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Event Notification Report for March 15, 2002

                         
                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           03/14/2002 - 03/15/2002

                              ** EVENT NUMBERS **

38766  38767  38768  38769  

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|General Information or Other                     |Event Number:   38766       |
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| REP ORG:  GEORGIA RADIOACTIVE MATERIAL PGM     |NOTIFICATION DATE:
03/14/2002|
|LICENSEE:  ATC ASSOCIATES                       |NOTIFICATION TIME: 07:54[EST]|
|    CITY:  LOGANVILLE               REGION:  2  |EVENT DATE:        03/10/2002|
|  COUNTY:                            STATE:  GA |EVENT TIME:             [EST]|
|LICENSE#:  GA 665-1              AGREEMENT:  Y  |LAST UPDATE DATE:  03/14/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |MARK LESSER          R2      |
|                                                |FRED BROWN           NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  LIZ SEALE                    |                             |
|  HQ OPS OFFICER:  STEVE SANDIN                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| AGREEMENT STATE REPORT INVOLVING A STOLEN MOISTURE DENSITY GAUGE           
 |
|                                                                              |
| "A construction trailer [located at the Home Depot construction site in      |
| Loganville, GA] was broken into during the night of 3/10/02.  A moisture     |
| density gauge along with other equipment was stolen. Police [and FBI] were   |
| notified and investigated. The gauge was a CPN Model MC-1, serial number:    |
| M17077782."                                                                  |
|                                                                              |
| The moisture density gauge contained two sources; 10 mCi Cs-137 and 50 mCi   |
| Am-241. Georgia Event Report ID No. GA-2002-07.                              |
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|Fuel Cycle Facility                              |Event Number:   38767       |
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| FACILITY: WESTINGHOUSE ELECTRIC CORPORATION    |NOTIFICATION DATE:
03/14/2002|
|   RXTYPE: URANIUM FUEL FABRICATION             |NOTIFICATION TIME: 09:51[EST]|
| COMMENTS: LEU CONVERSION (UF6 to UO2)          |EVENT DATE:        03/13/2002|
|           COMMERCIAL LWR FUEL                  |EVENT TIME:        12:30[EST]|
|                                                |LAST UPDATE DATE:  03/14/2002|
|    CITY:  COLUMBIA                 REGION:  2  +-----------------------------+
|  COUNTY:  RICHLAND                  STATE:  SC |PERSON          ORGANIZATION |
|LICENSE#:  SNM-1107              AGREEMENT:  Y  |MARK LESSER          R2      |
|  DOCKET:  07001151                             |FRED BROWN           NMSS    |
+------------------------------------------------+NADER MAMISH         IRO     |
| NRC NOTIFIED BY:  DAVID WILLIAMS               |                             |
|  HQ OPS OFFICER:  RICH LAURA                   |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| 24 HOUR NRC 91-01 REPORT INVOLVING OIL CONTAMINATION ON ADU BULK
CONTAINER   |
|                                                                              |
|                                                                              |
| "Westinghouse Electric Company, Commercial Fuel Fabrication Facility,        |
| Columbia SC, low enriched (less than or equal to 5.0 wt.% U-235) PWR fuel    |
| fabricator for commercial light water reactors, License: SNM-1107.           |
|                                                                              |
| "Time and Date of Event: Approxirnatcly 12:30 hours, Wednesday, March 13,    |
| 2002.                                                                        |
|                                                                              |
| "Reason for Notification: When an empty bulk container was returned to the   |
| bulk blending room after having been emptied on the erbia production line,   |
| an operator noticed a film of oil on the outside of the container and its    |
| feeder valve, and on an horizontal structural plate of the container.        |
|                                                                              |
| "Summary of Process: UO2 powder is blended in 1750 kg bulk containers in the |
| bulk blending room (a moderation control (Modcon) area) prior to being used  |
| on a pellet line. After blending, the bulk containers are taken to a         |
| production line, and placed into a second Modcon area for processing. After  |
| processing, the empty containers are returned to the bulk blending room.     |
|                                                                              |
| "As Found Condition; a summary of the as found conditions is as follows: The |
| Nuclear Criticality Safety (NCS) function was immediately notified, and an   |
| NCS engineer went immediately to the floor to evaluate the situation. The    |
| bulk container was empty. A film of oil was found on the side of the         |
| container and its feeder valve, and on a horizontal  structural plate of the |
| container. The total quantity of oil is estimated to be no more than a few   |
| ounces. The container was inspected, and found to apparently be intact, that |
| is, the integrity intact and the gaskets in place and firmly secured.        |
|                                                                              |
| "Double Contingency Protection: Double contingency protection for the ADU    |
| bulk container(s)  is based on moderation control, that is, (1) prevent      |
| greater than 20.48 liters of water equivalent from becoming available to a   |
| bulk container, and (2) prevent greater than 20.48 liters of water           |
| equivalent entering a container. It was determined double contingency        |
| protection was lost because of the failure of controls to prevent moderating |
| material from coming in contact with a bulk Container without prior written  |
| authorization, It is also noted that at no time was greater than the safety  |
| limit of moderator involved. Therefore the incident requires 24-hour         |
| notification in accordance with Westinghouse Operating License (SNM-1107),   |
| paragraph 3.7.3 (c.5).                                                       |
|                                                                              |
| "Summary of Activity: The NCS engineer made the preliminary determination    |
| that the incident was significant  because moderator had come into contact   |
| with a bulk container. The container was removed from service. No additional |
| immediate corrective action was required for the affected container because  |
| it was empty. The feeder valve was removed, and the gasket and interior of   |
| the container and feeder valve were inspected for oil contamination. None    |
| was found.                                                                   |
|                                                                              |
| "Conclusion: There was a loss of double contingency protection. At no time   |
| was greater than a safe limit of moderator involved. At no time was          |
| criticality possible. At no rime 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. A       |
| causal analysis will be performed."                                          |
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|Power Reactor                                    |Event Number:   38768       |
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| FACILITY: BROWNS FERRY             REGION:  2  |NOTIFICATION DATE: 03/14/2002|
|    UNIT:  [] [2] []                 STATE:  AL |NOTIFICATION TIME: 14:42[EST]|
|   RXTYPE: [1] GE-4,[2] GE-4,[3] GE-4           |EVENT DATE:        02/28/2002|
+------------------------------------------------+EVENT TIME:        17:52[CST]|
| NRC NOTIFIED BY:  JAMES WALLACE, JR            |LAST UPDATE DATE:  03/14/2002|
|  HQ OPS OFFICER:  RICH LAURA                   +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |MARK LESSER          R2      |
|10 CFR SECTION:                                 |                             |
|AINV 50.73(a)(1)         INVALID SPECIF SYSTEM A|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| INVALID ACTUATION OF TWO DIESEL GENERATORS DURING TESTING                    |
|                                                                              |
| "This is a verbal report in accordance with 10 CFR 50.73(a)(2)(iv)(A). It is |
| not considered a Licensee Event Report. This event occurred with Unit 2 at   |
| full power while performing scheduled testing of the common accident signal  |
| logic.  On February 28, 2002, at 1752 hours, an invalid signal caused the    |
| automatic actuation of the B and D Emergency Diesel Generators (EDGs). The   |
| EDGs functioned successfully. They were not required to tie to their         |
| respective 4kV shutdown boards because their boards were energized. The      |
| Reactor Protection System did not actuate.  No other systems listed in 10CFR |
| 50.73(a)(2)(iv)(B) were affected."                                           |
|                                                                              |
| The licensee stated that the inadvertent actuation resulted from a           |
| surveillance test procedural compliance issue.                               |
|                                                                              |
| The licensee will contact the NRC Resident.                                  |
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|Power Reactor                                    |Event Number:   38769       |
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| FACILITY: BROWNS FERRY             REGION:  2  |NOTIFICATION DATE: 03/14/2002|
|    UNIT:  [] [] [3]                 STATE:  AL |NOTIFICATION TIME: 14:42[EST]|
|   RXTYPE: [1] GE-4,[2] GE-4,[3] GE-4           |EVENT DATE:        03/06/2002|
+------------------------------------------------+EVENT TIME:        21:03[CST]|
| NRC NOTIFIED BY:  JAMES WALLACE JR             |LAST UPDATE DATE:  03/14/2002|
|  HQ OPS OFFICER:  GERRY WAIG                   +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |MARK LESSER          R2      |
|10 CFR SECTION:                                 |                             |
|AINV 50.73(a)(1)         INVALID SPECIF SYSTEM A|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|                                                   |                          |
|3     N          Y       94       Power Operation  |94       Power Operation  |
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                                   EVENT TEXT                                   
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| INVALID EMERGENCY DIESEL GENERATOR ACTUATION DURING TESTING                  |
|                                                                              |
| "This is a verbal report in accordance with 10 CFR 50.73(a) (2)(iv)(A). It   |
| is not considered a Licensee Event Report. This event occurred with Unit 3   |
| at 94 percent power while performing scheduled testing of the common         |
| accident signal logic. On March 6, 2002, at 2103 hours, an invalid signal    |
| caused the automatic actuation of the 3B Emergency Diesel Generator (EDG).   |
| The EDG functioned successfully, it was not required to tie to its           |
| respective 4kV shutdown board by design because the board was energized. The |
| Reactor Protection System did not actuate. No other systems listed in 10CFR  |
| 50.73(a)(2)(iv)(B) were affected."                                           |
|                                                                              |
| The licensee stated that the inadvertent actuation resulted from an          |
| insulator finger dislodging from an electrical contact during surveillance   |
| testing.                                                                     |
|                                                                              |
| The licensee will notify the NRC Resident.                                   |
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