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Event Notification Report for December 13, 2001

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           12/12/2001 - 12/13/2001

                              ** EVENT NUMBERS **

38558  38559  
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|Power Reactor                                    |Event Number:   38558       |
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| FACILITY: CALLAWAY                 REGION:  4  |NOTIFICATION DATE: 12/12/2001|
|    UNIT:  [1] [] []                 STATE:  MO |NOTIFICATION TIME: 11:32[EST]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        12/12/2001|
+------------------------------------------------+EVENT TIME:        08:20[CST]|
| NRC NOTIFIED BY:  STEVEN AUFDEMBERGE           |LAST UPDATE DATE:  12/12/2001|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |GREG PICK            R4      |
|10 CFR SECTION:                                 |                             |
|APRE 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  |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| OFFSITE NOTIFICATION REGARDING NPDES PERMIT VIOLATION                        |
|                                                                              |
| "This 4-hour call is being made to the NRC based on the requirements of      |
| 10CFR50.72(b)(2)(xi). A written report was submitted to the Missouri         |
| Department of Natural Resources concerning the discharge of plant processed  |
| water to a storm water runoff outfall inconsistent with the terms and        |
| conditions of Callaway Plant's NPDES permit. This written report was         |
| submitted on December 12, 2001, and addresses a discharge of water from the  |
| plant circulating water system that occurred on December 7, 2001.            |
|                                                                              |
| "On December 12, 2001, the Missouri Department of Natural Resources (Mo.     |
| DNR) was notified that a discharge of plant processed water from our         |
| circulating water system, occurred. This event occurred on December 7, 2001  |
| and was the result of a minor leak that developed at a caulked construction  |
| joint in our cooling tower basin.                                            |
|                                                                              |
| "This event resulted in a notification to the Mo. DNR on 12/12/01. It was    |
| concluded this event is reportable per 10CFR50.72(b)(2)(xi) since it         |
| represents a notification to a government agency relating to the protection  |
| of the environment."                                                         |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
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|Power Reactor                                    |Event Number:   38559       |
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| FACILITY: RIVER BEND               REGION:  4  |NOTIFICATION DATE: 12/12/2001|
|    UNIT:  [1] [] []                 STATE:  LA |NOTIFICATION TIME: 15:58[EST]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        10/15/2001|
+------------------------------------------------+EVENT TIME:        00:01[CST]|
| NRC NOTIFIED BY:  DAVID CLYMER                 |LAST UPDATE DATE:  12/12/2001|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |GREG PICK            R4      |
|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       80       Power Operation  |80       Power Operation  |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| ISOLATION OF DIVISION I CONTAINMENT ISOLATION VALVES DUE TO THE
UNEXPECTED   |
| TRIP OF THE FEEDER BREAKER FOR A NON-SAFETY 480-VOLT AC SWITCHGEAR 
(60-Day  |
| Report)                                                                      |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "On October 15, 2001, at approximately 12:01 a.m., with the plant at         |
| approximately 80% power, an isolation of Division I containment isolation    |
| valves occurred.  This event was caused by the unexpected trip of the feeder |
| breaker for one of the plant's non-safety 480-volt AC switchgears.  In       |
| addition, five manual breakers on the same switchgear opened.  This          |
| deenergized the normal power supply to the Division I reactor protection     |
| system (RPS), which caused the actuation of Division I containment isolation |
| valves.  This event is being reported in accordance with the 60-day          |
| telephone notification provision in 10CFR50.73(a)(2)(iv)(A) as an invalid    |
| general containment isolation signal."                                       |
|                                                                              |
| "Division I containment isolation valves automatically closed, and the       |
| Division I annulus mixing and standby gas treatment systems received an      |
| automatic start signal.  Consistent with plant design, isolation of the      |
| annulus pressure control system subsequently caused the Division II annulus  |
| mixing and standby gas treatment systems to start.  However, the Division II |
| annulus mixing fan breaker tripped open after receiving a close signal.      |
| Both divisions of the fuel building charcoal filter trains started.  The     |
| Division I containment atmosphere hydrogen analyzer automatically started."  |
|                                                                              |
| "After an initial assessment, operators implemented abnormal operating       |
| procedures and restored systems in containment to their normal alignment.    |
| Plant operation was not interrupted.  Except for the trip of the Division II |
| annulus mixing fan, all plant systems responded as designed to the event.    |
| The fan trip is being addressed within the stations corrective action        |
| program."                                                                    |
|                                                                              |
| "The investigation of the spurious breaker trips is still in progress.       |
| Tests completed thus far have not determined the cause of the trip, and      |
| switchgear inspections performed during a brief plant outage in the interim  |
| found no hardware deficiencies.  The Division I RPS system remains powered   |
| from its alternate source, which will prevent its loss should the switchgear |
| again be de-energized.  The switchgear has been instrumented in order to     |
| collect transient data in the event the trips recur."                        |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
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