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Event Notification Report for January 12, 2010

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
01/11/2010 - 01/12/2010

** EVENT NUMBERS **


45610 45615 45619 45620 45623 45624

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General Information or Other Event Number: 45610
Rep Org: WISCONSIN RADIATION PROTECTION
Licensee: UNKNOWN
Region: 3
City: MILWAUKEE State: WI
County:
License #:
Agreement: Y
Docket:
NRC Notified By: SHUNLAI ZHU
HQ OPS Officer: CHARLES TEAL
Notification Date: 01/06/2010
Notification Time: 11:56 [ET]
Event Date: 01/04/2010
Event Time: [CST]
Last Update Date: 01/11/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
ROBERT DALEY (R3DO)
ANGELA MCINTOSH (FSME)

Event Text

AGREEMENT STATE - MOISTURE DENSITY GAUGE FOUND IN SCRAP METAL

"The department received an email on January 4, 2010 from Miller Compressing, Milwaukee, WI, describing a load of scrap metal received on December 24, 2009 that set off the radiation detector. On January 4, 2010, they isolated a damaged Seaman Nuclear Model R-75 moisture density gauge containing 4.5 mCi of Radium-226, serial number 3276. Miller Compressing placed the device in a locked storage area. Seaman Nuclear has agreed to conduct a leak test to ensure source integrity and transport the device back to their facility in Oak Creek, WI this week."

WI Report No.: WI100001

* * * UPDATE FROM SHUNLAI ZHU TO JOE O'HARA VIA E-MAIL ON 1/11/10 AT 1115 * * *

"Seaman Nuclear conducted a leak test on January 8, 2010 and found the radioactive source was shielded and no removable contamination. They transported the device back to their facility in Oak Creek, WI."

Notified R3DO(Stone) and FSME EO(McIntosh)

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Power Reactor Event Number: 45615
Facility: FT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] CE
NRC Notified By: ERICK MATZKE
HQ OPS Officer: HOWIE CROUCH
Notification Date: 01/08/2010
Notification Time: 15:00 [ET]
Event Date: 01/08/2010
Event Time: 13:29 [CST]
Last Update Date: 01/11/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
MICHAEL SHANNON (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

EMERGENCY SIRENS MAY BE IMPACTED BY EXTREME WEATHER CONDITIONS

"The current NOAA weather forecast for the station is predicted to be about -25 degrees Fahrenheit [on the morning of January 9, 2010]. Based on this forecast, the station reviewed the impact of these temperatures on the 101 sirens in the Fort Calhoun Station 10-mile Emergency Planning Zone (EPZ). The siren manufacturer's and the FEMA approved siren design report information states that the sirens (Federal Signal model 2001) are designed for operation between the temperature readings of -22 degrees Fahrenheit and +140 degrees Fahrenheit.

"Event Numbers 44782 and 44783, on a similar condition at another utility having the same sirens, were reviewed. It was noted that the reports documented discussion with the manufacturer's technical representative confirming that the sirens are operational and no special testing is required when the temperature goes below and then returns within the operating temperature limits.

"The current temperature at the station is within the operational limits. Therefore, the 101 sirens are considered functional at this time.

"The following agencies were notified that if the temperature falls below a negative twenty-two degrees Fahrenheit, the established process of back-up route alerting is to be used notifying the public in the event of a nuclear emergency where the sirens are activated but fail to respond:

-Washington County, NE Emergency Management
-Pottawatomie County, IA Emergency Management
-Harrison County, IA Emergency Management

"This notification is being made in accordance with 10 CFR 50.72(b)(3)(xiii). No media press release is being made."

The licensee has notified the NRC Resident Inspector.

* * * UPDATE FROM ERICK MATZKE TO HOWIE CROUCH AT 1513 EST ON 1/11/10 * * *

"A review of area temperature indicates that the siren design was not exceeded."

The licensee will be notifying the NRC Resident Inspector. Notified R4DO (Hagar).

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Power Reactor Event Number: 45619
Facility: TURKEY POINT
Region: 2 State: FL
Unit: [ ] [4] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: JIM SPEICHER
HQ OPS Officer: HOWIE CROUCH
Notification Date: 01/11/2010
Notification Time: 12:54 [ET]
Event Date: 01/11/2010
Event Time: 10:55 [EST]
Last Update Date: 01/11/2010
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):
DEBORAH SEYMOUR (R2DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
4 M/R Y 30 Power Operation 0 Hot Standby

Event Text

MANUAL REACTOR TRIP INITIATED DUE TO HIGH STEAM GENERATOR LEVEL

"At 1055 on 1/11/2010, Turkey Point Unit 4 was manually tripped on high steam generator level. Steam generator level was high due to plant response to a turbine runback. The runback was manually initiated by stopping the 4A Steam Generator Feed Pump from the Control Room due to mechanical seal failure.

"At the time of the trip, reactor power was 30%. Auxiliary Feedwater was not required since Steam Generator levels were maintained above the low level actuation setpoint.

"Unit 4 has been stabilized in Mode 3 on normal off-site power. No significant equipment problems were encountered.

"This event is reportable per 10 CFR 50.72(b)(2)(iv)(B) - actuation of the Reactor Protection System with the reactor critical."

All rods inserted during the trip. There were no relief or safety valves that lifted during the transient. Decay heat is being removed via steam dumps to atmosphere. There is no known primary to secondary leakage. Unit 4 is in a normal shutdown electrical lineup. Unit 3 was not affected by the transient.

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 45620
Facility: COOK
Region: 3 State: MI
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BEN HUFFMAN
HQ OPS Officer: HOWIE CROUCH
Notification Date: 01/11/2010
Notification Time: 14:00 [ET]
Event Date: 01/12/2010
Event Time: 04:00 [EST]
Last Update Date: 01/11/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
CHRISTINE LIPA (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 Y 100 Power Operation 100 Power Operation

Event Text

UNAVAILABILITY OF TSC VENTILATION SYSTEM AND CHARCOAL FILTER FOR SCHEDULED MAINTENANCE

"The Cook Nuclear Plant (CNP) Technical Support Center (TSC) ventilation system air conditioning and filtration systems are scheduled to be removed from service for scheduled preventive maintenance at 0400 on January 12, 2010.

"Under certain accident conditions, the TSC may become unavailable due to the inability of the filtration system to maintain a habitable atmosphere. Compensatory measures exist to relocate TSC personnel to the unaffected unit's control room if necessary based upon results of procedurally required monitoring of TSC radiological conditions.

"The TSC ventilation system air conditioning and filtration systems are scheduled to be restored to service by 1400 on Tuesday January 12, 2010.

"The licensee has notified the NRC Senior Resident Inspector.

"This notification is being made in accordance with 10 CFR 50.72 (b)(3)(xiii) due to unavailability of an emergency response facility."

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Power Reactor Event Number: 45623
Facility: NORTH ANNA
Region: 2 State: VA
Unit: [1] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: PAGE KEMP
HQ OPS Officer: HOWIE CROUCH
Notification Date: 01/11/2010
Notification Time: 16:53 [ET]
Event Date: 01/11/2010
Event Time: 15:10 [EST]
Last Update Date: 01/11/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
DEBORAH SEYMOUR (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

Event Text

OFFSITE NOTIFICATION DUE TO WATER SEEPAGE ON AN ONSITE STRUCTURE

"A verbal report was made to the Federal Energy Regulatory Commission (FERC) Engineer on January 11, 2010 at 1510 hours pursuant to 18CFR12.10(a) for a condition affecting the safety of a project or works. A new wet area has been identified on the slope of Dike 6, approximately 25 feet from the top of the structure. Dike 6 was designed and created during original plant construction to support electrical towers and provide isolation between Lake Anna and the proposed Unit 3 & 4 intake structures. The Unit 3 & 4 intake area is currently being used as a settling pond. The settling pond is used to process storm water and other secondary water before the liquid is discharged from the station.

"This minor seepage is located about half way down the slope to the settling pond. Water samples were obtained from the wet area and it was determined that the seepage was not ground water. The sample composition was similar to the water in Lake Anna. Currently, there is no threat to the public or North Anna Power Station. Engineering is investigating this issue and a corrective action plan will be developed to correct the minor seepage.

"This issue is being reported pursuant to 10CFR50.72(b)(2)(xi)."

The licensee has notified the NRC Resident Inspector and the local government.

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Power Reactor Event Number: 45624
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [ ] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: JOHN DIGNAM
HQ OPS Officer: JOE O'HARA
Notification Date: 01/11/2010
Notification Time: 18:31 [ET]
Event Date: 01/11/2010
Event Time: 15:59 [EST]
Last Update Date: 01/11/2010
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):
ANTHONY DIMITRIADIS (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 TRIP DUE TO MAIN GENERATOR ELECTRICAL TRIP

"At 1559 on January 11, 2010, Indian Point Unit 2 tripped from 100% power due to a main generator electrical trip. The investigation into the generator trip is ongoing. All systems responded as expected. The auxiliary feedwater system responded as expected and is maintaining steam generator water levels. Decay heat removal is via the steam generators to the main condenser. Offsite power and plant electrical lineups are normal. No primary or secondary side relief valves lifted. The reactor plant is in mode 3 and stable.

"Indian Point Unit 3 was not affected and remains at 100% power."

The licensee notified the NRC Resident Inspector and the N.Y. State Public Service Commission. The licensee intends to notify the Mayor's Office and issue a press release.

Page Last Reviewed/Updated Thursday, March 29, 2012
Thursday, March 29, 2012