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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Page Last Reviewed/Updated Wednesday, March 24, 2021