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Event Notification Report for November 29, 2010

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
11/26/2010 - 11/29/2010

** EVENT NUMBERS **


46427 46436 46440 46441 46442

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Fuel Cycle Facility Event Number: 46427
Facility: PORTSMOUTH LEAD CASCADE
RX Type: URANIUM ENRICHMENT FACILITY
Comments: 2 DEMOCRACY CENTER
                   6903 ROCKLEDGE DRIVE
                   BETHESDA, MD 20817
Region: 2
City: PIKETON State: OH
County: PIKE
License #: SNM-7003
Agreement: Y
Docket: 70-7003
NRC Notified By: JIM MCCLEERY
HQ OPS Officer: JOE O'HARA
Notification Date: 11/18/2010
Notification Time: 16:40 [ET]
Event Date: 11/18/2010
Event Time: 13:41 [EST]
Last Update Date: 11/29/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
PART 70 APP A (c) - OFFSITE NOTIFICATION/NEWS REL
Person (Organization):
ALAN BLAMEY (R2DO)
TIM MCCARTIN (NMSS)
JEFFERY GRANT (IRD)

Event Text

OFFSITE NOTIFICATION TO OSHA DUE TO ONSITE FATALITY

The American Centrifuge Plant reported an employee collapsed in the Centrifuge Test and Training Facility, was transported offsite to a medical facility, and subsequently died. Initial reports indicate that the employee died of natural causes.

The licensee notified Region 2 (D. Hartland) of the event.

* * * UPDATE FROM CRABTREE TO KLCO ON 11/19/2010 AT 1054 EST * * *

On 11/18/2010, at 1551 EST, the licensee commenced notification of OSHA and completed notification at 1602 EST on the same day.

Notified R2DO (Rich), NMSS-E(McCartin) and IRD (Grant).


* * * UPDATE AT 1555 EST ON 11/29/10 FROM THOMAS MARTIN TO ERIC SIMPSON * * *

The licensee called with administrative corrections (facility, docket and license numbers) to the original event notification.

Notified R2DO (Schaffer), NMSS-E(Benner) and IRD (Grant).

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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: 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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Power Reactor Event Number: 46441
Facility: MILLSTONE
Region: 1 State: CT
Unit: [ ] [2] [ ]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: RICHARD VIGNEAU
HQ OPS Officer: HOWIE CROUCH
Notification Date: 11/28/2010
Notification Time: 17:27 [ET]
Event Date: 11/28/2010
Event Time: 15:15 [EST]
Last Update Date: 11/28/2010
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):
DON JACKSON (R1DO)

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

Event Text

AUTOMATIC REACTOR TRIP AFTER TURBINE TRIP DUE TO LOSS OF CONDENSER VACUUM

"Loss of two circulating water pumps in one condenser caused a high main condenser backpressure. The high main condenser back pressure caused an automatic main turbine and reactor trip while critical >15%.

"Low steam generator water level following the trip caused an automatic Auxiliary Feedwater actuation. The low water level condition has cleared. Normal post-trip response has been verified and the plant is stable."

The licensee removed one circulating water pump from service in preparation of performing scheduled maintenance when the other circulator unexpectedly tripped. The cause of the pump trip is under investigation. During the trip, all rods inserted into the core. There were no primary safety valves that lifted during the transient but main steam safeties "chattered" during the transient and have fully reseated. There is no known primary to secondary leakage. The electrical grid is stable and supplying plant loads in a normal shutdown electrical lineup. The reactor is stable at normal operating pressure and temperature with decay heat being removed via the steam dumps to condenser.

The licensee has notified the State of Connecticut Department of Environmental Protection, the town of Waterford, CT, and the NRC Resident Inspector.

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Power Reactor Event Number: 46442
Facility: VOGTLE
Region: 2 State: GA
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: AL SWEAT
HQ OPS Officer: PETE SNYDER
Notification Date: 11/29/2010
Notification Time: 19:20 [ET]
Event Date: 11/29/2010
Event Time: 16:12 [EST]
Last Update Date: 11/29/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
SCOTT SHAEFFER (R2DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 98 Power Operation 98 Power Operation

Event Text

PLANT COMPUTER MAINTENANCE OUTAGE

"At 1612 today, November 29, 2010 Unit 2 Integrated Plant Computer (IPC) was shutdown for upgrade work. This includes the SPDS [Safety Parameter Display] system which is a function of the IPC. The IPC will be returned to service in approximately two weeks and SPDS function will be restored at that time. In addition, the ERDS [Emergency Response Data System] is out of service and will be restored in the same time frame.

"Per the 50.54.Q that was prepared by our Emergency Preparedness group, notification has been made to the NRC ERDS group (Roger Chow) of the unavailability of the ERDS. While the IPC is out of service, control board indications are being utilized by the control room crew. In addition, the safety-related Plant Safety Monitoring System (PSMS) is operable. Restoration of SPDS and ERDS functions have been given the highest priority during restoration of the system. Both the NRC Ops Center and the NRC ERDS group will be notified when SPDS and ERDS capability have been restored."

The licensee notified the NRC Resident Inspector.

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Tuesday, August 11, 2015