SULPHUR State: LA
County:
License #: LA-2393-L01A
Agreement: Y
Docket:
NRC Notified By: JAMES PATE
HQ OPS Officer: HOWIE CROUCH
Notification Date: 01/12/2016
Notification Time: 10:56 [ET]
Event Date: 01/11/2016
Event Time: 03:16 [CST]
Last Update Date: 01/12/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RAY KELLAR (R4DO)
LANCE ENGLISH (ILTA)
PAMELA HENDERSON (NMSS)
NMSS_EVENTS_NOTIFICA (EMAI)

Event Text

AGREEMENT STATE REPORT - QUANTITY OF CONCERN ATTEMPTED THEFT

Unauthorized entry and attempted theft of Category 2 material. Licensee informed local law enforcement.

Louisiana Event Report ID # LA160001

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Agreement State Event Number: 51647
Rep Org: TEXAS DEPT OF STATE HEALTH SERVICES
Licensee: QUALSPEC SERVICES INC
Region: 4
City: CORPUS CHRISTI State: TX
County:
License #: 06351
Agreement: Y
Docket:
NRC Notified By: GENTRY HEARN
HQ OPS Officer: STEVEN VITTO
Notification Date: 01/12/2016
Notification Time: 11:31 [ET]
Event Date: 01/11/2016
Event Time: 22:45 [CST]
Last Update Date: 01/12/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RAY KELLAR (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)

Event Text

AGREEMENT STATE REPORT - RADIOGRAPHY SOURCE COULD NOT BE RETRACTED TO SHIELDED POSITION

The following information was provided by the State of Texas via email:

"On January 12, 2016, the Agency [Texas Department of State Health Services] received notice that on January 11, 2016, a radiography source could not be retracted to the shielded position. The camera was an 880D with a 99.8 curie Iridium-192 source. An extension to the guide tube had not been connected, and the drive cable slipped the gears of the crank assembly. The drive cable and crank assembly were reassembled and the source was returned to the shielded position. No overexposures resulted from this event. Additional information will be provided as it is received in accordance with SA-300."

Texas Incident #: I-9370

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Non-Agreement State Event Number: 51648
Rep Org: CRITTENTON HOSPITAL MEDICAL CENTER
Licensee: CRITTENTON HOSPITAL MEDICAL CENTER
Region: 3
City: ROCHESTER State: MI
County:
License #: 21-13562-01
Agreement: N
Docket:
NRC Notified By: WILLIAM BELL Jr.
HQ OPS Officer: DONALD NORWOOD
Notification Date: 01/12/2016
Notification Time: 15:39 [ET]
Event Date: 01/11/2016
Event Time: [EST]
Last Update Date: 01/12/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
35.3045(a)(1) - DOSE <> PRESCRIBED DOSAGE
Person (Organization):
ERIC DUNCAN (R3DO)
NMSS_EVENTS_NOTIFIC (EMAI)

Event Text

MEDICAL EVENT - PATIENT RECEIVED DOSE GREATER THAN PRESCRIBED

In preparation for lymphoscintigraphy, a patient was injected with 2.4 mCi of unfiltered technetium sulfur colloid (Tc-99) instead of the prescribed dose of 0.5 to 1.0 mCi.

The Radiation Safety Officer and Hospital Medical Physicist were notified. The patient's primary physician was also notified. No adverse effects to the patient are expected.

This event was caused by the administering technologist's failure to double check the dose given to the patient. The technologist has been counseled.

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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Fuel Cycle Facility Event Number: 51662
Facility: GLOBAL NUCLEAR FUEL - AMERICAS
RX Type: URANIUM FUEL FABRICATION
Comments: LEU CONVERSION (UF6 TO UO2)
                   LEU FABRICATION
                   LWR COMMERICAL FUEL
Region: 2
City: WILMINGTON State: NC
County: NEW HANOVER
License #: SNM-1097
Agreement: Y
Docket: 07001113
NRC Notified By: SCOTT MURRAY
HQ OPS Officer: STEVE SANDIN
Notification Date: 01/19/2016
Notification Time: 15:56 [ET]
Event Date: 01/18/2016
Event Time: 21:00 [EST]
Last Update Date: 01/19/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
PART 70 APP A (b)(2) - LOSS OR DEGRADED SAFETY ITEMS
Person (Organization):
GERALD MCCOY (R2DO)
NMSS_EVENTS_NOTIFIC (EMAI)

Event Text

ACCUMULATION OF URANIUM OXIDE POWDER IN THE DRY SCRAP RECYCLE FURNACE OFF-GAS SYSTEM

"It was discovered on 1/18/16, that an accumulation of uranium oxide existed that indicated a degradation of an IROFS [Item Relied On For Safety] in the dry scrap recycle furnace off-gas system. Approximately 42 kg of uranium oxide powder was removed from the favorable geometry off-gas dropout. The degraded IROFS resulted in a failure to meet performance requirements in the event of a fire. The dry scrap recycle operation had been shut down on 1/14/16 and was not in operation at the time.

"Additional controls on combustibles, geometry and moderation remained intact and at no time was an unsafe condition present.

"Additional corrective actions, extent of condition, and extent of cause are being investigated.

"This event is being communicated to meet the reporting requirements of 10CFR70, Appendix A(b)(2)."

The licensee will inform State and local agencies and NRC Region II.

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Power Reactor Event Number: 51663
Facility: SALEM
Region: 1 State: NJ
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: THOMAS MULHOLLAND
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 01/19/2016
Notification Time: 17:42 [ET]
Event Date: 01/19/2016
Event Time: 16:30 [EST]
Last Update Date: 01/19/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
HAROLD GRAY (R1DO)

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

UNANALYZED CONDITION DISCOVERED DURING REVIEW OF OUTAGE DATA

"On January 19, 2016, while reviewing outage data, plant staff recognized that anomalous data collected in October, 2015, for the 21 Auxiliary Feed Pump time response loop resulted in an unanalyzed condition. Preliminary investigation has revealed that the condition most likely existed since April 20, 2015, when maintenance activities were performed on the auxiliary feedwater pump discharge pressure transmitter. Consequently, there were multiple instances when one of the other auxiliary feedwater pumps was removed from service, thus creating a condition which did not meet the accident analysis assumptions for auxiliary feedwater flow initial response.

"This event is being reported under the requirements of 10 CFR 50.72(b)(3)(ii)(B) as 'the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety.' This condition was corrected on November 20, 2015."

The auxiliary feedwater pump discharge pressure transmitter instrument isolation valve was inadvertently left closed after the April 20, 2015 maintenance.

The licensee has notified the NRC Resident Inspector and will notify the State of New Jersey, State of Delaware, and the local township.

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Power Reactor Event Number: 51664
Facility: DRESDEN
Region: 3 State: IL
Unit: [ ] [2] [3]
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: ROBERT MONTGOMERY
HQ OPS Officer: STEVE SANDIN
Notification Date: 01/19/2016
Notification Time: 18:41 [ET]
Event Date: 01/20/2016
Event Time: 04:00 [CST]
Last Update Date: 01/19/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
JAMNES CAMERON (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
3 N Y 100 Power Operation 100 Power Operation

Event Text

TECHNICAL SUPPORT CENTER OUT OF SERVICE FOR PLANNED PREVENTATIVE MAINTENANCE

"At 0400 CST on Wednesday, January 20, 2016, the Dresden Nuclear Power Station (DNPS) Technical Support Center (TSC) emergency ventilation system will be removed from service for planned maintenance activities. During the maintenance, the TSC Ventilation will be shut down. The TSC air filtration fan and dampers will be non-functional, rendering the TSC HVAC accident mode non-functional. This maintenance is scheduled to minimize out of service time. The planned TSC ventilation outage is scheduled to be completed in approximately 43 hours.

"Contingency plans are in place so that if an emergency is declared requiring TSC activation during this period, the TSC will be staffed and activated using existing Emergency Planning (EP) procedures and checklists. If radiological or environmental conditions require TSC facility evacuation during ventilation system restoration; the Station Emergency Director will relocate the TSC staff in accordance with station procedures.

"The NRC Resident Inspector has been notified."

Page Last Reviewed/Updated Wednesday, January 20, 2016
Wednesday, January 20, 2016