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Event Notification Report for January 29, 2002

                         
                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           01/28/2002 - 01/29/2002

                              ** EVENT NUMBERS **

38634  38656  38657  

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|Power Reactor                                    |Event Number:   38634       |
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| FACILITY: SAINT LUCIE              REGION:  2  |NOTIFICATION DATE: 01/17/2002|
|    UNIT:  [1] [2] []                STATE:  FL |NOTIFICATION TIME: 13:07[EST]|
|   RXTYPE: [1] CE,[2] CE                        |EVENT DATE:        01/17/2002|
+------------------------------------------------+EVENT TIME:        11:45[EST]|
| NRC NOTIFIED BY:  KELLY KORTH                  |LAST UPDATE DATE:  01/28/2002|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |ROBERT HAAG          R2      |
|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  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| OFFSITE NOTIFICATION  INVOLVING RECOVERED SEA TURTLE FROM INTAKE CANAL    
  |
|                                                                              |
| At approximately 1130 EST on 01/17/02, a green sea turtle was retrieved from |
| the intake canal and a determination was made that it was in need of         |
| rehabilitation.  As required by the Plant's Sea Turtle Permit, the Florida   |
| Fish and Wildlife Conservation Commission (FFWCC) was notified at 1145 EST.  |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
|                                                                              |
| See EN #38513 for 2001 occurrences.                                          |
|                                                                              |
| * * * UPDATE ON 1/28/02  @ 1243 BY KORTH TO GOULD * * *                      |
|                                                                              |
| At approximately 1115 on 1/28/02 a loggerhead turtle was retrieved from the  |
| plant's  intake canal.  The turtle was determined to be in need of           |
| rehabilitation.  Per the licensee's turtle permit, the Florida Fish and      |
| Wildlife Conservation Commission (FWCC) was notified at 1125.                |
|                                                                              |
| The NRC Resident Inspector was notified.   Notified Reg 2 RDO (Ninh)         |
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|Fuel Cycle Facility                              |Event Number:   38656       |
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| FACILITY: WESTINGHOUSE ELECTRIC CORPORATION    |NOTIFICATION DATE:
01/28/2002|
|   RXTYPE: URANIUM FUEL FABRICATION             |NOTIFICATION TIME: 15:45[EST]|
| COMMENTS: LEU CONVERSION (UF6 to UO2)          |EVENT DATE:        01/27/2002|
|           COMMERCIAL LWR FUEL                  |EVENT TIME:        21:15[EST]|
|                                                |LAST UPDATE DATE:  01/28/2002|
|    CITY:  COLUMBIA                 REGION:  2  +-----------------------------+
|  COUNTY:  RICHLAND                  STATE:  SC |PERSON          ORGANIZATION |
|LICENSE#:  SNM-1107              AGREEMENT:  Y  |SON NINH             R2      |
|  DOCKET:  07001151                             |JOHN HICKEY          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  WILLIAMS                     |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| 24 HOUR 91-01 BULLETIN RESPONSE                                              |
|                                                                              |
| Reason for Notification                                                      |
|                                                                              |
| At the time of the event, the Team Leader of the Burnable Absorber Expansion |
| System called the cognizant Nuclear Criticality Safety (NCS) engineer to     |
| inform him that 113.5 kg of uranium oxide powder had spilled from process    |
| equipment into the granulator hood.                                          |
|                                                                              |
|                                                                              |
| Summary of Process                                                           |
|                                                                              |
| Dry UO2 powder blended with U3O6 and erbium oxide is processed in a          |
| favorable geometry, gravity fed, vertical pipe from a roll compactor down to |
| a granulator.   Inside a hood, the granulator feeds down through a flexible  |
| tube into a polypak.                                                         |
|                                                                              |
|                                                                              |
| As Found Condition                                                           |
|                                                                              |
| A summary of the as found conditions is as follows:                          |
|                                                                              |
| It had been determined that the granulator screen needed to be replaced, and |
| operations were stopped.                                                     |
|                                                                              |
| When the granulator screen was removed, material in the vertical pipe        |
| spilled down onto the bottom of the hood, remaining contained within the     |
| hood.                                                                        |
|                                                                              |
| The spill was immediately placed into polypaks and telephone notification    |
| was made to Nuclear Criticality Safety.                                      |
|                                                                              |
|                                                                              |
| Double Contingency Protection                                                |
|                                                                              |
| Double contingency protection for this situation, which is classified as a   |
| spill, is based on control of mass and moderation, and assumes a             |
| hemispherical configuration.  The mass limit is 50.3 kgU or 57.1 kg UO2; the |
| moderator limit is 32.1 liters of water.  It was determined that double      |
| contingency protection was lost because the amount of material spilled       |
| exceeded the mass limit.                                                     |
|                                                                              |
| Moderation controls remained intact.  Double contingency protection was      |
| restored in approximately 30 minutes.  Therefore the incident requires       |
| notification in accordance with Westinghouse Operating License (SNM-107),    |
| paragraph 3.7.3 (c.5), in which greater than safe mass is involved, but      |
| controls are restored within four hours.                                     |
|                                                                              |
|                                                                              |
| Summary of Activity                                                          |
|                                                                              |
| Nuclear Criticality Safety gave permission to resume operations because      |
| double contingency protection had been restored.                             |
|                                                                              |
| On January 28, 2002, written instructions were issued to erbia operations    |
| personnel and training conducted reinforcing that before removal of the      |
| screen from the granulator, the material in the vertical process pipe is to  |
| be processed into polypaks.                                                  |
|                                                                              |
| Long term corrective actions to prevent the possibility of recurrence will   |
| be evaluated as part of apparent cause analysis.                             |
|                                                                              |
|                                                                              |
| Conclusions                                                                  |
|                                                                              |
| Loss of double contingency protection did occur, but was restored within     |
| approximately 30 minutes.                                                    |
|                                                                              |
| At no time was criticality possible because there was no moderator present.  |
|                                                                              |
| At no time was there any risk to the health or safety of any employee or     |
| member of the public.  No exposure to hazardous material was involved.       |
|                                                                              |
| It has been determined that this is a safety significant incident in         |
| accordance with governing procedures. An apparent cause analysis will be     |
| performed.                                                                   |
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|Power Reactor                                    |Event Number:   38657       |
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| FACILITY: HADDAM NECK              REGION:  1  |NOTIFICATION DATE: 01/28/2002|
|    UNIT:  [1] [] []                 STATE:  CT |NOTIFICATION TIME: 17:39[EST]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        01/28/2002|
+------------------------------------------------+EVENT TIME:        16:00[EST]|
| NRC NOTIFIED BY:  HOUFF                        |LAST UPDATE DATE:  01/28/2002|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |CURTIS COWGILL       R1      |
|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          N       0        Decommissioned   |0        Decommissioned   |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| OFFSITE NOTIFICATION OF AN OIL SPILL                                         |
|                                                                              |
| A spill of approximately 40 gallons of turbine lube oil in the turbine hall  |
| occurred with no release to the environment.  This amount was in excess of   |
| the reportable quantity of 10 gallons, so notification was made to the       |
| Connecticut Department of Environmental Protection of the spill.  This       |
| incident occurred during a decommissioning activities in the turbine hall.   |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
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