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Event Notification Report for May 10, 2001

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           05/09/2001 - 05/10/2001

                              ** EVENT NUMBERS **

37976  37977  37978  37979  

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|Power Reactor                                    |Event Number:   37976       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: TURKEY POINT             REGION:  2  |NOTIFICATION DATE: 05/09/2001|
|    UNIT:  [3] [4] []                STATE:  FL |NOTIFICATION TIME: 14:45[EDT]|
|   RXTYPE: [3] W-3-LP,[4] W-3-LP                |EVENT DATE:        05/09/2001|
+------------------------------------------------+EVENT TIME:        14:07[EDT]|
| NRC NOTIFIED BY:  CRAIG MOWREY                 |LAST UPDATE DATE:  05/09/2001|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CHARLES R. OGLE      R2      |
|10 CFR SECTION:                                 |                             |
|DDDD 73.71               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3     N          Y       100      Power Operation  |100      Power Operation  |
|4     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNESCORTED ACCESS GRANTED INAPPROPRIATELY.  IMMEDIATE COMPENSATORY ACTIONS   |
| TAKEN UPON DISCOVERY.                                                        |
|                                                                              |
| THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37977       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOPER                   REGION:  4  |NOTIFICATION DATE: 05/09/2001|
|    UNIT:  [1] [] []                 STATE:  NE |NOTIFICATION TIME: 16:23[EDT]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        05/09/2001|
+------------------------------------------------+EVENT TIME:        14:20[CDT]|
| NRC NOTIFIED BY:  DAVE VANDERKAMP              |LAST UPDATE DATE:  05/09/2001|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JEFF SHACKELFORD     R4      |
|10 CFR SECTION:                                 |                             |
|*UNA 50.72(b)(3)(ii)(B)  UNANALYZED CONDITION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| FIRE PROTECTION REQUIREMENTS NOT MET                                         |
|                                                                              |
| It has been discovered that all necessary compensatory actions for           |
| inoperable fire barriers are not included in the stations operating          |
| procedures for conditions when the swing 125 VDC and 250 VDC battery         |
| chargers are in service supplying the 'B' DC Electrical subsystem.  The      |
| required degree of separation per 10CFR50 Appendix R does not exist between  |
| divisions when either swing charger is connected to the 'B'  DC Electrical   |
| subsystem. Use of the swing chargers is not a normal lineup but has occurred |
| during the past three years. The uncompensated lack of an adequate fire      |
| barrier between divisions of safe shutdown equipment is considered an        |
| unanalyzed condition that significantly degrades plant safety.               |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37978       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PRAIRIE ISLAND           REGION:  3  |NOTIFICATION DATE: 05/09/2001|
|    UNIT:  [] [2] []                 STATE:  MN |NOTIFICATION TIME: 20:37[EDT]|
|   RXTYPE: [1] W-2-LP,[2] W-2-LP                |EVENT DATE:        05/09/2001|
+------------------------------------------------+EVENT TIME:        15:06[CDT]|
| NRC NOTIFIED BY:  ED HEINEMAN                  |LAST UPDATE DATE:  05/09/2001|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |BRUCE JORGENSEN      R3      |
|10 CFR SECTION:                                 |                             |
|*SHU 50.72(b)(2)(i)      PLANT S/D REQD BY TS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |18       Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| TECH SPEC REQUIRED SHUTDOWN                                                  |
|                                                                              |
| Initiation of a unit shutdown began at 1700 May 9, 2001, as required by T.S. |
| 3.7.B because Unit 2 Diesel Generators D5 and D6 were declared inoperable at |
| 1506.  They were declared inoperable because it was determined that they may |
| not be capable of long-term operation as assumed in the plant accident       |
| analyses.  This determination is based on the discovery that the diesel fuel |
| and lubricating fluids in the engines may be incompatible and may damage the |
| engines based on a re-review of industry operating experience.               |
|                                                                              |
| The plant will go to Mode 5 and remain their until corrective actions are    |
| complete.                                                                    |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37979       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PRAIRIE ISLAND           REGION:  3  |NOTIFICATION DATE: 05/09/2001|
|    UNIT:  [] [2] []                 STATE:  MN |NOTIFICATION TIME: 21:53[EDT]|
|   RXTYPE: [1] W-2-LP,[2] W-2-LP                |EVENT DATE:        05/09/2001|
+------------------------------------------------+EVENT TIME:        20:05[CDT]|
| NRC NOTIFIED BY:  ED HEINEMAN                  |LAST UPDATE DATE:  05/09/2001|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |BRUCE JORGENSEN      R3      |
|10 CFR SECTION:                                 |                             |
|*RPS 50.72(b)(2)(iv)(B)  RPS ACTUATION - CRITICA|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     A/R        Y       12       Power Operation  |0        Hot Standby      |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MANUAL TURBINE TRIP - AUTOMATIC REACTOR TRIP                                 |
|                                                                              |
| Initiated manual turbine trip due to condenser vacuum differential pressure  |
| which resulted in an automatic reactor trip.  Reactor power prior to the     |
| trip was 12.5%.  The cause of the high condenser vacuum differential         |
| pressure is undetermined at this time.                                       |
|                                                                              |
| All control rods fully inserted, reactor coolant pumps are running.  The     |
| steam generators are being fed with auxiliary feed.  Decay heat is being     |
| removed by dumping steam with the turbine bypass atmospheric dumps.  There   |
| are no known S/G tube leaks.                                                 |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
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