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Event Notification Report for January 3, 2002

                         
                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           01/02/2002 - 01/03/2002

                              ** EVENT NUMBERS **

38604  38605  38606  38607  

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|Power Reactor                                    |Event Number:   38604       |
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| FACILITY: HARRIS                   REGION:  2  |NOTIFICATION DATE: 01/02/2002|
|    UNIT:  [1] [] []                 STATE:  NC |NOTIFICATION TIME: 04:56[EST]|
|   RXTYPE: [1] W-3-LP                           |EVENT DATE:        01/02/2002|
+------------------------------------------------+EVENT TIME:        03:05[EST]|
| NRC NOTIFIED BY:  SCOTT SAUNDERS               |LAST UPDATE DATE:  01/02/2002|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |ANNE BOLAND          R2      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(iv)(B)  RPS ACTUATION - CRITICA|                             |
|AESF 50.72(b)(3)(iv)(A)  VALID SPECIF SYS ACTUAT|                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     M/R        Y       7        Power Operation  |0        Hot Standby      |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| MANUAL REACTOR TRIP DUE TO DECREASING STEAM GENERATOR WATER LEVEL.      
    |
|                                                                              |
| During a plant start-up at 7% reactor power, feedwater oscillations occurred |
| on all three steam generators.  At 0215 on 01/02/02 the main feedwater       |
| regulator bypass valves were placed in manual control to stabilize level.    |
| The bypass valves were then returned to automatic control at 0245 on         |
| 01/02/02, and the oscillations continued within the normal operating band of |
| 52-62%.  At 0300 0n 01/02/02. The Control Operator noted lowering level on   |
| the "C" steam generator at approximately 55% with indication that the "C"    |
| main feedwater regulator bypass valve was shut.  The operator placed the "C" |
| bypass valve in manual control and attempted to open the valve with no       |
| response noted in valve position indication.  At 30% indicated level in the  |
| "C" steam generator and a lowering trend, the Unit Shift Control Operator    |
| ordered a manual reactor trip prior to receipt of a steam generator low      |
| water level trip signal at 25%.  All safety systems functioned as expected.  |
| Both Motor Driven Auxiliary Feedwater Pumps automatically actuated on the    |
| subsequent 'C" steam generator low water level signal.  All rods fully       |
| inserted into the core and the electrical grid is stable.   An investigation |
| into what caused this event is in progress.                                  |
|                                                                              |
| The NRC resident inspector was notified of this event by the licensee.       |
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|Power Reactor                                    |Event Number:   38605       |
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| FACILITY: DAVIS BESSE              REGION:  3  |NOTIFICATION DATE: 01/02/2002|
|    UNIT:  [1] [] []                 STATE:  OH |NOTIFICATION TIME: 09:48[EST]|
|   RXTYPE: [1] B&W-R-LP                         |EVENT DATE:        01/02/2002|
+------------------------------------------------+EVENT TIME:        01:50[EST]|
| NRC NOTIFIED BY:  MYERS                        |LAST UPDATE DATE:  01/02/2002|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |GARY SHEAR           R3      |
|10 CFR SECTION:                                 |                             |
|ACOM 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                                   
+------------------------------------------------------------------------------+
| SAFETY PARAMETER DISPLAY SYSTEM (SPDS) IS OUT OF SERVICE                     |
|                                                                              |
| The SPDS has not been functioning since 01:50.  It has been operable for     |
| about one hour, but they are still monitoring it before they determine it to |
| be completely operable.                                                      |
|                                                                              |
| The NRC Resident Inspector will be notified.                                 |
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|Fuel Cycle Facility                              |Event Number:   38606       |
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| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE:
01/02/2002|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 12:47[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        01/02/2002|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        11:52[EST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  01/02/2002|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |GARY SHEAR           R3      |
|  DOCKET:  0707002                              |JOHN HICKEY          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  KEITH WILLIAMSON             |                             |
|  HQ OPS OFFICER:  STEVE SANDIN                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NONR                     OTHER UNSPEC REQMNT    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 4-HOUR REPORT DUE TO EPA NOTIFICATION REGARDING AN OPACITY VIOLATION        
|
|                                                                              |
| The #3 High Pressure Blower on Boiler #3 tripped due to a suspected          |
| equipment malfunction causing a pollutant discharge exceeding the 20%        |
| opacity limit in any one hour period specified by EPA to occur between 0915  |
| and 0921EST.  Operations notified the NRC Resident Inspector and the Ohio    |
| Environmental Protection Agency (OEPA) of the violation.                     |
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|Power Reactor                                    |Event Number:   38607       |
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| FACILITY: WOLF CREEK               REGION:  4  |NOTIFICATION DATE: 01/02/2002|
|    UNIT:  [1] [] []                 STATE:  KS |NOTIFICATION TIME: 21:34[EST]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        01/02/2002|
+------------------------------------------------+EVENT TIME:        12:30[CST]|
| NRC NOTIFIED BY:  JAMES GILMORE                |LAST UPDATE DATE:  01/02/2002|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |BLAIR SPITZBERG      R4      |
|10 CFR SECTION:                                 |                             |
|ACOM 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 SAFETY PARAMETER DISPLAY SYSTEM (SPDS)                               |
|                                                                              |
| At 1230CST SPDS was lost for reasons unknown.  Troubleshooting is currently  |
| in progress.  The licensee informed the NRC Resident Inspector.              |
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