Event Notification Report for April 14, 2005
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
04/13/2005 - 04/14/2005
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
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
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
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
JULIO LARA (R3)
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 |
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.
"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.
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
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
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
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
JULIO LARA (R3)
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 |
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.
"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.
Power Reactor
Event Number: 41600
Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: JOHN TAYLOR
HQ OPS Officer: BILL GOTT
Region: 1 State: MA
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: JOHN TAYLOR
HQ OPS Officer: BILL GOTT
Notification Date: 04/14/2005
Notification Time: 17:49 [ET]
Event Date: 04/14/2005
Event Time: 10:30 [EST]
Last Update Date: 04/14/2005
Notification Time: 17:49 [ET]
Event Date: 04/14/2005
Event Time: 10:30 [EST]
Last Update Date: 04/14/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
10 CFR Section:
26.73 - FITNESS FOR DUTY
Person (Organization):
JOHN WHITE (R1)
JOHN WHITE (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 87 | Power Operation | 87 | Power Operation |
FITNESS FOR DUTY
A contract employee had a positive test result for alcohol during a for-cause test. The employee's access to the plant was terminated. Contact the Headquarters Operations Officer for additional details.
The licensee notified the NRC Resident Inspector.
A contract employee had a positive test result for alcohol during a for-cause test. The employee's access to the plant was terminated. Contact the Headquarters Operations Officer for additional details.
The licensee notified the NRC Resident Inspector.