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Event Notification Report for October 28, 2010

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
10/27/2010 - 10/28/2010

** EVENT NUMBERS **


46353 46356 46357 46361 46367 46368 46369

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Power Reactor Event Number: 46353
Facility: PEACH BOTTOM
Region: 1 State: PA
Unit: [2] [3] [ ]
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: BRAD DEIHL
HQ OPS Officer: ERIC SIMPSON
Notification Date: 10/22/2010
Notification Time: 16:52 [ET]
Event Date: 10/22/2010
Event Time: 10:58 [EDT]
Last Update Date: 10/27/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
72.75(c )(1) - SPENT FUEL, HLW, RX GTCC DEFECT
72.75(c )(2) - SPENT FUEL, HLW OR RX-REL GTCC RED. EFECT
Person (Organization):
MARIE MILLER (R1DO)
TIM McGINTY (NRR)
BRITTAIN HILL (NMSS)
SCOTT MORRIS (IRD)

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

SPENT FUEL STORAGE RELATED DEFECT - CASK LEAKAGE RATE GREATER THAN TECHNICAL SPECIFICATION

"On 10/22/10, at 1058 EDT, a troubleshooting of Independent Spent Fuel Storage Installation (ISFSI) Cask TN-50-A indicated that a leak existed in the cask lid sealing area at a rate greater than allowed by ISFSI Cask Technical Specification (TS) Section 3.1.3, Cask Helium Leak Rate. TS 3.1.3 limits the Cask Helium Leak Rate to 1.0 E-05 ref-cc/sec. The cask is currently in unloading operations and is located within the Peach Bottom Atomic Power Station Unit 3 containment building. Preliminary review indicates that a leak exists at the weld plug that provides sealing of the drilled interseal passageway associated with the drain port penetration of the cask lid. This leak effectively provides a bypass of the main lid outer confinement seal.

"This report if being submitted pursuant to 10CFR72.75(c)(1) as a result of a material defect in a weld in the cask main lid. This report is also being submitted pursuant to 10CFR72.75 (c) (2) as a result of a resolution in the effectiveness of the cask confinement system.

"The Certificate of Compliance for this cask is 1027 (Amendment 1).

"The NRC Resident Inspector has been informed of this notification."

* * * UPDATE AT 1515 EDT ON 10/27/10 FROM JEREMY HITE TO DONG PARK * * *

"On 10/27/10, at 1107 [EDT], troubleshooting of Independent Spent Fuel Storage Installation (ISFSI) Cask TN-68-01 identified that a helium leak exists in the cask lid sealing area at a leak rate greater than allowed by ISFSI Cask Technical Specification Section 3.1.3, Cask Helium Leak Rate. TS 3.1.3 limits the Cask Helium Leak Rate to 1.0 E-O5 ref-cc/sec. The cask was in LOADING OPERATIONS and is currently located within the [Peach Bottom Atomic Power Station] PBAPS Unit 2 containment building. Preliminary review indicates that a leak exists in the Cask Main Lid Outer Closure Seal. The cask will be repaired and tested prior to returning the cask to the Independent Spent Fuel Storage Installation (ISFSI). No release of radiation occurred as a result of this issue.

"This report is being submitted pursuant to 10CFR 72.75(c)(2) as a result of a reduction in the effectiveness of the cask confinement system.

"The Certificate of Compliance for this cask is 1027 (Amendment 0)."

The NRC Resident Inspector has been informed.

Notified R1DO (Caruso), NRR EO (Thorp), NMSS EO (Lorson), and IRD (Grant).

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General Information or Other Event Number: 46356
Rep Org: NORTH DAKOTA DEPARTMENT OF HEALTH
Licensee: NORTHERN TECHNOLOGIES INC.
Region: 4
City: FARGO State: ND
County: CASS
License #: 33-32112-01
Agreement: Y
Docket:
NRC Notified By: DAN HARMAN
HQ OPS Officer: VINCE KLCO
Notification Date: 10/23/2010
Notification Time: 14:07 [ET]
Event Date: 10/21/2010
Event Time: 09:12 [MDT]
Last Update Date: 10/23/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
VIVIAN CAMPBELL (R4DO)
KEITH McCONNELL (FSME)

Event Text

AGREEMENT STATE REPORT - DAMAGE TO TROXLER PORTABLE DENSITY GAUGE

A Troxler portable density gauge was run over by a forklift at a construction site. The source rod was retrieved into the gauge by the RSO. The damaged gauge was surveyed and then the gauge was removed for transport to the company office. The construction site was surveyed to ensure both sources were in the gauge.

The licensee is reviewing their procedures to determine what can be done to reduce the risk of this type of incident happening again.

The density gauge is a Model 3430 Troxler with a nominal 8 mCi Cs-137 gamma source and a 40 mCi Am-241:Be neutron source.

North Dakota Incident #: ND10005

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General Information or Other Event Number: 46357
Rep Org: UTAH DIVISION OF RADIATION CONTROL
Licensee: QUALITY INSPECTION AND TESTING INC.
Region: 4
City: VERNAL State: UT
County:
License #: LA11238L01
Agreement: Y
Docket:
NRC Notified By: GWYN GALLOWAY
HQ OPS Officer: PETE SNYDER
Notification Date: 10/24/2010
Notification Time: 11:34 [ET]
Event Date: 10/24/2010
Event Time: 06:00 [MDT]
Last Update Date: 10/24/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
VIVIAN CAMPBELL (R4DO)
TIM MCCARTIN (NMSS)
KEITH McCONNELL (FSME)

Event Text

AGREEMENT STATE REPORT - RADIOGRAPHER TRUCK IN ROLLOVER ACCIDENT

A radiographer from Quality Inspection and Testing, Inc was involved in a single vehicle accident 18 miles west of Vernal, Utah on highway 40. According to witnesses, the truck rolled numerous times. The state police arrived, secured the highway, contacted state radiation control, and surveyed the area. The results of the survey indicated no spread of contamination or radiation levels above background. The SPEC Model 150 radiography camera S/N 1195 containing 40 Curies of Ir-192 was undamaged and placed into the custody of another representative of Quality Inspection and Testing Inc., who arrived on the scene at the request of the state. The driver survived the accident.

The radiography company is a Louisiana licensee with reciprocity in the State of Utah.

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General Information or Other Event Number: 46361
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: TICONA POLYMERS, INC.
Region: 4
City: BISHOP State: TX
County:
License #: L02441
Agreement: Y
Docket:
NRC Notified By: RAY JISHA
HQ OPS Officer: STEVE SANDIN
Notification Date: 10/25/2010
Notification Time: 13:30 [ET]
Event Date: 10/24/2010
Event Time: [CDT]
Last Update Date: 10/25/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
DAVID PROULX (R4DO)
KEITH McCONNELL (FSME)

Event Text

SHUTTER FOUND PARTIALLY STUCK OPEN ON A FIXED NUCLEAR GAUGE

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

"On October 25, 2010, the licensee reported that while making preparations to perform plant maintenance, the shutter on a Ohmart Corporation model SH-F2-45 nuclear gauge containing 60 milliCuries (original activity) of Cesium (Cs)-137 was found to be stuck in a partially opened position. The licensee stated that they are going to shield the source to reduce the dose rate to below 2 millirem/hour, remove it form the vessel, and lock it in their Radioactive Material storage building. No significant exposure has occurred due to this event. The licensee has contacted the manufacture for repairs or replacement of the gauge. The cause for the event is under investigation. Additional information will be provided as it is received IAW SA 300."

Texas Incident #: I-8795

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Power Reactor Event Number: 46367
Facility: COOPER
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: DAVID NELSON MADSEN
HQ OPS Officer: DONG HWA PARK
Notification Date: 10/27/2010
Notification Time: 16:39 [ET]
Event Date: 08/31/2010
Event Time: 17:37 [CDT]
Last Update Date: 10/27/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
DAVID PROULX (R4DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 100 Power Operation

Event Text

INVALID PRIMARY CONTAINMENT ISOLATION SYSTEM ACTUATION DUE TO A VOLTAGE TRANSIENT

"This telephone report is being made in accordance with 10 CFR 50.73(a)(2)(iv)(A) as an event or condition caused by an invalid signal that resulted in an automatic Group 6 isolation. On August 31, 2010 at 1737 CDT, Group 6 of Primary Containment Isolation System (PCIS) actuated. This resulted in completion of Secondary Containment isolation, initiation of the Standby Gas Treatment System and Control Room Emergency Filtration System. An invalid signal occurred apparently as a result of a voltage transient on the Nebraska City 345kV line. This was from a 3-phase fault to ground due to a structural failure during a severe thunder storm with high winds.

"The equipment associated with the Group 6 isolation functioned successfully and the isolation was complete. The Group 6 PCIS was reset. Cooper Nuclear Station operators reviewed the parameters that would cause a Group 6 trip signal (i.e. reactor water level, drywell pressure, reactor building radiation) and determined there were no valid conditions that would have caused the isolation.

"This event was most likely due an act of nature, thus no corrective actions were required."

The NRC Resident Inspector will be notified.

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Power Reactor Event Number: 46368
Facility: FT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] CE
NRC Notified By: AARON CHLADIL
HQ OPS Officer: STEVE SANDIN
Notification Date: 10/27/2010
Notification Time: 17:05 [ET]
Event Date: 10/27/2010
Event Time: 12:22 [CDT]
Last Update Date: 10/27/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
DAVID PROULX (R4DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 81 Power Operation

Event Text

UNIT COMMENCED SHUTDOWN AFTER DECLARING CONTAINMENT SPRAY INOPERABLE

"During pressure drop testing of the backup nitrogen supply for HCV-345 (Containment Spray Header isolation valve) the accumulator failed its test. This renders HCV-345 inoperable. HCV-344 the opposite header isolation valve also has an air leak that appears to be of similar magnitude to the leak on HCV-345. Fort Calhoun Station is conservatively considering both valves inoperable and has entered technical specification 2.0.1 which requires shutting the plant down to hot standby within 6 hours. The plant shutdown began at 1513 CDT. Repair efforts are underway on HCV-345 and HCV-344."

The leakage on both valves was identified by systems engineering during testing.

The licensee informed the NRC Resident Inspector.

* * * UPDATE AT 1756 EDT ON 10/27/10 FROM AARON CHLADIL TO S. SANDIN * * *

At 1647 CDT, the licensee exited technical specification 2.0.1 after declaring HCV-344 operable. The Unit is currently at 74% power. The licensee will stabilize power at 70% and then commence power escalation.

The licensee informed the NRC Resident Inspector.

Notified R4DO (Proulx).

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Power Reactor Event Number: 46369
Facility: TURKEY POINT
Region: 2 State: FL
Unit: [3] [4] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: RANDY FLYNN
HQ OPS Officer: STEVE SANDIN
Notification Date: 10/27/2010
Notification Time: 18:34 [ET]
Event Date: 10/27/2010
Event Time: [EDT]
Last Update Date: 10/27/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
REBECCA NEASE (R2DO)
JOHN LUBINSKI (NRR)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
3 N N 0 Cold Shutdown 0 Cold Shutdown
4 N Y 100 Power Operation 100 Power Operation

Event Text

FITNESS FOR DUTY REPORT INVOLVING A SUPERVISOR

A licensed employee supervisor had a confirmed positive for alcohol during a random fitness-for-duty test. The employee's access to the plant has been denied. Contact the Headquarters Operations Officer for additional details.

The NRC Resident Inspector has been notified.

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Thursday, March 29, 2012