Event Notification Report for June 20, 2001

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           06/19/2001 - 06/20/2001

                              ** EVENT NUMBERS **

38079  38080  

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|Power Reactor                                    |Event Number:   38079       |
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| FACILITY: MONTICELLO               REGION:  3  |NOTIFICATION DATE: 06/19/2001|
|    UNIT:  [1] [] []                 STATE:  MN |NOTIFICATION TIME: 12:13[EDT]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        06/19/2001|
+------------------------------------------------+EVENT TIME:        09:15[CDT]|
| NRC NOTIFIED BY:  PEDERSON                     |LAST UPDATE DATE:  06/19/2001|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |MONTE PHILLIPS       R3      |
|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  |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM DECLARED INOPERABLE            |
|                                                                              |
| HPCI system was declared inoperable due to all alarm functions not           |
| operating.  The local undervoltage alarms did not annunciate in the control  |
| room.  This condition was discovered during a normal routine test.  They     |
| were attempting to send a signal from the local HPCI panel in the plant to   |
| the control room, but the control room did not receive it.  They verified    |
| that the local panel is operable.  An operator was locally stationed at the  |
| subject panel to verify current alarm status and call the control room.      |
| Therefore, in this mode of operation, the HPCI system has been declared      |
| operable.  They are still investigating the problem with signal              |
| transmission.                                                                |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
|                                                                              |
| The State and local agencies will be informed.                               |
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+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38080       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: KEWAUNEE                 REGION:  3  |NOTIFICATION DATE: 06/20/2001|
|    UNIT:  [1] [] []                 STATE:  WI |NOTIFICATION TIME: 04:07[EDT]|
|   RXTYPE: [1] W-2-LP                           |EVENT DATE:        06/20/2001|
+------------------------------------------------+EVENT TIME:        00:11[CDT]|
| NRC NOTIFIED BY:  GEORGE RUITER                |LAST UPDATE DATE:  06/20/2001|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |MONTE PHILLIPS       R3      |
|10 CFR SECTION:                                 |                             |
|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       96       Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR TRIP DUE TO FEEDWATER REGULATING VALVE FAILING SHUT.       |
|                                                                              |
| At 0011 CDT feedwater regulating valve to steam generator "B" failed to the  |
| closed position and manual control was not effective.  The reactor/turbine   |
| tripped on steam flow greater than feed flow coincident with low steam       |
| generator water level.  Following the trip, the rod bottom light for rod D4  |
| (interior rod) was off and valve LD-2 indicated mid-position (letdown        |
| isolated on low pressurizer water level).  Individual Rod Position           |
| Indication for rod D4 indicates zero, however, emergency boration was used   |
| to inject the required amount of boric acid for one stuck rod.  Excess       |
| letdown was established at 0028 CDT hours, since normal letdown was not      |
| available due to the failure of valve LD-2.   All emergency core cooling     |
| systems, emergency diesel generators are fully operable if needed and the    |
| electrical grid is stable.                                                   |
|                                                                              |
| Both Motor Driven and the Turbine Driven Auxiliary Feedwater Pumps           |
| automatically started.  The Turbine Driven Auxiliary Feedwater pump was      |
| secured per procedure and steam generator water is being maintained by the   |
| Motor Driven Auxiliary Feedwater Pumps.                                      |
|                                                                              |
| At this time the licensee thinks that rod bottom light for rod D4 is burned  |
| out.  The licensee is also investigating why letdown isolation valve, LD-2,  |
| indicates mid-position and the unexpected closure of  feedwater regulating   |
| valve for steam generator "B".  The steam dump bypass control system is      |
| operating properly.                                                          |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
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