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Event Notification Report for May 1, 2003








                    U.S. Nuclear Regulatory Commission

                              Operations Center



                              Event Reports For

                           04/30/2003 - 05/01/2003



                              ** EVENT NUMBERS **



39798  39806  39812  39813  



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|General Information or Other                     |Event Number:   39798       |

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| REP ORG:  KENTUCKY DEPT OF RADIATION CONTROL   |NOTIFICATION DATE: 04/25/2003|

|LICENSEE:  HAYES TESTING LABORATORY             |NOTIFICATION TIME: 10:26[EDT]|

|    CITY:  LOUISVILLE               REGION:  2  |EVENT DATE:        04/25/2003|

|  COUNTY:  JEFFERSON                 STATE:  KY |EVENT TIME:             [CDT]|

|LICENSE#:  201-168-05            AGREEMENT:  Y  |LAST UPDATE DATE:  04/25/2003|

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

|                                                |PERSON          ORGANIZATION |

|                                                |MIKE ERNSTES         R2      |

|                                                |DANIEL GILLEN        NMSS    |

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

| NRC NOTIFIED BY:  BOB JOHNSON                  |                             |

|  HQ OPS OFFICER:  HOWIE CROUCH                 |                             |

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

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|NAGR                     AGREEMENT STATE        |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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                                   EVENT TEXT                                   

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| AGREEMENT STATE REPORT - KENTUCKY                                            |

|                                                                              |

| "This letter is notification of a stuck radiography source event that        |

| occurred on March 28, 2003 at Marathon Petroleum in Louisville Kentucky.     |

| The licensee involved was Hayes Testing Laboratory, Inc., Radioactive        |

| Material License Number 201-168-05.  The radiography source was 92.7         |

| [curies] of Ir-192, housed in a 660 B Camera, S/N 1175.                      |

|                                                                              |

| "On March 28, 2003, during performance of radiography with the source        |

| extended, a magnet stand fell approximately 10 feet onto the source tube.    |

| This resulted in a crimp in the source tube, and the radiography source      |

| could not be retracted into the camera.  The area had been initially roped   |

| off and posted off at the 2 mrem/hr boundaries, but once the radiography     |

| source could not be retrieved, personnel followed licensed emergency         |

| procedures and secured the entire area.                                      |

|                                                                              |

| "The radiographer and the radiographer's supervisor attempted to use all     |

| safe means to retrieve the radiography source without success.  The          |

| Radiation Safety Officer (RSO) was contacted immediately, and was able to    |

| determine source location, and shielded the exposed source with four (4) 25  |

| lb. bags of lead shot.  The RSO using extended handle channel locks, was     |

| able to un-crimp the source tube and retrieve the radiography source back    |

| into the camera. The estimated time to un-crimp the source tube and retrieve |

| the source was approximately 2.5 minutes.                                    |

|                                                                              |

| "The radiographer, radiographer's assistant, radiographer's supervisor and   |

| RSO's dosimetry were immediately sent to ICN [a film processing lab] for     |

| processing.  The exposure results were highest in all aspects for the RSO at |

| 111 mrem deep dose, 107 mrem eye dose, and 103 shallow dose.                 |

|                                                                              |

| "The response to this event was considered appropriate and met licensing     |

| conditions. The Commonwealth of Kentucky considers this event closed."       |

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|General Information or Other                     |Event Number:   39806       |

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| REP ORG:  GE NUCLEAR ENERGY                    |NOTIFICATION DATE: 04/28/2003|

|LICENSEE:  GE NUCLEAR ENERGY                    |NOTIFICATION TIME: 21:37[EDT]|

|    CITY:  SAN JOSE                 REGION:  4  |EVENT DATE:        04/28/2003|

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

|LICENSE#:                        AGREEMENT:  Y  |LAST UPDATE DATE:  04/30/2003|

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

|                                                |PERSON          ORGANIZATION |

|                                                |GREG PICK            R4      |

|                                                |RONALD GARDNER       R3      |

+------------------------------------------------+TODD JACKSON         R1      |

| NRC NOTIFIED BY:  JASON POST                   |JACK FOSTER          NRR     |

|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |

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

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|CCCC 21.21               UNSPECIFIED PARAGRAPH  |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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                                   EVENT TEXT                                   

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| INTERIM SURVEILLANCE PROGRAM FOR FUEL CHANNEL BOW MONITORING (PART 21)       |

|                                                                              |

| The control rod-fuel channel interference evaluation has been completed. It  |

| determined that BWR/6 and BWR/4 & 5 C-lattice plants with GNF thick/thin     |

| channels potentially have increased channel bow that can impact fuel bundle  |

| lift, loads on reactor internals, and control rod operability. An interim    |

| surveillance program has been developed to augment the surveillance          |

| requirements in the plant Technical Specifications until other actions,      |

| which mitigate or limit the potential for control rod-channel interference   |

| due to channel bow can be identified and implemented. The recommendations    |

| address the extent and frequency of surveillance actions, and the plants to  |

| which they should be applied. This surveillance program provides early       |

| indication of potentially degraded operational performance and assurance     |

| that action is taken before reaching excessive levels of control rod         |

| friction.  This surveillance plan is limited to BWR/6 and BWR/4 &5 C-lattice |

| plants with GNF thick/thin channels and GE control rods.  There have been no |

| indications of operational or scram problems on BWR/2, 3 and 4 D-lattice     |

| plants, and as a result, they are excluded from the interim surveillance     |

| program.                                                                     |

|                                                                              |

| Plants Recommended for Surveillance Program                                  |

|                                                                              |

| Clinton                                                                      |

| Hope Creek                                                                   |

| Nine Mile Point 2                                                            |

| Fermi 2                                                                      |

| Grand Gulf                                                                   |

| River Bend                                                                   |

| LaSalle 1                                                                    |

| LaSalle 2                                                                    |

| Limerick 1                                                                   |

| Limerick 2                                                                   |

| Perry 1                                                                      |

| Susquehanna 1                                                                |

| Susquehanna 2                                                                |

|                                                                              |

| *** UPDATE ON 4/30/03 AT 1841 FROM J.S. POST TO A. COSTA ***                 |

|                                                                              |

| GE Nuclear Energy has submitted correspondence to the USNRC to exclude the   |

| following plants from the surveillance program: Hope Creek, LaSalle1,        |

| LaSalle2, Susquehanna 1 and Susquehanna 2.                                   |

|                                                                              |

| Notified R1DO(Jackson), R3DO(Gardner), R4DO(Pick) and NRR EO(Gillespie).     |

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|Power Reactor                                    |Event Number:   39812       |

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| FACILITY: SAINT LUCIE              REGION:  2  |NOTIFICATION DATE: 04/30/2003|

|    UNIT:  [] [2] []                 STATE:  FL |NOTIFICATION TIME: 21:52[EDT]|

|   RXTYPE: [1] CE,[2] CE                        |EVENT DATE:        04/30/2003|

+------------------------------------------------+EVENT TIME:        14:20[EDT]|

| NRC NOTIFIED BY:  CHARLES PIKE                 |LAST UPDATE DATE:  04/30/2003|

|  HQ OPS OFFICER:  ARLON COSTA                  +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |JOEL MUNDAY          R2      |

|10 CFR SECTION:                                 |FRANK GILLESPIE      NRR     |

|ADEG 50.72(b)(3)(ii)(A)  DEGRADED CONDITION     |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|                                                   |                          |

|2     N          N       0        Refueling        |0        Refueling        |

|                                                   |                          |

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                                   EVENT TEXT                                   

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| DEGRADED CONDITION DUE TO DEFECT IN REACTOR VESSEL HEAD PENETRATION          |

|                                                                              |

| "On April 30, 2003, at 1420 hours, with St. Lucie Unit 2 in a refueling      |

| outage, FPL discovered a defect in reactor vessel head penetration 72. This  |

| flaw was found during the ongoing reactor vessel head inspection being       |

| performed in accordance with the requirements of NRC Order EA-03-009.  The   |

| defect is OD surface connected, extends into the nozzle and penetrates into  |

| the J-groove weld between the nozzle and reactor vessel head. The defect is  |

| described as an axial flaw, 0.28 inches deep X 0.96 inches long, on the      |

| downhill side of the penetration. Per the inspection guidance, surface flaws |

| located in the attachment weld area are not acceptable.                      |

|                                                                              |

| "There had been no indication of RCS leakage during the previous cycle's     |

| operation. This notification is being made in accordance with 10 CFR         |

| 50.72(b)(3)(ii)(A)."                                                         |

|                                                                              |

| The Licensee notified the NRC Resident Inspector.                            |

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|Hospital                                         |Event Number:   39813       |

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| REP ORG:  SIOUX VALLEY HOSPITAL                |NOTIFICATION DATE: 04/30/2003|

|LICENSEE:  SIOUX VALLEY HOSPITAL                |NOTIFICATION TIME: 18:41[EDT]|

|    CITY:  SIOUX FALLS              REGION:  4  |EVENT DATE:        04/01/2003|

|  COUNTY:                            STATE:  SD |EVENT TIME:        12:00[MDT]|

|LICENSE#:  40-12378-01           AGREEMENT:  N  |LAST UPDATE DATE:  04/30/2003|

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

|                                                |PERSON          ORGANIZATION |

|                                                |GREG PICK            R4      |

|                                                |PATRICIA HOLAHAN     NMSS    |

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

| NRC NOTIFIED BY:  RICHARD MASSOTH              |                             |

|  HQ OPS OFFICER:  ARLON COSTA                  |                             |

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

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|NINF                     INFORMATION ONLY       |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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                                   EVENT TEXT                                   

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| POTENTIAL OVEREXPOSURE AS RECORDED IN PERSONAL DOSIMETER                     |

|                                                                              |

| This is a preliminary report of a potential reportable event under 10 CFR    |

| 20.2203(2)(i). Nuclear Technologist dosimeter readings values for the month  |

| of February 2003 were reported by the NVLAP-accredited dosimeter company at  |

| 7877 mrem DDE. The Hospital does not have any other technologists,           |

| physicists or physicians with dosimeter readings above ALARA-1 levels for    |

| the month of February 200. The Licensee reported that there has been no      |

| unusual sources or amounts of activity present within their facility which   |

| could explain only one individual receiving 100 times their "normal" range   |

| occupational exposure in a single month.                                     |

|                                                                              |

| The Licensee is making preparations to conduct experiments in conjunction    |

| with the dosimeter company to duplicate the unusual exposure pattern and     |

| will complete and file a final report.                                       |

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