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Event Notification Report for June 10, 2005

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
06/09/2005 - 06/10/2005

** EVENT NUMBERS **


41749 41759 41760

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General Information or Other Event Number: 41749
Rep Org: FLORIDA BUREAU OF RADIATION CONTROL
Licensee: MIAMI CHILDREN'S HOSPITAL
Region: 1
City: MIAMI State: FL
County: MIAMI-DADE
License #: 993-1
Agreement: Y
Docket:
NRC Notified By: CHARLES ADAMS
HQ OPS Officer: HOWIE CROUCH
Notification Date: 06/07/2005
Notification Time: 07:37 [ET]
Event Date: 06/06/2005
Event Time: [EDT]
Last Update Date: 06/07/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
TODD JACKSON (R1)
TOM ESSIG (NMSS)

Event Text

FLORIDA AGREEMENT STATE REPORT - LOST AM-241 SOURCE

The following information was obtained from the State of Florida Bureau of Radiation Control via e-mail:

"Searle marker containing Am-241 source was reported missing from Children's Hospital Miami. Device was bought in early 1980's. This source is in a 'storage only' mode and was last seen during the May 2005 inventory. Florida is investigating."

The device description is a Searle marker, manufacturer and model unknown, serial number ACM-24, containing 14 milliCuries of Am-241.

Florida Incident Number FL05-088

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Power Reactor Event Number: 41759
Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: BOB MURRELL
HQ OPS Officer: JOHN KNOKE
Notification Date: 06/09/2005
Notification Time: 14:12 [ET]
Event Date: 04/14/2005
Event Time: 06:13 [CDT]
Last Update Date: 06/09/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
JULIO LARA (R3)

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

Event Text

INVALID PRIMARY CONTAINMENT ISOLATION SYSTEM (PCIS) ACTUATION DURING POST MAINTENANCE TESTING


"This 60-day telephone notification is being made under reporting requirements specified by 10CFR50.73 (a)(2)(iv)(A) to describe an invalid actuation of a containment isolation signal affecting more than one system.

"At 0613 on April 14, 2005, with the Duane Arnold Energy Center (DAEC) shutdown for refueling, a PCIS Group 7 (Well Water and RBCCW Drywall Isolation Valves) signal was generated during post-maintenance testing on MO-4841A. This event was caused by an error in work planning which resulted in an incorrect relay being listed in a work order. When a jumper was installed across the terminals of the incorrect relay, an isolation signal was generated.

"All equipment responded in accordance with the plant design. Specifically, all isolations were complete and successful.

"There were no safety consequences or impacts on the health and safety of the public. The event was entered into DAEC's corrective action program for resolution."


The licensee will notify the NRC Resident Inspector.

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Power Reactor Event Number: 41760
Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: BOB MURRELL
HQ OPS Officer: JOHN KNOKE
Notification Date: 06/09/2005
Notification Time: 14:12 [ET]
Event Date: 04/14/2005
Event Time: 15:40 [CDT]
Last Update Date: 06/09/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
JULIO LARA (R3)

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

Event Text

INVALID PRIMARY CONTAINMENT ISOLATION SYSTEM (PCIS) ACTUATION WHILE PERFORMING RE-TERMINATION.

"This 60-day telephone notification is being made under reporting requirements specified by 10CFR50.73 (a)(2)(iv)(A) to describe an invalid actuation of a containment isolation signal affecting more than one system.

"At 1540 on April 14, 2005, with the Duane Arnold Energy Center (DAEC) shutdown for refueling, an invalid Group 3 isolation on the 'A' side of PCIS occurred. Group 3 isolation signals were generated for Primary Containment Isolation Valves for Drywell and Torus Ventilation, and Purge, Containment Nitrogen Compressor Suction and Discharge; Recirculation Pump Seals, and Post Accident Sample System.

"This event was caused while landing a lead on a relay terminal. During this activity the lead brushed another terminal, causing a fuse to blow which resulted in the inadvertent Group 3 isolation.

"All equipment responded In accordance with the plant design. Specifically, all actuations were complete and successful.

"There were no safety consequences or impacts on the health and safety of the public. The event was entered into DAEC's corrective action program for resolution."


The licensee will notify the NRC Resident Inspector.

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