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Event Notification Report for October 23, 2013

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
10/22/2013 - 10/23/2013

** EVENT NUMBERS **


49438 49439 49440 49443 49459 49460 49461 49462 49463 49464

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Non-Agreement State Event Number: 49438
Rep Org: EQ DETROIT
Licensee: EQ DETROIT
Region: 3
City: DETROIT State: MI
County:
License #: GENERAL
Agreement: N
Docket:
NRC Notified By: KRISTEN ROCHWALL
HQ OPS Officer: BILL HUFFMAN
Notification Date: 10/14/2013
Notification Time: 14:50 [ET]
Event Date: 10/14/2013
Event Time: [EDT]
Last Update Date: 10/14/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
Person (Organization):
RICHARD SKOKOWSKI (R3DO)
PAMELA HENDERSON (FSME)
FSME EVENTS RESOURCE (E-MA)

Event Text

SURFACE CONTAMINATION DISCOVERED ON SEALED SOURCE DURING BIANNUAL WIPE TEST

A general license holder reported a leaking Nickel-63 source that is used in an Agilent Electron Capture Detector. The source was wipe tested and discovered to have a surface contamination of 0.011 micro-curies. The Ni-63 source for the detector has a rated source strength of 15 micro-curies. The company sent the source to a contractor for further determination if the source is leaking or can be cleaned and returned to service.

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Agreement State Event Number: 49439
Rep Org: OK DEQ RAD MANAGEMENT
Licensee: OKLAHOMA DEPARTMENT OF TRANSPORTATION
Region: 4
City:  State: OK
County: WOODWARD
License #: OK-15794-01
Agreement: Y
Docket:
NRC Notified By: KEVIN SAMPSON
HQ OPS Officer: BILL HUFFMAN
Notification Date: 10/14/2013
Notification Time: 15:16 [ET]
Event Date: 10/10/2013
Event Time: [CDT]
Last Update Date: 10/14/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
MICHAEL HAY (R4DO)
PAMELA HENDERSON (FSME)
FSME EVENTS RESOURCE (E-MA)

Event Text

AGREEMENT STATE REPORT - DAMAGED TROXLER MOISTURE DENSITY GAUGE

The following report was received from the Oklahoma Department of Environmental Quality via e-mail:

"On Oct. 10 we were informed by the Oklahoma Dept. of Transportation that one of their Troxler Model 3440 gauges (S/N 32291) had been run over at a road construction site on Hwy 412 east of Woodward, OK. The Radiation Safety Officer responded to the site that day, recovered the gauge and transported it back to their facility in Oklahoma City. Department of Environmental Quality staff inspected the gauge the next day. Although the source rod had been completely snapped off, it did not appear that either of the sealed sources had been damaged."

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Agreement State Event Number: 49440
Rep Org: KENTUCKY DEPT OF RADIATION CONTROL
Licensee: MOMENTIVE SPECIALTY CHEMICAL
Region: 1
City: LOUISVILLE State: KY
County:
License #: GL 401-349-10
Agreement: Y
Docket:
NRC Notified By: CURT PENDERGRASS
HQ OPS Officer: BILL HUFFMAN
Notification Date: 10/14/2013
Notification Time: 16:10 [ET]
Event Date: 06/17/2013
Event Time: [CDT]
Last Update Date: 10/14/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JON LILLIENDAHL (R1DO)
PAMELA HENDERSON (FSME)
FSME EVENTS RESOUCE (E-MA)

Event Text

AGREEMENT STATE REPORT - STUCK PROCESS GAUGE SHUTTERS

The following information was received from the Kentucky Radiation Health Branch via facsimile:

"Kentucky Radiation Health Branch (RHB) was notified by telephone on 10/2/13 by a representative from a generally licensed facility, Momentive Specialty Chemicals, of the fact that the shutter ON-OFF control mechanisms had been stuck in the open position on two level gauges undergoing routine servicing almost four (4) months previously. The two gauges, Thermo TN Technologies model 7063P each with 100 mCi Cs-137 [sources] (S/N S92BO601 and S94K1101) were being routinely serviced by a licensed manufacturer, VEGA Americas, on June 17, 2013 when the shutters were found to be stuck in the open position. The VEGA service representatives returned to the licensee's two days later (6/19/13) and repaired the sticking shutters so they would operate freely.

"The VEGA representatives informed the general licensee's representative that a report to RHB was required but the person responsible for the gauges and for making the report was not notified of the problem until almost four months later. When he did learn of the event and the reporting requirement, he reported the event to RHB by telephone on 10/2/13 and followed up with a written report on 10/11/13.

"The reporting criteria is defined in 902 KAR 100:050 Section 3(3)(c)5 and 10 CFR 31.5(c)(5)."

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Agreement State Event Number: 49443
Rep Org: COLORADO DEPT OF HEALTH
Licensee: MARTINEZ ASSOCIATES, LLC
Region: 4
City: DENVER State: CO
County:
License #: 1076-01
Agreement: Y
Docket:
NRC Notified By: JAMES JARVIS
HQ OPS Officer: BILL HUFFMAN
Notification Date: 10/15/2013
Notification Time: 13:53 [ET]
Event Date: 10/13/2013
Event Time: [MDT]
Last Update Date: 10/17/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
MICHAEL HAY (R4DO)
FSME EVENTS RESOURCE (E-MA)
PAMELA HENDERSON (FSME)
ILTAB (E-MA)

This material event contains a "Less than Cat 3" level of radioactive material.

Event Text

AGREEMENT STATE REPORT - STOLEN TROXLER MOISTURE DENSITY GAUGE

The following report was received from the Colorado Department of Public Health and Environment Radioactive Materials Unit via e-mail:

"On Tuesday, October 15, 2013, at approximately 8:30 am MDT (Mountain Daylight Time), the Radiation Safety Officer (RSO) for a portable gauge licensee (Martinez Associates, LLC; Colorado License No. 1076-01, Amendment 09) based in Denver, Colorado notified the Colorado Department of Public Health and Environment (CDPHE) Radioactive Materials Unit that a Troxler moisture density gauge was stolen on Sunday, October 13, 2013 from a private vehicle parked at the private residence of an employee. The private residence was located in Thornton, Colorado. The stolen gauge was last used on Friday, October 11, 2013 and the theft was reported (by the employee) to the RSO and local law enforcement (Thornton, Colorado, Police) on Sunday, October 13, 2013 at approximately 8:30 pm MDT.

"The stolen gauge was a Troxler model 3430 (gauge serial number 23358), containing approximately 8 mCi (03/17/1994 assay date) of Cs-137 (source serial #75-5374) and 40 mCi (03/08/1994 assay date) of Am-241:Be (source serial #47-19240).

"CDPHE will conduct an investigation and evaluation of the circumstances surrounding the reported theft and intends to issue a press release regarding the incident. Further details and information from the licensee is pending."

* * * UPDATE FROM JAMES JARVIS TO CHARLES TEAL ON 10/16/13 AT 0944 EDT * * *

"On October 15, 2013, the Radiation Program of the Colorado Department of Public Health and Environment (CDPHE) reported to the NRC Operations Center that a gauge had been stolen from an apartment complex in Thornton, Colorado. The City of Thornton, Colorado Police reported to CDPHE at approximately 10 pm on October 15, 2013 that the gauge had been recovered and that suspects were in custody. The gauge was transported to the City of Thornton Police for further criminal evaluation. The CDPHE will assist the Thornton Police as they evaluate the device."

Notified R4DO (Hay), FSME (Henderson), ILTAB (Wray) via email, and FSME Event Resource via email.

* * * UPDATE FROM JAMES JARVIS TO CHARLES TEAL ON 10/17/13 AT 1019 EDT * * *

"In our email dated 10/16/13 (7:43 am), it was incorrectly reported that the Thornton, Colorado Police Department (PD) had suspects in custody. The Thornton PD had questioned suspects at the time of their notification to our agency, but did not have the individuals in custody nor were any arrests made. All other information is correct to the best of our knowledge and the gauge remains in the custody of the police at this time."

Notified R4DO (Azua), ILTAB (Wray) and FSME Event Resource via email.

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

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Fuel Cycle Facility Event Number: 49459
Facility: HONEYWELL INTERNATIONAL, INC.
RX Type: URANIUM HEXAFLUORIDE PRODUCTION
Comments: UF6 CONVERSION (DRY PROCESS)
Region: 2
City: METROPOLIS State: IL
County: MASSAC
License #: SUB-526
Agreement: Y
Docket: 04003392
NRC Notified By: ROSS LINDBERG
HQ OPS Officer: PETE SNYDER
Notification Date: 10/22/2013
Notification Time: 12:41 [ET]
Event Date: 10/22/2013
Event Time: 09:30 [CDT]
Last Update Date: 10/22/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
40.60(b)(3) - MED TREAT INVOLVING CONTAM
Person (Organization):
STEVEN VIAS (R2DO)
MICHELE SAMPSON (NMSS)

Event Text

EMPLOYEE EXPERIENCING CHEST PAIN TRANSPORTED FOR OFFSITE MEDICAL TREATMENT

"An employee experiencing chest pains reported to the on-site dispensary this morning. The plant nurse administered first aid and then sent the employee to an off-site medical facility. A whole body survey of the employee's plant clothing was performed. The maximum amount of contamination found was present on the employee's right boot, 197,000 dpm/100cm2. Prior to leaving the Restricted Area, the employee's plant clothing was removed, and he was whole body frisked out of the plant. The employee was free of contamination upon release."

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Power Reactor Event Number: 49460
Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: MOT HEDGES
HQ OPS Officer: DONALD NORWOOD
Notification Date: 10/22/2013
Notification Time: 12:43 [ET]
Event Date: 08/23/2013
Event Time: 07:54 [PDT]
Last Update Date: 10/22/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
WAYNE WALKER (R4DO)

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

60-DAY OPTIONAL TELEPHONIC NOTIFICATION FOR AN INVALID PRIMARY CONTAINMENT ISOLATION VALVE ACTUATION

"At 0754 on 8/23/13, a loss of power to the Reactor Protection System (RPS) 'B' occurred due to the unexpected opening of the circuit breaker (RPS-CB-MG2) for the RPS 'B' motor generator due to a failure of the voltage regulator circuit card. The loss of RPS 'B' resulted in a half scram signal, closure of Primary Containment Isolation Valves (PCIVs) from multiple systems and loss of power to main steam line radiation monitors (MS-RIS-610B & MS-RIS-610D). No plant parameters or maintenance activities existed which would cause the opening of RPS-CB-MG2 or actuation of the primary containment isolation; therefore, this is considered to be an invalid actuation of a system listed in 10CFR50.73(a)(2)(iv).

"The half scram signal, closure of Primary Containment Isolation Valves (PCIVs) from multiple systems, and loss of power to main steam line radiation monitors were an expected response to the loss of RPS 'B'.

"RPS 'B' was repowered from an alternate power supply. The half scram signal was reset, the containment isolation valves were opened and the affected systems were returned to normal operation. The voltage regulator circuit card was replaced and RPS 'B' was returned to its normal power supply.

"As indicated in 10CFR50.73(a)(1), in the case of an invalid actuation reported under 10CFR50.73(a)(2)(iv)(A), the licensee may, at its option, provide a telephonic notification to the NRC Operations Center within 60 days of discovery of the event instead of submitting a written LER. This 60-day telephone notification is being made to meet the reporting requirements instead of submitting an LER since the actuation was invalid.

"The following additional information is provided as specified in NUREG-1022:

"The specific train(s) and system(s) that were actuated: PCIVs in multiple systems
EDR-V-19 Drywell Equipment Drain Inboard Isolation Valve
EDR-V-20 Drywell Equipment Drain Outboard Isolation Valve
FDR-V-3 Drywell Floor Drain Inboard Isolation Valve
FDR-V-4 Drywell Floor Drain Outboard Isolation Valve
RWCU-V-1 Reactor Water Cleanup Suction Inboard Isolation Valve
RWCU-V-4 Reactor Water Cleanup Suction Outboard Isolation Valve
RRC-V-19 Reactor Water Sample Inboard Isolation Valve
RRC-V-20 Reactor Water Sample Outboard Isolation Valve
TIP-V-15 Traversing In-Core Probe Purge Isolation Valve
CRD-V-11 Control Rod Drive Scram Discharge Volume Drain Valve

"Whether each train actuation was complete or partial:
All PCIVs actuations for a loss of RPS 'B' were complete.
The reactor half scram for a loss of RPS 'B' was a partial activation.

"Whether or not the system started and functioned successfully:
All PCIVs functioned successfully."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 49461
Facility: VOGTLE
Region: 2 State: GA
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: KEVIN LOWE
HQ OPS Officer: DONALD NORWOOD
Notification Date: 10/22/2013
Notification Time: 13:18 [ET]
Event Date: 10/22/2013
Event Time: 11:44 [EDT]
Last Update Date: 10/22/2013
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):
STEVEN VIAS (R2DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 M/R Y 27 Power Operation 0 Hot Standby

Event Text

MANUAL REACTOR TRIP DUE TO DECREASING CONDENSER VACUUM

"At 1144 EDT, Vogtle Unit Two was manually tripped in response to lowering Main Condenser vacuum. The Unit 2 Bravo Main Feed Pump was tagged out for scheduled maintenance and the casing was being removed when condenser vacuum started lower due to isolation valve not holding pressure. Main Condenser vacuum lowered to less than procedural limits for continued plant operation.

"All systems operated correctly in response to the reactor trip. All control rods fully inserted. AFW was placed in service to control Steam Generator levels. System response allowed for an uncomplicated reactor trip response. Plant is stable in Mode 3 while performing a cause investigation.

"The NRC Senior Resident Inspector was notified and at plant site."

The plant is in a normal post-trip electrical line-up. Decay heat is being removed via the steam dumps to the Main Condenser.

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Power Reactor Event Number: 49462
Facility: LASALLE
Region: 3 State: IL
Unit: [1] [2] [ ]
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: JASON DEPRIEST
HQ OPS Officer: DONALD NORWOOD
Notification Date: 10/22/2013
Notification Time: 15:34 [ET]
Event Date: 10/22/2013
Event Time: 11:29 [CDT]
Last Update Date: 10/22/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
ROBERT ORLIKOWSKI (R3DO)

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

SECONDARY CONTAINMENT PERSONNEL AIR LOCK DOOR INTERLOCK FAILURE

"This report is being made pursuant to 10CFR50.72(b)(3)(v)(C), 'Event or condition that could have prevented fulfillment of a safety function needed to control the release of radioactive material.' An employee entered a secondary containment interlock and while the door was closing, another employee opened the other secondary containment interlock door thereby having two doors open. The employee immediately secured both doors in the interlock and notified the main control room supervisor. Both doors in the interlock were open for approximately 10 seconds. With both doors open, TS SR 3.6.4.1.2 was not met. This rendered secondary containment inoperable per TS 3.6.4.1. Reactor Building differential pressure, as observed in the main control room, has remained satisfactory and less than -0.25 inches of H20 at all times. Initial investigation determined that a mechanical interlock for the doors was malfunctioning. Administrative controls have been put in place to ensure the doors remain closed pending repairs to the mechanical interlock."

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 49463
Facility: CALVERT CLIFFS
Region: 1 State: MD
Unit: [1] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: TIM HUBER
HQ OPS Officer: PETE SNYDER
Notification Date: 10/22/2013
Notification Time: 16:59 [ET]
Event Date: 10/22/2013
Event Time: 10:59 [EDT]
Last Update Date: 10/22/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
DANIEL HOLODY (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
2 N Y 100 Power Operation 100 Power Operation

Event Text

RANDOM FITNESS FOR DUTY CONFIRMED POSITIVE FOR A NON-LICENSED CONTRACT SUPERVISOR

A non-licensed contract employee supervisor had a confirmed positive for alcohol during a random fitness for duty test. The contractor's access to the plant has been terminated.

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 49464
Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [1] [2] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: MICHAEL SMITH
HQ OPS Officer: DONALD NORWOOD
Notification Date: 10/22/2013
Notification Time: 19:28 [ET]
Event Date: 10/22/2013
Event Time: 14:00 [EDT]
Last Update Date: 10/22/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
DANIEL HOLODY (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
2 N Y 100 Power Operation 100 Power Operation

Event Text

POSTULATED HOT SHORT FIRE EVENT THAT COULD ADVERSELY IMPACT SAFE SHUTDOWN EQUIPMENT

"A review of industry operating experience regarding the impact of unfused Direct Current (DC) ammeter circuits in the control room has determined the described condition to be applicable to Nine Mile Point, Units 1 and 2 resulting in an unanalyzed condition with respect to 10 CFR 50 Appendix R analysis requirements. The original plant wiring design and associated analysis for the Class 1E batteries control room ampere indications do not include overcurrent protection features to limit the fault current.

"In the postulated event, a fire in the control room could cause one of the ammeter wires to short to the ground plane. Simultaneously, it is postulated that the fire causes another DC wire from the opposite polarity on the same battery to also short to the ground plane. This could cause a ground loop through the unprotected ammeter wiring. This event could result in excessive current flow (i.e., heating) in the ammeter wiring to the point of causing a secondary fire in the raceway system. The secondary fire could adversely affect safe shutdown equipment and potentially cause the loss of the ability to conduct a safe shutdown as required by 10 CFR 50 Appendix R. This condition has been entered into the Nine Mile Point corrective action program as Condition Reports CR-2013-008747 (NMP1) and CR-2013-008749 (NMP2).

"This condition is being reported in accordance with 10 CFR 50.72(b)(3(ii)(B). Interim compensatory measures (i.e., fire watches) have been implemented for affected areas of the plants.

"The licensee has notified the NRC Resident Inspector."

Page Last Reviewed/Updated Wednesday, October 23, 2013
Wednesday, October 23, 2013