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Event Notification Report for March 22, 2005

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
03/21/2005 - 03/22/2005

** EVENT NUMBERS **


41506 41508 41509 41510 41511

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Power Reactor Event Number: 41506
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: GORDON ROBINSON
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 03/21/2005
Notification Time: 03:35 [ET]
Event Date: 03/20/2005
Event Time: 22:30 [EST]
Last Update Date: 03/21/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
LAWRENCE DOERFLEIN (R1)

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

PRESSURE BOUNDARY LEAKAGE DISCOVERED DURING HYDRO TEST

The following information was obtained from the licensee via fax (licensee text in quotes):

"At 22:30 on 3/20/2005, the Control Room was notified by the test director that ASME CLASS I Boundary System Leakage Hydrostatic Pressure Test (SE-200-002) had failed. The reason was a leak identified on Reactor Recirc Pump B Discharge Valve, HV243F031B. The leak is coming from the Stub Tube Weld Leakoff Connection for the valve. It is leaking approx. 10 drops per minute. Technical Requirement 3.4.2 was entered. It was determined to be unacceptable under the ASME Section XI Code. Based on guidance provided in NUREG-1022, Rev. 2, this material defect in the primary coolant boundary constitutes a seriously degraded condition and is reportable under 10CFR50.72(b)(3)(ii)(A). A final evaluation of the flaw and a repair plan is being developed."

The NRC Resident was notified.

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Power Reactor Event Number: 41508
Facility: TURKEY POINT
Region: 2 State: FL
Unit: [3] [4] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: JIM RUSSELL
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 03/21/2005
Notification Time: 12:20 [ET]
Event Date: 03/21/2005
Event Time: 10:45 [EST]
Last Update Date: 03/21/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
STEPHEN CAHILL (R2)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
3 N Y 100 Power Operation 100 Power Operation
4 N Y 100 Power Operation 100 Power Operation

Event Text

OFFSITE NOTIFICATION TO DERM ABOUT FUEL OIL SPILL

On 3/21/05 at 1045, the Control Room was notified of a fuel oil spill. The event was believed to have occurred on Saturday, 3/19/05 between 1900 and 0300. The amount of fuel oil ( Grade 2 Diesel) that was spilled was approximately 219 gallons and dispersed over a distance of about 1 mile. The cause of the spill was possibly due to a valve left open on the tanker after making a fuel delivery. The long trail of oil was made as the tanker left the site. The spill is contained and being cleaned up at this time. The area will be excavated and transported to Redland Construction.

The location of the fuel oil spill occurred outside of the Nuclear Plant protected area at the new fossil plant. Construction site.

DERM (Department of Environmental Resources Management) will be notified by Turkey Point Land Utilization representative.

The NRC Resident Inspector will be notified.

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Power Reactor Event Number: 41509
Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: STEVE GIFFORD
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 03/21/2005
Notification Time: 18:25 [ET]
Event Date: 03/21/2005
Event Time: 15:53 [CST]
Last Update Date: 03/21/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
GREG PICK (R4)

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

LOSS OF SAFETY PARAMETER DISPLAY SYSTEM (SPDS) FUNCTION FOR GREATER THAN 8 HOURS.

The following information was provided by the licensee

"On 3-21-05 the Plant Computer system was removed from service at 0753 for scheduled maintenance. The system was not verified restored until 1558. This is in excess of the eight hours allowed by 10CFR50.72(b)(3)(xiii). The Plant Computer system supplies the Safety Parameter Display System (SPDS) function, which is required for Emergency Assessment Capability. The Plant Computer is currently operable."

"This event did not effect the plant operations. The unit is stable in Mode 1 at 100% power."

"The NRC Resident inspector has been informed."

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Power Reactor Event Number: 41510
Facility: PEACH BOTTOM
Region: 1 State: PA
Unit: [ ] [3] [ ]
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: BILL DALTON
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 03/21/2005
Notification Time: 22:34 [ET]
Event Date: 03/21/2005
Event Time: 17:00 [EST]
Last Update Date: 03/21/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
JOHN ROGGE (R1)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
3 N Y 100 Power Operation 100 Power Operation

Event Text

HPCI DECLARED INOPERABLE - ENTERING 14 DAY LCO ACTION STATEMENT

The following information was provided by the licensee by fax.

"At approximately 17:00 on March 21, 2005, while performing required surveillance testing on the Unit 3 HPCI system, the HPCI Condensate Storage Tank (CST) suction valve (MO-3-23-17) failed to close after the HPCI Torus suction valves (MO-3-23-57 & MO-3-23-58) were full open. Failure of the CST suction valve MO-3-23-17 to close when a Torus suction path was established, required entry into Technical Specification 3.3.5.1 for loss of initiation function for CST level low and Torus level high (Functions 3d, 3e). The loss of initiation function under Technical Specification 3.3.5.1 required that the HPCI system be declared inoperable in one (1) hour after discovery. HPCI was initially declared inoperable at 16:41 for surveillance testing. HPCI inoperability has been maintained as of that time. Pursuant to 10CFR 50.72(b)(3), this notification is being made due to Unit 3 HPCI inoperability, which prevents fulfillment of a Safety Function."

Initial troubleshooting hints that the cause of the failure may be due to a limit switch malfunction.

The NRC Resident Inspector was notified.

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Power Reactor Event Number: 41511
Facility: TURKEY POINT
Region: 2 State: FL
Unit: [ ] [4] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: PAUL REIMERS
HQ OPS Officer: BILL HUFFMAN
Notification Date: 03/22/2005
Notification Time: 04:21 [ET]
Event Date: 03/22/2005
Event Time: 03:47 [EST]
Last Update Date: 03/22/2005
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):
STEPHEN CAHILL (R2)

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

Event Text

REACTOR MANUALLY TRIPPED FOLLOWING LOSS OF MAIN FEED PUMP

The licensee provided the following information via fax (licensee text in quotes)

"The 4A SGFP [Steam Generator Feed Pump] tripped, initiating a Turbine Runback. Operators manually inserted a Reactor Trip at 15% Steam Generator level. The reactor tripped and all control rods inserted. Auxiliary Feedwater automatically initiated as expected. All systems operated as expected except the 4A SGFP discharge MOV which has no [position] indication [in the main control room and is being] investigated."

Decay heat is being removed by atmospheric steam dumps. The licensee will notify the NRC Resident Inspector.

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