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Event Notification Report for February 28, 2013

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
02/27/2013 - 02/28/2013

** EVENT NUMBERS **


48606 48768 48773 48774 48787 48788 48789 48790 48791

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Non-Agreement State Event Number: 48606
Rep Org: US GEOLOGICAL SURVEY
Licensee: US GEOLOGICAL SURVEY
Region: 4
City: MENLO PARK State: CA
County:
License #: 04-06674
Agreement: Y
Docket:
NRC Notified By: CRAIG HENDRICKSON
HQ OPS Officer: CHARLES TEAL
Notification Date: 12/19/2012
Notification Time: 14:17 [ET]
Event Date: 11/20/2012
Event Time: 15:07 [PST]
Last Update Date: 02/27/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(ii) - LOST/STOLEN LNM>10X
Person (Organization):
BLAIR SPITZBERG (R4DO)
FSME EVENT RESOURCE (EMAI)
MEXICO (FAX)

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

Event Text

POTENTIAL LOST OR STOLEN C-14 SOURCE

The licensee is reporting approximately 1.35 mCi of C-14 in liquid form that is missing from it's Menlo Park facility.

On March 18, 1991, it was reported by the licensee to the Menlo Park Radiation Safety Committee that they had in their possession 9.3 mCi of C-14 which exceeded their maximum possession limit for their permit. At the time they recorded that, they had ordered, or logged as ordered, 5 mCi and 0.25 mCi of C-14. However, the licensee could not find any records that those isotopes had been actually received.

The RSO believes that the cause of the discrepancy between the quantity they actually have on-hand and the quantity that should be in inventory, as indicated by records, is due to a bookkeeping error. On November 7, 1990, the records show that they transferred 1.725 mCi which would leave a balance of 2.171 mCi. This transfer does not show up on the records until August 20, 1991. The quantity was adjusted on the record to 2.173 mCi. They believe that back in 1991 they misreported the amount of Carbon-14 that they actually had in inventory and the error was carried forward.

The licensee is going to start doing physical inventories of all isotopes on a 6-month basis as a corrective action.

* * * RETRACTION FROM HENDRICKSON TO SNYDER AT 1658 ON 2/27/13 * * *

This report was made due to an inventory error. This is event is retracted.

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

This source is not amongst those sources or devices identified by the IAEA Code of Conduct for the Safety & Security of Radioactive Sources to be of concern from a radiological standpoint. Therefore is it being categorized as a less than Category 3 source

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Agreement State Event Number: 48768
Rep Org: TENNESSEE DIV OF RAD HEALTH
Licensee: K & S ASSOCIATES, INC.
Region: 1
City: NASHVILLE State: TN
County:
License #: R-19136-B15
Agreement: Y
Docket:
NRC Notified By: LAURA TURNER
HQ OPS Officer: BILL HUFFMAN
Notification Date: 02/19/2013
Notification Time: 15:00 [ET]
Event Date: 02/18/2013
Event Time: [EST]
Last Update Date: 02/19/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
TODD JACKSON (R1DO)
FSME EVENTS RESOURCE (E-MA)

Event Text

AGREEMENT STATE REPORT - BEAM IRRADIATOR EQUIPMENT FAILURE

The following event notification was received from Tennessee Division of Radiological Health via e-mail:

"On Monday, February 18, 2013, the Division of Radiological Health received notification regarding K&S's Eldorado 78 device, and the failure of the source drawer not moving to the ON position. After the Eldorado device was turned on, the console indicated all interlocks were clear, however, when the beam was activated the source drawer did not move to the ON position. A Foss Therapy Technician was contacted and will make a service call on Wednesday February 20, 2013. The device is identified as Foss Therapy Services, Inc., Eldorado 78 Beam Irradiation Device, containing an International Isotopes Idaho, Inc. Co-60 source. Model and Serial No., INIS-SF-X.X-YY-Z.

"A written report is being prepared and will be sent to the Tennessee Division of Radiological Health."

Tennessee Report: TN-13-028

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Agreement State Event Number: 48773
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: FORMOSA PLASTICS CORPORATION
Region: 4
City: POINT COMFORT State: TX
County:
License #: TX - 03893
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: BILL HUFFMAN
Notification Date: 02/20/2013
Notification Time: 16:07 [ET]
Event Date: 02/19/2013
Event Time: [CST]
Last Update Date: 02/20/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
GEOFFREY MILLER (R4DO)
FSME EVENTS RESOURCE (E-MA)

Event Text

AGREEMENT STATE REPORT - SOURCES STUCK IN PROCESS GAUGES

The following report was received from the Texas Department of State Health Services, Radiation Branch, via e-mail:

"On February 20, 2013, the Agency was notified by the licensee that on February 19, 2013, during routine maintenance checks the sources on two nuclear gauges were found stuck inside the dip tubes. Both gauges are Berthold model 21357 gauges each containing a 500 millicurie (original activity) cesium - 137 source. In this type gauge, the source is moved from the source housing inside a tube to the desired location. The sources are stuck in the normal operating position and do not pose an exposure risk to any individual. The licensee has contacted the manufacturer for repairs.

"[The Texas Radiation Branch classifies this report as a] 30.50(b)(2) event type involving equipment failure or disability to function as designed when equipment is required to be available and operable and no redundant equipment is available and operable, includes source disconnection and failure to retract source.

"Additional information will be provided as it is received in accordance with SA - 300."

Texas Report I-9043

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Agreement State Event Number: 48774
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: STERIGENICS
Region: 4
City: FT. WORTH State: TX
County:
License #: L03851
Agreement: Y
Docket:
NRC Notified By: ROBERT FRESS
HQ OPS Officer: BILL HUFFMAN
Notification Date: 02/20/2013
Notification Time: 17:01 [ET]
Event Date: 02/20/2013
Event Time: [CST]
Last Update Date: 02/20/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
GEOFFREY MILLER (R4DO)
FSME EVENTS RESOURCE (E-MA)

Event Text

AGREEMENT STATE REPORT - IRRADIATOR SOURCE RETRACTION MALFUNCTION

The following report was received from the Texas Department of State Health Services, Radiation Branch, via e-mail:

"The licensee RSO reported that, during securing the source rack [on a pool irradiator], a tote on the conveyor became lodged against the rack mechanism causing it to halt before being completely secured. The maintenance manager and an operation technician were able to dislodge the tote without receiving any additional exposure. They manually moved the conveyor belt dislodging the tote and allowing the rack to continue to its secure position in the irradiator pool. The licensee will submit a complete report within 30 days.

"[The Texas Radiation Branch classifies this report as a] 30.50(b)(2) event type involving equipment failure or disability to function as designed when equipment is required to be available and operable and no redundant equipment is available and operable, includes source disconnection and failure to retract source."

Texas Report I-9044

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Power Reactor Event Number: 48787
Facility: FORT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: (1) CE
NRC Notified By: SCOTT MOECK
HQ OPS Officer: BILL HUFFMAN
Notification Date: 02/27/2013
Notification Time: 00:55 [ET]
Event Date: 02/26/2013
Event Time: 20:12 [CST]
Last Update Date: 02/27/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
DON ALLEN (R4DO)

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

Event Text

RELAY BACKING PLATE FASTENERS DISCOVERED TO BE AT LESS THAN SPECIFIED TORQUE

"During a follow-up review of off-site testing of a sample of General Electric model HFA relays, it was discovered that some of these relays did not pass testing for full qualification in their as-found condition. Additional torquing of the relay backing plate mounting screws was required to fully meet the required qualification. Further investigation into the as-found condition of these relays installed in the plant continues at this time. The relays in question are installed in Engineered Safeguards Features, Auxiliary Feed Water, and 4160 volt systems and are used in protective and actuation functions. "

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 48788
Facility: VOGTLE
Region: 2 State: GA
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BILL DUNN
HQ OPS Officer: DONALD NORWOOD
Notification Date: 02/27/2013
Notification Time: 02:07 [ET]
Event Date: 02/26/2013
Event Time: 23:02 [EST]
Last Update Date: 02/27/2013
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):
RANDY MUSSER (R2DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 M/R Y 94 Power Operation 0 Hot Standby

Event Text

MANUAL REACTOR TRIP DUE TO EXCESSIVE REACTOR COOLANT PUMP SEAL LEAKOFF FLOW

"At 2302 EST, Vogtle Unit Two was manually tripped in response to excessive Reactor Coolant Pump #4, seal #1 leakoff flow. Seal leakoff flow exceeded the procedural limits for continued operation of the pump. Following the reactor trip, RCP #4 was shutdown per procedure guidance.

All systems operated correctly in response to the reactor trip. All control rods fully inserted. The Auxiliary Feed Water (AFW) system automatically actuated as expected. System responses allowed for an uncomplicated reactor trip response. The plant is stable in Mode 3 during cause investigation.

"The NRC Senior Resident was notified and is enroute to the plant for investigation."

AFW is supplying the steam generators and decay heat removal is to the condenser via steam dumps. No safety valves or relief valves lifted during the transient. The unit is in a normal post-trip electrical line-up. There was no impact on Unit One.

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Power Reactor Event Number: 48789
Facility: OCONEE
Region: 2 State: SC
Unit: [1] [2] [3]
RX Type: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP
NRC Notified By: BYRON Le CROY
HQ OPS Officer: STEVE SANDIN
Notification Date: 02/27/2013
Notification Time: 14:47 [ET]
Event Date: 02/26/2013
Event Time: 20:30 [EST]
Last Update Date: 02/27/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
RANDY MUSSER (R2DO)

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
3 N Y 100 Power Operation 100 Power Operation

Event Text

SEWAGE SPILL IN THE TURBINE BUILDING THAT DISCHARGED TO THE KEOWEE RIVER

"On 2/26/13 at 2030 hrs [EST], a four (4) inch sewage line in the Oconee Nuclear Station turbine building failed. This failure allowed sanitary wastewater to spill into the turbine building basement. An estimated 750 gallons entered into trench drains and traveled to the station sump which discharges into the conventional wastewater system. This conventional wastewater system is discharged to the Keowee River from NPDES (National Pollutant Discharge Elimination System) outfall 002. The discharge of outfall 002 is into the Keowee River below the Keowee Hydro Station. The normal discharge path for sanitary wastewater is to the City of Seneca, South Carolina (SC). South Carolina Department of Health and Environmental Control (SCDHEC) and the Oconee Joint Regional Sewer Authority (OJRSA) were notified of the spill on 2/27/13 at approximately 1358 hrs [EST].

"Note: SCDHEC requires the reporting of any overflow that reaches waters of the state, for overflows that exceed an estimated 500 gallons that don't reach water, and for any overflow that may cause a public health or environment concern.

"This event was determined to be reportable pursuant to 10CFR50.72(b)(2)(xi) due to notification of the SCDHEC and OJRSA.

"Initial Safety Significance: The sewage leak did not contain any plant produced radiological material and due to dilution, this event posed no safety risk with respect with respect to the health and safety of the public.

"Corrective Actions: The affected portions of the sanitary sewage system has been isolated and an investigation is underway to determine the cause. There was no impact on plant operations, and the cleanup has been completed. The event was entered into the correction action program.

"The licensee notified the NRC Resident Inspector."

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Power Reactor Event Number: 48790
Facility: CALVERT CLIFFS
Region: 1 State: MD
Unit: [ ] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: RAY HOFFMAN
HQ OPS Officer: PETE SNYDER
Notification Date: 02/27/2013
Notification Time: 16:08 [ET]
Event Date: 02/27/2013
Event Time: 15:38 [EST]
Last Update Date: 02/27/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
ART BURRITT (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N N 0 Defueled 0 Defueled

Event Text

PLANNED MAINTENANCE ON UNIT 2 PLANT PROCESS COMPUTER

"Calvert Cliffs Nuclear Power Plant will perform planned maintenance on the Unit 2 Plant Process Computer (PPC) and associated network infrastructure starting on February 27, 2013. The maintenance will remove the Unit 2 PPC for a planned duration of 5 days and will render the Unit 2 ERDS out of service for this timeframe. The current outage schedule has power being restored on 03/04/2013.

"Should an emergency be declared during this period, the Control Room will continue to have the capability to retrieve plant data inputs to assess plant conditions and perform core damage assessment at all times. Control Room Emergency Response personnel will use emergency response procedures to disseminate plant parameter data points to the effected Emergency Response Facilities until the U-2 PPC is restored. MIDAS (Meteorological Data) transmission will remain functional during the maintenance window. The Unit 2 ERDS data will not be available during the power outage from 02/27/2013 to 03/04/2013.

"All work associated with this plant data network software installation will be performed in an expeditious manner consistent with the goal of minimizing unavailability of the systems listed above. ERDS was functionally tested before the outage and will be in service as soon as power is restored."

The licensee will notify the NRC Resident Inspector.

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Power Reactor Event Number: 48791
Facility: LASALLE
Region: 3 State: IL
Unit: [1] [2] [ ]
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: TOM DEAN
HQ OPS Officer: BILL HUFFMAN
Notification Date: 02/28/2013
Notification Time: 09:43 [ET]
Event Date: 02/28/2013
Event Time: 04:00 [CST]
Last Update Date: 02/28/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
JAMNES CAMERON (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 N 0 Refueling 0 Refueling

Event Text

SECONDARY CONTAINMENT DOOR INTERLOCK MALFUNCTION

"This report is being made pursuant to 10 CFR 50.72(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 identified that both doors of the interlock opened simultaneously when the door on the reactor building side was opened. 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 less than -0.25" H2O 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.

Page Last Reviewed/Updated Thursday, February 28, 2013
Thursday, February 28, 2013