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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(5F).               |
|                                                                              |
| 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 28F, with a maximum of 30.4F, and estimated that the maximum      |
| discharge temperature would have been ~ 63F.  For the period ~ 0800 - 1100  |
| hours, delta t was again above the 28F limit, attaining a maximum delta t   |
| of 62F, with an estimated discharge temperature of ~ 95F.  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.                                                                    |
+------------------------------------------------------------------------------+