Event Notification Report for December 19, 2002
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
12/18/2002 - 12/19/2002
EVENT NUMBERS
39460394623946339464
Power Reactor
Event Number: 39460
Facility: ARKANSAS NUCLEAR
Region: 4 State: AR
Unit: [] [2] []
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: JAMES CRABILL
HQ OPS Officer: MIKE NORRIS
Region: 4 State: AR
Unit: [] [2] []
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: JAMES CRABILL
HQ OPS Officer: MIKE NORRIS
Notification Date: 12/19/2002
Notification Time: 05:42 [ET]
Event Date: 12/19/2002
Event Time: 03:59 [CST]
Last Update Date: 12/19/2002
Notification Time: 05:42 [ET]
Event Date: 12/19/2002
Event Time: 03:59 [CST]
Last Update Date: 12/19/2002
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
LINDA HOWELL (R4)
LINDA HOWELL (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
AUTOMATIC REACTOR TRIP DUE TO MAIN TURBINE GENERATOR TRIP
"Main Turbine Generator and Reactor trip from 100% power. All control rods inserted. Plant is stable in Mode 3, Hot Standby. No release in progress."
The Licensee has notified the NRC Resident Inspector and the State of Arkansas.
The Licensee indicated that no ECCS actuation occurred, the electrical grid is stable with all Emergency Diesel Generators available, and that there is no primary to secondary Steam Generator leakage.
"Main Turbine Generator and Reactor trip from 100% power. All control rods inserted. Plant is stable in Mode 3, Hot Standby. No release in progress."
The Licensee has notified the NRC Resident Inspector and the State of Arkansas.
The Licensee indicated that no ECCS actuation occurred, the electrical grid is stable with all Emergency Diesel Generators available, and that there is no primary to secondary Steam Generator leakage.
General Information or Other
Event Number: 39462
Rep Org: NE DIV OF RADIOACTIVE MATERIALS
Licensee: HOLDREGE, NE COUNTRY CLUB
Region: 4
City: HOLDREGE State: NE
County:
License #: GL0200
Agreement: Y
Docket:
NRC Notified By: TRUDY HILL
HQ OPS Officer: ERIC THOMAS
Licensee: HOLDREGE, NE COUNTRY CLUB
Region: 4
City: HOLDREGE State: NE
County:
License #: GL0200
Agreement: Y
Docket:
NRC Notified By: TRUDY HILL
HQ OPS Officer: ERIC THOMAS
Notification Date: 12/19/2002
Notification Time: 16:20 [ET]
Event Date: 12/19/2002
Event Time: 12:00 [CST]
Last Update Date: 12/19/2002
Notification Time: 16:20 [ET]
Event Date: 12/19/2002
Event Time: 12:00 [CST]
Last Update Date: 12/19/2002
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
LINDA HOWELL (R4)
FRED BROWN (NMSS)
LINDA HOWELL (R4)
FRED BROWN (NMSS)
AGREEMENT STATE REPORT INVOLVING A LOST EXIT SIGN
Lost tritium source (exit sign). Purchased in 1987, 15 Curies at time of purchase. Lost at Holdrege, NE Country Club following a renovation.
Lost tritium source (exit sign). Purchased in 1987, 15 Curies at time of purchase. Lost at Holdrege, NE Country Club following a renovation.
Power Reactor
Event Number: 39463
Facility: BRUNSWICK
Region: 2 State: NC
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: WOODBURY
HQ OPS Officer: CHAUNCEY GOULD
Region: 2 State: NC
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: WOODBURY
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 12/19/2002
Notification Time: 17:49 [ET]
Event Date: 12/19/2002
Event Time: 14:30 [EST]
Last Update Date: 12/19/2002
Notification Time: 17:49 [ET]
Event Date: 12/19/2002
Event Time: 14:30 [EST]
Last Update Date: 12/19/2002
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):
PAUL FREDRICKSON (R2)
PAUL FREDRICKSON (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
REACTOR CORE ISOLATION COOLING(RCIC) SYSTEM OPERATION FROM THE REMOTE S/D PANEL MAY NOT BE AVAILABLE FOR SAFE SHUTDOWN OF THE UNIT.
On December 19, 2002, during an engineering review of the impact of electrical faults on the ability of systems required to safely shutdown the facility in the event of a fire, it was determined that Reactor Core Isolation Cooling (RCIC) system operation from the remote shutdown panel (RSDP) may not be available for safe shutdown of the unit.
A postulated fire that results in an electrical short of the Division 2 125/250 VDC distribution system to ground may cause a voltage control device to fail integral to a RSDP instrument power supply inverter. If the inverter fails as a result of the ground, no power supply would be available for automatic or manual control of the RCIC turbine at the RSDP. In addition, loss of the same inverter would also result in the loss of reactor, drywell and suppression pool monitoring instruments at the remote shutdown panel.
The current fire safe shutdown analysis credits only the RCIC system for post-fire inventory control during a worst case main control room fire. This analysis requires RCIC to be operational from the RSDP. With this postulated loss of RCIC RSDP capability during a main control room fire, this event is reportable under 10CFR50.72(b)(3)(ii).
There were no actual safety consequences associated with this reportable event since there was no fire in the control room. The design basis fire in the control room assumes an all encompassing fire which is unlikely and would more likely be limited to a single panel.
An Alternate Safe Shutdown impairment has been established in accordance with station requirements. Compensatory measures consist of calibrating a spare inverter for installation and expediting installation of a plant modification to remove the postulated failure mechanism.
The NRC Resident Inspector was notified.
On December 19, 2002, during an engineering review of the impact of electrical faults on the ability of systems required to safely shutdown the facility in the event of a fire, it was determined that Reactor Core Isolation Cooling (RCIC) system operation from the remote shutdown panel (RSDP) may not be available for safe shutdown of the unit.
A postulated fire that results in an electrical short of the Division 2 125/250 VDC distribution system to ground may cause a voltage control device to fail integral to a RSDP instrument power supply inverter. If the inverter fails as a result of the ground, no power supply would be available for automatic or manual control of the RCIC turbine at the RSDP. In addition, loss of the same inverter would also result in the loss of reactor, drywell and suppression pool monitoring instruments at the remote shutdown panel.
The current fire safe shutdown analysis credits only the RCIC system for post-fire inventory control during a worst case main control room fire. This analysis requires RCIC to be operational from the RSDP. With this postulated loss of RCIC RSDP capability during a main control room fire, this event is reportable under 10CFR50.72(b)(3)(ii).
There were no actual safety consequences associated with this reportable event since there was no fire in the control room. The design basis fire in the control room assumes an all encompassing fire which is unlikely and would more likely be limited to a single panel.
An Alternate Safe Shutdown impairment has been established in accordance with station requirements. Compensatory measures consist of calibrating a spare inverter for installation and expediting installation of a plant modification to remove the postulated failure mechanism.
The NRC Resident Inspector was notified.
Power Reactor
Event Number: 39464
Facility: FT CALHOUN
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: ERICK MATZKE
HQ OPS Officer: ERIC THOMAS
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: ERICK MATZKE
HQ OPS Officer: ERIC THOMAS
Notification Date: 12/19/2002
Notification Time: 22:09 [ET]
Event Date: 12/19/2002
Event Time: 00:00 [CST]
Last Update Date: 12/19/2002
Notification Time: 22:09 [ET]
Event Date: 12/19/2002
Event Time: 00:00 [CST]
Last Update Date: 12/19/2002
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):
LINDA HOWELL (R4)
LINDA HOWELL (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 |
8-HOUR NOTIFICATION FOR UNANALYZED CONDITION
"During a review of the Fort Calhoun Station fire protection program, it was discovered that for a potential fire in two fire areas in the plant the protected train of reactor inventory control would not be free of fire damage. During a postulated fire in either one of two fire areas the charging pump credited for maintaining hot shutdown reactor coolant inventory may be affected by a fire in one of the areas. This represents a technical noncompliance with 10CFR50 Appendix R section III.G.2 and does not affect current plant operation. As a compensatory measure, the plant is instituting hourly fire watches in the affected fire areas."
The licensee notified the Resident Inspector
"During a review of the Fort Calhoun Station fire protection program, it was discovered that for a potential fire in two fire areas in the plant the protected train of reactor inventory control would not be free of fire damage. During a postulated fire in either one of two fire areas the charging pump credited for maintaining hot shutdown reactor coolant inventory may be affected by a fire in one of the areas. This represents a technical noncompliance with 10CFR50 Appendix R section III.G.2 and does not affect current plant operation. As a compensatory measure, the plant is instituting hourly fire watches in the affected fire areas."
The licensee notified the Resident Inspector