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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  

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   39798       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 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."       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   39806       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 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).     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39812       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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        |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 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.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Hospital                                         |Event Number:   39813       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 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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