Event Notification Report for June 10, 1999
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
06/09/1999 - 06/10/1999
Fuel Cycle Facility
Event Number: 35816
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: M.C. MAURER
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: M.C. MAURER
HQ OPS Officer: STEVE SANDIN
Notification Date: 06/12/1999
Notification Time: 06:03 [ET]
Event Date: 06/10/1999
Event Time: 16:33 [CDT]
Last Update Date: 06/12/1999
Notification Time: 06:03 [ET]
Event Date: 06/10/1999
Event Time: 16:33 [CDT]
Last Update Date: 06/12/1999
Emergency Class: NON EMERGENCY
10 CFR Section:
76.120(c)(2) - SAFETY EQUIPMENT FAILURE 76.120(c)(2)(ii) - EQUIP DISABLED/FAILS 76.120(c)(2)(iii) - REDUNDANT EQUIP INOP
10 CFR Section:
76.120(c)(2) - SAFETY EQUIPMENT FAILURE 76.120(c)(2)(ii) - EQUIP DISABLED/FAILS 76.120(c)(2)(iii) - REDUNDANT EQUIP INOP
Person (Organization):
BRUCE JORGENSEN (R3)
TED SHERR (NMSS)
BRUCE JORGENSEN (R3)
TED SHERR (NMSS)
LOSS OF CRITICALITY ACCIDENT ALARM SYSTEM DURING MAINTENANCE
"At 1633 CDT on 6/10/99, electricians were performing scheduled maintenance on the C-400 building criticality accident alarm system (CAAS). During this maintenance activity, circuit breaker EP1 in C-400 was opened resulting in a system trouble alarm on the C-409 building 'AE' CAAS cluster. TSR LCO actions were implemented for the C-409 facility due to the unknown cause of the trouble alarm. After further review of this maintenance activity, there is evidence that control power for the CAAS building horns in C-409 and C-720-M was lost for approximately four hours during the subject maintenance evolution. CAAS detectability and C-409 local CAAS horn operability were not affected by the loss of control power.
"It has been determined that this event is reportable under 10CFR76.120(c)(2) as an event in which equipment is disabled or fails to function as designed.
"The NRC resident inspector has been notified of this event."
"At 1633 CDT on 6/10/99, electricians were performing scheduled maintenance on the C-400 building criticality accident alarm system (CAAS). During this maintenance activity, circuit breaker EP1 in C-400 was opened resulting in a system trouble alarm on the C-409 building 'AE' CAAS cluster. TSR LCO actions were implemented for the C-409 facility due to the unknown cause of the trouble alarm. After further review of this maintenance activity, there is evidence that control power for the CAAS building horns in C-409 and C-720-M was lost for approximately four hours during the subject maintenance evolution. CAAS detectability and C-409 local CAAS horn operability were not affected by the loss of control power.
"It has been determined that this event is reportable under 10CFR76.120(c)(2) as an event in which equipment is disabled or fails to function as designed.
"The NRC resident inspector has been notified of this event."
Power Reactor
Event Number: 35812
Facility: PEACH BOTTOM
Region: 1 State: PA
Unit: [2] [] []
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: CAMPBELL
HQ OPS Officer: CHAUNCEY GOULD
Region: 1 State: PA
Unit: [2] [] []
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: CAMPBELL
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 06/10/1999
Notification Time: 15:29 [ET]
Event Date: 06/10/1999
Event Time: 14:30 [EDT]
Last Update Date: 06/11/1999
Notification Time: 15:29 [ET]
Event Date: 06/10/1999
Event Time: 14:30 [EDT]
Last Update Date: 06/11/1999
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(1)(v) - OTHER ASMT/COMM INOP
10 CFR Section:
50.72(b)(1)(v) - OTHER ASMT/COMM INOP
Person (Organization):
JOHN CARUSO (R1)
JOHN CARUSO (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
PLANT LOST THEIR SAFETY PARAMETER DISPLAY SYSTEM (SPDS)
A HARDWARE FAILURE OCCURRED ON THE UNIT 2 PLANT PROCESS COMPUTER SYSTEM. THIS RESULTED IN THE LOSS OF THE SPDS, WHICH IS ONE METHOD USED FOR EMERGENCY ASSESSMENT. ALL THE CONTROL ROOM INDICATIONS ARE OPERABLE AND AVAILABLE FOR EMERGENCY ASSESSMENT.
THE RESIDENT INSPECTOR WAS NOTIFIED.
* * * UPDATE AT 0250 ON 06/11/99 BY EILOLA, TAKEN BY WEAVER * * *
THE HARDWARE FAILURE HAS BEEN REPAIRED AND THE SYSTEM HAS BEEN RETURNED TO SERVICE. THE LICENSEE WILL NOTIFY THE NRC RESIDENT INSPECTOR. THE OPERATIONS OFFICER NOTIFIED THE R1DO (CARUSO).
A HARDWARE FAILURE OCCURRED ON THE UNIT 2 PLANT PROCESS COMPUTER SYSTEM. THIS RESULTED IN THE LOSS OF THE SPDS, WHICH IS ONE METHOD USED FOR EMERGENCY ASSESSMENT. ALL THE CONTROL ROOM INDICATIONS ARE OPERABLE AND AVAILABLE FOR EMERGENCY ASSESSMENT.
THE RESIDENT INSPECTOR WAS NOTIFIED.
* * * UPDATE AT 0250 ON 06/11/99 BY EILOLA, TAKEN BY WEAVER * * *
THE HARDWARE FAILURE HAS BEEN REPAIRED AND THE SYSTEM HAS BEEN RETURNED TO SERVICE. THE LICENSEE WILL NOTIFY THE NRC RESIDENT INSPECTOR. THE OPERATIONS OFFICER NOTIFIED THE R1DO (CARUSO).
Power Reactor
Event Number: 35813
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: HASBRUCK
HQ OPS Officer: CHAUNCEY GOULD
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: HASBRUCK
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 06/10/1999
Notification Time: 16:01 [ET]
Event Date: 06/10/1999
Event Time: 14:00 [CDT]
Last Update Date: 06/10/1999
Notification Time: 16:01 [ET]
Event Date: 06/10/1999
Event Time: 14:00 [CDT]
Last Update Date: 06/10/1999
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iii)(A) - POT UNABLE TO SAFE SD
10 CFR Section:
50.72(b)(2)(iii)(A) - POT UNABLE TO SAFE SD
Person (Organization):
BRUCE JORGENSEN (R3)
BRUCE JORGENSEN (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 |
HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM COULD HAVE BEEN INOPERABLE DURING PAST SURVEILLANCES.
The licensee discovered a condition during HPCI surveillances that could result in the system becoming inoperable. The HPCI test return isolation valve, MO-2071, is opened to support HPCI testing and it may not close as required during a required activation of the system. There are valve components, which are not part of the pressure boundary, that could exceed their structural limits. MO-2071 is normally closed and HPCI is currently operable. This condition is being reported due to failure to enter appropriate plant Technical Specification LCOs during past plant operation when MO-2071 was open during surveillance testing.
The licensee notified the NRC Resident Inspector as well as the state and local agencies.
The licensee discovered a condition during HPCI surveillances that could result in the system becoming inoperable. The HPCI test return isolation valve, MO-2071, is opened to support HPCI testing and it may not close as required during a required activation of the system. There are valve components, which are not part of the pressure boundary, that could exceed their structural limits. MO-2071 is normally closed and HPCI is currently operable. This condition is being reported due to failure to enter appropriate plant Technical Specification LCOs during past plant operation when MO-2071 was open during surveillance testing.
The licensee notified the NRC Resident Inspector as well as the state and local agencies.