Event Notification Report for March 15, 2000
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
03/14/2000 - 03/15/2000
EVENT NUMBERS
3680336799368003680136797
Power Reactor
Event Number: 36803
Facility: GRAND GULF
Region: 4 State: MS
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: MARTY McADORY
HQ OPS Officer: LEIGH TROCINE
Region: 4 State: MS
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: MARTY McADORY
HQ OPS Officer: LEIGH TROCINE
Notification Date: 03/16/2000
Notification Time: 15:22 [ET]
Event Date: 03/15/2000
Event Time: 02:15 [CST]
Last Update Date: 03/22/2000
Notification Time: 15:22 [ET]
Event Date: 03/15/2000
Event Time: 02:15 [CST]
Last Update Date: 03/22/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
10 CFR Section:
26.73 - FITNESS FOR DUTY
Person (Organization):
KRISS KENNEDY (R4)
KRISS KENNEDY (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 |
LICENSEE SUPERVISOR ARRESTED AND CHARGED WITH FELONY POSSESSION OF A CONTROLLED SUTSTANCE
The following text is a portion of a facsimile received from the licensee:
"[At 0215 CST on 03/15/00, a] licensee supervisor was arrested and charged with felony possession of a controlled substance. The individual's unescorted access was immediately revoked upon discovery of the event [at] 1510 [CST] on [03/15/00]. A licensee investigation has been initiated to obtain additional details related to this off-site event."
"The NRC [resident inspectors] and licensee senior management [have] been informed."
Call the NRC operations officer for additional details.
* * * UPDATE 1714 3/22/2000 FROM DAVID HANKS TAKEN BY BOB STRANSKY * * *
The individual tested positive for drug use after being administered a for-cause test by the licensee following the arrest. The individual's unescorted access remains suspended. The licensee is currently reviewing work performed by this individual. The NRC resident inspector has been informed of this update by the licensee.
Notified R4DO (Yandell).
The following text is a portion of a facsimile received from the licensee:
"[At 0215 CST on 03/15/00, a] licensee supervisor was arrested and charged with felony possession of a controlled substance. The individual's unescorted access was immediately revoked upon discovery of the event [at] 1510 [CST] on [03/15/00]. A licensee investigation has been initiated to obtain additional details related to this off-site event."
"The NRC [resident inspectors] and licensee senior management [have] been informed."
Call the NRC operations officer for additional details.
* * * UPDATE 1714 3/22/2000 FROM DAVID HANKS TAKEN BY BOB STRANSKY * * *
The individual tested positive for drug use after being administered a for-cause test by the licensee following the arrest. The individual's unescorted access remains suspended. The licensee is currently reviewing work performed by this individual. The NRC resident inspector has been informed of this update by the licensee.
Notified R4DO (Yandell).
Power Reactor
Event Number: 36799
Facility: WATERFORD
Region: 4 State: LA
Unit: [3] [] []
RX Type: [3] CE
NRC Notified By: MCKINNEY
HQ OPS Officer: CHAUNCEY GOULD
Region: 4 State: LA
Unit: [3] [] []
RX Type: [3] CE
NRC Notified By: MCKINNEY
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 03/15/2000
Notification Time: 16:58 [ET]
Event Date: 03/15/2000
Event Time: 15:11 [CST]
Last Update Date: 03/15/2000
Notification Time: 16:58 [ET]
Event Date: 03/15/2000
Event Time: 15:11 [CST]
Last Update Date: 03/15/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
73.71(b)(1) - SAFEGUARDS REPORTS
10 CFR Section:
73.71(b)(1) - SAFEGUARDS REPORTS
Person (Organization):
DAVID GRAVES (R4)
DAVID GRAVES (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | Y | 100 | Power Operation | 100 | Power Operation |
SAFEGUARD SYSTEM VULNERABILITY DUE INABILITY TO RESPOND TO PERIMETER ALARMS AROUND THE PROTECTED AREA BECAUSE OF ADVERSE WEATHER CONDITIONS.
IMMEDIATE COMPENSATORY MEASURES NOT TAKEN UPON DISCOVERY; HOWEVER, THEY ARE NOW FULLY IMPLEMENTED.
THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED.
CONTACT THE NRC OPERATIONS CENTER FOR ADDITIONAL DETAILS.
IMMEDIATE COMPENSATORY MEASURES NOT TAKEN UPON DISCOVERY; HOWEVER, THEY ARE NOW FULLY IMPLEMENTED.
THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED.
CONTACT THE NRC OPERATIONS CENTER FOR ADDITIONAL DETAILS.
Power Reactor
Event Number: 36800
Facility: FERMI
Region: 3 State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: CRAINE
HQ OPS Officer: CHAUNCEY GOULD
Region: 3 State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: CRAINE
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 03/15/2000
Notification Time: 17:03 [ET]
Event Date: 03/15/2000
Event Time: 15:32 [EST]
Last Update Date: 03/15/2000
Notification Time: 17:03 [ET]
Event Date: 03/15/2000
Event Time: 15:32 [EST]
Last Update Date: 03/15/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(vi) - OFFSITE NOTIFICATION
10 CFR Section:
50.72(b)(2)(vi) - OFFSITE NOTIFICATION
Person (Organization):
RONALD GARDNER (R3)
RONALD GARDNER (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
OFFSITE NOTIFICATION MADE TO THE MICHIGAN DEPARTMENT OF ENVIRONMENTAL QUALITY(MDEQ)
Cooling tower water was identified to be leaking from the south cooling tower to the ground. The water accumulated and ran over land to the overflow canal which lead to the Swan Creek. Samples were obtained to determine if chlorine could be detected in the water flowing to the overflow canal. Communication was made with Corporate Environmental and it was determined that this event is reportable to the State of Michigan. The spill reaching the surface water was discovered at 1150 on 03/15/00. Temporary earthen dikes have been installed to stop flow to the overflow canal. Initial studies indicated that no detectable chlorine reached the surface water.
Follow-up samples will be obtained from the overflow canal and near the point where the overflow canal meet Swan Creek. A temporary deflector is being installed to route the water back into the tower instead of allowing it to flow to the ground. A permanent fix will be installed in April 2000 during the refueling outage.
The State MDEQ was contacted at 1532.
The NRC Resident Inspector was informed.
Cooling tower water was identified to be leaking from the south cooling tower to the ground. The water accumulated and ran over land to the overflow canal which lead to the Swan Creek. Samples were obtained to determine if chlorine could be detected in the water flowing to the overflow canal. Communication was made with Corporate Environmental and it was determined that this event is reportable to the State of Michigan. The spill reaching the surface water was discovered at 1150 on 03/15/00. Temporary earthen dikes have been installed to stop flow to the overflow canal. Initial studies indicated that no detectable chlorine reached the surface water.
Follow-up samples will be obtained from the overflow canal and near the point where the overflow canal meet Swan Creek. A temporary deflector is being installed to route the water back into the tower instead of allowing it to flow to the ground. A permanent fix will be installed in April 2000 during the refueling outage.
The State MDEQ was contacted at 1532.
The NRC Resident Inspector was informed.
Power Reactor
Event Number: 36801
Facility: FARLEY
Region: 2 State: AL
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: MURPHY
HQ OPS Officer: CHAUNCEY GOULD
Region: 2 State: AL
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: MURPHY
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 03/15/2000
Notification Time: 22:38 [ET]
Event Date: 03/15/2000
Event Time: 21:15 [CST]
Last Update Date: 03/15/2000
Notification Time: 22:38 [ET]
Event Date: 03/15/2000
Event Time: 21:15 [CST]
Last Update Date: 03/15/2000
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):
AL BELISLE (R2)
AL BELISLE (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
PLANT HAD ESF ACTUATION DUE TO A HIGH RADIATION ALARM
While performing fuel sipping in the unit 1 spent fuel pool, rad monitors R25A and R25B upscaled with R25B going into high alarm. The alarm activated both trains of the penetration room filtration system and secured the spent fuel pool ventilation system. The alarm was valid due to a leaking fuel assembly that was discovered during the fuel sipping activity. There was no indication of any radiation release, fuel sipping operations were suspended and evacuation of the spent fuel pool was initiated. They have not yet secured all of the actuations.
The NRC Resident Inspector will be notified.
While performing fuel sipping in the unit 1 spent fuel pool, rad monitors R25A and R25B upscaled with R25B going into high alarm. The alarm activated both trains of the penetration room filtration system and secured the spent fuel pool ventilation system. The alarm was valid due to a leaking fuel assembly that was discovered during the fuel sipping activity. There was no indication of any radiation release, fuel sipping operations were suspended and evacuation of the spent fuel pool was initiated. They have not yet secured all of the actuations.
The NRC Resident Inspector will be notified.
Power Reactor
Event Number: 36797
Facility: FERMI
Region: 3 State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: GILES
HQ OPS Officer: CHAUNCEY GOULD
Region: 3 State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: GILES
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 03/15/2000
Notification Time: 14:15 [ET]
Event Date: 03/15/2000
Event Time: 10:36 [EST]
Last Update Date: 03/15/2000
Notification Time: 14:15 [ET]
Event Date: 03/15/2000
Event Time: 10:36 [EST]
Last Update Date: 03/15/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(ii) - ESF ACTUATION 50.72(b)(2)(iii)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(2)(ii) - ESF ACTUATION 50.72(b)(2)(iii)(D) - ACCIDENT MITIGATION
Person (Organization):
RONALD GARDNER (R3)
RONALD GARDNER (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 97 | Power Operation | 97 | Power Operation |
THE PLANT ENTERED A 72 HOUR LCO ACTION STATEMENT DUE TO AN INOPERABLE HIGH PRESSURE COOLANT INJECTION SYSTEM.
On 3/15/2000 at 1036 hours, the High Pressure Coolant Injection System (HPCI) Reactor Vessel Water Level 8 turbine trip was inadvertently received while performing surveillance 44.030.254, ECCS - Reactor Vessel Water Level (Levels 1, 2, and 8) Division 2 Channel D Functional Test. The ability for HPCI to add water to the reactor vessel at Level 2 may have been inhibited with the Level 8 HPCI turbine trip initiated. This may have made the HPCI system inoperable. The cause of the problem is currently under investigation.
The Level 8 HPCI turbine trip was reset at 1112 hours. Technical Specifications 3.5.1.E, emergency core cooling systems, and 3.3.5.1.C, emergency core cooling system instrumentation, were entered.
The plant has 72 hours to return HPCI to operable condition or be in hot shutdown within the following 12 hrs.
This report is being made in accordance with 10 CFR 50.72 (b)(2)( iii)( D), any event or condition that alone could have prevented the fulfillment of the safety function of structures or systems necessary to mitigate the consequences of an accident.
The NRC Resident Inspector will be informed.
On 3/15/2000 at 1036 hours, the High Pressure Coolant Injection System (HPCI) Reactor Vessel Water Level 8 turbine trip was inadvertently received while performing surveillance 44.030.254, ECCS - Reactor Vessel Water Level (Levels 1, 2, and 8) Division 2 Channel D Functional Test. The ability for HPCI to add water to the reactor vessel at Level 2 may have been inhibited with the Level 8 HPCI turbine trip initiated. This may have made the HPCI system inoperable. The cause of the problem is currently under investigation.
The Level 8 HPCI turbine trip was reset at 1112 hours. Technical Specifications 3.5.1.E, emergency core cooling systems, and 3.3.5.1.C, emergency core cooling system instrumentation, were entered.
The plant has 72 hours to return HPCI to operable condition or be in hot shutdown within the following 12 hrs.
This report is being made in accordance with 10 CFR 50.72 (b)(2)( iii)( D), any event or condition that alone could have prevented the fulfillment of the safety function of structures or systems necessary to mitigate the consequences of an accident.
The NRC Resident Inspector will be informed.