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Event Notification Report for December 21, 2010

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
12/20/2010 - 12/21/2010

** EVENT NUMBERS **


46392 46444 46491 46492 46493 46494 46495 46496 46499

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 46392
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [ ] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: FRANK KICH
HQ OPS Officer: STEVE SANDIN
Notification Date: 11/04/2010
Notification Time: 03:05 [ET]
Event Date: 11/04/2010
Event Time: 01:23 [EDT]
Last Update Date: 12/20/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
Person (Organization):
JOHN WHITE (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

CHARGING PUMP '23' DECLARED INOPERABLE DURING SURVEILLANCE TESTING

"On November 4, 2010 at 0123 [EDT], '23' Charging Pump was declared inoperable due to not meeting required test parameters during surveillance testing. '23' Charging Pump is required for remote shutdown per Technical Specification 3.3.4, Remote Shutdown, and is a single component system intended to perform the inventory control safety function. Since '23' Charging Pump has been declared inoperable, a loss of safely function has occurred and is reportable per 10CFR50.72 (b)(3)(v)(A).

"The cause of the inoperability is under investigation. Per Technical Specification 3.3.4, Remote Shutdown, '23' Charging Pump must be restored to operable status within 30 days."

The licensee will inform the NY State PSC (Public Service Commission) and the NRC Resident Inspector.

* * * RETRACTION FROM CHARLES ROKES TO DONG PARK AT 1028 EST ON 12/20/10 * * *

"Indian Point Unit 2 is withdrawing the 8-hour non-emergency notification made on November 4, 2010, at 0305 EST. The notification on November 4, 2010, reported a safety system functional failure (SSFF) as a result of declaring the 23 Charging Pump (CP) inoperable. The 23 CP failed to meet test parameters during testing. Because the 23 CP is credited in Technical Specification (TS) 3.3.4 for Remote Shutdown, the inoperable condition was determined to be a loss of safety function. The TS 3.3.4 Allowed Outage Time (AOT) for inoperable conditions is 30 days. The remote shutdown function is not credited in the accident analysis.

"Subsequent investigations determined that during a two year comprehensive test (IST) the 23 CP failed the flow test due to low pump discharge flow (79.3 gpm) at the prescribed test speed (85% of rated speed). Troubleshooting determined that the 23 CP recirculation line valves 1279 and 4902 had leak-by of approximately 6.7 gpm. The leak-by results in a reduction of available discharge flow from the 23 CP to the Reactor Coolant System (RCS) due to a small amount of the pump discharge being diverted through the recirculation line. Engineering determined that the CP capacity for emergency boration with the recirculation line valves leak-by was within the capability of the 23 CP to maintain overall system function. The 23 CP is also credited for RCS inventory maintenance per TS 3.3.4 and Station Administrative Order (SAO) 703 for fire protection. Engineering concluded that with a normal CP output of approximately 87-90 gpm and a nominal rated capacity of 98 gpm, the reduction by approximately 6.7 gpm due to leak-by did not significantly impact normal operation of the CP. Therefore, the 23 CP continues to meet the established IST requirement when the 6.7 gpm recirculation line valve leak-by is accounted for. The degraded output is associated with the system rather than the 23 CP therefore the IST requirement for the 23 CP is satisfied. Additionally, the 23 CP test was performed at approximately 85% of rated speed in accordance with the IST requirements. At 100% rated speed, the remaining available capability to the RCS would be approximately 92 gpm. Engineering concludes that although degraded the 23 CP and system can perform their intended function and no SSFF occurred."

The licensee will notify the NRC Resident Inspector. The R1DO (Perry) was notified.

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Fuel Cycle Facility Event Number: 46444
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: MARK WOLF
HQ OPS Officer: STEVE SANDIN
Notification Date: 12/01/2010
Notification Time: 15:20 [ET]
Event Date: 11/30/2010
Event Time: 05:00 [CST]
Last Update Date: 12/20/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
40.60(b)(2) - SAFETY EQUIPMENT FAILURE
Person (Organization):
SCOTT SHAEFFER (R2DO)
KING STABLEIN (NMSS)

Event Text

LOSS OF POWER TO INSTRUMENTATION IN THE OPERATING UNITS OF THE FEED MATERIALS BUILDING

"Description of the Event: This report is performed pursuant to 10 CFR 40.60(b)(2) reporting requirements.

"On Tuesday, November 30, 2010, at approximately 0500, the failure of F-Substation caused a loss of instrumentation in operating units in the Feed Materials Building. At 0505, various weight, temperature and pressure indications were not available.

"Due to the loss of power to a load cell component, the UF6 Vaporizer weight exceeded the administrative limit. During the power loss the vessel's weight measurement was not available to the operator.

"At 0538, power was restored and instrumentation readings returned to normal. The loss of the Vaporizer weight control did not have any safety consequences.

"Isotope, Quantities and Chemical Form: No material release.

"Personnel Radiation Exposure Date (if applicable): No additional exposure to radiation or radioactive materials."

The licensee will inform the NRC Region II Office.

* * * RETRACTION FROM MICHAEL GREENO TO JOE O'HARA AT 1659 ON 12/20/10 * * *

"On December 1, 2010, Honeywell Metropolis Works made notification of Event #46444 to the NRC Operations Center. This November 30, 2010 incident occurred due to the loss of power to a load cell component. During the power loss the weight measurement was not available to the operator, and the UF6 Vaporizer weight exceeded the administrative limit.

"This twenty-four hour report was made following 10 CFR 40.60(b)(2) reporting requirements:

"Each licensee shall notify the NRC within 24 hours after the discovery of any of the following events involving licensed material: ...

"(2) An event in which equipment is disabled or fails to function as designed when:
(i) The equipment is required by regulation or license condition to prevent releases exceeding regulatory limits, to prevent exposures to radiation and radioactive materials exceeding regulatory limits, or to mitigate the consequences of an accident;
(ii) The equipment is required to be available and operable when it is disabled or fails to function; and
(iii) No redundant equipment is available and operable to perform the required safety function.

"As determined by Honeywell's safety analysis, potential UF6 release may occur due to failure to control process resulting in process vessel failure. UF6 Vaporizer load cells, which are identified in the safety analysis as a safety feature to control the total weight in this vessel, were not operable during the incident. However, load cells are not the only component designed to perform the equivalent safety function - to prevent UF6 Vaporizer failure. Thus, UF6 Vaporizer failure due to over-pressurization is prevented by the existing relief system which is designed to relieve at a pressure below the maximum allowable working pressure. This Vaporizer relief system was available and operable during the event.

"As a result of these additional considerations, Honeywell determined that the redundant equipment (Vaporizer relief system) was available and operable to perform the required safety function (Vaporizer failure prevention), and therefore the initially reported incident (# 46444) does not meet the reporting requirement (iii). Since this incident does not constitute a reportable event, Honeywell requests to withdraw its event notification #46444."

Notified R2DO(Henson) and NMSS EO(Davis)

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Power Reactor Event Number: 46491
Facility: VOGTLE
Region: 2 State: GA
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: HANS BISHOP
HQ OPS Officer: PETE SNYDER
Notification Date: 12/20/2010
Notification Time: 01:09 [ET]
Event Date: 12/20/2010
Event Time: 00:21 [EST]
Last Update Date: 12/20/2010
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
JAY HENSON (R2DO)
LUIS REYES (R2)
MICHELE EVANS (NRR)
BRUCE BOGER (NRR)
JEFFERY GRANT (IRD)
CHIP STRANGFELD (DHS)
STEPHEN HOLLIS (FEMA)

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

FIRE IN FUEL HANDLING BUILDING HVAC PANEL

"Smoke and sparks were identified as coming from a level 4 Control Building Normal Fuel Handling Building HVAC Heater Control Panel. The heater control panel was deenergized. The fire team was dispatched. The fire was contained in the heater control panel. Smoke removal is in progress."

The licensee notified the NRC Resident Inspector.

* * * UPDATE FROM HANS BISHOP TO PETE SNYDER AT 0219 EST ON 12/20/10 * * *

At 0218 the licensee terminated the Notice of Unusual Event.

Notified R2DO (Henson), NRR EO (Evans), DHS (Strangfeld), and FEMA (Hollis).

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Power Reactor Event Number: 46492
Facility: SEQUOYAH
Region: 2 State: TN
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: STEVE TUTHILL
HQ OPS Officer: DONG HWA PARK
Notification Date: 12/20/2010
Notification Time: 03:47 [ET]
Event Date: 12/20/2010
Event Time: 00:50 [EST]
Last Update Date: 12/20/2010
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):
JAY HENSON (R2DO)
MICHELE EVANS (NRR)
JEFFERY GRANT (IRD)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 M/R Y 100 Power Operation 0 Hot Standby

Event Text

MANUAL REACTOR TRIP DUE TO A FIRE IN THE MAIN GENERATOR BUS DUCT

"At 0050 EST on 12/20/2010, Unit 1 reactor was manually tripped due to a reported fire inside the Unit 1 main generator bus duct.

"A fire was reported at 0045 EST in the Unit 1 bus duct which is located inside the turbine building. The Unit 1 reactor was tripped to remove power from the generator bus. After the reactor trip, the fire was extinguished by the application of water to the bus duct by the fire brigade. The fire was reported extinguished at 0100 EST.

"Method of decay heat removal is via steam dumps. Current temperature and pressure: Temp. 548 degrees and stable; Pressure 2239 psig and stable. No indication of any primary/secondary leakage. All rods are inserted. Electrical alignment is normal, supplied from off-site power. No impact to Unit 2, [and] Unit 2 is operating at 100% power [in] Mode 1."

The NRC Resident Inspector has been notified.

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Power Reactor Event Number: 46493
Facility: PEACH BOTTOM
Region: 1 State: PA
Unit: [2] [3] [ ]
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: CHRIS WEICHLER
HQ OPS Officer: PETE SNYDER
Notification Date: 12/20/2010
Notification Time: 05:15 [ET]
Event Date: 12/20/2010
Event Time: 07:00 [EST]
Last Update Date: 12/20/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
DANIEL HOLODY (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
3 N Y 100 Power Operation 100 Power Operation

Event Text

TECHNICAL SUPPORT CENTER VENTILATION MAINTENANCE

"On 12/20/10, at 0700, planned maintenance is being performed on the Onsite Technical Support Center (TSC) Ventilation System. Air handling unit #1 for the TSC supply ventilation is undergoing its 5 year PM. The TSC ventilation system will be tested following maintenance and returned to normal in service lineup. The system is expected to be out of service for a total time of 8 hours.

"This report is being submitted pursuant to 10CFR50.72(b)(3)(xiii) as a result of a reduction in the effectiveness of the Onsite Technical Support Center."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 46494
Facility: POINT BEACH
Region: 3 State: WI
Unit: [1] [2] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: ALEX RIVAS
HQ OPS Officer: DONG HWA PARK
Notification Date: 12/20/2010
Notification Time: 10:48 [ET]
Event Date: 12/20/2010
Event Time: 06:24 [CST]
Last Update Date: 12/20/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
ERIC DUNCAN (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 Hot Standby 0 Hot Standby

Event Text

EVENT REQUIRING OFFSITE NOTIFICATION WITH POTENTIAL MEDIA INTEREST

"On 12/20/10 at approximately 0624 CST, the control room received notification that a vehicle/pedestrian accident had occurred on plant property near the south office building complex outside of the protected area. An emergency medical technician from the station's security department immediately responded to the scene of the accident to render emergency medical treatment. A 911 call was placed to local authorities to obtain response by appropriate agencies. Local fire department and ambulance services responded to the site. The individual was transported via helicopter to a trauma center in Green Bay, Wisconsin.

"The Senior Resident Inspector has been notified of this event. A press release is not planned at this time, however, the station will respond to media inquiries as needed. This event is being reported in accordance with 10 CFR 50.72(b)(2)(xi)."

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Power Reactor Event Number: 46495
Facility: OYSTER CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-2
NRC Notified By: ERIC SWAIN
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 12/20/2010
Notification Time: 11:01 [ET]
Event Date: 12/20/2010
Event Time: 08:05 [EST]
Last Update Date: 12/20/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
NEIL PERRY (R1DO)

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

Event Text

FISH KILL CAUSED BY RATE OF TEMPERATURE CHANGE IN DISCHARGE CANAL

"At 0938 hours (EST), the New Jersey Department of Environmental Protection (NJDEP) was notified of a fish kill. The fish kill is due to the rate of temperature change in the discharge canal, associated with an unscheduled and non-routine plant shutdown for a reactor recirculation pump repair. As of 0930 hours, seven (7) Speckled Sea Trout and two (2) Black Drums were reported dead west of the route 9 bridge in the stations discharge canal.

"The [New Jersey Pollutant Discharge Elimination System] NJPDES discharge to surface water permit No. 0005550 part IV-B/C item 11, rate of temperature change states, "The rate of temperature change shall not cause mortality of fish or shellfish."

"This report is being made in accordance with 10 CFR 50.72(b)(2)(xi) for the occurrence of any event or situation related to protection of the environment, for which a news release is planned or notification to other government agencies has been made."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 46496
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: TOM PROELL
HQ OPS Officer: JOHN KNOKE
Notification Date: 12/20/2010
Notification Time: 12:26 [ET]
Event Date: 12/20/2010
Event Time: 03:57 [CST]
Last Update Date: 12/20/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
ERIC DUNCAN (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

Event Text

FUEL POOL/REACTOR BUILDING EXHAUST PLENUM PRIMARY POWER SUPPLY FAILED

"At 0357 December 20, 2010 the 'A' division Fuel Pool/Reactor Building Exhaust Plenum Primary Power Supply failed, resulting in upscale readings on both the Fuel Pool and Reactor Building Ventilation Plenum radiation monitors. This condition resulted in closure of the Group II Primary Containment Isolation Valves (PCIV), isolation of Secondary Containment (SCT), initiation of the Standby Gas Treatment System (SBGT), and a transfer of the Control Room Ventilation (CRV) and Control Room Emergency Filtration (CREF) systems to the High Radiation Mode. Conditions and Required Actions were entered for Technical Specification 3.3.6.2 (SCT Instrumentation), 3.3.7.1 (CREF Instrumentation), and 3.4.5 (RCS Leakage Detection - CAM). Radiation levels were verified to be normal in the affected areas. Isolations signals were reset and Secondary Containment ventilation systems were restored to a normal lineup.

"Repairs are currently in progress to replace the high voltage power supply to the affected radiation monitors and are expected to complete within the required action time limits of the applicable technical specifications."

The licensee is in a 24 hour LCO. The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 46499
Facility: SAN ONOFRE
Region: 4 State: CA
Unit: [ ] [2] [3]
RX Type: [1] W-3-LP,[2] CE,[3] CE
NRC Notified By: TRAVIS FELDER
HQ OPS Officer: DONG HWA PARK
Notification Date: 12/21/2010
Notification Time: 01:40 [ET]
Event Date: 12/20/2010
Event Time: 20:20 [PST]
Last Update Date: 12/21/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
GREG WERNER (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
3 N N 0 Refueling 0 Refueling

Event Text

ACCESS TO PRIMARY EMERGENCY OPERATIONS FACILITY NOT POSSIBLE DUE TO FLOODING

"Notified by the Security Shift Commander at 2020 [PST] that access to the primary EOF is not possible due to flooding. San Onofre will activate the alternate EOF if an event is declared. There are no other affected systems or loss to emergency response capabilities due to this flooding."

Access to the site has not been impacted due to the flooding. The NRC Resident Inspector has been notified.

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