Event Notification Report for October 08, 2000
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
10/07/2000 - 10/08/2000
Fuel Cycle Facility
Event Number: 37417
Facility: PADUCAH GASEOUS DIFFUSION PLANT
Region: 3 State: KY
Unit: [] [] []
RX Type: URANIUM ENRICHMENT FACILITY
Comments: 2 DEMOCRACY CENTER
6903 ROCKLEDGE DRIVE
BETHESDA, MD 20817 (301)564-3200
NRC Notified By: J.M. UNDERWOOD
HQ OPS Officer: STEVE SANDIN
Region: 3 State: KY
Unit: [] [] []
RX Type: URANIUM ENRICHMENT FACILITY
Comments: 2 DEMOCRACY CENTER
6903 ROCKLEDGE DRIVE
BETHESDA, MD 20817 (301)564-3200
NRC Notified By: J.M. UNDERWOOD
HQ OPS Officer: STEVE SANDIN
Notification Date: 10/08/2000
Notification Time: 17:59 [ET]
Event Date: 10/08/2000
Event Time: 05:18 [CDT]
Last Update Date: 10/08/2000
Notification Time: 17:59 [ET]
Event Date: 10/08/2000
Event Time: 05:18 [CDT]
Last Update Date: 10/08/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
JOHN MADERA (R3)
M. WAYNE HODGES (NMSS)
JOHN MADERA (R3)
M. WAYNE HODGES (NMSS)
24-HOUR REPORT INVOLVING A SAFETY SYSTEM ACTUATION DUE TO FAILURE OF FREEZER/SUBLIMER INLET VALVE TO CLOSE
"At 0518 on 10/8/00 the PSS office was notified that the C-333 Unit 4 Cell 9 freezer/sublimer (F/S) 'B' valve had failed to close following completion of a high-high weight safety system trip test. The F/S high-high weight trip actuated due to accumulation of UF6 in the vessel caused by the failure of the 'B' valve. The F/S high-high weight trip system is required to be operable while in modes F/S 1 and F/S 3 per TSR 2.4.3.1. The F/S high-high weight trip actuated within the specified limiting control settings of TSR 2.4.3.1. The F/S 'B' valve was manually closed, the F/S was declared inoperable and the excess UF6 was removed from the vessel. The F/S was placed in mode F/S 6 (out of service).
"The safety system actuation is reportable to the NRC as required by Safety Analysis Report section 6.9, table 1, criteria J.2, Safety System actuation due to a valid signal as a 24-hour event notification.
"The NRC Resident inspector has been notified of this event."
"At 0518 on 10/8/00 the PSS office was notified that the C-333 Unit 4 Cell 9 freezer/sublimer (F/S) 'B' valve had failed to close following completion of a high-high weight safety system trip test. The F/S high-high weight trip actuated due to accumulation of UF6 in the vessel caused by the failure of the 'B' valve. The F/S high-high weight trip system is required to be operable while in modes F/S 1 and F/S 3 per TSR 2.4.3.1. The F/S high-high weight trip actuated within the specified limiting control settings of TSR 2.4.3.1. The F/S 'B' valve was manually closed, the F/S was declared inoperable and the excess UF6 was removed from the vessel. The F/S was placed in mode F/S 6 (out of service).
"The safety system actuation is reportable to the NRC as required by Safety Analysis Report section 6.9, table 1, criteria J.2, Safety System actuation due to a valid signal as a 24-hour event notification.
"The NRC Resident inspector has been notified of this event."
Power Reactor
Event Number: 37418
Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: DAN BOYLE
HQ OPS Officer: STEVE SANDIN
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: DAN BOYLE
HQ OPS Officer: STEVE SANDIN
Notification Date: 10/08/2000
Notification Time: 18:11 [ET]
Event Date: 10/08/2000
Event Time: 16:20 [EDT]
Last Update Date: 10/08/2000
Notification Time: 18:11 [ET]
Event Date: 10/08/2000
Event Time: 16:20 [EDT]
Last Update Date: 10/08/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iii)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(2)(iii)(D) - ACCIDENT MITIGATION
Person (Organization):
JAMES LINVILLE (R1)
JAMES LINVILLE (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 99 | Power Operation | 99 | Power Operation |
"B" REACTOR RECIRC PUMP MOTOR GENERATOR OVERSPEED STOPS FOUND SET HIGH (NON-CONSERVATIVE) DURING SURVEILLANCE TESTING
"During the performance of the 18 month surveillance requirement to demonstrate operability of the reactor recirc pump motor set scoop tube mechanical and electrical stop overspeed setpoints to be less than or equal to 109% and 107%, respectively, the 'B' MG set stops were found non-conservatively high. The magnitude of offset has not been calculated as of this time, but the setpoints have been readjusted to their proper settings as of 1732 hours this date.
"The potential impact of this condition would be a function of the reactor recirc pump 'runaway' transient. If that analyzed transient were to have occurred, the potential existed for the flow dependent minimum critical power ratio to have been exceeded. This could result in exceeding the safety limit (MCPR) under those postulated conditions.
"Evaluation of the potential cause of the improper settings is under way."
The licensee will inform the NRC resident inspector and the Lower Alloways Creek Township.
"During the performance of the 18 month surveillance requirement to demonstrate operability of the reactor recirc pump motor set scoop tube mechanical and electrical stop overspeed setpoints to be less than or equal to 109% and 107%, respectively, the 'B' MG set stops were found non-conservatively high. The magnitude of offset has not been calculated as of this time, but the setpoints have been readjusted to their proper settings as of 1732 hours this date.
"The potential impact of this condition would be a function of the reactor recirc pump 'runaway' transient. If that analyzed transient were to have occurred, the potential existed for the flow dependent minimum critical power ratio to have been exceeded. This could result in exceeding the safety limit (MCPR) under those postulated conditions.
"Evaluation of the potential cause of the improper settings is under way."
The licensee will inform the NRC resident inspector and the Lower Alloways Creek Township.