Event Notification Report for January 30, 2003
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
01/29/2003 - 01/30/2003
EVENT NUMBERS
39547395483955039551
Power Reactor
Event Number: 39547
Facility: PALO VERDE
Region: 4 State: AZ
Unit: [1] [2] [3]
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: DAN MARKS
HQ OPS Officer: YAMIR DIAZ
Region: 4 State: AZ
Unit: [1] [2] [3]
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: DAN MARKS
HQ OPS Officer: YAMIR DIAZ
Notification Date: 01/30/2003
Notification Time: 14:23 [ET]
Event Date: 01/30/2003
Event Time: 11:30 [MST]
Last Update Date: 01/30/2003
Notification Time: 14:23 [ET]
Event Date: 01/30/2003
Event Time: 11:30 [MST]
Last Update Date: 01/30/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
WILLIAM JONES (R4)
WILLIAM JONES (R4)
| 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 |
| 3 | N | Y | 100 | Power Operation | 100 | Power Operation |
INFORMATION CALL CONCERNING PRESS RELEASE ON SAFEGUARDS EVENT
Press release regarding a safeguards event involving a flyover at Palo Verde. The press release was made by a local radio station, KTAR.
The NRC resident inspector was notified.
Press release regarding a safeguards event involving a flyover at Palo Verde. The press release was made by a local radio station, KTAR.
The NRC resident inspector was notified.
Power Reactor
Event Number: 39548
Facility: GRAND GULF
Region: 4 State: MS
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: BEARD
HQ OPS Officer: CHAUNCEY GOULD
Region: 4 State: MS
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: BEARD
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 01/30/2003
Notification Time: 14:42 [ET]
Event Date: 01/30/2003
Event Time: 10:54 [CST]
Last Update Date: 01/30/2003
Notification Time: 14:42 [ET]
Event Date: 01/30/2003
Event Time: 10:54 [CST]
Last Update Date: 01/30/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(A) - ECCS INJECTION 50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(2)(iv)(A) - ECCS INJECTION 50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
WILLIAM JONES (R4)
WILLIAM JONES (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | M/R | Y | 100 | Power Operation | 0 | Hot Shutdown |
MANUAL REACTOR SCRAM ON DECREASING REACTOR VESSEL LEVEL
"At 10:54 CDT Grand Gulf Nuclear Station inserted a manual scram on decreasing vessel level as a result of the loss of all 3 condensate booster pumps. Loss of the booster pumps resulted in loss of normal feedwater to the vessel. Vessel level decreased to the auto initiation set point for High Pressure Core Spray (HPCS), Reactor Isolation Cooling System (RCIC), and Containment Isolation System. HPCS and RCIC started and injected to the vessel and the containment isolated. The HPCS initiation also included an auto start of the HPCS Diesel as expected. Reactor level was restored by injection of HPCS and RCIC. Vessel pressure was maintained by the turbine bypass valves. At present vessel level has been restored to normal. Systems affected by the containment isolation have been restored as needed. The cause of the condensate booster trips is under investigation. A review of plant data is underway to confirm proper response by equipment."
There was an ECCS injection for 5 - 10 minutes. All control rods inserted and no relief valves lifted.
The NRC Resident Inspector was notified.
"At 10:54 CDT Grand Gulf Nuclear Station inserted a manual scram on decreasing vessel level as a result of the loss of all 3 condensate booster pumps. Loss of the booster pumps resulted in loss of normal feedwater to the vessel. Vessel level decreased to the auto initiation set point for High Pressure Core Spray (HPCS), Reactor Isolation Cooling System (RCIC), and Containment Isolation System. HPCS and RCIC started and injected to the vessel and the containment isolated. The HPCS initiation also included an auto start of the HPCS Diesel as expected. Reactor level was restored by injection of HPCS and RCIC. Vessel pressure was maintained by the turbine bypass valves. At present vessel level has been restored to normal. Systems affected by the containment isolation have been restored as needed. The cause of the condensate booster trips is under investigation. A review of plant data is underway to confirm proper response by equipment."
There was an ECCS injection for 5 - 10 minutes. All control rods inserted and no relief valves lifted.
The NRC Resident Inspector was notified.
General Information or Other
Event Number: 39550
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: UNIVERSITY OF TEXAS AT AUSTIN
Region: 4
City: AUSTIN State: TX
County:
License #: L00485-000
Agreement: Y
Docket:
NRC Notified By: JAMES H. OGDEN
HQ OPS Officer: YAMIR DIAZ
Licensee: UNIVERSITY OF TEXAS AT AUSTIN
Region: 4
City: AUSTIN State: TX
County:
License #: L00485-000
Agreement: Y
Docket:
NRC Notified By: JAMES H. OGDEN
HQ OPS Officer: YAMIR DIAZ
Notification Date: 01/31/2003
Notification Time: 14:00 [ET]
Event Date: 01/30/2003
Event Time: 00:00 [CST]
Last Update Date: 01/31/2003
Notification Time: 14:00 [ET]
Event Date: 01/30/2003
Event Time: 00:00 [CST]
Last Update Date: 01/31/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
WILLIAM JONES (R4)
FRED BROWN (NMSS)
WILLIAM JONES (R4)
FRED BROWN (NMSS)
TEXAS AGREEMENT STATE REPORT FOR LEAKING SOURCE
"The University of Texas ordered a Sodium 22 (Na-22) positron source for research use. The Type A package arrived during the evening of January 30, 2003, and was unpackaged. During un-packaging it was noted that the Source was either leaking or contaminated. Attempts to decontaminate the source only resulted in higher reading. Leakage was measured at 30,000 DPM, therefore, over the 0.0005 uCi [microcurie] leakage limit.
"The source arrived from the manufacturer: National Accelerator Center, Somerset West, South Africa. The report was made IAW 25 TAC 289.202 (bbb). A follow-up written report will follow by facsimile within 5 days. Chemical form of the source is solid sodium bicarbonate sealed in a titanium body. Source was leak tested due to the lack of a leak test certificate with the shipment. The inner packaging of the Type A container is also contaminated. No Model # or Serial # is readily apparent."
"The University of Texas ordered a Sodium 22 (Na-22) positron source for research use. The Type A package arrived during the evening of January 30, 2003, and was unpackaged. During un-packaging it was noted that the Source was either leaking or contaminated. Attempts to decontaminate the source only resulted in higher reading. Leakage was measured at 30,000 DPM, therefore, over the 0.0005 uCi [microcurie] leakage limit.
"The source arrived from the manufacturer: National Accelerator Center, Somerset West, South Africa. The report was made IAW 25 TAC 289.202 (bbb). A follow-up written report will follow by facsimile within 5 days. Chemical form of the source is solid sodium bicarbonate sealed in a titanium body. Source was leak tested due to the lack of a leak test certificate with the shipment. The inner packaging of the Type A container is also contaminated. No Model # or Serial # is readily apparent."
Power Reactor
Event Number: 39551
Facility: LIMERICK
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: SOSSON
HQ OPS Officer: CHAUNCEY GOULD
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: SOSSON
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 01/31/2003
Notification Time: 19:55 [ET]
Event Date: 01/30/2003
Event Time: 13:00 [EST]
Last Update Date: 01/31/2003
Notification Time: 19:55 [ET]
Event Date: 01/30/2003
Event Time: 13:00 [EST]
Last Update Date: 01/31/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
DANIEL HOLODY (R1)
DANIEL HOLODY (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
PLANT IN UNANALYZED CONDITION DUE TO INCORRECT INSTALLATION OF DRAIN SYSTEM CLEANOUT PLUG
"At 13:00 EST on 1/31/2003, a system manager discovered a dirty radwaste floor drain system cleanout plug installed incorrectly in the Unit 1 A/C RHR room. The threads on cleanout plug were found not engaged. The plug was immediately installed terminating the condition. No check valves are installed in this cleanout line and therefore significant back leakage could occur into the RHR room.
"This event resulted in a condition that could have rendered all trains of the RHR system inoperable during a flooding event by bypassing the normal floor drain system.
"The time that this condition began is not currently known, pending investigation. A walk down of similar drains on both units is being conducted."
The NRC Resident Inspector will be notified.
"At 13:00 EST on 1/31/2003, a system manager discovered a dirty radwaste floor drain system cleanout plug installed incorrectly in the Unit 1 A/C RHR room. The threads on cleanout plug were found not engaged. The plug was immediately installed terminating the condition. No check valves are installed in this cleanout line and therefore significant back leakage could occur into the RHR room.
"This event resulted in a condition that could have rendered all trains of the RHR system inoperable during a flooding event by bypassing the normal floor drain system.
"The time that this condition began is not currently known, pending investigation. A walk down of similar drains on both units is being conducted."
The NRC Resident Inspector will be notified.