Event Notification Report for March 01, 2004
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
02/29/2004 - 03/01/2004
EVENT NUMBERS
40561405584055940696
Power Reactor
Event Number: 40561
Facility: PALO VERDE
Region: 4 State: AZ
Unit: [] [] [3]
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: DAN MARKS
HQ OPS Officer: BILL GOTT
Region: 4 State: AZ
Unit: [] [] [3]
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: DAN MARKS
HQ OPS Officer: BILL GOTT
Notification Date: 03/02/2004
Notification Time: 12:50 [ET]
Event Date: 03/01/2004
Event Time: 16:49 [MST]
Last Update Date: 03/02/2004
Notification Time: 12:50 [ET]
Event Date: 03/01/2004
Event Time: 16:49 [MST]
Last Update Date: 03/02/2004
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):
GREG PICK (R4)
GREG PICK (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
PRESS RELEASE REGARDING BORON RESIDUE
The license provided the following via facsimile:
"This ENS notification is to inform the agency of a news release that was issued 03/01/04 at 1649 Mountain Standard Time (MST) regarding the shutdown of Palo Verde Nuclear Generating Station Unit 3 and discovery of boron residue on a pressurizer heater sleeve which was reported to the Headquarters Operations Center in ENS ID 40556.
"The unit has been cooled down to Mode 5 in preparation of maintenance to repair the pressurizer heater sleeve. Current plant conditions are approximately 125 degrees F and 35 psia."
The unit was shutdown on 2/29/03 while troubleshooting a turbine-generator excitation problem. The residue was discovered by engineering personnel performing preplanned visual examinations of reactor coolant system (RCS) piping.
"The NRC Resident Inspector has been notified of this ENS call."
The license provided the following via facsimile:
"This ENS notification is to inform the agency of a news release that was issued 03/01/04 at 1649 Mountain Standard Time (MST) regarding the shutdown of Palo Verde Nuclear Generating Station Unit 3 and discovery of boron residue on a pressurizer heater sleeve which was reported to the Headquarters Operations Center in ENS ID 40556.
"The unit has been cooled down to Mode 5 in preparation of maintenance to repair the pressurizer heater sleeve. Current plant conditions are approximately 125 degrees F and 35 psia."
The unit was shutdown on 2/29/03 while troubleshooting a turbine-generator excitation problem. The residue was discovered by engineering personnel performing preplanned visual examinations of reactor coolant system (RCS) piping.
"The NRC Resident Inspector has been notified of this ENS call."
Power Reactor
Event Number: 40558
Facility: FARLEY
Region: 2 State: AL
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: WAYNE VAN LANDINGHAM
HQ OPS Officer: STEVE SANDIN
Region: 2 State: AL
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: WAYNE VAN LANDINGHAM
HQ OPS Officer: STEVE SANDIN
Notification Date: 03/01/2004
Notification Time: 07:23 [ET]
Event Date: 03/01/2004
Event Time: 05:22 [CST]
Last Update Date: 03/01/2004
Notification Time: 07:23 [ET]
Event Date: 03/01/2004
Event Time: 05:22 [CST]
Last Update Date: 03/01/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
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)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
CHARLES R. OGLE (R2)
CHARLES R. OGLE (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
UNIT 1 EXPERIENCED A REACTOR TRIP ON TURBINE TRIP DUE TO A FEEDWATER SYSTEM PROBLEM
"Reactor trip Unit 1 as a result of Turbine Trip from Hi-Hi Steam Generator level '1C' Steam Generator. Steam Generator Feed pump suction pressure initially dropped, deviation alarms were received on 'A' and 'C' Steam Generator levels. Third condensate [pump] was started, increasing feed to S/Gs. '1C' S/G went high and caused turbine trip/reactor trip. Autostart of 'A' and 'B' motor driven feed pumps occurred following the trip."
All rods fully inserted following the reactor trip. Both motor-driven auxiliary feedwater pumps are currently supplying the steam generators with the steam dump system in-service to remove decay heat via the main condenser. Offsite power is stable with the EDGs in standby, if needed. All systems functioned as required. The licensee is conducting an investigation to determine the root cause.
The licensee will inform the NRC Resident Inspector.
"Reactor trip Unit 1 as a result of Turbine Trip from Hi-Hi Steam Generator level '1C' Steam Generator. Steam Generator Feed pump suction pressure initially dropped, deviation alarms were received on 'A' and 'C' Steam Generator levels. Third condensate [pump] was started, increasing feed to S/Gs. '1C' S/G went high and caused turbine trip/reactor trip. Autostart of 'A' and 'B' motor driven feed pumps occurred following the trip."
All rods fully inserted following the reactor trip. Both motor-driven auxiliary feedwater pumps are currently supplying the steam generators with the steam dump system in-service to remove decay heat via the main condenser. Offsite power is stable with the EDGs in standby, if needed. All systems functioned as required. The licensee is conducting an investigation to determine the root cause.
The licensee will inform the NRC Resident Inspector.
Power Reactor
Event Number: 40559
Facility: BRAIDWOOD
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: LAWRENCE BROOKS
HQ OPS Officer: ARLON COSTA
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: LAWRENCE BROOKS
HQ OPS Officer: ARLON COSTA
Notification Date: 03/01/2004
Notification Time: 19:05 [ET]
Event Date: 03/01/2004
Event Time: 16:00 [CST]
Last Update Date: 03/01/2004
Notification Time: 19:05 [ET]
Event Date: 03/01/2004
Event Time: 16:00 [CST]
Last Update Date: 03/01/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
JAMES CREED (R3)
BILL BATEMAN (NRR)
JAMES CREED (R3)
BILL BATEMAN (NRR)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
24-HOUR CONDITION OF LICENSE REPORT INVOLVING POTENTIAL VIOLATION OF MAXIMUM POWER LEVEL
"This 24-hour report is being made as required by Braidwood Unit 1 License Condition 2.G as a potential violation of the maximum power level 3586.6 MWt as stated in Unit 1 License Condition 2.C(1).
"Braidwood is conservatively reporting an overpower condition on Unit 1 due to the implementation of an ultrasonic flow measurement system. Unit 1 was potentially overpowered a maximum of 1.07%. This value is based upon the maximum ultrasonic flow meter correction factor used for Unit 1 during the period between June 1999 and September 2003.
"During post installation testing of the permanent ultrasonic flow measurement system, discrepancies in the ultrasonic flow measurement system were identified that could have resulted in an overpower condition of Unit 2 during the previous use of the ultrasonic system (i.e., during the period between June 1999 and September 2003). The ultrasonic flow measurement system was used to correct venturi feedwater flow measurements. The corrected feedwater flow measurements were then used is the calorimetric calculation for reactor power.
"Currently Braidwood Unit 1 and Unit 2 are controlling power level based only on the venturi feedwater flow indication."
The licensee notified the NRC Resident Inspector.
"This 24-hour report is being made as required by Braidwood Unit 1 License Condition 2.G as a potential violation of the maximum power level 3586.6 MWt as stated in Unit 1 License Condition 2.C(1).
"Braidwood is conservatively reporting an overpower condition on Unit 1 due to the implementation of an ultrasonic flow measurement system. Unit 1 was potentially overpowered a maximum of 1.07%. This value is based upon the maximum ultrasonic flow meter correction factor used for Unit 1 during the period between June 1999 and September 2003.
"During post installation testing of the permanent ultrasonic flow measurement system, discrepancies in the ultrasonic flow measurement system were identified that could have resulted in an overpower condition of Unit 2 during the previous use of the ultrasonic system (i.e., during the period between June 1999 and September 2003). The ultrasonic flow measurement system was used to correct venturi feedwater flow measurements. The corrected feedwater flow measurements were then used is the calorimetric calculation for reactor power.
"Currently Braidwood Unit 1 and Unit 2 are controlling power level based only on the venturi feedwater flow indication."
The licensee notified the NRC Resident Inspector.
Hospital
Event Number: 40696
Rep Org: MISSOURI BAPTIST MEDICAL CENTER
Licensee: MISSOURI BAPTIST MEDICAL CENTER
Region: 3
City: ST LOUIS State: MO
County:
License #: 24-11128-02
Agreement: N
Docket:
NRC Notified By: DAVID KEYS
HQ OPS Officer: BILL GOTT
Licensee: MISSOURI BAPTIST MEDICAL CENTER
Region: 3
City: ST LOUIS State: MO
County:
License #: 24-11128-02
Agreement: N
Docket:
NRC Notified By: DAVID KEYS
HQ OPS Officer: BILL GOTT
Notification Date: 04/22/2004
Notification Time: 08:38 [ET]
Event Date: 03/01/2004
Event Time: 00:00 [CDT]
Last Update Date: 04/22/2004
Notification Time: 08:38 [ET]
Event Date: 03/01/2004
Event Time: 00:00 [CDT]
Last Update Date: 04/22/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
35.3045(a)(3) - DOSE TO OTHER SITE > SPECIFIED LIMITS
10 CFR Section:
35.3045(a)(3) - DOSE TO OTHER SITE > SPECIFIED LIMITS
Person (Organization):
DAVID HILLS (R3)
LINDA PSYK (NMSS)
DAVID HILLS (R3)
LINDA PSYK (NMSS)
DOSE TO THE SKIN OTHER THAN THE INTENDED TREATMENT SITE
A female patient received a potential dose to the skin on the inner thigh during a High Dose Rate Treatment. The treatment occurred in late February to early March. This was discovered on 4/21/04, when the patient returned for follow-up and markings on the inner thigh were noticed that were unusual for the intended treatment area. The licensee is determining the actual exposure to the skin. The patient has been notified.
A female patient received a potential dose to the skin on the inner thigh during a High Dose Rate Treatment. The treatment occurred in late February to early March. This was discovered on 4/21/04, when the patient returned for follow-up and markings on the inner thigh were noticed that were unusual for the intended treatment area. The licensee is determining the actual exposure to the skin. The patient has been notified.