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Event Notification Report for March 13, 2001

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           03/12/2001 - 03/13/2001

                              ** EVENT NUMBERS **

37821  37826  37827  37828  37829  37830  

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|Power Reactor                                    |Event Number:   37821       |
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| FACILITY: CALLAWAY                 REGION:  4  |NOTIFICATION DATE: 03/09/2001|
|    UNIT:  [1] [] []                 STATE:  MO |NOTIFICATION TIME: 20:46[EST]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        03/09/2001|
+------------------------------------------------+EVENT TIME:        12:51[CST]|
| NRC NOTIFIED BY:  GARY OLMSTEAD                |LAST UPDATE DATE:  03/12/2001|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |WILLIAM JOHNSON      R4      |
|10 CFR SECTION:                                 |                             |
|*ESF 50.72(b)(3)(iv)(A)  VALID SPECIF SYS ACTUAT|                             |
|*PRE 50.72(b)(2)(xi)     OFFSITE NOTIFICATION   |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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      |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| LOSS OF BOTH CONTROL ROD DRIVE MOTOR GENERATORS CAUSES REACTOR TRIP          |
|                                                                              |
| During performance of work on the 'B' Rod Drive Motor Generator set, the     |
| output breaker for 'A' Rod Drive Motor Generator set opened causing a loss   |
| of power to the Rod Control System.  The cause of the 'A' Rod Drive Motor    |
| Generator set output breaker opening is being investigated.  With a loss of  |
| power, all rods were de-energized and inserted into the core.  Rod K-10      |
| developed an alarm and the problem was determined to be a faulty circuit     |
| card.  The circuit card was replaced and the problem corrected.              |
|                                                                              |
| This event resulted in a Reactor Protection System (RPS) actuation, when     |
| rods were inserted, an Over Temperature delta T (OTdeltaT) trip was          |
| generated which generated the RPS actuation.  After the RPS system actuated, |
| an Auxiliary Feedwater System actuation was generated.                       |
|                                                                              |
| It was concluded this event is reportable per 10CFR50.72(b)(3)(iv)(A)        |
| since:                                                                       |
| (1) The actuation of the Reactor Protection System occurred after the rods   |
| were at the bottom of the Reactor core (i.e. shut down) as indicated by      |
| computer point alarm printout.                                               |
|                                                                              |
| The NRC Resident inspector was notified of this event by the licensee.       |
|                                                                              |
| * * * UPDATE 1500EST ON 3/12/01 FROM ROBERT BARTON TO S. SANDIN * * *        |
|                                                                              |
| The licensee is updating this report with the following information:         |
|                                                                              |
| "Update to the NRC Notification of Reactor Trip due to Loss of Both Rod      |
| Drive Motor Generator Sets at Callaway Event Number 37821.                   |
|                                                                              |
| "This 4-hour call is being made to the NRC 1) to inform the NRC that a       |
| Notification was made to the Missouri Public Service Commission reporting    |
| the Reactor Trip due to the loss of both Rod Drive Motor Generators which    |
| resulted in an outage expected to last longer than 72 hours and 2) to        |
| clarify information presented on March 9, 2001 concerning the Reactor Trip   |
| due to a loss of electrical power to the Rod Control System at the Callaway  |
| Plant.                                                                       |
|                                                                              |
| Time of Notification to NRC Ops Center                           1400        |
| Event Number assigned by NRC                                       37821     |
| NRC staff contacted at Ops Center                                     Steve  |
| Sandin                                                                       |
| Event Time (time of notification)                                            |
| 1400                                                                         |
| Event Date (date of notification)                                            |
| 3/12/0 1                                                                     |
| Mode/Power before event                                                      |
| 2/1 percent Reactor Power                                                    |
| Mode/Power after event                                                       |
| 2/1 percent Reactor Power                                                    |
| Event Classification                                                         |
| 10CFR50.72(b)(2)(xi)                                                         |
| Was NRC Resident notified                                                    |
| Yes                                                                          |
| Was State notified                                                           |
| No                                                                           |
| Was other local government agencies notified             Yes                 |
| Is media press release planned                                        No     |
| Anything unusual or not understood about the event   N/A                     |
| Did all systems function as required                                 N/A     |
|                                                                              |
| "1) The following was reported to the Missouri PSC at 1248, 3/12/01:         |
|                                                                              |
| 'The following is a report to the Missouri Public Service Commission (MPSC)  |
| involving a Reactor Trip due to a loss of both Rod Drive Motor Generators at |
| the Callaway Plant and is reportable under 4CSR240-20.080(3)(B) because the  |
| outage is expected to last longer than 72 hours.                             |
|                                                                              |
| 'At 1251 on March 9, 2001, work was commencing on one Rod Drive Motor        |
| Generator when the alternate Rod Drive Motor Generator electrical output     |
| breaker failed open. This caused the Reactor Control Rods to be de-energized |
| and insert into the Reactor core. Thc rod insertion shut the Reactor down    |
| and the plant continues to remain shut down to support repairs on equipment  |
| not related to the primary Reactor systems.'                                 |
|                                                                              |
| "2) On March 9, 2001, the NRC Ops Center was informed of the Reactor Trip at |
| Callaway that occurred because of a loss of both Rod Control Motor           |
| Generators. During the notification, it was mentioned that the press had     |
| been notified and a copy of the statement faxed to the NRC Ops Center also   |
| reflected this. What was not covered was the time of the news release. The   |
| news media was faxed a release at 1645 on 3/9/01. This information is being  |
| supplied to ensure clarity that the NRC had been notified of a news release  |
| within the required 4-hour time limit.                                       |
|                                                                              |
| "The NRC Resident Inspector was notified of this event by the licensee."     |
|                                                                              |
| Notified R4DO (Johnson).                                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37826       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MAINE YANKEE             REGION:  1  |NOTIFICATION DATE: 03/12/2001|
|    UNIT:  [1] [] []                 STATE:  ME |NOTIFICATION TIME: 11:25[EST]|
|   RXTYPE: [1] CE                               |EVENT DATE:        03/12/2001|
+------------------------------------------------+EVENT TIME:        10:30[EST]|
| NRC NOTIFIED BY:  RON DOIRON                   |LAST UPDATE DATE:  03/12/2001|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |PETE ESELGROTH       R1      |
|10 CFR SECTION:                                 |FEMA, DOA, HHS       FAX     |
|*PRE 50.72(b)(2)(xi)     OFFSITE NOTIFICATION   |EPA, DOT (VIA NRC)   FAX     |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Decommissioned   |0        Decommissioned   |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION DUE TO FUEL OIL SPILL                                   |
|                                                                              |
| The licensee notified the Maine Department of Environmental Protection (DEP) |
| about a fuel oil spill.  The spill was from a fuel tank on a portable        |
| compressor, at about 1015 EST the fuel line broke dumping about 30 gallons   |
| on the ground.  About 20 to 25 gallons went into the storm water system and  |
| ended up in the adjacent cove.  The licensee is working on containing the    |
| spill on the water and has contained the balance of the spill on the ground. |
| The licensee has also notified the State Nuclear Inspector, the National     |
| Response Center, and will notify NRC Region 1 Decommissioning Branch         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37827       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SOUTH TEXAS              REGION:  4  |NOTIFICATION DATE: 03/12/2001|
|    UNIT:  [1] [] []                 STATE:  TX |NOTIFICATION TIME: 11:32[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        03/12/2001|
+------------------------------------------------+EVENT TIME:        00:45[CST]|
| NRC NOTIFIED BY:  W. E. MOOKHOEK               |LAST UPDATE DATE:  03/12/2001|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |WILLIAM JOHNSON      R4      |
|10 CFR SECTION:                                 |                             |
|HFIT 26.73               FITNESS FOR DUTY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| A supervisor contractor was determined to be under the influence of alcohol  |
| during a for cause fitness for duty test.  The individuals access to the     |
| protected area was terminated.                                               |
|                                                                              |
| Call HOO for further details.                                                |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37828       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COMANCHE PEAK            REGION:  4  |NOTIFICATION DATE: 03/12/2001|
|    UNIT:  [] [2] []                 STATE:  TX |NOTIFICATION TIME: 16:23[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        03/12/2001|
+------------------------------------------------+EVENT TIME:        10:28[CST]|
| NRC NOTIFIED BY:  MIKE SMITH                   |LAST UPDATE DATE:  03/12/2001|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |WILLIAM JOHNSON      R4      |
|10 CFR SECTION:                                 |                             |
|NONR                     OTHER UNSPEC REQMNT    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |85       Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 24-HOUR VIOLATION OF LICENSEE CONDITION DUE TO EXCEEDING THERMAL POWER       |
| LIMIT                                                                        |
|                                                                              |
| "License restriction of 3445 MWth for the unit was exceeded.  Highest        |
| reading N-16 power was 104.93%.  Highest reading Nuclear Instrumentation     |
| Power was approximately 97%.  This event was initiated by a failure of Main  |
| Turbine EHC fluid pressure switch, which closed [the] extraction steam       |
| valves to [the] feedwater heaters.  Unit has been stabilized at 85% Reactor  |
| Power."                                                                      |
|                                                                              |
| Control Room Operators received a feedwater heater high level alarm alerting |
| them to the isolation of extraction steam to both the high and low pressure  |
| feedwater heaters on both feedwater trains.  The isolation of extraction     |
| steam caused a decrease in feedwater temperature thus adding positive        |
| reactivity which increased reactor thermal power.  Operators responded       |
| promptly by reducing turbine load.  The licensee plans on replacing the      |
| failed pressure switch and resuming full power operations.  The licensee     |
| informed the NRC resident inspector.                                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37829       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: RIVER BEND               REGION:  4  |NOTIFICATION DATE: 03/12/2001|
|    UNIT:  [1] [] []                 STATE:  LA |NOTIFICATION TIME: 16:59[EST]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        03/12/2001|
+------------------------------------------------+EVENT TIME:        08:31[CST]|
| NRC NOTIFIED BY:  GEORGE TURNER                |LAST UPDATE DATE:  03/12/2001|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |WILLIAM JOHNSON      R4      |
|10 CFR SECTION:                                 |                             |
|*COM 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       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LOSS OF VARIOUS COMMUNICATIONS CAPABILITIES DUE TO SEVERE WEATHER            |
|                                                                              |
| "Following a series of severe thunderstorms that passed through the Baton    |
| Rouge area during the night it was discovered and reported to the Main       |
| Control Room at 0831 that all offsite sirens, State and Local Hotlines, the  |
| ESP Computer Notification System and Emergency Preparedness Radio were not   |
| available. Commercial telephones and NRC ETS phone lines were available      |
| during this period and continue to be available. The Offsite sirens were     |
| transferred to the backup transmitter within 10 minutes of discovery and     |
| restored as of 0828. As of 1500 hours, all but 2 State and Local Hotlines    |
| were restored. Efforts to restore the remaining communications systems       |
| continue."                                                                   |
|                                                                              |
| The licensee informed the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37830       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MONTICELLO               REGION:  3  |NOTIFICATION DATE: 03/12/2001|
|    UNIT:  [1] [] []                 STATE:  MN |NOTIFICATION TIME: 20:47[EST]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        03/12/2001|
+------------------------------------------------+EVENT TIME:        18:40[CST]|
| NRC NOTIFIED BY:  JOLENE TEMPLE                |LAST UPDATE DATE:  03/12/2001|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |GEOFFREY WRIGHT      R3      |
|10 CFR SECTION:                                 |                             |
|*UNA 50.72(b)(3)(ii)(B)  UNANALYZED COND OP     |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNANALYZED CONDITION DUE TO AN INADEQUATE HELB BARRIER DURING A POSTULATED   |
| FEEDWATER LINE BREAK                                                         |
|                                                                              |
| "An unanalyzed plant condition may exist regarding a HELB barrier within the |
| turbine building.  The HELB barrier in question separates two different      |
| trains of essential 480 volt motor control centers and may be inadequate if  |
| subjected."                                                                  |
|                                                                              |
| An Extent of Condition investigation of High Energy Line Break (HELB)        |
| barriers determined that a barrier separating two adjacent areas (upper and  |
| lower) in the turbine building may not withstand a 0.6 psid due to a         |
| postulated heated feedwater line break.  This could result in the loss of    |
| both trains of equipment controlled by 480 volt MCCs.  The licensee will     |
| develop appropriate corrective action.                                       |
|                                                                              |
| The licensee informed the NRC resident inspector.                            |
+------------------------------------------------------------------------------+