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Event Notification Report for May 8, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           05/05/2000 - 05/08/2000

                              ** EVENT NUMBERS **

36976  36977  36978  36979  36980  36981  36982  36983  

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36976       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: QUAD CITIES              REGION:  3  |NOTIFICATION DATE: 05/05/2000|
|    UNIT:  [] [2] []                 STATE:  IL |NOTIFICATION TIME: 12:40[EDT]|
|   RXTYPE: [1] GE-3,[2] GE-3                    |EVENT DATE:        05/05/2000|
+------------------------------------------------+EVENT TIME:        09:40[CDT]|
| NRC NOTIFIED BY:  JOHN LECHMAIER               |LAST UPDATE DATE:  05/05/2000|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |BRUCE BURGESS        R3      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     A/R        Y       100      Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| REACTOR SCRAM DURING PLANNED INSTRUMENT MAINTENANCE                          |
|                                                                              |
| "At 0940 hours on 5-5-00, Unit 2 scrammed while performing a scheduled       |
| Instrument Maintenance surveillance that resulted in a Group 1 isolation.    |
| The Unit 2 Emergency Diesel Generator received a spurious Auto Start signal  |
| during the Auxiliary Power transfer. During the transient reactor water      |
| level reached +8 inches and all Group 2 actuations occurred as expected.     |
| Unit 2 is now in Mode 3 with reactor water level within its normal band."    |
|                                                                              |
| All rods fully inserted with the reactor scram and the plant is now stable   |
| in normal plant configuration for Mode 3.  Preliminary investigation         |
| determined that a technician valved out one instrument then tripped a        |
| different  instrument causing the reactor scram.  Investigation is still on  |
| going and startup will not proceed until complete.                           |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36977       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HOPE CREEK               REGION:  1  |NOTIFICATION DATE: 05/07/2000|
|    UNIT:  [1] [] []                 STATE:  NJ |NOTIFICATION TIME: 03:01[EDT]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        05/06/2000|
+------------------------------------------------+EVENT TIME:        23:24[EDT]|
| NRC NOTIFIED BY:  NICK CONICELLA               |LAST UPDATE DATE:  05/07/2000|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |NIEL DELLA GRECA     R1      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     A          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR SCRAM SIGNAL WITH ALL CONTROL RODS INSERTED AND UNIT       |
| DEFUELED                                                                     |
|                                                                              |
| "At the time of the event, the Hope Creek reactor was in a preplanned outage |
| with the core completely offloaded to the spent fuel pool, all control rods  |
| inserted, and the control rod drive hydraulic system isolated.               |
|                                                                              |
| "Outage work required isolating air to the scram discharge volume vent and   |
| drain valves which resulted in these valves being closed. Water inleakage    |
| was identified to the scram discharge volume. Since there was no drain path, |
| water level continued to rise in the discharge volume until the high scram   |
| discharge volume level scram signal was reached. No components repositioned  |
| as a result of the scram signal since they were already in their fail safe   |
| positions as a result of preplanned outage work.                             |
|                                                                              |
| "Based on the condition of the reactor, the control rod drive hydraulic      |
| system, and the reactor protection system at the time of the event, the      |
| validity of the ESF signal is being evaluated."                              |
|                                                                              |
| The licensee will inform the NRC resident inspector of this event.           |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36978       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NORTH ANNA               REGION:  2  |NOTIFICATION DATE: 05/07/2000|
|    UNIT:  [1] [] []                 STATE:  VA |NOTIFICATION TIME: 09:42[EDT]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        05/07/2000|
+------------------------------------------------+EVENT TIME:        07:57[EDT]|
| NRC NOTIFIED BY:  JIM BLANKENSHIP              |LAST UPDATE DATE:  05/07/2000|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |ROBERT HAAG          R2      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     A/R        Y       100      Power Operation  |0        Hot Standby      |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUTOMATIC TURBINE/REACTOR TRIP DUE TO FAULT OF GENERATOR OUTPUT BREAKER      |
|                                                                              |
| "Unit 1 generator output breaker malfunction (G12) causing Unit 1 Reactor    |
| Trip and AFW pump actuation."                                                |
|                                                                              |
| A generator lockout occurred after the generator output breaker (G12)        |
| faulted. The generator lockout caused an automatic turbine trip/reactor      |
| trip. All control rods inserted completely following the trip. The unit is   |
| currently stable in Hot Standby with steam generators being fed by the       |
| auxiliary feedwater system and decay heat being removed by the main          |
| condenser.                                                                   |
|                                                                              |
| The licensee reported that smoke and flames were observed in the area of the |
| G12 breaker. The site fire brigade responded, and the fire and smoke         |
| subsided within 10 minutes. The licensee plans to investigate the cause of   |
| the breaker fault and any necessary repairs. The NRC resident inspector will |
| be informed of this event by the licensee.                                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36979       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NINE MILE POINT          REGION:  1  |NOTIFICATION DATE: 05/07/2000|
|    UNIT:  [1] [] []                 STATE:  NY |NOTIFICATION TIME: 13:45[EDT]|
|   RXTYPE: [1] GE-2,[2] GE-5                    |EVENT DATE:        05/05/2000|
+------------------------------------------------+EVENT TIME:        11:25[EDT]|
| NRC NOTIFIED BY:  QUENTIN HICKS                |LAST UPDATE DATE:  05/07/2000|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |NIEL DELLA GRECA     R1      |
|10 CFR SECTION:                                 |                             |
|AINB 50.72(b)(2)(iii)(B) POT RHR INOP           |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| POTENTIAL FOR RESIDUAL HEAT REMOVAL SYSTEM NOT ABLE TO PERFORM SAFETY        |
| FUNCTION                                                                     |
|                                                                              |
| "During the performance of the cold shutdown surveillance N1-ST-V 14         |
| (SERVICE WATER CHECK VALVE AND EMERGENCY SERVICE WATER PUMP AND CHECK VALVE  |
| TEST) it was determined that ESW (EMERGENCY SERVICE WATER) check valves      |
| 72-21 and 72-22 failed to isolate. The failure of these valves to close may  |
| have resulted in ESW not being able to perform its safety function to        |
| support residual heat removal (RHR)."                                        |
|                                                                              |
| The two check valves serve to isolate the non-safety loads of ESW.  The      |
| valves were serviced and the test was performed again successfully.  It was  |
| on 5/7/00 about 1230 CDT that the licensee recognized that a four hour       |
| notification should have been made on 5/5/00.                                |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36980       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: KEWAUNEE                 REGION:  3  |NOTIFICATION DATE: 05/07/2000|
|    UNIT:  [1] [] []                 STATE:  WI |NOTIFICATION TIME: 13:53[EDT]|
|   RXTYPE: [1] W-2-LP                           |EVENT DATE:        05/07/2000|
+------------------------------------------------+EVENT TIME:        11:25[CDT]|
| NRC NOTIFIED BY:  TERRY GENCIUS                |LAST UPDATE DATE:  05/07/2000|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |BRUCE BURGESS        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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNEXPECTED LOAD SHED OCCURRED DURING ELECTRICAL MAINTENANCE TESTING          |
|                                                                              |
| "On May 7, 2000 at 0933, electrical testing was being performed on the       |
| emergency diesel generator A load sequencer.  The diesel generator was       |
| out-of-service at the time [for annual maintenance].  An unexpected load     |
| shed signal was developed, which removed charging pump C, service water pump |
| A2, containment fan coil A, and residual heat removal (RHR) pump A from the  |
| train A emergency safeguards bus (Bus 5).  In response to the load shed,     |
| equipment was manually restarted from the control room.  RHR pump A was      |
| restarted in 90 seconds, restoring shutdown cooling.  The cause of the load  |
| shed was the post modification testing of the load sequencer, and is         |
| continuing to be investigated."                                              |
|                                                                              |
| There was no increase in reactor coolant temperature during the 90 seconds   |
| without RHR flow.  Also, the RHR B pump was available if it had been         |
| needed.                                                                      |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36981       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MILLSTONE                REGION:  1  |NOTIFICATION DATE: 05/08/2000|
|    UNIT:  [] [2] []                 STATE:  CT |NOTIFICATION TIME: 00:44[EDT]|
|   RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP           |EVENT DATE:        05/08/2000|
+------------------------------------------------+EVENT TIME:        00:15[EDT]|
| NRC NOTIFIED BY:  STEVE MYERS                  |LAST UPDATE DATE:  05/08/2000|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |NIEL DELLA GRECA     R1      |
|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        Refueling        |0        Refueling        |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DIESEL GENERATOR STARTED DURING TESTING                                      |
|                                                                              |
| The 'A' emergency diesel generator (EDG ) automatically started due to a bus |
| undervoltage signal that was inadvertently caused when a procedural step was |
| misinterpreted. The EDG was secured. The licensee has informed the NRC       |
| resident inspector of this event.                                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36982       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HOPE CREEK               REGION:  1  |NOTIFICATION DATE: 05/08/2000|
|    UNIT:  [1] [] []                 STATE:  NJ |NOTIFICATION TIME: 01:37[EDT]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        05/07/2000|
+------------------------------------------------+EVENT TIME:        22:43[EDT]|
| NRC NOTIFIED BY:  NICK CONICELLA               |LAST UPDATE DATE:  05/08/2000|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |NIEL DELLA GRECA     R1      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| REACTOR WATER CLEANUP ISOLATION DUE TO INADVERTENT STANDBY LIQUID CONTROL    |
| SIGNAL                                                                       |
|                                                                              |
| "On 5/7/00 at 2243 hours, a Reactor Water Cleanup System (RWCU) isolation    |
| occurred due to an inadvertent Standby Liquid Control System (SLC)           |
| initiation. At the time of the event, Hope Creek was in Operational          |
| Condition 5, Refueling, with core reload activities recently initiated and   |
| with all control rods fully inserted. SLC was not required to be operable    |
| and was removed from service (injection line check valves were closed) when  |
| the SLC initiation signal occurred. No sodium pentaborate was injected into  |
| the Reactor Coolant System. Preliminary investigation into the event         |
| determined that the SLC initiation signal resulted from activities           |
| supporting required surveillance testing of SLC along with surveillances of  |
| the Redundant Reactivity Control System (RRCS). The RRCS provides automatic  |
| SLC initiation. Although the RWCU isolation instrumentation was also not     |
| required to be operable at the time of the event, it was not removed from    |
| service. The RWCU isolation due to a SLC initiation signal is an ESF         |
| actuation. Both SLC pumps actuated as designed in response to the initiation |
| signal, however, a crack was observed in a weld in the 'A' SLC injection     |
| line when the SLC pump was removed from service. Event investigation is      |
| continuing and repairs to SLC are being initiated. The RWCU isolation signal |
| was reset and the RWCU was placed back in service. Core reload activities    |
| are continuing."                                                             |
|                                                                              |
| The NRC resident inspector has been informed of this event by the licensee.  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36983       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PILGRIM                  REGION:  1  |NOTIFICATION DATE: 05/08/2000|
|    UNIT:  [1] [] []                 STATE:  MA |NOTIFICATION TIME: 05:25[EDT]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        05/08/2000|
+------------------------------------------------+EVENT TIME:        03:56[EDT]|
| NRC NOTIFIED BY:  RANDY HAISLET                |LAST UPDATE DATE:  05/08/2000|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |NIEL DELLA GRECA     R1      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| POST-ACCIDENT SAMPLING SYSTEM ISOLATION DURING TAGOUT                        |
|                                                                              |
| While performing a tagout on the 'A' train of the post-accident sampling     |
| system (PASS) H2/O2 sampling system, solenoid isolation valve SV-5065-20B,   |
| which is a 'B' train valve, closed unexpectedly. The licensee restored the   |
| 'A' train of PASS H2/O2 monitoring to service and closed the redundant       |
| solenoid isolation valve in the 'B' train. The licensee declared valve       |
| SV-5065-20B inoperable.                                                      |
|                                                                              |
| After review of system electrical diagrams, the licensee determined that the |
| closure of valve SV-5065-20B was appropriate, although its closure was not   |
| anticipated in the tagout procedure. The NRC resident inspector has been     |
| informed of this event by the licensee.                                      |
+------------------------------------------------------------------------------+