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Event Notification Report for March 9, 2005

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
03/08/2005 - 03/09/2005

** EVENT NUMBERS **

Power Reactor	Event Number: 41382
Facility: COOPER Region: 4 State: NE Unit: [1] [ ] [ ] RX Type: [1] GE-4 NRC Notified By: ANDREW OHRABLO HQ OPS Officer: MIKE RIPLEY	Notification Date: 02/07/2005 Notification Time: 22:11 [ET] Event Date: 02/07/2005 Event Time: 15:58 [CST] Last Update Date: 03/08/2005
Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(3)(v)(B) - POT RHR INOP	Person (Organization): BLAIR SPITZBERG (R4)

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

Event Text

RESIDUAL HEAT REMOVAL SYSTEM INOPERABLE DUE TO EMERGENCY DIESEL GENERATOR TRIP DURING TESTING

"This report is being made pursuant to 10CFR50.72(b)(3)(v)(B) 'Any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to: (B) Remove residual heat;'

"This report is being made due to a trip of the Emergency Diesel Generator during testing that resulted in the RHR loops potentially becoming depressurized. This has the potential to render all RHR Shutdown Cooling unavailable and prevent the removal of decay heat.

"Sequence of events (all times CST):
At 12:00 [02/07/05], Shutdown Cooling was removed from service to prepare for Sequential Load testing of DG #1. This was a planned evolution. At this time decay heat was being removed by the fuel pool cooling system with 2 fuel pool cooling pumps and 2 fuel pool cooling heat exchangers. Time to boil was calculated to be 26 hours.

"At 15:58, the Sequential Load Test commenced on the inoperable DG. The DG came up to speed and sequenced on the initial loads (RHR pumps, a CS pump and a SW pump). Shortly into the sequencing of the DG, the DG tripped due to a blown fuse in the DG control circuit. Sequential loading was not completed. The trip occurred between 13 seconds and 20 seconds of the sequential load. This resulted in the initial loads losing power. Procedurally, the minimum flow valves for the RHR and CS pumps were being remotely opened from the Control Room at the time the DG tripped. This resulted in low-pressure alarms on both RHR systems and one CS system. One fuel pool cooling pump was deenergized, per design, during the sequential load test. Both fuel pool cooling heat exchangers remained in service. With these conditions, the fuel pool cooling lineup does not qualify as an alternate decay heat removal method.

"At 16:04, both RHR loops were declared inoperable due to depressurizing the RHR loops. At 16:02, the tripped fuel pool cooling pump was restored to operation and previous decay heat removal was restored. No unexpected rise in temperature occurred during the time that only 1 fuel pool cooling pump was in operation. This reestablished the fuel pool cooling system as an alternate decay heat removal method.

"At 19:11, the B loop of RHR was returned to a standby lineup and declared operable.

"At this time investigation into why the DG fuse blew is ongoing. All indications are that other equipment performed as designed."

The licensee notified the NRC Resident Inspector.

* * * UPDATE FROM C. BLAIR TO M. RIPLEY 1548 EST 03/08/05 * * *

The following is a correction to the original report received via facsimile (licensee text in quotes):

"Instead of the minimum flow valves for RHR and CS being opened, the suppression pool inboard cooling valve for RHR and the test line recirculation valve for CS were being opened."

The licensee will notify the NRC Resident Inspector. Notified R4 DO (T. Pruett)

General Information or Other	Event Number: 41461
Rep Org: OR DEPT OF HEALTH RAD PROTECTION Licensee: GEO PACIFIC, INC Region: 4 City: BEND State: OR County: License #: ORE-90950 Agreement: Y Docket: NRC Notified By: ED WRIGHT HQ OPS Officer: MIKE RIPLEY	Notification Date: 03/04/2005 Notification Time: 12:49 [ET] Event Date: 03/04/2005 Event Time: 08:00 [PST] Last Update Date: 03/04/2005
Emergency Class: NON EMERGENCY 10 CFR Section: AGREEMENT STATE	Person (Organization): CHUCK CAIN (R4) TOM ESSIG (NMSS) BEN SANDLER (EMAIL) (TAS)

Event Text

AGREEMENT STATE REPORT - STOLEN MOISTURE DENSITY GAUGE

A Troxler Model 3440 Moisture Density Gauge (Serial Number 35472) was stolen from a licensee's pickup truck sometime during the night or early morning of 03/03/05 - 03/04/05 while parked at a Holiday Inn Express Motel in Bend, OR. The gauge contains an 8 milliCurie Cs-137 source (Serial Number 772585) and a 40 milliCurie Am-241/Be source (Serial Number 78-408). The licensee notified the Oregon State Police and the Bend, OR Police Department. The State of Oregon has dispatched an investigator to the area and plans on issuing a press release.

Oregon Incident No. RPS 05-0013.

Power Reactor	Event Number: 41468
Facility: MONTICELLO Region: 3 State: MN Unit: [1] [ ] [ ] RX Type: [1] GE-3 NRC Notified By: RANDY SAND HQ OPS Officer: BILL GOTT	Notification Date: 03/08/2005 Notification Time: 11:41 [ET] Event Date: 03/08/2005 Event Time: 04:54 [CST] Last Update Date: 03/08/2005
Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(3)(v)(B) - POT RHR INOP	Person (Organization): MARK RING (R3)

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

Event Text

RHR PUMP TRIPPED DUE TO LOSS OF VALVE POSITION INDICATION

The following information was provided by the licensee (licensee text in quotes)

"During isolation of the 'A' Safety Relief Valve, the 12 Residual Heat Removal (RHR) Pump tripped while in service for shutdown cooling. The isolation and shutdown cooling were subsequently restored such that shutdown cooling was lost for approximately 13 minutes.

"Several Control Room alarms were received at approximately 0454 [CST] while the isolation was being hung. The Control Room Supervisor investigated the alarms and the Reactor Operator identified that the 12 RHR Pump had tripped. The isolation was lifted and shutdown cooling was restored at approximately 0507 [CST]. Operators observed that reactor water temperature and level remained stable at 99 degrees F and 651 inches (above the bottom of the vessel), respectively, during the event.

"The isolation being hung apparently caused a loss of position indication for the RHR pump inlet valve. With no position indication, the pump logic sensed a loss of suction flow path, which caused the RHR pump to trip. The event is under investigation.

"The NRC resident has been notified."

Power Reactor	Event Number: 41471
Facility: CATAWBA Region: 2 State: SC Unit: [1] [2] [ ] RX Type: [1] W-4-LP,[2] W-4-LP NRC Notified By: DANNY HESTER HQ OPS Officer: HOWIE CROUCH	Notification Date: 03/08/2005 Notification Time: 15:14 [ET] Event Date: 03/08/2005 Event Time: 12:30 [EST] Last Update Date: 03/08/2005
Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(2)(xi) - OFFSITE NOTIFICATION	Person (Organization): BRIAN BONSER (R2) SCOTT MOORE (NMSS)

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 TO SOUTH CAROLINA DEPARTMENT OF HEALTH AND ENVIRONMENTAL CONTROL

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

"During routine test shots, a 24 Curie Iridium-192 source was stuck partially inserted in a radiography camera inside of radiography vault. The source was returned to the fully locked and shielded position in the camera at 1345 [EST]. There was no unplanned exposure to plant personnel. South Carolina DHEC [Department of Health and Environmental Control] notified at 1230 on 03/08/05."

The licensee has notified the NRC Resident Inspector.