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Event Notification Report for October 13, 2005

U.S. Nuclear Regulatory Commission
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Event Reports For
10/12/2005 - 10/13/2005

** EVENT NUMBERS **


42049 42051 42052 42053 42054

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General Information or Other Event Number: 42049
Rep Org: IOWA DEPARTMENT OF PUBLIC HEALTH
Licensee: CMT
Region: 3
City: DES MOINES State: IA
County:
License #: 0299-1-77PG
Agreement: Y
Docket:
NRC Notified By: DONALD A. FLATER
HQ OPS Officer: STEVE SANDIN
Notification Date: 10/10/2005
Notification Time: 15:55 [ET]
Event Date: 10/10/2005
Event Time: 09:35 [CDT]
Last Update Date: 10/11/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
BRUCE BURGESS (R3)
E. WILLIAM BRACH (NMSS)

Event Text

AGREEMENT STATE REPORT INVOLVING A DAMAGED TROXLER MOISTURE DENSITY GAUGE

At approximately 0930 CDT on 10/10/05, a Troxler moisture density gauge, Model 3430 containing both a 8-9 mCi Cs-137 and 44 mCi Am-241:Be source, was run over by a bulldozer at the new NASCAR track construction site south of I-80 Exit 168 near Newton, IA. The State of Iowa responded to the incident and determined that the source was not breached and that there was no spread of contamination. The damaged gauge was boxed up and transported by the licensee to their office in Des Moines. The State has requested that the manufacturer, i.e., Troxler, examine the gauge at the licensee's facility before shipment to a Troxler repair facility.

The State of Iowa does not plan a press release.

* * * UPDATE FROM D. FLATER TO M. RIPLEY 0715 ET 10/11/05 * * *

The State reported that the serial number of the damaged gauge is 32198.

Notified R3 DO (B. Burgess) and NMSS EO (T. Essig)

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Power Reactor Event Number: 42051
Facility: DRESDEN
Region: 3 State: IL
Unit: [ ] [2] [ ]
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: DAVID HAMILTON
HQ OPS Officer: BILL HUFFMAN
Notification Date: 10/12/2005
Notification Time: 14:25 [ET]
Event Date: 09/08/2005
Event Time: 10:08 [CDT]
Last Update Date: 10/12/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
DAVE PASSEHL (R3)

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

INVALID SYSTEM ACTUATION

"This telephone notification is provided in accordance with 10 CFR 50.73 (a)(1), to report an invalid actuation reportable under 10 CFR 50.73 (a)(2)(iv)(A), 'Any event or condition that resulted in manual or automatic actuation of any system listed in paragraph (a)(2)(iv)(B).' General containment isolation signals affecting containment isolation valves in more than one system is identified in paragraph (a)(2)(iv)(B).

"On September 8, 2005, at 1008 hours, with Unit 2 in Mode 4 'Cold Shutdown,' fuse 2-902-3-AA-F7 in the 902-3 panel blew which resulted in a partial Group 2 Primary Containment Isolation. The containment isolation signal affected containment isolation valves in more than one system. All affected containment isolation valves operated as designed.

"The fuse was successfully replaced and all affected components were restored to operable status."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 42052
Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [1] [ ] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: ALAN HALL
HQ OPS Officer: BILL HUFFMAN
Notification Date: 10/12/2005
Notification Time: 16:53 [ET]
Event Date: 10/12/2005
Event Time: 14:40 [EDT]
Last Update Date: 10/12/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
THOMAS DECKER (R2)

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

TECHNICAL SPECIFICATION SHUTDOWN BASED ON LOSS OF TWO CHANNELS OF CONTAINMENT ISOLATION RADIATION MONITOR

On 10/12/05 at 14:40 EDT, Unit 1 experienced a loss of Channel A of the CIS (Containment Isolation Signal) Radiation Monitor which, when combined with the previous existing inoperability of Channel D of the CIS radiation monitor, required Unit 1 to enter technical specification LCO 3.0.3. If the action statement [for the CIS], LCO 3.3.2.1, cannot be met, within 1 hour, action shall be initiated to place the unit in Hot Standby with the next 6 hours, Hot Shutdown within the following 6 hours, and cold shutdown within the subsequent 24 hours. Unit shutdown is in progress.

The licensee notified the NRC Resident Inspector.

* * * UPDATE FROM LICENSEE (C. MARPLE) TO NRC (HUFFMAN) AT 2145 EDT ON 10/12/05 * * *

At 2101 EDT on 10/12/05, the Unit 1 exited Technical Specification 3.0.3 when Channel D of the CIS radiation monitor was returned to service. The down-power of Unit 1 was halted at 97% power.

The licensee notified the NRC Resident Inspector. R2DO(Decker) informed.

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Power Reactor Event Number: 42053
Facility: PALISADES
Region: 3 State: MI
Unit: [1] [ ] [ ]
RX Type: [1] CE
NRC Notified By: GEORGE SLEEPER
HQ OPS Officer: BILL HUFFMAN
Notification Date: 10/12/2005
Notification Time: 21:55 [ET]
Event Date: 10/12/2005
Event Time: 17:09 [EDT]
Last Update Date: 10/13/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
DAVE PASSEHL (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

Event Text

PARTIAL LOSS OF PLANT PROCESS COMPUTER

"Portions of the Palisades Plant Process Computer (PPC) including the Emergency Response Data System (ERDS) became inoperable due to failure of a plant inverter (EY-210). The failed inverter supplies power to portions of the PPC. The inverter failed for unknown reasons. Options for bypassing the inverter and inverter repairs are being evaluated."

The licensee notified the NRC Resident Inspector.

* * *UPDATE PROVIDED BY MULFORD TO ROTTON AT 0511 EDT ON 10/13/05 * * *

At 0500 the Palisades Plant Process Computer (PPC) including ERDS was declared operable after bypassing plant inverter EY-210 per plant procedure and restoring power to equipment.

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 42054
Facility: LIMERICK
Region: 1 State: PA
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: MARK CRIM
HQ OPS Officer: JEFF ROTTON
Notification Date: 10/12/2005
Notification Time: 23:55 [ET]
Event Date: 10/12/2005
Event Time: 22:24 [EDT]
Last Update Date: 10/13/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
JAMES DWYER (R1)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 A/R Y 100 Power Operation 0 Hot Shutdown

Event Text

AUTOMATIC SCRAM DUE TO REACTOR HIGH PRESSURE SIGNAL

"Unit 2 Reactor automatically scrammed at 2224 [EDT] as a result of an RPS actuation due to Reactor High Pressure. All control rods inserted. The plant is stable. No ECCS or SRV actuation occurred. This report is made pursuant to 50.72(B)(2)(iv)(B). An investigation into the cause is currently in progress."

Electric plant lineup is in a normal stable lineup. Reactor water level is being maintained via main feedwater system and removing decay heat via the steam bypass valves to the main condenser. This event had no effect on Unit 1.

The licensee notified the NRC Resident Inspector, Pennsylvania Emergency Management Agency (PEMA), and the Berks, Chester, and Montgomery County emergency agencies.

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