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Event Notification Report for January 8, 2002

                         
                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           01/07/2002 - 01/08/2002

                              ** EVENT NUMBERS **

38612  38613  

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   38612       |
+------------------------------------------------------------------------------+
                         
+------------------------------------------------------------------------------+
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| FACILITY: WESTINGHOUSE ELECTRIC CORPORATION    |NOTIFICATION DATE:
01/07/2002|
|   RXTYPE: URANIUM FUEL FABRICATION             |NOTIFICATION TIME: 11:52[EST]|
| COMMENTS: LEU CONVERSION (UF6 to UO2)          |EVENT DATE:        01/06/2002|
|           COMMERCIAL LWR FUEL                  |EVENT TIME:        13:45[EST]|
|                                                |LAST UPDATE DATE:  01/07/2002|
|    CITY:  COLUMBIA                 REGION:  2  +-----------------------------+
|  COUNTY:  RICHLAND                  STATE:  SC |PERSON          ORGANIZATION |
|LICENSE#:  SNM-1107              AGREEMENT:  Y  |THOMAS DECKER        R2      |
|  DOCKET:  07001151                             |FRED BROWN           NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  JIM HEATH                    |                             |
|  HQ OPS OFFICER:  BOB STRANSKY                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 24-HOUR NRC BULLETIN 91-01 REPORT (VOLUNTARY)                                |
|                                                                              |
| "Water Leak in Burnable Absorber Expansion System Modcon Area January 6,     |
| 2002                                                                         |
|                                                                              |
| "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 that the roofs over the moderation control (Modcon) area in the erbia |
| blending area had developed a small water leak.                              |
|                                                                              |
|                                                                              |
| "As Found Condition                                                          |
| A summary of the as found conditions is as follows:                          |
| *  No operations were being performed in the erbia blending area.            |
| *  The leak was small trickle of water that ran down a structural I-beam and |
| puddled onto the floor.                                                      |
| *  The water was not dripping onto any process equipment.                    |
| *  The erbia blender was empty (contained no SNM), and the blender and all   |
| bulk containers were tightly closed.                                         |
| *  The leak stopped by approx. 17:00 hours.                                  |
| *  The total amount of leakage was approx. 2 gallons (7.6 liters)of water    |
| over approx. 5 hours.                                                        |
|                                                                              |
| "Double Contingency Protection                                               |
| Double contingency protection for the erbia blender and bulk containers is   |
| based on moderation control (prevent greater than 20.48 liters of water      |
| equivalent from entering blender/container). It was determined that double   |
| contingency protection remained for the system. It is also noted that at no  |
| time was greater than the safety limit of moderator involved. Therefore the  |
| incident does not technically require notification in accordance with        |
| Westinghouse Operating License (SNM-1107), paragraph 3.7.3. However, the     |
| decision was made to provide this notification since it was considered to be |
| a serious 'near miss'.                                                       |
|                                                                              |
| "Summary of Activity                                                         |
| *  The incident was discussed thoroughly between the Team Manager and thc    |
| NCS engineer by phone as soon as the leak was discovered.                    |
| *  The NCS engineer made the preliminary determination that double           |
| contingency protection remained.                                             |
| *  The NCS engineer then came to the plant, inspected the area of the leak   |
| with Operations, applied the incident to the previously documented fault     |
| tree analysis of the system, and confirmed that double contingency           |
| remained.                                                                    |
|                                                                              |
| "Conclusions                                                                 |
| *  Loss of double contingency protection did not occur.                      |
| *  Partial degradation of the controls did occur.                            |
| *  Detection and corrective actions were effective in preventing ~y water    |
| from becoming available to the blender or bulk containers.                   |
| *  At no time was greater than a safe limit of moderator involved.           |
| *  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.        |
| *  The Incident Review Committee (IRC) determined that this is a safety      |
| significant incident in accordance with governing procedures. An apparent    |
| cause analysis will be performed."                                           |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38613       |
+------------------------------------------------------------------------------+
                         
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOPER                   REGION:  4  |NOTIFICATION DATE: 01/08/2002|
|    UNIT:  [1] [] []                 STATE:  NE |NOTIFICATION TIME: 03:15[EST]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        01/08/2002|
+------------------------------------------------+EVENT TIME:        01:20[CST]|
| NRC NOTIFIED BY:  HANCE                        |LAST UPDATE DATE:  01/08/2002|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |MARK SHAFFER         R4      |
|10 CFR SECTION:                                 |                             |
|DDDD 73.71               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| SAFEGUARDS SYSTEM DEGRADATION RELATED TO AN AREA DOOR.                       |
| COMPENSATORY MEASURES WERE PUT IN PLACE WITHIN 10 MINS                       |
| CONTACT HOO FOR ADDITIONAL INFORMATION                                       |
|                                                                              |
| The NRC Resident Inspector will be notified.                                 |
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