Event Notification Report for April 17, 2003
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 04/16/2003 - 04/17/2003 ** EVENT NUMBERS ** 39755 39756 39762 39764 39765 +------------------------------------------------------------------------------+ |General Information or Other |Event Number: 39755 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: TEXAS DEPARTMENT OF HEALTH |NOTIFICATION DATE: 04/14/2003| |LICENSEE: ALBEMARELE CORPORATION |NOTIFICATION TIME: 11:34[EDT]| | CITY: PASADENA REGION: 4 |EVENT DATE: 04/11/2003| | COUNTY: STATE: TX |EVENT TIME: 14:00[CDT]| |LICENSE#: L04072-000 AGREEMENT: Y |LAST UPDATE DATE: 04/14/2003| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |CLAUDE JOHNSON R4 | | |JANET SCHLUETER NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: JAMES OGDEN | | | HQ OPS OFFICER: RICH LAURA | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TEXAS AGREEMENT STATE REPORT FOR FIRE DAMAGED THREE SOURCE HOLDERS | | | | "Fire detectors activated in the multi-Product Unit 1 on Friday afternoon, | | insulation and sheeting on the unit were damaged by the fire. Three Ohmart | | SH-F1 source holders were installed on the unit. Each source holder contains | | a Cesium-137 source with an estimated activity of 120 millicuries each. The | | on-site fire department was notified and extinguished the fire. It was | | suspect that the gauges had been engulfed in the fire. However, after | | notification to Techstar, an on-site visit for inspection and verification | | determined that none of the gauges were burned in the fire but had been | | affected by the heat of the fire. It has been explained that the detectors | | were damaged. The Techstar firm confirms that all labels are intact and | | legible. A leak test was performed on each unit for gross contamination and | | a radiation survey and occupancy evaluation was performed. No contamination | | was detected. The ion chamber detectors will have to be replaced, as the | | greater part of the fire was on the detector side of the vessels. Techstar | | placed the three units shutters in the closed position until repairs to the | | facility can be made. Estimated time to repair the facility is approximately | | 10 working days. After repair the ion detectors will be replaced and the | | gauges will be tested by Techstar." | | | | Notified NMSS EO (F. Brown) | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |General Information or Other |Event Number: 39756 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: NV DIV OF RAD HEALTH |NOTIFICATION DATE: 04/14/2003| |LICENSEE: ACCLAIM MATERIAL TESTING AND INSPECTI|NOTIFICATION TIME: 13:05[EDT]| | CITY: Las Vegas REGION: 4 |EVENT DATE: 04/10/2003| | COUNTY: STATE: NV |EVENT TIME: 17:30[PDT]| |LICENSE#: 00-11-0470-01 AGREEMENT: Y |LAST UPDATE DATE: 04/15/2003| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |CLAUDE JOHNSON R4 | | |JANET SCHLUETER NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: STAN MARSHALL | | | HQ OPS OFFICER: ERIC THOMAS | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOST MOISTURE DENSITY GAUGE | | | | A Campbell Pacific Nuclear Model MC-DR1P s/n MD20200680 moisture/density | | gauge was lost out of a transport vehicle on 4/10/03. The gauge contains 10 | | millicuries of Cs-137 and 50 millicuries of Am-241:Be. The gauge was not | | properly secured in the transport vehicle prior to transportation. | | Licensee's corrective actions included a meeting with all gauge users on | | 4/14/03, and issuing an orange cone to be put in the back of each transport | | vehicle to remind users to secure gauges before transport. Local law | | enforcement was notified of this event. The licensee may issue a violation | | letter for failure to follow procedures. | | | | Notified R4 DO (C. Johnson) and NMSS EO (F. Brown) | | | | *****UPDATE ON 4/15/03 AT 10:40 FROM MARSHALL TO LAURA***** | | | | The licensee called at 6:15 pm PDT to advise the gauge had been found on | | April 14 in the middle of the street in vicinity of where it had been lost. | | It had taken the finder some time to track down the owner of the gauge. The | | gauge case was missing but the gauge was reported to be undamaged. | | | | Notified the R4DO (Johnson) and NMSS (ESSIG). | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Fuel Cycle Facility |Event Number: 39762 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 04/16/2003| | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 06:32[EDT]| | COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 04/15/2003| | 6903 ROCKLEDGE DRIVE |EVENT TIME: 09:45[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 04/16/2003| | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION | |LICENSE#: GDP-1 AGREEMENT: Y |THOMAS KOZAK R3 | | DOCKET: 0707001 |TOM ESSIG NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: TOM WHITE | | | HQ OPS OFFICER: MIKE RIPLEY | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | BULLETIN 91-01 24 HOUR REPORT FOR CRITICALITY CONTROL | | | | "At 0945 on 4/15/03, the Plant Shift Superintendent (PSS) was notified that | | SX/WA (Seal Exhaust/Wet Air) pump components were discovered outside the | | C-337 SX/WA FCA (Fissile Control Area) not properly tagged and spaced, as | | required by NCSA CAS-007. Tagging of items removed from the SX/WA FCA | | ensure proper identification of potential fissile components requiring | | spacing controls. Components include used oil solenoid valve, 3 inch elbow, | | oil mist filter crushing tool, 3 gas ballast pipes and valves, oil level | | sight glass, oil or water flow sight glass and copper tubing. The NRC | | Resident Inspector has been notified of this event." | | | | SAFETY SIGNIFICANCE OF EVENTS: While an approved analysis does exist for | | subcriticality of this upset condition, a control relied upon for double | | contingency was violated. | | | | POTENTIAL CRITICALITY PATHWAYS INVOLVED: In order for a criticality to be | | possible, a second independent and unlikely event would need to occur | | concurrently with the loss of spacing accident. | | | | CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION, ETC): | | Double contingency is maintained by implementing controls on interaction and | | an independent failure. | | | | ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL: Less than the safe | | mass of uranium at plant maximum assay of 5.5 wt. % U235. | | | | NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION | | OF THE FAILURES OR DEFICIENCIES: The first leg of double contingency relies | | on interaction. Components removed from a SX/WA FCA shall be spaced a | | minimum 2 feet, edge-to-edge from other potentially fissile material or | | components, the SX/WA components were spaced less than the required 2 foot | | spacing. Therefore, the control on interaction was violated and the | | parameter was lost. | | | | The second leg of double contingency is based on the subcriticality of the | | loss of spacing. The improperly spaced components are of small size and | | limited uranium loading which are in a configuration that is bounded by | | calculations performed for the SX/WA station. Therefore, this leg of double | | contingency is maintained. | | | | Since the interaction parameter was lost; therefore, the double contingency | | principle was not maintained. | | | | CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEMS AND WHEN EACH WAS IMPLEMENTED: | | See remediation guide. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 39764 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 04/16/2003| | UNIT: [1] [2] [3] STATE: SC |NOTIFICATION TIME: 14:14[EDT]| | RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-L|EVENT DATE: 04/16/2003| +------------------------------------------------+EVENT TIME: 11:45[EDT]| | NRC NOTIFIED BY: RANDY TODD |LAST UPDATE DATE: 04/16/2003| | HQ OPS OFFICER: ERIC THOMAS +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |THOMAS DECKER R2 | |10 CFR SECTION: | | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N Y 100 Power Operation |100 Power Operation | |2 N Y 100 Power Operation |100 Power Operation | |3 N Y 82 Power Operation |82 Power Operation | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FITNESS FOR DUTY | | | | "Event: At 11:45 on April 16, 2003, the Oconee Medical Review Officer | | notified the affected individual of a confirmed positive test result | | following a random Fitness For Duty (FFD) screening test. The confirmed | | positive was for alcohol. The individual being tested is a Supervisor in | | the Radiation Protection Section. | | | | "Initial Safety Significance: None: There is no reason to believe there | | has been any adverse consequences from this event. The employee had been in | | meetings all morning until he reported for the random screening test. This | | event is not considered to have impacted operation of the plant in any way. | | | | "Corrective Action(s): The immediate action was to place the individual's | | security badge on FFD hold, which will deny access to the protected area. | | Also, the individual was referred for immediate assessment by the Employee | | Assistance Program counselor, who will determine the extent of additional | | actions." | | | | The licensee notified the NRC Resident Inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 39765 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 04/16/2003| | UNIT: [] [2] [] STATE: IL |NOTIFICATION TIME: 15:46[EDT]| | RXTYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 04/16/2003| +------------------------------------------------+EVENT TIME: 13:59[CDT]| | NRC NOTIFIED BY: MIKE WAGNER |LAST UPDATE DATE: 04/16/2003| | HQ OPS OFFICER: ERIC THOMAS +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: ALERT |THOMAS KOZAK R3 | |10 CFR SECTION: |BOB DENNIG NRR | |AAEC 50.72(a) (1) (i) EMERGENCY DECLARED |CLAUDE JOHNSON R4 | | |GILL DHS | | |GARY BELCHER FEMA | | |SAL MORRONEN DOE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | |2 N Y 100 Power Operation |0 Hot Shutdown | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ALERT DECLARED | | | | "At 1359 CDT, Quad Cities declared and ALERT condition on Unit 2. This | | ALERT was declared due to a stuck open [power operated] relief valve (3B | | PORV). A manual scram was initiated [at 1337 CDT]. Priorities include | | actions to close the 3B relief valve and to maximize Torus cooling. Note | | that the ALERT was declared due to condition FA1 (relief valve stuck open | | and Torus temperature." | | | | The reactor was scrammed due to a 95 deg F Torus temperature. All rods | | fully inserted on the scram. The Torus temperature peaked at 118 degrees F, | | and then started to decrease due to Torus cooling. The tech spec limit on | | Torus temperature is 110 deg F. Cooldown rate exceeded 100 deg F per hour, | | and all MSIVs were closed to limit the cooldown rate. | | | | The NRC Region III Incident response center was fully staffed at 1415 CDT. | | The NRC entered Monitoring mode at 1435 CDT, with Region III in the lead. | | | | * * * SUMMARY AT 1600 CDT ON 4/16/03 FROM DAVID WASNIACK (EXELON) TO NRC | | STAFF * * * | | | | Torus temperature now <110 deg F. Expect to be in Mode IV by 1900 CDT. In | | order to de-inert the Torus, must have Torus temperature <95 deg F, and have | | shutdown cooling supplied to the core. Anticipate 15-16 hours before the | | drywell can be accessed to attempt to manually shut the valve. | | | | The licensee has attempted to close the PORV from the control room via | | several means (switch and pulling control power fuses) and been | | unsuccessful. | | | | * * * SUMMARY AT 1715 CDT ON 4/16/03 FROM DAVID WASNIACK TO NRC STAFF * * * | | | | The licensee is continuing plant and Torus cooldown, and anticipates | | terminating the ALERT when the plant is in Mode 4, at approximately 1900 | | CDT. Suspected cause of the PORV lifting is a failed pilot. | | | | * * * SUMMARY AT 2130 CDT ON 4/16/03 FROM DAVID WASNIACK TO NRC STAFF * * * | | | | Shutdown cooling was established at 2104 CDT. Current temperature 275 deg | | F, cooldown rate is 80 degrees per hour. At 2237 CDT, the licensee declared | | that Unit 2 was in Mode 4. | | | | * * * SUMMARY AT 2245 CDT ON 4/16/03 FROM DAVID WASNIACK TO NRC STAFF * * * | | | | The NRC exited Monitoring mode at 2255 CDT. | | | | * * * SUMMARY AT 2340 CDT ON 4/16/03 FROM RALPH BASSETT TO NRC STAFF * * * | | | | The licensee terminated the alert at 2251 CDT. The plant is in Cold | | Shutdown Mode 4 with the RCS depressurized and less than 212 deg F. | | Notified DHS (Stucky), FEMA (Saunder), DOE (Rick) , USDA (L. Thomas), HHS | | (M. Miller), EPA (Flach), NRR EO (S. Black), HQ PAO (W. Beecher), R3 (S. | | Reynolds). | +------------------------------------------------------------------------------+
Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021