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Event Notification Report for December 7, 2001

                         
                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           12/06/2001 - 12/07/2001

                              ** EVENT NUMBERS **

38542  38543  38544  38545  
.
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|Power Reactor                                    |Event Number:   38542       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FERMI                    REGION:  3  |NOTIFICATION DATE: 12/06/2001|
|    UNIT:  [2] [] []                 STATE:  MI |NOTIFICATION TIME: 04:55[EST]|
|   RXTYPE: [2] GE-4                             |EVENT DATE:        12/06/2001|
+------------------------------------------------+EVENT TIME:        03:50[EST]|
| NRC NOTIFIED BY:  JEFF GROFF                   |LAST UPDATE DATE:  12/06/2001|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |PATRICK HILAND       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  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     M/R        Y       100      Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MANUAL REACTOR SCRAM DUE TO A LOSS OF STATOR WATER COOLING                   |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "At 0350 on 12/6/01 with the reactor at 100%, a manual reactor scram was     |
| inserted due to the loss of stator water cooling.  All control rods fully    |
| inserted into the core.  While taking a stator water sample, the heat        |
| exchanger vent line broke off the heat exchanger losing stator water from    |
| the system.  A reactor scram was inserted prior to an [imminent] turbine     |
| generator trip."                                                             |
|                                                                              |
| "Following the reactor scram, water level dropped to approximately 120".     |
| Reactor water level is being maintained in the normal level band (197") with |
| feedwater/condensate.  The following 'Level 3' isolations occurred as        |
| expected:"                                                                   |
|                                                                              |
| "Group 4 - RHR Shutdown Cooling and Head Spray"                              |
| "Group 13 - Drywell Sumps"                                                   |
| "Group 15 - Traversing Incore Probe Systems"                                 |
|                                                                              |
| "All valves in [Groups] 4 and 15 were closed prior to the event.  Group 13   |
| valves closed as designed.  No ECCS systems initiated, and no SRVs lifted.   |
| All Emergency Diesel Generators are operable."                               |
|                                                                              |
| The licensee stated that the main steam isolation valves remained open and   |
| that the main condenser is being used as the heat sink.  Containment         |
| parameters are normal, and the grid is stable.                               |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+
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+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   38543       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  CROW BUTTE RESOURCES                 |NOTIFICATION DATE: 12/06/2001|
|LICENSEE:  CROW BUTTE RESOURCES                 |NOTIFICATION TIME: 09:39[EST]|
|    CITY:  CRAWFORD                 REGION:  4  |EVENT DATE:        12/05/2001|
|  COUNTY:  DAWES                     STATE:  NE |EVENT TIME:        14:30[CST]|
|LICENSE#:  SUA-1534              AGREEMENT:  Y  |LAST UPDATE DATE:  12/06/2001|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |ANTHONY GODY         R4      |
|                                                |FRED BROWN           NMSS    |
+------------------------------------------------+MIKE LAYTON (MINING) NMSS    |
| NRC NOTIFIED BY:  MIKE GRIFFIN                 |                             |
|  HQ OPS OFFICER:  LEIGH TROCINE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NONR                     OTHER UNSPEC REQMNT    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DISCOVERY OF A SHALLOW MONITOR WELL IN EXCURSION FOR SULFATE                 |
|                                                                              |
| At approximately 1430 CST on 12/05/01, the licensee received second          |
| confirmation of well #SM723 being in excursion for sulfate.  Sulfate was     |
| discovered to be at a concentration of 68 mg/l which exceeded the upper      |
| control limit of 65 mg/l.  This excursion is believed to be naturally        |
| occurring, and the licensee has submitted a license amendment request to     |
| change the upper control limit.  The licensee also plans to maintain an      |
| increased monitoring frequency.  The licensee stated that well #SM723 is     |
| located within a controlled well field with a shallow aquifer and that there |
| was no adverse impact expected on individuals or the environment.            |
|                                                                              |
| (Call the NRC operations officer for licensee contact information.)          |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38544       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CALLAWAY                 REGION:  4  |NOTIFICATION DATE: 12/06/2001|
|    UNIT:  [1] [] []                 STATE:  MO |NOTIFICATION TIME: 11:34[EST]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        12/06/2001|
+------------------------------------------------+EVENT TIME:        09:05[CST]|
| NRC NOTIFIED BY:  WEEKLEY                      |LAST UPDATE DATE:  12/06/2001|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |ANTHONY GODY         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       12       Power Operation  |1        Startup          |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| THE LICENSEE MADE AN OFFSITE NOTIFICATION TO THE MISSOURI PUBLIC SERVICE   
 |
| COMMISSION                                                                   |
|                                                                              |
| The following is a report to the Missouri Public Service Commission (MPSC)   |
| to notify the them of a forced outage at the Callaway Nuclear Plant. This    |
| notification is reportable under 4CSR240-20.080(3)(B) because the outage is  |
| expected to last longer than 72 hours.                                       |
|                                                                              |
| At 2248 CST, December 3, 2001, Callaway Plant shut down to effect repairs on |
| the Main Generator.   A leak had developed on a Main Generator cooling       |
| system requiring repairs which could only be made with the unit off-line.    |
| Initially, the Plant was expected to return to service within 72 hours, but  |
| due to the complexity of the repairs, the unit is now expected to return to  |
| service after the 72-hour deadline has expired.  Expectations are to return  |
| to service by December 7, 2001.                                              |
|                                                                              |
| The Licensee has informed the NRC Resident Inspector of the MPSC             |
| notification.                                                                |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38545       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FARLEY                   REGION:  2  |NOTIFICATION DATE: 12/06/2001|
|    UNIT:  [1] [2] []                STATE:  AL |NOTIFICATION TIME: 13:52[EST]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        12/06/2001|
+------------------------------------------------+EVENT TIME:        10:20[CST]|
| NRC NOTIFIED BY:  CHERI COLLINS                |LAST UPDATE DATE:  12/06/2001|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |MARK LESSER          R2      |
|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  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| FITNESS FOR DUTY                                                             |
|                                                                              |
| A licensed operator (currently inactive) tested positive for illegal drug    |
| use under the licensee's fitness-for-duty (FFD) program. The individual was  |
| not on shift assignment, nor had the individual performed on-shift           |
| activities during the past year. The individual's site access has been       |
| terminated. The NRC resident inspector has been informed of this event by    |
| the licensee.                                                                |
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