Event Notification Report for February 23, 2001

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           02/22/2001 - 02/23/2001

                              ** EVENT NUMBERS **

37771  37772  

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|Power Reactor                                    |Event Number:   37771       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CALLAWAY                 REGION:  4  |NOTIFICATION DATE: 02/22/2001|
|    UNIT:  [1] [] []                 STATE:  MO |NOTIFICATION TIME: 16:28[EST]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        02/21/2001|
+------------------------------------------------+EVENT TIME:        18:45[CST]|
| NRC NOTIFIED BY:  HENSON                       |LAST UPDATE DATE:  02/22/2001|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |LINDA SMITH          R4      |
|10 CFR SECTION:                                 |                             |
|*PRE 50.72(b)(2)(xi)     OFFSITE NOTIFICATION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION MADE TO MISSOURI PUBLIC SERVICE COMMISSION              |
|                                                                              |
| An onsite apprentice welder injured his left hand.  Onsite Medical Emergency |
| Team evaluated the injury and had the individual transported offsite to the  |
| local hospital.  The Missouri Public Service Commission was notified of this |
| incident by the licensee.                                                    |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37772       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MONTICELLO               REGION:  3  |NOTIFICATION DATE: 02/22/2001|
|    UNIT:  [1] [] []                 STATE:  MN |NOTIFICATION TIME: 21:34[EST]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        02/22/2001|
+------------------------------------------------+EVENT TIME:        18:30[CST]|
| NRC NOTIFIED BY:  B. WELLER                    |LAST UPDATE DATE:  02/22/2001|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MARK RING            R3      |
|10 CFR SECTION:                                 |                             |
|*INB 50.72(b)(3)(v)(B)   POT RHR INOP           |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| "EVEN" TRAIN CORE SPRAY, RHR OR RHRSW PUMPS OPERATION FROM THE ALTERNATE     |
| SHUTDOWN SYSTEM COULD BE LOST DUE TO A POSTULATED HOT SHORT.                 |
|                                                                              |
| An Alternate Shutdown System design deficiency resulting in a vulnerability  |
| to a single hot short during a Control Room Cable Spreading Room fire has    |
| been identified.  The effect of the postulated hot short would be to actuate |
| the Bus 16 load shed logic  while the bus is powered from the emergency      |
| diesel generator.  This could result in the inability to operate the even    |
| train Core Spray, Residual Heat Removal (RHR)  or RHR Service Water  pumps.  |
| No means are in place to circumvent the postulated hot short.  A one hour    |
| fire watch patrol in the cable spreading room and control room has been      |
| established with Alternate Shutdown System inoperable.  All other Emergency  |
| Core Cooling Systems are fully operable.                                     |
|                                                                              |
| The NRC Resident Inspector will be notified of this event by the licensee.   |
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