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Event Notification Report for June 9, 2003






                    U.S. Nuclear Regulatory Commission

                              Operations Center



                              Event Reports For

                           06/06/2003 - 06/09/2003



                              ** EVENT NUMBERS **



39469  39634  



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|General Information or Other                     |Event Number:   39469       |

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| REP ORG:  NEW MEXICO RAD CONTROL PROGRAM       |NOTIFICATION DATE: 12/23/2002|

|LICENSEE:  P & M CONSTRUCTION INC.              |NOTIFICATION TIME: 15:07[EST]|

|    CITY:  PONDEROSA                REGION:  4  |EVENT DATE:        12/12/2002|

|  COUNTY:                            STATE:  NM |EVENT TIME:             [MST]|

|LICENSE#:  DM159-03              AGREEMENT:  Y  |LAST UPDATE DATE:  06/06/2003|

|  DOCKET:                                       |+----------------------------+

|                                                |PERSON          ORGANIZATION |

|                                                |LINDA HOWELL         R4      |

|                                                |CHARLES COX          NMSS    |

+------------------------------------------------+                             |

| NRC NOTIFIED BY:  MILLER                       |                             |

|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |

+------------------------------------------------+                             |

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|NAGR                     AGREEMENT STATE        |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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                                   EVENT TEXT                                   

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| STOLEN TROXLER DENSITY MOISTURE GAUGE                                        |

|                                                                              |

| P & M Construction, Inc. notified the state on 12/12/02 that a Troxler model |

| 3411B (serial # 12073) density moisture gauge was stolen from their shop in  |

| Ponderosa, New Mexico sometime in September or October of this year.  The    |

| gauge contained a 9 millicurie Cs-137 source (serial # 409584) and a 50      |

| millicurie Am-241: Be source (serial # 477368).  The gauge was locked in its |

| transport container with a locked chain securing the container.  This chain  |

| was cut and the locked container was removed from the shop.  A police report |

| was made.                                                                    |

|                                                                              |

| * * * UPDATE ON 6/5/03 FROM BILL FLOYD TO NRC OFFICE OF PUBLIC AFFAIRS * *   |

| *                                                                            |

|                                                                              |

| A local man found the stolen gauge in the Albuquerque West Mesa area on      |

| 5/24/03.  He had knowledge of this type of instrument and was able to trace  |

| it to the proper owner by the paperwork accompanying the gauge.  The gauge   |

| is in good condition, but will remain secured and out of service until       |

| results of a leak test are received.                                         |

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|General Information or Other                     |Event Number:   39634       |

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| REP ORG:  GENERAL ELECTRIC                     |NOTIFICATION DATE: 03/03/2003|

|LICENSEE:  GENERAL ELECTRIC                     |NOTIFICATION TIME: 20:51[EST]|

|    CITY:  San Jose                 REGION:  4  |EVENT DATE:        03/03/2003|

|  COUNTY:                            STATE:  CA |EVENT TIME:             [PST]|

|LICENSE#:                        AGREEMENT:  Y  |LAST UPDATE DATE:  06/06/2003|

|  DOCKET:                                       |+----------------------------+

|                                                |PERSON          ORGANIZATION |

|                                                |MOHAMED SHANBAKY     R1      |

|                                                |WALTER RODGERS       R2      |

+------------------------------------------------+MONTE PHILLIPS       R3      |

| NRC NOTIFIED BY:  JASON S. POST                |DALE POWERS          R4      |

|  HQ OPS OFFICER:  ERIC THOMAS                  |MICHAEL JOHNSON      NRR     |

+------------------------------------------------+                             |

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|CCCC 21.21               UNSPECIFIED PARAGRAPH  |                             |

|                                                |                             |

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                                   EVENT TEXT                                   

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| PART 21 NOTIFICATION - FUEL CHANNEL BOW                                      |

|                                                                              |

| GE Nuclear reports a new phenomenon that causes fuel channel bow.  "Shadow   |

| Corrosion" is the hydrogen-induced growth of the channel wall closest to the |

| control blade when the fuel channel is in a highly controlled location       |

| during its initial fuel cycle.  The hydrogen-induced growth leads to channel |

| bowing toward the control blade late in life.  This condition is believed to |

| be most significant for BWR/6 plants.                                        |

|                                                                              |

| There are two effects of the new phenomenon:                                 |

| 1.  It is not accounted for by thermal limit calculations                    |

| 2.  The bias towards the control blade can lead to control rod-fuel channel  |

| interference.                                                                |

|                                                                              |

| To mitigate the impact on thermal limits, an interim penalty of .02 has been |

| applied to the Operating Limit Minimum Critical Power Ratio for all BWR/6's. |

| In the long-term, updated channel bow data will be used in the approved fuel |

| licensing models and this data will be incorporated into future reload       |

| licensing analyses.  Recommended actions for non-BWR/6 plants are expected   |

| by June 6, 2003.                                                             |

|                                                                              |

| Concerns related to the control rod-fuel channel interference include: 1)    |

| friction that could cause fuel bundle lift, 2) transfer of forces to reactor |

| internals causing higher stresses, and 3) slower scram speeds.  There have   |

| been no interim actions designated to mitigate these effects, but            |

| recommendation for a surveillance to help detect control rod-fuel channel    |

| interference is expected by April 28, 2003.                                  |

|                                                                              |

| Affected plants at present are all BWR/6's.  Potentially affected plants are |

| all BWR's, with the exception of Columbia Generating Station.                |

|                                                                              |

| * * * UPDATE ON 6/6/03 AT 1821EDT FROM JASON POST TO GERRY WAIG * * *        |

|                                                                              |

| "The NRC was previously notified of a Reportable Condition for fuel thermal  |

| limits calculations on BWR/6 plants. Subsequent analysis has shown that it   |

| is not a reportable condition on BWR/2-5 plants. This completes the          |

| commitment made in the reference letter to evaluate the impact on BWR/2-5    |

| thermal limits calculations by June 6, 2003."                                |

|                                                                              |

| Notified (via email) R1DO (James Linville), R2DO ( Kerry Landis), R3DO (Ken  |

| O'Brien), R4DO (Dave Loveless), NRR (David Matthews).                        |

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