Event Notification Report for April 16, 2003
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
04/15/2003 - 04/16/2003
** EVENT NUMBERS **
39647 39758 39759 39760
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 39647 |
+------------------------------------------------------------------------------+
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| FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 03/08/2003|
| UNIT: [] [2] [] STATE: NC |NOTIFICATION TIME: 01:58[EST]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 03/07/2003|
+------------------------------------------------+EVENT TIME: 23:55[EST]|
| NRC NOTIFIED BY: DAVE JESTER |LAST UPDATE DATE: 04/15/2003|
| HQ OPS OFFICER: ARLON COSTA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |CAROLYN EVANS R2 |
|10 CFR SECTION: | |
|AESF 50.72(b)(3)(iv)(A) VALID SPECIF SYS ACTUAT| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 22 Power Operation |0 Hot Shutdown |
| | |
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EVENT TEXT
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| AUTOMATIC DIESEL ACTUATION CAUSED BY LOSS OF GENERATION EXCITATION TRIP |
| |
| "During planned Unit Two manual scram in preparation for refueling outage, |
| all four Emergency Diesel Generators received an auto start signal. Auto |
| start signal was generated from a Primary Generator Lockout caused by a Loss |
| of Generator ExcitatIon Trip. A 1/2 Group 1 signal was also received during |
| the shutdown due to a steam flow trip unit failure, which has been repaired. |
| All other systems operated as designed, scram actions completed, plant |
| stable. The Loss of Excitation Trip should have been blocked by main |
| generator PCB openings. Investigation currently underway to determine cause |
| of Loss of Excitation Trip malfunction." |
| |
| There was no loss of power. The busses were not loaded after all four |
| diesels started. The diesels operated normally and have been returned to a |
| standby lineup. All other systems operated as required. |
| |
| The Licensee notified the NRC Resident Inspector. |
| |
| ****RETRACTION on 04/15/03 at 1320 EDT by Charles Elberfeld taken by |
| MacKinnon**** |
| |
| Upon further evaluation, it has been determined that the signal that started |
| the EDGs did not meet the definition of a valid signal and so the reporting |
| criterion contained in 10 CFR 50.72 (b)(3)(iv)(A) is not applicable to the |
| condition reported on March 8, 2003 (Event Number 39647). Valid actuations |
| of the EDGs are the result of loss of coolant accident signals (from either |
| Unit 1 or 2) or as the result of emergency bus degraded voltage or |
| undervoltage signals. Therefore, the actuation of the EDGs reported as a |
| valid actuation in accordance with 10 CFR 50.72 (b)(3)(iv)(A) is retracted |
| and is being reported, as allowed by 10 CFR 50.73 (a), in this telephone |
| notification in accordance with 10 CFR 50.73 (a)(2)(iv)(A) as an invalid |
| actuation. |
| |
| EDGs 1, 2, 3, and 4 automatically started and functioned successfully. |
| Because electrical power was never lost to the emergency busses and none of |
| the EDGs loaded to their respective emergency busses, the actuations were |
| considered to be partial. |
| |
| Safety significance is considered to be minimal. Emergency Diesel |
| Generators started and operated normally. Electrical power was never lost |
| to the emergency busses. |
| |
| Power Circuit Breaker trip operating mechanism assembly was replaced. |
| NRC R2DO (Tom Decker) notified. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
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|Power Reactor |Event Number: 39758 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 04/15/2003|
| UNIT: [] [2] [] STATE: PA |NOTIFICATION TIME: 09:18[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 04/15/2003|
+------------------------------------------------+EVENT TIME: 02:30[EDT]|
| NRC NOTIFIED BY: GRANT FERNSIER |LAST UPDATE DATE: 04/15/2003|
| HQ OPS OFFICER: RICH LAURA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |DAVID SILK R1 |
|10 CFR SECTION: | |
|ACOM 50.72(b)(3)(xiii) LOSS COMM/ASMT/RESPONSE| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
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| UNPLANNED LOSS OF SPDS/ERDS FOR GREATER THAN 8 HOURS AT SUSQUEHANNA |
| |
| "On 4/15/03 the Main Control Room received alarms indicating failure of the |
| power supplies to the Safety Parameter Display System (SPDS). At the time |
| the 2 uninterruptible power supplies were crosstied due to maintenance. |
| Investigation into the cause of the failure is ongoing with repairs expected |
| to take longer than 8 hours. |
| |
| "Currently, Unit 2 is in a refueling outage in Cold Shutdown. Control room |
| indication and the plant computer system is still available with the |
| exception of those points supplied by the SPDS power supply. |
| |
| "Due to the failure of the SPDS UPS, 12 of approximately 300 inputs to the |
| ERDS system will be displayed as invalid data until the SPDS power is |
| restored. |
| |
| "Since the Unit 2 SPDS computer system will be unavailable for greater than |
| 8 hours, this is considered a Loss of Emergency Assessment Capability and |
| therefore reportable under 10CFR50.72(b)(3)(xiii)." |
| |
| The NRC Resident Inspector has been notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39759 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 04/15/2003|
| UNIT: [1] [2] [] STATE: NC |NOTIFICATION TIME: 13:03[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 02/25/2003|
+------------------------------------------------+EVENT TIME: 21:39[EST]|
| NRC NOTIFIED BY: STEVE TABOR |LAST UPDATE DATE: 04/15/2003|
| HQ OPS OFFICER: ERIC THOMAS +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |THOMAS DECKER R2 |
|10 CFR SECTION: | |
|AINV 50.73(a)(1) INVALID SPECIF SYSTEM A| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 94 Power Operation |94 Power Operation |
|2 N Y 98 Power Operation |98 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| INVALID SPECIFIED SYSTEM ACTUATION |
| |
| "60-Day Optional 10 CFR 50.73(a)(1) Report - Invalid Actuation of Primary |
| Containment Isolation System (PCIS) and Secondary Containment Isolation |
| Dampers (SCIDs). |
| |
| "In accordance with 10 CFR 50.73(a)(2)(iv)(A), the following is a report of |
| an invalid actuation of the PCIS and |
| SCIDs for Units 1 and 2. This notification is provided in lieu of submitting |
| a written LER. |
| |
| "On February 25, 2003, at approximately 2139 hours, failure of the main |
| stack radiation monitor resulted in a PCIS Group 6 isolation and SCIDs. PCIS |
| Group 6 valves include isolation valves from the Containment Atmosphere |
| Control, Containment Atmosphere Dilution, Containment Atmosphere Monitoring, |
| and Post Accident Sampling Systems. Due to the shared configuration of the |
| main stack radiation monitoring system, these isolations occurred on both |
| Unit 1 and Unit 2. In addition the Standby Gas Treatment system initiated on |
| both Units, as expected for the given plant conditions. The actuations of |
| PCIS Group 6 valves and SCIDs were complete and the affected equipment |
| responded as designed to the invalid signal (i.e., the valves and dampers |
| that were open at the time of the event closed). The main stack radiation |
| monitor was subsequently returned to service and the other affected systems |
| returned to their normal operating lineup. No deficiencies or abnormalities |
| were noted during this event. The NRC Resident Inspector was notified of |
| this 60-Day report. |
| Discussion of the cause and corrective actions associated with this event |
| are documented in the site corrective action program (i.e., AR 85815)." |
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|Power Reactor |Event Number: 39760 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LACROSSE REGION: 3 |NOTIFICATION DATE: 04/15/2003|
| UNIT: [1] [] [] STATE: WI |NOTIFICATION TIME: 13:30[EDT]|
| RXTYPE: [1] AC (ALLIS CHAMBERS) |EVENT DATE: 04/15/2003|
+------------------------------------------------+EVENT TIME: 11:58[CDT]|
| NRC NOTIFIED BY: DANIEL TESSAR |LAST UPDATE DATE: 04/15/2003|
| HQ OPS OFFICER: ERIC THOMAS +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: UNUSUAL EVENT |THOMAS KOZAK R3 |
|10 CFR SECTION: |TOM ESSIG NMSS |
|AAEC 50.72(a) (1) (i) EMERGENCY DECLARED |RICHARD WESSMAN IRO |
| |TERRRY REIS NRR |
| |BRIAN MCDERMOTT EDO |
| |C. BAGWELL FEMA |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Decommissioned |0 Decommissioned |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNUSUAL EVENT |
| |
| At approximately 1158 CDT, the CO2 system discharged in the 1B Emergency |
| Diesel Generator (EDG) building. The licensee declared a UE at 1215 CDT |
| because they had to call an offsite fire department for assistance in |
| re-entering the building. The fire department arrived on site at 1233 CDT |
| and promptly entered the 1B EDG building. The cause of the CO2 discharge |
| was high temperature in the building (140 degrees F) caused by a |
| malfunctioning space heater. The licensee exited the UE at 1252 CDT. |
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Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021