Event Notification Report for January 26, 2001
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
01/25/2001 - 01/26/2001
Power Reactor
Event Number: 37692
Facility: ZION
Region: 3 State: IL
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: M RODE
HQ OPS Officer: JOHN MacKINNON
Region: 3 State: IL
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: M RODE
HQ OPS Officer: JOHN MacKINNON
Notification Date: 01/26/2001
Notification Time: 09:57 [ET]
Event Date: 01/26/2001
Event Time: 08:15 [CST]
Last Update Date: 01/26/2001
Notification Time: 09:57 [ET]
Event Date: 01/26/2001
Event Time: 08:15 [CST]
Last Update Date: 01/26/2001
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
JAMES CREED (R3)
FRANK CONGEL (IRO)
JOE GIITTER (IRO)
CALDWELL (FEMA)
ED GOODWIN, EO (NRR)
JAMES CREED (R3)
FRANK CONGEL (IRO)
JOE GIITTER (IRO)
CALDWELL (FEMA)
ED GOODWIN, EO (NRR)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Decommissioned | 0 | Decommissioned |
| 2 | N | N | 0 | Decommissioned | 0 | Decommissioned |
LOSS OF SPENT FUEL NUCLEAR ISLAND COOLING.
Both 12kV feeder lines to the Spent Fuel Nuclear Island deenergized causing a loss of cooling to the Spent Fuel Island. Initial Spent Fuel Nuclear Island temperature was 91 degrees F. In one hour and forty five minutes after a loss of power the water temperature of the Spent Fuel Island increased from 91 degrees F to 92 degrees F. Worst case time to boil is 84 hours. Licensee entered EAL MU3 (Unusual Event for a loss of Spent Fuel Island Cooling) at 0815CT. 12kV power was initially lost at 0715CT. Radiation Monitor in the Spent Fuel Island Area is functioning properly and radiation levels in the area are normal. The licensee expects to have Spent Fuel Island Cooling back in service in less than one hour. Licensee notified State and Local officials.
The NRC Resident Inspector was notified of this event by the licensee.
* * * UPDATE BY M. RODE AT 1039 ET TAKEN BY MACKINNON * * *
Unusual Event was terminated at 0939 CT after power was restored and the highest Spent Fuel Island water temperature reached was 92 degrees F. R3DO (J Creed), IRO (Congel), NRR EO (Ed Goodwin), and FEMA (Steindurf) notified.
The NRC Resident Inspector will be notified by the licensee.
Both 12kV feeder lines to the Spent Fuel Nuclear Island deenergized causing a loss of cooling to the Spent Fuel Island. Initial Spent Fuel Nuclear Island temperature was 91 degrees F. In one hour and forty five minutes after a loss of power the water temperature of the Spent Fuel Island increased from 91 degrees F to 92 degrees F. Worst case time to boil is 84 hours. Licensee entered EAL MU3 (Unusual Event for a loss of Spent Fuel Island Cooling) at 0815CT. 12kV power was initially lost at 0715CT. Radiation Monitor in the Spent Fuel Island Area is functioning properly and radiation levels in the area are normal. The licensee expects to have Spent Fuel Island Cooling back in service in less than one hour. Licensee notified State and Local officials.
The NRC Resident Inspector was notified of this event by the licensee.
* * * UPDATE BY M. RODE AT 1039 ET TAKEN BY MACKINNON * * *
Unusual Event was terminated at 0939 CT after power was restored and the highest Spent Fuel Island water temperature reached was 92 degrees F. R3DO (J Creed), IRO (Congel), NRR EO (Ed Goodwin), and FEMA (Steindurf) notified.
The NRC Resident Inspector will be notified by the licensee.
Power Reactor
Event Number: 37693
Facility: TURKEY POINT
Region: 2 State: FL
Unit: [] [4] []
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: P LAFONTAINE
HQ OPS Officer: JOHN MacKINNON
Region: 2 State: FL
Unit: [] [4] []
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: P LAFONTAINE
HQ OPS Officer: JOHN MacKINNON
Notification Date: 01/26/2001
Notification Time: 11:29 [ET]
Event Date: 01/26/2001
Event Time: 10:00 [EST]
Last Update Date: 01/30/2001
Notification Time: 11:29 [ET]
Event Date: 01/26/2001
Event Time: 10:00 [EST]
Last Update Date: 01/30/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
KERRY LANDIS (R2)
FRANK CONGEL (IRO)
ED GOODWIN (NRR)
KERRY LANDIS (R2)
FRANK CONGEL (IRO)
ED GOODWIN (NRR)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 4 | N | N | 0 | Hot Standby | 0 | Hot Standby |
POSSIBLE REACTOR COOLANT SYSTEM (RCS) LEAKAGE
Possible RCS boundary leakage from around a part length CRDM housing. Dry boric acid crystal buildup, less than one cup, was found around a part length CRDM housing. Licensee will have to remove missile shield, etc. to determine which part length CRDM housing has the leak or possibly leaked in the past. Currently the licensee is cooling down the plant and should be in a cold shutdown condition in 6 or 7 hours from 1130 ET.
The NRC Resident was notified of this by the licensee.
* * * UPDATE ON 1/30/01 @ 1123 BY HICKEY TO GOULD * * *
Wet boric acid was identified on the mechanical seal area at the top of CRDM H-14. and a small ring of dry boric acid was found at the CRDM B-8 vent plug cap. Neither leak point constituted RCS pressure boundary leakage, as defined in Technical Specifications. H-14 and B-8 are both abandoned part-length CRDM housings. Boric acid had run down the outside of the H-14 housing, but there was no visual indication of leakage in the welded areas. The welds on H-14 were examined by NDE; no indications were found. Unit 4 was refueled in October, 2000. Neither of these leaks was identified during the restart inspection at the end of the refueling outage. The top closure assembly on both housings was replaced with a threaded and welded plug design. Preparations are underway to return Unit 4 to service.
The NRC Resident Inspector was notified. The Reg 2 RDO(Wert) was notified.
Possible RCS boundary leakage from around a part length CRDM housing. Dry boric acid crystal buildup, less than one cup, was found around a part length CRDM housing. Licensee will have to remove missile shield, etc. to determine which part length CRDM housing has the leak or possibly leaked in the past. Currently the licensee is cooling down the plant and should be in a cold shutdown condition in 6 or 7 hours from 1130 ET.
The NRC Resident was notified of this by the licensee.
* * * UPDATE ON 1/30/01 @ 1123 BY HICKEY TO GOULD * * *
Wet boric acid was identified on the mechanical seal area at the top of CRDM H-14. and a small ring of dry boric acid was found at the CRDM B-8 vent plug cap. Neither leak point constituted RCS pressure boundary leakage, as defined in Technical Specifications. H-14 and B-8 are both abandoned part-length CRDM housings. Boric acid had run down the outside of the H-14 housing, but there was no visual indication of leakage in the welded areas. The welds on H-14 were examined by NDE; no indications were found. Unit 4 was refueled in October, 2000. Neither of these leaks was identified during the restart inspection at the end of the refueling outage. The top closure assembly on both housings was replaced with a threaded and welded plug design. Preparations are underway to return Unit 4 to service.
The NRC Resident Inspector was notified. The Reg 2 RDO(Wert) was notified.