Event Notification Report for February 10, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
02/09/2000 - 02/10/2000
** EVENT NUMBERS **
36671 36672 36673 36674 36675 36676 36677
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36671 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 02/09/2000|
| UNIT: [] [2] [] STATE: IL |NOTIFICATION TIME: 06:45[EST]|
| RXTYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 02/09/2000|
+------------------------------------------------+EVENT TIME: 04:21[CST]|
| NRC NOTIFIED BY: MACLENNAN |LAST UPDATE DATE: 02/09/2000|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MICHAEL PARKER R3 |
|10 CFR SECTION: | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| INVALID ESF ACTUATION CAUSED BY BACKFILLING OF REACTOR LEVEL |
| INSTRUMENTATION |
| |
| On 02/09/2000 @ 0421 hours, Unit Two received a full reactor SCRAM and a |
| full Group II and Group lll isolation, including a Shutdown Cooling |
| isolation. This event occurred as a result of scheduled backfilling of |
| reactor level instrumentation, and is being reported as an invalid ESF |
| actuation. |
| |
| At the time of the event, all control rods were fully inserted, so no rod |
| motion occurred. All systems responded as designed. Shutdown Cooling was |
| restored at 0432 hours with minimal temperature increase(5�F). |
| |
| The NRC Resident Inspector was notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36672 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: GINNA REGION: 1 |NOTIFICATION DATE: 02/09/2000|
| UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 11:16[EST]|
| RXTYPE: [1] W-2-LP |EVENT DATE: 02/09/2000|
+------------------------------------------------+EVENT TIME: 09:15[EST]|
| NRC NOTIFIED BY: GOMEZ |LAST UPDATE DATE: 02/09/2000|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |HAROLD GRAY R1 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| THE LICENSEE NOTIFIED THE NEW YORK DEPARTMENT OF ENVIRONMENTAL CONSERVATION |
| THEY EXCEEDED THEIR DELTA T DISCHARGE LIMIT. |
| |
| On 2/9/00 @ 0915, the following information was reported as a State |
| Pollutant Discharge Elimination System(SPDES) exception to the New York |
| State DEC per the 24 hour notification requirement. On 2/8/00 from ~0630 - |
| 0715 hours, the delta t for the main condenser at the site was above the |
| limit of 28�F, with a maximum of 30.4�F, and estimated that the maximum |
| discharge temperature would have been ~ 63�F. For the period ~ 0800 - 1100 |
| hours, delta t was again above the 28�F limit, attaining a maximum delta t |
| of 62�F, with an estimated discharge temperature of ~ 95�F. Observations |
| indicate that no significant fish kill occurred. |
| |
| |
| The NRC Resident Inspector was notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36673 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COMANCHE PEAK REGION: 4 |NOTIFICATION DATE: 02/09/2000|
| UNIT: [1] [2] [] STATE: TX |NOTIFICATION TIME: 12:35[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 02/09/2000|
+------------------------------------------------+EVENT TIME: 11:33[CST]|
| NRC NOTIFIED BY: TOM BEAUDIN |LAST UPDATE DATE: 02/09/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |LINDA HOWELL R4 |
|10 CFR SECTION: | |
|AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| THE SERVER TO THE EMERGENCY OFFSITE FACILITY FAILED CAUSING THE SAFETY |
| PARAMETER DISPLAY SYSTEM (SPDS) AND EMERGENCY RESPONSE DATA SYSTEM (ERDS) |
| TO BECOME INOPERABLE |
| |
| At 1645 CT on February 8, 2000 the server which transfers Plant Computer |
| data to the two SDSs in the EOF and the ERDS modems failed. This caused the |
| Safety Parameter Display System (SPDS) and the Emergency Response Data |
| System (ERDS) to become unavailable in the EOF as specified in the FSAR |
| section III.A.1.2. The server was replaced by Telecommunications and SPDS |
| and ERDS restored to the EOF at 0834 CT on February 9, 2000. The total time |
| that SPDS and ERDS were unavailable to the EOF is 15 hours and 49 minutes. |
| The failure of the server occurred at the same time as a report of a fire at |
| the Nuclear Operations Support Facility (the EOF is located inside) |
| building. |
| |
| The server was replaced by Telecommunication. The SPDS and ERDS are |
| available at the EOF. |
| |
| The NRC Resident Inspector was notified of this event by the Licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36674 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 02/09/2000|
| UNIT: [1] [2] [] STATE: FL |NOTIFICATION TIME: 13:49[EST]|
| RXTYPE: [1] CE,[2] CE |EVENT DATE: 02/09/2000|
+------------------------------------------------+EVENT TIME: 12:45[EST]|
| NRC NOTIFIED BY: DAVE WILLIAMS |LAST UPDATE DATE: 02/09/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MARK LESSER R2 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION TO THE FLORIDA DEP INVOLVING THE REMOVAL OF A |
| LOGGERHEAD SEA TURTLE IN THE PLANT INTAKE CANAL BARRIER NET. |
| |
| NOTIFICATION MADE TO FLORIDA DEPARTMENT OF ENVIRONMENTAL PROTECTION (DEP) |
| REGARDING REMOVAL OF LOGGERHEAD TURTLE FROM PLANT INTAKE CANAL BARRIER NET. |
| THE TURTLE WILL BE SENT OFFSITE FOR REHABILITATION. THERE WERE NO INJURIES |
| TO THE TURTLE. |
| |
| THE LICENSEE INFORMED THE FLORIDA DEP AND THE NRC RESIDENT INSPECTOR. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36675 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 02/09/2000|
| UNIT: [] [2] [] STATE: IL |NOTIFICATION TIME: 16:36[EST]|
| RXTYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 02/09/2000|
+------------------------------------------------+EVENT TIME: 12:12[CST]|
| NRC NOTIFIED BY: D. COVEYOU |LAST UPDATE DATE: 02/09/2000|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MICHAEL PARKER R3 |
|10 CFR SECTION: | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| EMERGENCY DIESEL GENERATOR TRIPPED FOLLOWING TESTING |
| |
| "While performing LOS-DG-M3, Monthly Operability Run of 2B Diesel Generator, |
| Division three, the Diesel Generator tripped on reverse power before the |
| output breaker was opened while preparing to take the Diesel Generator off |
| line following this surveillance. Concurrently, a local alarm was received |
| indicating a DC power failure, The reverse power trip is a function that is |
| bypassed under accident conditions. Upon investigation, two fuses supplying |
| engine control power were discovered blown. It is not known whether the |
| fuses would have blown with the reverse power bypassed. The fuses which were |
| installed were verified to be the correct type. The fuses were replaced with |
| like for like and the power failure alarm cleared and the installed fuses |
| did not blow. A plan is being developed to investigate the cause of the |
| fuses blowing. The Diesel Generator is not available and is inoperable per |
| LaSalle Technical Specifications, pending troubleshooting and potential |
| corrective actions. The cause of the blown fuses is unknown at this time." |
| |
| The NRC resident inspector has been informed of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36676 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 02/09/2000|
| UNIT: [1] [] [] STATE: PA |NOTIFICATION TIME: 16:50[EST]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 02/08/2000|
+------------------------------------------------+EVENT TIME: 12:09[EST]|
| NRC NOTIFIED BY: CHRISTOPHER HYNES |LAST UPDATE DATE: 02/09/2000|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |HAROLD GRAY R1 |
|10 CFR SECTION: | |
|NINF INFORMATION ONLY | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 93 Power Operation |93 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| INFORMATION CALL REGARDING RIVER WATER PUMP PROBLEMS |
| |
| "This report is being made to provide preliminary notification of an event |
| that is currently under investigation at Beaver Valley Power Station Unit |
| No. 1 (BVPS-1). |
| |
| "River Water Pump WR-P-1B at Beaver Valley Power Station Unit 1 tripped on |
| overcurrent shortly after it was attempted to be started at 1209 on |
| 02/08/2000. The Action Statement for Technical Specification 3/4.7.4.1 was |
| entered for less than two River Water subsystems being operable. River Water |
| Pump WR-P-1C (swing pump) was then aligned to the 'B' train header and it |
| also tripped on overcurrent shortly after it was started at 1716 on |
| 02/08/2000. |
| |
| "Preliminary information identified that the 1B and 1C River Water Pumps |
| would not operate due to the loss of gap between the pumps rotating assembly |
| and the pump bowl. Investigation into the cause of the loss of the pumps' |
| gap is ongoing. |
| |
| "BVPS-1 River Water Pump 1A on the 'A' train continues to operate |
| satisfactorily and is operable. The 'A' train is being treated as protected |
| equipment (i.e., no elective work is being done on or near 'A' train |
| components). The BVPS-1 operating crews have reviewed the procedures |
| associated with operating the BVPS-1 Auxiliary River Water System in the |
| Alternate Intake Structure and the use of the cross tie connection with the |
| diesel driven fire pump." |
| |
| The licensee stated that the unit entered a 72 hour Technical Specification |
| Limiting Condition for Operation (LCO) at 1209 on 2/8/2000. The NRC resident |
| inspector has been informed of this notification by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36677 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 02/09/2000|
| UNIT: [] [2] [] STATE: TX |NOTIFICATION TIME: 18:38[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 02/09/2000|
+------------------------------------------------+EVENT TIME: 15:46[CST]|
| NRC NOTIFIED BY: TIM FRAWLEY |LAST UPDATE DATE: 02/09/2000|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |LINDA HOWELL R4 |
|10 CFR SECTION: | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 32 Power Operation |2 Startup |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AUXILIARY FEEDWATER SYSTEM ACTUATION DUE TO UNEXPECTED AMSAC ACTUATION |
| |
| A main turbine trip and auxiliary feedwater system actuation occurred due to |
| an unexpected ATWS mitigation system actuation circuitry (AMSAC) actuation. |
| Because the reactor was operating below 50% power, the turbine trip did not |
| cause an automatic reactor trip. The licensee is currently investigating the |
| cause of the AMSAC actuation. |
| |
| The NRC resident inspector has been informed of this notification by the |
| licensee. |
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Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021