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. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Wednesday, March 24, 2021