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Event Notification Report for June 6, 2001

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           06/05/2001 - 06/06/2001

                              ** EVENT NUMBERS **

37997  38052  38053  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
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|Power Reactor                                    |Event Number:   37997       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NORTH ANNA               REGION:  2  |NOTIFICATION DATE: 05/16/2001|
|    UNIT:  [1] [2] []                STATE:  VA |NOTIFICATION TIME: 18:26[EDT]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        05/16/2001|
+------------------------------------------------+EVENT TIME:        11:11[EDT]|
| NRC NOTIFIED BY:  BRAD BROWN                   |LAST UPDATE DATE:  06/05/2001|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |CHARLES R. OGLE      R2      |
|10 CFR SECTION:                                 |                             |
|AIND 50.72(b)(3)(v)(D)   ACCIDENT MITIGATION    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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  |
|                                                   |                          |
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                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DISCOVERY THAT THE CONTROL ROOM HABITABILITY SYSTEM MAY NOT MEET DESIGN      |
| REQUIREMENTS UNDER CERTAIN CONDITIONS                                        |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "The control room habitability system may not meet design requirements under |
| certain conditions.  Specifically, any design accident where the control     |
| room bottled air pressurization system actuates and the exhaust fan of the   |
| cable vault and tunnel area trips with the supply fan to the cable vault and |
| tunnel continuing to run, the minimum delta pressure between these areas may |
| not be maintained."                                                          |
|                                                                              |
| "The control room bottled air systems of both Unit 1 and 2 have been         |
| declared inoperable, and a 7-day [technical specification action statement   |
| has] been entered."                                                          |
|                                                                              |
| The licensee plans to notify the NRC resident inspector.                     |
|                                                                              |
| * * * RETRACTED AT 1141 EDT ON 6/6/01 BY JAMES CROSSMAN TO FANGIE JONES * *  |
| *                                                                            |
|                                                                              |
| After subsequent engineering evaluation, the licensee has determined that    |
| this event was not reportable and is retracting the event notification.  The |
| evaluation concluded that the effect of a failure of a non-safety related    |
| component on the control room envelope and bottle air system is not required |
| during a design basis accident.  Therefore, the proposed (not actual)        |
| failure assumptions are not considered reasonable and there is no need to    |
| report this condition.                                                       |
|                                                                              |
| The licensee notified the NRC Resident Inspector.  The R2DO (Ken Barr) was   |
| notified.                                                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38052       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: KEWAUNEE                 REGION:  3  |NOTIFICATION DATE: 06/05/2001|
|    UNIT:  [1] [] []                 STATE:  WI |NOTIFICATION TIME: 04:59[EDT]|
|   RXTYPE: [1] W-2-LP                           |EVENT DATE:        06/05/2001|
+------------------------------------------------+EVENT TIME:        00:00[CDT]|
| NRC NOTIFIED BY:  BRADLY McMAHON               |LAST UPDATE DATE:  06/05/2001|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |BRENT CLAYTON        R3      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       97       Power Operation  |97       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LOSS OF PROCESS COMPUTER WITH LINK TO SAFETY PARAMETERS DISPLAY SYSTEM       |
|                                                                              |
| The plant process computer system failed.  This system provides a link to    |
| the Safety Parameter Display System (SPDS).  Immediate actions were taken to |
| restore the computer and SPDS to no avail.  The plant computer group         |
| representative has been called in to address the computer problem.  Work     |
| continues to try and restore the computer to operation.  Also, the           |
| availability of the Emergency Response Data System (ERDS) availability is    |
| questionable.                                                                |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38053       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAINT LUCIE              REGION:  2  |NOTIFICATION DATE: 06/05/2001|
|    UNIT:  [1] [] []                 STATE:  FL |NOTIFICATION TIME: 13:24[EDT]|
|   RXTYPE: [1] CE,[2] CE                        |EVENT DATE:        06/05/2001|
+------------------------------------------------+EVENT TIME:        10:48[EDT]|
| NRC NOTIFIED BY:  C. MARPLE                    |LAST UPDATE DATE:  06/05/2001|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |BRIAN BONSER         R2      |
|10 CFR SECTION:                                 |                             |
|AESF 50.72(b)(3)(iv)(A)  VALID SPECIF SYS ACTUAT|                             |
|ARPS 50.72(b)(2)(iv)(B)  RPS ACTUATION - CRITICA|                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| UNEXPECTED TRIP OF THE "1A2" REACTOR COOLANT PUMP CAUSED A TURBINE           |
| TRIP/REACTOR TRIP.                                                           |
|                                                                              |
| On 06/05/01 at 1048ET St. Lucie Unit 1 experienced an unexpected trip of the |
| "1A2" Reactor Coolant Pump.  This was immediately followed by an automatic   |
| reactor trip from the Reactor Protection System on reactor coolant low flow  |
| and subsequent turbine trip.  All rods fully inserted into the core.         |
| Approximately one minute later the "1B" Main Feedwater pump tripped and then |
| the Auxiliary Feedwater System actuated, "B" Electric Driven Auxiliary       |
| Feedwater Pump and the Turbine Driven Auxiliary Feedwater Pump, to the "1B"  |
| Steam Generator.  The Reactor Coolant System is stable in Mode 3, Hot        |
| Standby, with the secondary steaming via the steam bypass control system and |
| feedwater from the "1A"  Main Feedwater Pump.  The causes of the Reactor     |
| Coolant Pump trip and the Main Feedwater pump trip are currently under       |
| investigation.  All Emergency Core Cooling Systems and the Emergency Diesel  |
| Generators are fully operable if needed.                                     |
|                                                                              |
| Steam generator safety valves opened/closed. No leaking steam generator      |
| tubes.                                                                       |
|                                                                              |
| "1A" Component Cooling Water Heat Exchanger and the "1A" Reactor Vessel      |
| Level Monitoring System were inoperable during the reactor trip.             |
|                                                                              |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
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