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Event Notification Report for November 26, 2010

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
11/24/2010 - 11/26/2010

** EVENT NUMBERS **


46196 46430 46436 46437 46438 46440

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 46196
Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: SETH BELL
HQ OPS Officer: STEVE SANDIN
Notification Date: 08/22/2010
Notification Time: 00:15 [ET]
Event Date: 08/21/2010
Event Time: 17:00 [CDT]
Last Update Date: 11/24/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
GEOFFREY MILLER (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

ONE TRAIN ECCS DECLARED INOPERABLE DUE TO VOID IN "A" RHR HEAT EXCHANGER

"On 8/21/10 at 1700 [CDT] with the Unit in Mode 1, 100% power, Engineering personnel provided information to the Control Room that a known void in the 'A' Residual Heat Removal (RHR) heat exchanger could move from the heat exchanger to other locations in the Emergency Core Cooling System (ECCS). The analysis provided by a vendor indicates that during a specific RCS leak scenario with a failure of the A' RHR Pump, our [Unit 1] piping configuration could potentially allow the void to be swept from the 'A' RHR heat exchanger and be transported to the 'A' Centrifugal Charging Pump (CCP) and 'A' Safety Injection Pump (SIP) while in the cold leg recirculation mode of operation. This condition results in one train of ECCS being inoperable. The ECCS safety function is maintained due to redundant and interconnecting piping, in both injection and recirculation phases of operation.

"The NRC Resident has been informed."

The licensee declared one train of ECCS inoperable placing Unit 1 in the 72-hour Technical Specification [TS] 3.5.2, Condition A, Action A.1. Corrective actions are on going to remove the void and exit the TS Action Statement.

* * * RETRACTION FROM RICK HUBBARD TO JOHN SHOEMAKER ON 11/24/10 AT 12:24 EST * * *

"Additional information has been obtained by Engineering. The largest void identified in the 'A' RHR heat exchanger would not prevent the RHR system from performing its safety function. Hydraulic analysis models of this void moving through the system have shown that no pressure pulses will occur that could challenge the structural integrity of the system. The model results also show that ingestion of the void by the higher head ECCS pumps during the ECCS recirculation mode has no adverse affect on the ECCS high head pumps and they would remain capable of performing their safety function.

"As a result, this event is not reportable per 50.72(b)(3)(ii)(B). This event is being retracted."

The licensee notified the NRC Resident Inspector. R4DO (Lantz) has been notified.

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General Information or Other Event Number: 46430
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: TEAM INDUSTRIAL SERVICES
Region: 4
City: ALVIN State: TX
County:
License #: 00087
Agreement: Y
Docket:
NRC Notified By: ANNIE BACKHAUS
HQ OPS Officer: JOE O'HARA
Notification Date: 11/22/2010
Notification Time: 11:38 [ET]
Event Date: 11/21/2010
Event Time: 12:00 [CST]
Last Update Date: 11/22/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RYAN LANTZ (R4DO)
GLENDA VILLAMAR (FSME)

Event Text

AGREEMENT STATE REPORT - SOURCE DISCONNECT AND RETRIEVAL

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

"On November 22, 2010, the [Texas Department of Health Services] Agency received notification from the licensee that it had experienced a source disconnect yesterday, November 21, 2010 at approximately 1200 CST. The licensee stated that a two person radiography crew was working at a refinery near Alvin, Texas when they experienced a source disconnect.

"The radiographers were using a QSA Global device (Model: 660-B) that housed a 67 curie, Selenium (Se) - 75 source. According to the licensee, the radiographers had made 24 exposures and on the 25th exposure, the source disconnected from the drive cable. The radiographers were able to crank the cable back into the camera, but the source remained out. The radiographers contacted their Site Radiation Safety Officer (SRSO).

"The SRSO, who is authorized to retrieve sources, traveled to the site and returned the source to the camera at approximately 1700 CST. The radiographers at the site waited for the SRSO to arrive while verifying the 2 millirem per hour boundary, and keeping constant security on the radioactive material. According to the licensee, the highest exposure measured by the radiographers' pocket dosimeters was that of the SRSO, whose dose was measured to be 45 millirem for the event.

"The licensee stated that they were unsure why the source disconnected from the drive cable. However, the licensee has contacted the manufacturer, and will send the entire set-up (camera, guide tube, drive cable, etc) to the manufacturer for inspection and repair."

TX: I-8798

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Power Reactor Event Number: 46436
Facility: FERMI
Region: 3 State: MI
Unit: [2] [ ] [ ]
RX Type: [2] GE-4
NRC Notified By: JIM KONRAD
HQ OPS Officer: DONALD NORWOOD
Notification Date: 11/24/2010
Notification Time: 16:00 [ET]
Event Date: 11/24/2010
Event Time: 15:15 [EST]
Last Update Date: 11/26/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
BILLY DICKSON (R3DO)

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

Event Text

SAFETY PARAMETER DISPLAY SYSTEM AND EMERGENCY RESPONSE DATA SYSTEM OUT OF SERVICE FOR PLANNED MAINTENANCE

"On 11/24/10 at 1515 EST, the Safety Parameter Display System (SPDS) and Emergency Response Data System (ERDS) were removed from service to support activities for a planned maintenance outage on the UPS vital bus power supply. The duration of work is expected to be approximately 48 hours. During this time, the majority of the Control Room indications remain available to the plant staff, and will be used for emergency response, if needed. Information will be communicated to the NRC using other available communication systems, if needed. The plant is currently in Mode 4, and will remain in Mode 4, for the duration of the SPDS and ERDS unavailability. Since the unavailability will last greater than 8 hours, this is considered a Loss of Emergency Assessment Capability, and reportable under 10CFR50.72(b)(3)(xiii).

"Followup notification will be made when SPDS and ERDS have been restored."

The licensee notified the NRC Resident Inspector.

* * * UPDATE AT 1850 EST ON 11/26/10 FROM JIM KONRAD TO S. SANDIN * * *

"Update to Event #46436: On 11/26/10 at 1733 EST, regarding Safety Parameter Display System (SPDS) and Emergency Response Data System (ERDS) systems removed from service to support planned maintenance on the UPS vital bus power supply.

"Planned work which resulted in the loss of SPDS and ERDS is complete. All Emergency Assessment Capabilities have been restored."

The licensee informed the NRC Resident Inspector. Notified R3DO (Dickson).

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Power Reactor Event Number: 46437
Facility: CRYSTAL RIVER
Region: 2 State: FL
Unit: [3] [ ] [ ]
RX Type: [3] B&W-L-LP
NRC Notified By: EDDIE RIFFLE
HQ OPS Officer: HOWIE CROUCH
Notification Date: 11/24/2010
Notification Time: 17:43 [ET]
Event Date: 11/24/2010
Event Time: 15:50 [EST]
Last Update Date: 11/24/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
DANIEL RICH (R2DO)

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

Event Text

OFFSITE NOTIFICATION DUE TO RELEASE OF AN OILY MIXTURE TO DISCHARGE CANAL

"During maintenance activities at Crystal River Unit 3, approximately 25 to 30 gallons of an oily water mixture was pumped from a manway/vault. A small amount of this mixture was inadvertently discharged to a storm drain that leads to the Crystal River Unit 3 outfall (discharge canal). There was a slight sheen observed at the outfall as approximately 1/2 cup of the mixture entered the outfall area. This is reportable under 40CFR110 due to a light sheen observed on the site discharge canal. Crystal River Environmental Specialists responded to the spill with a combination of sand bags, floating sorbent boom, as well as sorbent pads. After deployment of the sand bags, floating sorbent booms, and securing the pumping activities, the spill status was confirmed as ceased and contained. Notifications will be made to the Florida Department of Environmental Protection State Warning Point and the National Response Center. This is 4-hour reportable per 10 CFR 50.72(b)(2)(xi) as a situation related to protection of environment, for which government agencies will be notified."

The substance discharged appears to be some sort of motor oil. Prior to pumping, a sample of the liquid was analyzed and did not contain any radioactive nuclides. The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 46438
Facility: FERMI
Region: 3 State: MI
Unit: [2] [ ] [ ]
RX Type: [2] GE-4
NRC Notified By: MARK EGHIGIAN
HQ OPS Officer: DONG HWA PARK
Notification Date: 11/25/2010
Notification Time: 09:01 [ET]
Event Date: 11/25/2010
Event Time: 03:57 [EST]
Last Update Date: 11/25/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xii) - OFFSITE MEDICAL
Person (Organization):
BILLY DICKSON (R3DO)

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

Event Text

INJURED PERSONNEL WITH SEVERED CONTAMINATED FINGERS TRANSPORTED OFFSITE

"No reactor systems were impacted, no initiations of any safety systems or any plant events occurred. Report is for transportation of contaminated fingers with an injured non-contaminated person to a hospital for potential reattachment.

"Fermi 2 is currently in a refueling outage. At 0300, the control room was informed that an individual, who was assisting in rigging of a Reactor Shield Block ([approximately] 100 tons), received an injury when his fingers were pinched between the Reactor Cavity wall and the Reactor Shield Block severing portions of two fingers.

"The portions of the fingers remained in PC Clothing (gloves) and decontamination was unsuccessful. The fingers were treated as contaminated material and transported to the hospital by radiation protection personnel. This material [contaminated fingers] was deemed unusable and at 0540 all bio-hazard/contaminated material was returned to the Fermi site."

The NRC Resident Inspector has been notified.

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Power Reactor Event Number: 46440
Facility: DRESDEN
Region: 3 State: IL
Unit: [ ] [ ] [3]
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: DAN MILLER
HQ OPS Officer: HOWIE CROUCH
Notification Date: 11/26/2010
Notification Time: 23:36 [ET]
Event Date: 11/26/2010
Event Time: 17:34 [CST]
Last Update Date: 11/26/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
BILLY DICKSON (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
3 N Y 20 Power Operation 20 Power Operation

Event Text

HIGH PRESSURE COOLANT INJECTION DECLARED INOPERABLE DUE TO A STEAM LEAK

"While performing the High Pressure Coolant Injection (HPCI) high pressure run required by SR 3.5.1.6 following Unit 3 refueling outage D3R21, a steam leak developed from the HPCI turbine. The steam leak resulted in a HPCI room high temperature alarm and the HPCI turbine was manually tripped. The U3 HPCI system was declared inoperable and Tech Spec LCO 3.5.1 condition G.1 and G.2 were entered.

"The condition is being reported in accordance with 10 CFR 50.72 (b)(3)(v)(D) as a condition that at the time of discovery could have prevented the fulfillment of the safety function of a system that is needed to mitigate the consequences of an accident.

"Maintenance activities are currently in progress to restore system to operable status."

The failure resulted in the licensee entering a 14-day LCO action statement for restoration. The licensee has notified the NRC Resident Inspector.

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