Event Notification Report for September 03, 2003
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
09/02/2003 - 09/03/2003
Power Reactor
Event Number: 40130
Facility: BRAIDWOOD
Region: 3 State: IL
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: CRAIG INGOLD
HQ OPS Officer: NATHAN SANFILIPPO
Region: 3 State: IL
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: CRAIG INGOLD
HQ OPS Officer: NATHAN SANFILIPPO
Notification Date: 09/03/2003
Notification Time: 16:57 [ET]
Event Date: 09/03/2003
Event Time: 07:30 [CDT]
Last Update Date: 09/03/2003
Notification Time: 16:57 [ET]
Event Date: 09/03/2003
Event Time: 07:30 [CDT]
Last Update Date: 09/03/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
RONALD GARDNER (R3)
RONALD GARDNER (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 |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
24-HOUR REPORT REQUIRED BY LICENSE CONDITION -- POTENTIAL VIOLATION OF MAXIMUM POWER LEVEL
The following report was submitted by the licensee via fax:
"This 24-hour report is being made as required by Braidwood Unit 1 License Condition 2.G and Braidwood Unit ~ License Condition 2.G as a potential violation of the maximum power level (3586.6 MWt) as stated in Unit 1 and Unit 2 License Condition 2.C(1).
"Braidwood received Nuclear Safety Advisory Letter (NSAL) 03-6 from Westinghouse Electric Company. This NSAL documented that errors were found in calculations that may result in the use of a non conservatively high net heat input value to the plant calorimetric calculation. The net heat input is the difference between the reactor core power and the nuclear steam supply system power.
"The values used in the NSAL were based on generic values for certain operational parameters. The NSAL documented that an increase in actual reactor power could be as much as 0.4 MWt. This equates to an error in reactor power of approximately 0.011%. Braidwood reviewed the power history and 8-hour average calorimetric values on Unit 1 and Unit 2 since full power uprate was applied on each Unit. Several time periods were identified on each Unit where the 8-hour calorimetric value exceeded the license thermal power limit when the 0.011% error was added to the 8-hour calorimetric value. Therefore, the licensed power limit of 3586.6 MWt was slightly exceeded on both Unit 1 and Unit 2.
"The power level on both Units was reduced to less than 100% to account for the 0.4 MWt error. The calorimetric program was then updated to account for this error. This issue was identified at 0730 on September 3, 2003, and has been entered into the Corrective Action Program. Additional information will be contained in the 30-day licensee event report."
The licensee has notified the NRC Resident Inspector.
The following report was submitted by the licensee via fax:
"This 24-hour report is being made as required by Braidwood Unit 1 License Condition 2.G and Braidwood Unit ~ License Condition 2.G as a potential violation of the maximum power level (3586.6 MWt) as stated in Unit 1 and Unit 2 License Condition 2.C(1).
"Braidwood received Nuclear Safety Advisory Letter (NSAL) 03-6 from Westinghouse Electric Company. This NSAL documented that errors were found in calculations that may result in the use of a non conservatively high net heat input value to the plant calorimetric calculation. The net heat input is the difference between the reactor core power and the nuclear steam supply system power.
"The values used in the NSAL were based on generic values for certain operational parameters. The NSAL documented that an increase in actual reactor power could be as much as 0.4 MWt. This equates to an error in reactor power of approximately 0.011%. Braidwood reviewed the power history and 8-hour average calorimetric values on Unit 1 and Unit 2 since full power uprate was applied on each Unit. Several time periods were identified on each Unit where the 8-hour calorimetric value exceeded the license thermal power limit when the 0.011% error was added to the 8-hour calorimetric value. Therefore, the licensed power limit of 3586.6 MWt was slightly exceeded on both Unit 1 and Unit 2.
"The power level on both Units was reduced to less than 100% to account for the 0.4 MWt error. The calorimetric program was then updated to account for this error. This issue was identified at 0730 on September 3, 2003, and has been entered into the Corrective Action Program. Additional information will be contained in the 30-day licensee event report."
The licensee has notified the NRC Resident Inspector.
Power Reactor
Event Number: 40131
Facility: GRAND GULF
Region: 4 State: MS
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: FRANK WEAVER
HQ OPS Officer: NATHAN SANFILIPPO
Region: 4 State: MS
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: FRANK WEAVER
HQ OPS Officer: NATHAN SANFILIPPO
Notification Date: 09/03/2003
Notification Time: 23:18 [ET]
Event Date: 09/03/2003
Event Time: 20:05 [CDT]
Last Update Date: 09/03/2003
Notification Time: 23:18 [ET]
Event Date: 09/03/2003
Event Time: 20:05 [CDT]
Last Update Date: 09/03/2003
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):
CHARLES MARSCHALL (R4)
CHARLES MARSCHALL (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 |
OFFSITE NOTIFICATION DUE TO DEATH OF EMPLOYEE
The following was received via fax from the licensee:
"Radiation protection technician passed away due to what appears to be a heart attack. On-site emergency medical attention was given and the individual was transported to a local hospital where he was pronounced dead. Although this event occurred on-site, the individual was not within the Controlled Access Area (CAA) and was not contaminated."
The licensee made an offsite notification to the Occupational Safety & Health Administration (OSHA) and notified the NRC Resident Inspector.
The following was received via fax from the licensee:
"Radiation protection technician passed away due to what appears to be a heart attack. On-site emergency medical attention was given and the individual was transported to a local hospital where he was pronounced dead. Although this event occurred on-site, the individual was not within the Controlled Access Area (CAA) and was not contaminated."
The licensee made an offsite notification to the Occupational Safety & Health Administration (OSHA) and notified the NRC Resident Inspector.