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 |
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| NRC NOTIFIED BY: MILLER | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
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|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 |
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|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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