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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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!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                                   

+------------------------------------------------------------------------------+

| 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.                                |

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+------------------------------------------------------------------------------+

|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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