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Event Notification Report for September 13, 2005

U.S. Nuclear Regulatory Commission
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Event Reports For
09/12/2005 - 09/13/2005

** EVENT NUMBERS **


41972 41983 41984

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General Information or Other Event Number: 41972
Rep Org: COLORADO DEPT OF HEALTH
Licensee: LAYNE CHRISTENSEN CO COLOG DIV
Region: 4
City: LAKEWOOD State: CO
County:
License #: COLO.971-01
Agreement: Y
Docket:
NRC Notified By: FAX
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 09/07/2005
Notification Time: 12:42 [ET]
Event Date: 07/28/2005
Event Time: [MDT]
Last Update Date: 09/07/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
DALE POWERS (R4)
LAWRENCE KOKAJKO (NMSS)

Event Text

WELL LOGGING SOURCE LODGED NEAR THE BOTTOM OF A 240 FOOT SHAFT

On July 28, 2005, a 100 milliCurie Cs-137 sealed source (New England Nuclear, Model 572, serial number 1623) became lodged near the bottom of a 240 foot shaft The logging probe and source had descended to that depth after breaking loose from the logging cable at the surface of the well. Repeated efforts to retrieve the source failed, Retrieval efforts were discontinued when a 4 foot section of an overshot device twisted off at approximately 210 feet down-hole.

The licensee submitted a written description of the event on August 23, 2005 and provided supplemental information on September 1, 2005 and September 2, 2005. Authorization to abandon the well formally approved on September 6, 2005.

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Power Reactor Event Number: 41983
Facility: BRUNSWICK
Region: 2 State: NC
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: KEITH HANZ
HQ OPS Officer: ARLON COSTA
Notification Date: 09/12/2005
Notification Time: 23:27 [ET]
Event Date: 09/12/2005
Event Time: 23:14 [EDT]
Last Update Date: 09/12/2005
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
JAMES MOORMAN (R2)
EDWIN HACKETT (NRR)
MELVYN LEACH (IRD)
LIGGETT (FEMA)
JASON (DHS)

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

UNUSUAL EVENT DECLARED DUE TO HURRICANE OPHELIA WARNING

"On September 12, 2005, at 2300 hours, a hurricane warning was issued, which resulted in the declaration of an unusual event for both units. Unit 1 and 2 are currently operating at 100 percent of rated thermal power. The plant area is not currently experiencing any hurricane force winds. The wind speed at the site is approximately 24 miles per hour. State and county emergency response organizations have been notified. The resident inspector has been notified.

"There is no significant impact to the safety of the plant at this time.

"The plant is currently in Abnormal Operating Procedure 0AOP-13.0, 'Operation During Hurricane, Flood Conditions, Tornado, or Earthquake,' and Plant Emergency Procedure 0PEP-02.6, 'Severe Weather,' in preparation for hurricane conditions."

On-site facilities are not being activated at this time. No off-site assistance is requested. Request suspension of additional follow up notification unless plant conditions change. All Emergency Core Cooling Systems and the Emergency Diesel Generators are fully operable if needed. The electrical grid is stable.

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Power Reactor Event Number: 41984
Facility: BEAVER VALLEY
Region: 1 State: PA
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: RICHARD BOLOGNA
HQ OPS Officer: JOHN MacKINNON
Notification Date: 09/12/2005
Notification Time: 23:27 [ET]
Event Date: 09/12/2005
Event Time: 17:09 [EDT]
Last Update Date: 09/12/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
Person (Organization):
JAMES TRAPP (R1)

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

OVERPOWER OF REACTOR DUE TO CALIBRATION ERROR ON STEAM DUMP CONTROL SYSTEM

"On September 12, 2005 at 1709 hours, one feedwater train bypass valve (TV-1CN-100) unexpectedly opened at Beaver Valley Power Station Unit No. 1, causing the temperature of the feedwater going to the three steam generators to reduce. Reactor power then increased due to cooler feedwater temperature entering the steam generators. Reactor power increased to approximately 103 percent. The control room crew commenced reducing plant load and reactor power. Approximately 4 minutes later, TV-1CN-100 automatically closed as designed following an automatic opening signal. Reactor power decreased below 100% at approximately the same time. Currently, the plant is stable with reactor power at 93 percent.

"A calibration procedure of the Steam Dump Control System was ongoing at the time of the event. Preliminary investigation determined that this event occurred due to removal of an instrument card within the Steam Dump Control System which caused TV-1CN-100 to inappropriately open. Actuation of TV-1CN-100 was not initiated by a valid actuation signal.

"This event is being reported as a voluntary notification since the reactor power exceeded maximum licensed steady state power level of 102 percent."

The licensee notified the NRC Resident Inspector.

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Friday, March 30, 2012