Event Notification Report for November 08, 1999
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
11/07/1999 - 11/08/1999
Power Reactor
Event Number: 36413
Facility: SAN ONOFRE
Region: 4 State: CA
Unit: [1] [2] [3]
RX Type: [1] W-3-LP,[2] CE,[3] CE
NRC Notified By: G. L. PLUMLEE
HQ OPS Officer: DOUG WEAVER
Region: 4 State: CA
Unit: [1] [2] [3]
RX Type: [1] W-3-LP,[2] CE,[3] CE
NRC Notified By: G. L. PLUMLEE
HQ OPS Officer: DOUG WEAVER
Notification Date: 11/08/1999
Notification Time: 17:24 [ET]
Event Date: 11/08/1999
Event Time: 13:45 [PST]
Last Update Date: 11/08/1999
Notification Time: 17:24 [ET]
Event Date: 11/08/1999
Event Time: 13:45 [PST]
Last Update Date: 11/08/1999
Emergency Class: NON EMERGENCY
10 CFR Section:
73.71(b)(1) - SAFEGUARDS REPORTS
10 CFR Section:
73.71(b)(1) - SAFEGUARDS REPORTS
Person (Organization):
PHIL HARRELL (R4)
PHIL HARRELL (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Decommissioned | 0 | Decommissioned |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
| 3 | N | Y | 100 | Power Operation | 100 | Power Operation |
SAFEGUARDS SYSTEM DEGRADATION RELATED TO AREA BOUNDARY. IMMEDIATE COMPENSATORY ACTIONS TAKEN UPON DISCOVERY. THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE
CONTACT THE NRC OPERATIONS CENTER FOR ADDITIONAL DETAILS.
CONTACT THE NRC OPERATIONS CENTER FOR ADDITIONAL DETAILS.
Power Reactor
Event Number: 36414
Facility: POINT BEACH
Region: 3 State: WI
Unit: [1] [] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: MIKE MEYER
HQ OPS Officer: DOUG WEAVER
Region: 3 State: WI
Unit: [1] [] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: MIKE MEYER
HQ OPS Officer: DOUG WEAVER
Notification Date: 11/08/1999
Notification Time: 18:30 [ET]
Event Date: 11/08/1999
Event Time: 16:00 [CST]
Last Update Date: 11/08/1999
Notification Time: 18:30 [ET]
Event Date: 11/08/1999
Event Time: 16:00 [CST]
Last Update Date: 11/08/1999
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(ii) - ESF ACTUATION
10 CFR Section:
50.72(b)(2)(ii) - ESF ACTUATION
Person (Organization):
MICHAEL PARKER (R3)
MICHAEL PARKER (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
ESF ACTUATION - SAFETY INJECTION SIGNAL INADVERTENTLY INSERTED DURING TESTING
While performing post maintenance testing on 1P-ISA (Safety Injection Pump), an inadvertent ESF occurred. The 'A' Safety Injection Train actuated on Unit 1 after the electrician installed a jumper which was intended to simulate an Auto Start signal for 1P-ISA. The jumper terminals appear to have been incorrectly identified in the work plan. All systems started as designed. The SI pumps did not start because they were in pull-to-lock per procedure for the existing plant conditions. The following components/activations occurred: Aux feed pump start, EDG start (Train A), and containment isolation. Because the affected unit was defueled, systems that would normally inject into the reactor coolant system were tagged out. There was no ECCS discharge. Service water was momentarily isolated to Spent Fuel Pool Cooling resulting in spent fuel pool temperature increasing slightly. Bulk spent fuel pool temperature remained at approximately 85°F. Current calculated time to boil is 19 hours.
The licensee notified the NRC resident inspector.
While performing post maintenance testing on 1P-ISA (Safety Injection Pump), an inadvertent ESF occurred. The 'A' Safety Injection Train actuated on Unit 1 after the electrician installed a jumper which was intended to simulate an Auto Start signal for 1P-ISA. The jumper terminals appear to have been incorrectly identified in the work plan. All systems started as designed. The SI pumps did not start because they were in pull-to-lock per procedure for the existing plant conditions. The following components/activations occurred: Aux feed pump start, EDG start (Train A), and containment isolation. Because the affected unit was defueled, systems that would normally inject into the reactor coolant system were tagged out. There was no ECCS discharge. Service water was momentarily isolated to Spent Fuel Pool Cooling resulting in spent fuel pool temperature increasing slightly. Bulk spent fuel pool temperature remained at approximately 85°F. Current calculated time to boil is 19 hours.
The licensee notified the NRC resident inspector.