Event Notification Report for April 20, 2003
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
04/19/2003 - 04/20/2003
Power Reactor
Event Number: 39774
Facility: PALO VERDE
Region: 4 State: AZ
Unit: [1] [2] [3]
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: RUSSELL STROUD
HQ OPS Officer: ARLON COSTA
Region: 4 State: AZ
Unit: [1] [2] [3]
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: RUSSELL STROUD
HQ OPS Officer: ARLON COSTA
Notification Date: 04/20/2003
Notification Time: 05:40 [ET]
Event Date: 04/20/2003
Event Time: 00:00 [MST]
Last Update Date: 04/20/2003
Notification Time: 05:40 [ET]
Event Date: 04/20/2003
Event Time: 00:00 [MST]
Last Update Date: 04/20/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
CLAUDE JOHNSON (R4)
CLAUDE JOHNSON (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 98 | Power Operation | 98 | Power Operation |
| 2 | N | Y | 98 | Power Operation | 98 | Power Operation |
| 3 | N | N | 0 | Refueling | 0 | Refueling |
PALO VERDE SPURIOUS ACTUATION OF OFFSITE EMERGENCY NOTIFICATION SIREN
"At 0000 MST on April 20, 2003, the Palo Verde Unit 1 Control Room was notified of a spurious actuation of an emergency warning siren in the vicinity of 348th avenue and Buckeye Road. While not confirmed at this time, the siren is believed to be siren #17 which is approximately five miles to the Northeast of Palo Verde. At approximately 0035 MST, the Unit 1 Control Room was informed [that] the siren was no longer actuating. This siren provides emergency notification to approximately 89 members of the public.
"No press release is planned at this time, however, the event is being reported due to the inquiry of a citizen to the Energy Control Center (ECC) and a subsequent notification to the Maricopa County Sheriff's Office.
"There is no event in progress and no risk to the health and safety of the public. Members of the public within audible range of the siren may have a concern for their radiological health and safety.
"Unit 1 is at approximately 98% power in Mode 1 at normal operating temperature and pressure.
"Unit 2 is at approximately 98% power in Mode 1 at normal operating temperature and pressure.
"Unit 3 is at 0% [power] in a refueling outage.
"The NRC Sr. Resident Inspector has been informed of the siren actuation and [of] this ENS notification.
"Note: The checkbox below for 'OTHER GOV AGENCIES' is referring to the Maricopa County Sheriff's Office."
"At 0000 MST on April 20, 2003, the Palo Verde Unit 1 Control Room was notified of a spurious actuation of an emergency warning siren in the vicinity of 348th avenue and Buckeye Road. While not confirmed at this time, the siren is believed to be siren #17 which is approximately five miles to the Northeast of Palo Verde. At approximately 0035 MST, the Unit 1 Control Room was informed [that] the siren was no longer actuating. This siren provides emergency notification to approximately 89 members of the public.
"No press release is planned at this time, however, the event is being reported due to the inquiry of a citizen to the Energy Control Center (ECC) and a subsequent notification to the Maricopa County Sheriff's Office.
"There is no event in progress and no risk to the health and safety of the public. Members of the public within audible range of the siren may have a concern for their radiological health and safety.
"Unit 1 is at approximately 98% power in Mode 1 at normal operating temperature and pressure.
"Unit 2 is at approximately 98% power in Mode 1 at normal operating temperature and pressure.
"Unit 3 is at 0% [power] in a refueling outage.
"The NRC Sr. Resident Inspector has been informed of the siren actuation and [of] this ENS notification.
"Note: The checkbox below for 'OTHER GOV AGENCIES' is referring to the Maricopa County Sheriff's Office."
Power Reactor
Event Number: 39775
Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: ROBERT TEMPLE
HQ OPS Officer: GERRY WAIG
Region: 3 State: IA
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: ROBERT TEMPLE
HQ OPS Officer: GERRY WAIG
Notification Date: 04/20/2003
Notification Time: 16:28 [ET]
Event Date: 04/20/2003
Event Time: 15:13 [CDT]
Last Update Date: 04/20/2003
Notification Time: 16:28 [ET]
Event Date: 04/20/2003
Event Time: 15:13 [CDT]
Last Update Date: 04/20/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
THOMAS KOZAK (R3)
THOMAS KOZAK (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 18 | Power Operation | 18 | Power Operation |
LEAK DISCOVERED ON HIGH PRESSURE CORE INJECTION PIPING DURING SURVEILLANCE TESTING
"During the performance of STP [Surveillance Test Procedure] 3.5.1-09, HPCI [High Pressure Core Injection] System Post-Startup Operability Test, on 4/20/03, a small leak was detected on a ¾ inch pipe nipple on the seal water line on the main HPCI pump. Engineers determined that the leak is from a small crack at a threaded connection. This piping is ASME class 2 piping. This leak constitutes a loss of structural integrity of a Class 2 component as required by section 3.7.3 of the Technical Requirements Manual [TRM].
"At 1337 CDT, on 4/20/03, entered T[TRM] LCO [Limiting Condition of Operation] T3.7.3 condition A, Structural Integrity of Class 1 or Class 2 components not maintained in MODES 1, 2 and 3.
"At 1513 CDT on 4/20/03, the HPCI system was isolated and declared Inoperable. Entered [Technical Specification] LCO 3.5.1 Condition F, HPCI System Inoperable, 14 days to restore HPCI. This unplanned HPCI System inoperability is reportable under 10CFR50.72(b)(3)(v)(d) as a single train failure that could have prevented the fulfillment of a safety function of structures or systems designed to mitigate the consequences of an accident."
The licensee has notified the NRC Resident Inspector.
"During the performance of STP [Surveillance Test Procedure] 3.5.1-09, HPCI [High Pressure Core Injection] System Post-Startup Operability Test, on 4/20/03, a small leak was detected on a ¾ inch pipe nipple on the seal water line on the main HPCI pump. Engineers determined that the leak is from a small crack at a threaded connection. This piping is ASME class 2 piping. This leak constitutes a loss of structural integrity of a Class 2 component as required by section 3.7.3 of the Technical Requirements Manual [TRM].
"At 1337 CDT, on 4/20/03, entered T[TRM] LCO [Limiting Condition of Operation] T3.7.3 condition A, Structural Integrity of Class 1 or Class 2 components not maintained in MODES 1, 2 and 3.
"At 1513 CDT on 4/20/03, the HPCI system was isolated and declared Inoperable. Entered [Technical Specification] LCO 3.5.1 Condition F, HPCI System Inoperable, 14 days to restore HPCI. This unplanned HPCI System inoperability is reportable under 10CFR50.72(b)(3)(v)(d) as a single train failure that could have prevented the fulfillment of a safety function of structures or systems designed to mitigate the consequences of an accident."
The licensee has notified the NRC Resident Inspector.
Power Reactor
Event Number: 39776
Facility: SURRY
Region: 2 State: VA
Unit: [1] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: JOHN DUFF
HQ OPS Officer: GERRY WAIG
Region: 2 State: VA
Unit: [1] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: JOHN DUFF
HQ OPS Officer: GERRY WAIG
Notification Date: 04/20/2003
Notification Time: 17:21 [ET]
Event Date: 04/20/2003
Event Time: 12:35 [EDT]
Last Update Date: 04/20/2003
Notification Time: 17:21 [ET]
Event Date: 04/20/2003
Event Time: 12:35 [EDT]
Last Update Date: 04/20/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
THOMAS DECKER (R2)
THOMAS DECKER (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
LOSS OF SAFETY PARAMETER DISPLAY SYSTEM (SPDS) FOR GREATER THAN 1 HOUR
"At 1235 hours EDT on 04/20/03, the Safety Parameter Display System (SPDS) portion of the Emergency Response Facility Computer System (ERFCS) was noted to be inoperable due to all outputs being displayed in 'magenta' color. At the time of the failure, the ERFCS computer was being re-initiated by Instrumentation & Controls personnel and failed to restart following the re-initiation sequence.
"As of 1335 hours EDT on 4/20/03, SPDS has been out of service for greater then 1 hour. which is considered a major loss of emergency assessment capability.
"Troubleshooting of the ERFCS by Instrumentation & Controls personnel identified a software problem. At 1600 hours EDT on 04/20/03, Instrumentation & Controls personnel were able to restore the 'A' train ERFCS and at 1630 hours EDT on 04/20/03 the ERFCS and SPDS were declared operable [efforts to restore the 'B' train are ongoing].
"This report is being made in accordance with I0CFR50.72(b)(3)(xiii)."
The Licensee has notified the NRC Resident Inspector.
"At 1235 hours EDT on 04/20/03, the Safety Parameter Display System (SPDS) portion of the Emergency Response Facility Computer System (ERFCS) was noted to be inoperable due to all outputs being displayed in 'magenta' color. At the time of the failure, the ERFCS computer was being re-initiated by Instrumentation & Controls personnel and failed to restart following the re-initiation sequence.
"As of 1335 hours EDT on 4/20/03, SPDS has been out of service for greater then 1 hour. which is considered a major loss of emergency assessment capability.
"Troubleshooting of the ERFCS by Instrumentation & Controls personnel identified a software problem. At 1600 hours EDT on 04/20/03, Instrumentation & Controls personnel were able to restore the 'A' train ERFCS and at 1630 hours EDT on 04/20/03 the ERFCS and SPDS were declared operable [efforts to restore the 'B' train are ongoing].
"This report is being made in accordance with I0CFR50.72(b)(3)(xiii)."
The Licensee has notified the NRC Resident Inspector.