Event Notification Report for February 19, 2001
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
02/18/2001 - 02/19/2001
EVENT NUMBERS
3776437765377663776237795
Power Reactor
Event Number: 37764
Facility: PERRY
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: KENNETH RUSSELL
HQ OPS Officer: FANGIE JONES
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: KENNETH RUSSELL
HQ OPS Officer: FANGIE JONES
Notification Date: 02/19/2001
Notification Time: 15:24 [ET]
Event Date: 02/19/2001
Event Time: 12:00 [EST]
Last Update Date: 02/19/2001
Notification Time: 15:24 [ET]
Event Date: 02/19/2001
Event Time: 12:00 [EST]
Last Update Date: 02/19/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
PATRICK HILAND (R3)
PATRICK HILAND (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Hot Shutdown | 0 | Hot Shutdown |
THE OHIO EPA NOTIFIED OF AN UNINTENTIONAL DISCHARGE OF CONDENSER COOLING WATER
The Ohio EPA was notified of an unintentional bypass of the wastewater treatment system as required by the NPDES Permit. No reportable quantities were discharged. This was a non-radioactive effluent, main condenser cooling water.
The license intends to notify the NRC Resident Inspector.
The Ohio EPA was notified of an unintentional bypass of the wastewater treatment system as required by the NPDES Permit. No reportable quantities were discharged. This was a non-radioactive effluent, main condenser cooling water.
The license intends to notify the NRC Resident Inspector.
Power Reactor
Event Number: 37765
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: DUANE SCHMIDT
HQ OPS Officer: FANGIE JONES
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: DUANE SCHMIDT
HQ OPS Officer: FANGIE JONES
Notification Date: 02/19/2001
Notification Time: 23:38 [ET]
Event Date: 02/19/2001
Event Time: 20:30 [CST]
Last Update Date: 02/19/2001
Notification Time: 23:38 [ET]
Event Date: 02/19/2001
Event Time: 20:30 [CST]
Last Update Date: 02/19/2001
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):
PATRICK HILAND (R3)
PATRICK HILAND (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 |
UNANALYZED CONDITION FOR RESIDUAL HEAT REMOVAL CAPABILITY
The licensee has determined that torus cooling initiation has not been validated as part of operator actions to be initiated within 10 minutes of a design basis accident in the containment. The licensee, as an interim action, has added an extra licensed operator whose only responsibility is the initiation of torus cooling at the direction of the emergency operating procedures. Further analysis is being carried out for a final resolution.
The licensee intends to notify the NRC Resident Inspector.
The licensee has determined that torus cooling initiation has not been validated as part of operator actions to be initiated within 10 minutes of a design basis accident in the containment. The licensee, as an interim action, has added an extra licensed operator whose only responsibility is the initiation of torus cooling at the direction of the emergency operating procedures. Further analysis is being carried out for a final resolution.
The licensee intends to notify the NRC Resident Inspector.
Power Reactor
Event Number: 37766
Facility: COOPER
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: JOHN MYERS
HQ OPS Officer: STEVE SANDIN
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: JOHN MYERS
HQ OPS Officer: STEVE SANDIN
Notification Date: 02/20/2001
Notification Time: 01:56 [ET]
Event Date: 02/19/2001
Event Time: 21:08 [CST]
Last Update Date: 02/20/2001
Notification Time: 01:56 [ET]
Event Date: 02/19/2001
Event Time: 21:08 [CST]
Last Update Date: 02/20/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
GREG PICK (R4)
GREG PICK (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 54 | Power Operation |
TECH SPEC REQUIRED SHUTDOWN COMMENCED AFTER DECLARING BOTH STANDBY GAS TREATMENT (SGT) TRAINS INOPERABLE
"While performing Surveillance 6.SUMP.101, Z SUMP AND AIR EJECTOR HOLDUP LINE DRAIN OPERABILITY TEST (IST), Z-1 sump pump exceeded its operability time limit of 151 seconds by 3 seconds. When Z-2 sump pump was subsequently tested, the pump failed to start on the essential HI-HI level switch. Both sump pumps were declared INOPERABLE. These pumps support Standby Gas Treatment OPERABILITY. The SGT line from the plant runs underground to the Elevated Release Point tower, and the offgas line and SGT both enter this sump. The pumps remove condensation from both the offgas lines and SGT, and must be available post-accident to prevent flooding of the SGT lines.
"Per administrative direction in the Surveillance procedure, both trains of SGT were declared INOPERABLE at 2108. Per Technical Specification 3.6.4.3, Condition D, with two SGT subsystems INOPERABLE in Mode 1, the Required Action is to enter LCO 3.0.3 immediately. LCO 3.0.3 requires the plant to be in Mode 2 within 7 hours, Mode 3 within 13 hours, and Mode 4 within 37 hours. A power reduction was commenced at 2250. Present power level is 54%.
"Engineering personnel have responded to the plant and are evaluating the two conditions."
The above surveillance is performed quarterly. The licensee noted a past history of problems with the system's level switches. The current rate of power reduction is approximately 100 MW/hr or 12-15% reactor power. The licensee informed the NRC resident inspector.
* * * UPDATE 0441 2/20/01 FROM TERRY BORGAN TO S. SANDIN * * *
Tech Spec required shutdown exited at 0334CST after engineering determined that one train of SGT was OPERABLE. The Unit remains in a 7-day LCO for the other INOPERABLE train. Notified R4DO(Pick).
"While performing Surveillance 6.SUMP.101, Z SUMP AND AIR EJECTOR HOLDUP LINE DRAIN OPERABILITY TEST (IST), Z-1 sump pump exceeded its operability time limit of 151 seconds by 3 seconds. When Z-2 sump pump was subsequently tested, the pump failed to start on the essential HI-HI level switch. Both sump pumps were declared INOPERABLE. These pumps support Standby Gas Treatment OPERABILITY. The SGT line from the plant runs underground to the Elevated Release Point tower, and the offgas line and SGT both enter this sump. The pumps remove condensation from both the offgas lines and SGT, and must be available post-accident to prevent flooding of the SGT lines.
"Per administrative direction in the Surveillance procedure, both trains of SGT were declared INOPERABLE at 2108. Per Technical Specification 3.6.4.3, Condition D, with two SGT subsystems INOPERABLE in Mode 1, the Required Action is to enter LCO 3.0.3 immediately. LCO 3.0.3 requires the plant to be in Mode 2 within 7 hours, Mode 3 within 13 hours, and Mode 4 within 37 hours. A power reduction was commenced at 2250. Present power level is 54%.
"Engineering personnel have responded to the plant and are evaluating the two conditions."
The above surveillance is performed quarterly. The licensee noted a past history of problems with the system's level switches. The current rate of power reduction is approximately 100 MW/hr or 12-15% reactor power. The licensee informed the NRC resident inspector.
* * * UPDATE 0441 2/20/01 FROM TERRY BORGAN TO S. SANDIN * * *
Tech Spec required shutdown exited at 0334CST after engineering determined that one train of SGT was OPERABLE. The Unit remains in a 7-day LCO for the other INOPERABLE train. Notified R4DO(Pick).
Power Reactor
Event Number: 37762
Facility: FARLEY
Region: 2 State: AL
Unit: [1] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: BRAD MOORE
HQ OPS Officer: FANGIE JONES
Region: 2 State: AL
Unit: [1] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: BRAD MOORE
HQ OPS Officer: FANGIE JONES
Notification Date: 02/19/2001
Notification Time: 13:04 [ET]
Event Date: 02/19/2001
Event Time: 06:12 [CST]
Last Update Date: 02/19/2001
Notification Time: 13:04 [ET]
Event Date: 02/19/2001
Event Time: 06:12 [CST]
Last Update Date: 02/19/2001
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):
ANNE BOLAND (R2)
ANNE BOLAND (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 |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
LOSS OF EMERGENCY COMMUNICATIONS TO THE STATE
The licensee lost the emergency communications line to the states of Alabama and Georgia at 0512 CST on 2/19/01 due to the failure of a communications power inverter located offsite in Dothan, Alabama. The inverter was restored at 0758 CST, restoring the emergency communications line. All other communications were available during this time.
The licensee intends to notify the NRC Resident Inspector.
The licensee lost the emergency communications line to the states of Alabama and Georgia at 0512 CST on 2/19/01 due to the failure of a communications power inverter located offsite in Dothan, Alabama. The inverter was restored at 0758 CST, restoring the emergency communications line. All other communications were available during this time.
The licensee intends to notify the NRC Resident Inspector.
General Information or Other
Event Number: 37795
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: QC LABORATORIES, INC.
Region: 4
City: HOUSTON State: TX
County: HARRIS
License #: L04750
Agreement: Y
Docket:
NRC Notified By: HELEN WATKINS (VIA FAX)
HQ OPS Officer: STEVE SANDIN
Licensee: QC LABORATORIES, INC.
Region: 4
City: HOUSTON State: TX
County: HARRIS
License #: L04750
Agreement: Y
Docket:
NRC Notified By: HELEN WATKINS (VIA FAX)
HQ OPS Officer: STEVE SANDIN
Notification Date: 03/01/2001
Notification Time: 17:00 [ET]
Event Date: 02/19/2001
Event Time: 09:45 [CST]
Last Update Date: 03/01/2001
Notification Time: 17:00 [ET]
Event Date: 02/19/2001
Event Time: 09:45 [CST]
Last Update Date: 03/01/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
LINDA HOWELL (R4)
JOSEPH HOLONICH (NMSS)
LINDA HOWELL (R4)
JOSEPH HOLONICH (NMSS)
AGREEMENT STATE REPORT INVOLVING A MISSING NUCLEAR DENSITY GAUGE
On 2/15/01 an employee of QC Laboratories, Inc. went to a jobsite and never returned. The police were notified and are looking for the individual and the company's 1997 Nissan truck. The employee was in the possession of a nuclear density gauge manufactured by Humbolt Scientific, Inc., model #HS-5001EZ, serial #3145. The gauge contains two sources; 10 millicuries Cs-137 (as of 7/14/97 or 10/30/98) and 40 millicuries Am-241:Be.
On 3/1/01 additional information was available updating this incident. The gauge has been recovered. The Nissan truck with the gauge locked securely was parked at a drug rehab facility where the operator had checked himself in.
Texas Incident #7718.
On 2/15/01 an employee of QC Laboratories, Inc. went to a jobsite and never returned. The police were notified and are looking for the individual and the company's 1997 Nissan truck. The employee was in the possession of a nuclear density gauge manufactured by Humbolt Scientific, Inc., model #HS-5001EZ, serial #3145. The gauge contains two sources; 10 millicuries Cs-137 (as of 7/14/97 or 10/30/98) and 40 millicuries Am-241:Be.
On 3/1/01 additional information was available updating this incident. The gauge has been recovered. The Nissan truck with the gauge locked securely was parked at a drug rehab facility where the operator had checked himself in.
Texas Incident #7718.