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Event Notification Report for June 29, 2005

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
06/28/2005 - 06/29/2005

** EVENT NUMBERS **


41802 41803 41804 41805 41807 41808

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Other Nuclear Material Event Number: 41802
Rep Org: EASTERN ASSOCIATED COAL CORPORATION
Licensee: EASTERN ASSOCIATED COAL CORPORATION
Region: 1
City: FAIRVIEW State: WV
County:
License #: 47-23053-01
Agreement: N
Docket:
NRC Notified By: FRANK PEDUTI
HQ OPS Officer: MIKE RIPLEY
Notification Date: 06/28/2005
Notification Time: 08:20 [ET]
Event Date: 06/24/2005
Event Time: 16:55 [EDT]
Last Update Date: 06/28/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
INFORMATION ONLY
Person (Organization):
JOHN WHITE (R1)
TOM ESSIG (NMSS)

Event Text

NUCLEAR DENSITY GAUGE SOURCE SEPARATED FROM GUAGE

Following troubleshooting to remedy density measurement problems, the Cs-137 source (100 milliCuries) and source holder were found missing from its liquid line gauge mounting. It was then determined that the source and holder had become separated from the gauge and had fallen into a sump directly beneath. The gauge is a Ronan Model SA-1-C5, S/N EE823. The licensee isolated the area and performed surveys with no contamination or abnormal radiation readings noted. The licensee contacted the manufacturer and subsequently contracted with a consultant (Jendco, Inc. of Pittsburg, PA) who retrieved the source and source holder from the sump without incident. The source was found intact and undamaged. The gauge was re-assembled and returned to service.

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Power Reactor Event Number: 41803
Facility: SOUTH TEXAS
Region: 4 State: TX
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: TRIPP FRAHM
HQ OPS Officer: BILL GOTT
Notification Date: 06/28/2005
Notification Time: 13:17 [ET]
Event Date: 05/17/2005
Event Time: 16:02 [CDT]
Last Update Date: 06/28/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
JEFFERY CLARK (R4)

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

Event Text

INVALID SYSTEM ACTUATION - AUXILIARY FEEDWATER PUMP STARTED DURING SURVEILLANCE

"Per 10 CFR 50.73(a)(1), this telephone notification is made under 10 CFR 50.73(a)(2)(iv)(A) for an invalid actuation. The train D steam-driven Auxiliary Feedwater Pump was inadvertently started while performing post-maintenance testing on another component.

"The test was conducted using applicable steps in a surveillance procedure for the solid state protection system. A procedure step for isolating the auxiliary feedwater pump steam turbine was incorrectly performed so that the steam turbine was not isolated, as intended, and started when the test actuation signal was initiated. The steam-driven turbine and pump functioned successfully as a result of the invalid signal.

"The signal was determined to be invalid in that it was not initiated in response to actual plant conditions or parameters satisfying the requirements for initiation of the safety function of the system. The pump start was not an intentional manual initiation. The invalid actuation is reportable in that it did not occur while the system was properly removed from service and did not occur after the safety function had already been completed"

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 41804
Facility: PALO VERDE
Region: 4 State: AZ
Unit: [ ] [2] [ ]
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: DUANE KANITZ
HQ OPS Officer: BILL GOTT
Notification Date: 06/28/2005
Notification Time: 15:30 [ET]
Event Date: 04/29/2005
Event Time: 00:43 [MST]
Last Update Date: 06/28/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
JEFFERY CLARK (R4)

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

Event Text

INVALID SYSTEM ACTUATION

"This report is being made under 50.73 (a)(2)(iv)(A).

"On April 29, 2005, at approximately 0043 Mountain Standard Time, Palo Verde Nuclear Generating Station Unit 2 experienced an invalid 1/2 leg Engineered Safety Feature Actuation Signal (ESFAS) actuation (B train) when operations personnel prematurely implemented a tag out causing loss of vital power to the 'B' train ESFAS cabinet. The following alarms were received; Recirculation Actuation Signal B, Auxiliary Feedwater Actuation Signal-1B, Containment Spray Actuation Signal B, Main Steam Isolation Signal B, Containment Isolation Actuation Signal B, Safety Injection Actuation Signal B, Auxiliary Feedwater Actuation Signal-2B (all Leg 1-3), and Emergency Diesel Generator (EDG) Start Signal B. At the time of the event Unit 2 was in the 'B' train work window for refueling outage 2R12 and not all 'B' train equipment actuated - EDG B, Low Pressure Safety Injection B, Containment Spray B, and the B train Recirculation Actuation Signal sump valves were tagged out of service for maintenance. During the performance of the 'Inadvertent Plant Protection System - ESFAS Actuations' procedure, Operations personnel determined that all 'B' ESFAS equipment operated as expected considering the 'B' train equipment that was tagged out for maintenance."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 41805
Facility: LASALLE
Region: 3 State: IL
Unit: [1] [2] [ ]
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: HAROLD VINYARD
HQ OPS Officer: BILL GOTT
Notification Date: 06/28/2005
Notification Time: 16:24 [ET]
Event Date: 06/28/2005
Event Time: 13:00 [CDT]
Last Update Date: 06/28/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
JAMNES CAMERON (R3)

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 MINOR FISH KILL

"At 1300 CDST on 06/28/05, it was discovered that a minor fish kill took place in LaSalle County Nuclear Station's cooling lake, due to increased temperature. As summer air temperatures increased, the cooling lake temperature increased above 95F, the threshold at which species susceptible to increased temperature begin to perish. It was communicated to the Illinois Department of Natural Resources, that approximately 300 fish, the majority of which were striped bass, had perished.

"This notification is made in accordance with Exelon Reportability manual SAF 1.9, ENV 3.26, LaSalle County Station Facility Operating License Appendix B Section 4.1 'Unusual or Important Environmental Events,' and 10CFR50.72(b)(2)(xi)."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 41807
Facility: BRAIDWOOD
Region: 3 State: IL
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOHN BROWNING
HQ OPS Officer: HOWIE CROUCH
Notification Date: 06/28/2005
Notification Time: 17:38 [ET]
Event Date: 06/28/2005
Event Time: 13:00 [CDT]
Last Update Date: 06/28/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
JAMNES CAMERON (R3)

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 ILLINOIS DEPARTMENT OF NATURAL RESOURCES

"A 1300 CDST on 06/28/05, it was discovered that a minor fish kill took place in Braidwood Nuclear Station's cooling lake, due to increased temperature. As Summer air temperatures increased, the cooling lake temperature increased above 95F, the threshold at which species susceptible to increased temperature begin to perish. It was communicated to the Illinois Department of Natural Resources, that approximately 1000 fish, the majority of which were Gizzard Shad, had perished.

"This notification is made in accordance with Exelon Reportability manual SAF 1.9, ENV 3.26, Braidwood Station Facility Operating License Appendix B Section 4.1 'Unusual or Important Environmental Events,' and 10CFR50.72(b)(2)(xi)."


The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 41808
Facility: PEACH BOTTOM
Region: 1 State: PA
Unit: [2] [3] [ ]
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: TODD A. STRAYER
HQ OPS Officer: HOWIE CROUCH
Notification Date: 06/28/2005
Notification Time: 18:20 [ET]
Event Date: 06/28/2005
Event Time: 14:00 [EDT]
Last Update Date: 06/28/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
JOHN WHITE (R1)

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

Event Text

TECHNICAL SUPPORT CENTER VENTILATION INOPERABLE

"This 8 Hour Non-Emergency report is pursuant to 10CFR50.72(b)(3)(xiii). Main Control Room personnel were notified that normal and emergency Technical Support Center (TSC) ventilation was inoperable. The loss of ventilation in the TSC constitutes a Major Loss of Emergency Preparedness Capability because it significantly impaired the fulfillment of the Peach Bottom emergency plan in the event of a potential radiological release. Peach Bottom maintenance personnel immediately began investigating the inability to place TSC ventilation in service and were able to restore both normal and emergency ventilation. The initial failure of both normal and emergency TSC ventilation is still being investigated. Normal plant operation is unaffected by the loss of TSC ventilation."

The licensee has notified the NRC Resident Inspector.

Page Last Reviewed/Updated Friday, March 30, 2012
Friday, March 30, 2012