Event Notification Report for February 21, 2003
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 02/20/2003 - 02/21/2003 ** EVENT NUMBERS ** 39468 39594 39602 39603 39604 39605 39608 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 39468 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PALISADES REGION: 3 |NOTIFICATION DATE: 12/23/2002| | UNIT: [1] [] [] STATE: MI |NOTIFICATION TIME: 15:02[EST]| | RXTYPE: [1] CE |EVENT DATE: 12/23/2002| +------------------------------------------------+EVENT TIME: 13:00[EST]| | NRC NOTIFIED BY: ROGER SHAFFER |LAST UPDATE DATE: 02/20/2003| | HQ OPS OFFICER: HOWIE CROUCH +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |ANNE MARIE STONE R3 | |10 CFR SECTION: | | |AINC 50.72(b)(3)(v)(C) POT UNCNTRL RAD REL | | |AIND 50.72(b)(3)(v)(D) ACCIDENT MITIGATION | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N Y 100 Power Operation |100 Power Operation | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CONTAINMENT HYDROGEN MONITOR CHANNEL OUT OF SERVICE | | | | At 1300 on 12/23/02, it was determined that two vent caps were found removed | | from the supply and return headers on the right channel of the containment | | hydrogen monitor, EC-162, which constituted a reportable condition under 10 | | CFR 50.72(b)(3)(v)(C) and (D), 8-hour report. This is based on a release | | path available such that if the hydrogen monitor was placed in service, | | post-accident, the site release limits could be exceeded. Also, with the | | openings in the supply and return lines, a valid hydrogen concentration | | could not be obtained. As a result, operator action to place the hydrogen | | recombiner in service could have been missed. There are no indications that | | these caps were removed maliciously or as an act of sabotage. It should be | | noted that the other (left channel) hydrogen monitor is the preferred | | monitor to be placed in service due to input to the Emergency Response Data | | System. Both the 3/8 inch vent caps were re-installed upon discovery. | | | | The licensee stated that no recent maintenance in the area. The last time | | the vent caps were known to be removed were in May, 2001 for testing. The | | caps were documented as being re-installed after the test was complete. | | | | The licensee notified the NRC resident inspector. | | | | | | * * * UPDATE ON 2/20/03 @ 1041 BY MALONE TO GOULD * * * RETRACTION | | | | THE LICENSEE IS RETRACTING THIS EVENT | | | | An analysis has since determined that the potential release from the | | uninstalled pipe caps and the potential delay in placing a hydrogen | | recombiner in service are bounded by their respective analyses of record, | | considering reasonable assumptions of recognition of the condition from | | available indications. | | | | Consequently, there was no condition which could have prevented the | | fulfillment of a safety function needed to control the release of | | radioactive material or mitigate the consequences of an accident. | | | | The NRC Resident Inspector was notified. | | | | Region 3 RDO(Madera) was notified. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |General Information or Other |Event Number: 39594 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: MISSISSIPPI DIV OF RAD HEALTH |NOTIFICATION DATE: 02/18/2003| |LICENSEE: SOUTHERN INSPECTION SERVICES |NOTIFICATION TIME: 09:36[EST]| | CITY: MOSS POINT REGION: 2 |EVENT DATE: 02/17/2003| | COUNTY: STATE: MS |EVENT TIME: [CST]| |LICENSE#: MS-747-01 AGREEMENT: Y |LAST UPDATE DATE: 02/18/2003| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |CHARLES R. OGLE R2 | | |FRED BROWN NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: B. J. SMITH | | | HQ OPS OFFICER: GERRY WAIG | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AGREEMENT STATE - RADIATION WORKER EXCEEDED TEDE DOSE LIMIT | | | | "Description of Incident: On the afternoon of February 14, 2003, DRH | | received a call from Sonny Mallette with Southern Inspection Services, | | concerning a radiographer receiving a TEDE for calendar year 2002 exceeding | | 5 rem. Mr. Mallette stated that the employee had received 4722 mrem | | [millirem] by the end of the 11th report for 2002, and they had watched his | | dosimeter readings closely, but when they received the end of year report he | | had gone over the 5 rem limit [5,066 millirem]. He stated that the dose was | | received in work situations where shielding and distance are at a minimum. | | One setup involved shooting up in a oil drilling rig derrick where no | | shielding is available." | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Fuel Cycle Facility |Event Number: 39602 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: FRAMATOME ANP RICHLAND |NOTIFICATION DATE: 02/20/2003| | RXTYPE: URANIUM FUEL FABRICATION |NOTIFICATION TIME: 15:04[EST]| | COMMENTS: LEU CONVERSION |EVENT DATE: 02/20/2003| | FABRICATION & SCRAP RECOVERY |EVENT TIME: 06:30[PST]| | COMMERCIAL LWR FUEL |LAST UPDATE DATE: 02/20/2003| | CITY: RICHLAND REGION: 4 +-----------------------------+ | COUNTY: BENTON STATE: WA |PERSON ORGANIZATION | |LICENSE#: SNM-1227 AGREEMENT: Y |KRISS KENNEDY R4 | | DOCKET: 07001257 |ROBERT PIERSON NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: CAL MANNING | | | HQ OPS OFFICER: RICH LAURA | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |KFIR 70.50(b)(4) FIRE/EXPLOSION | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOW LEVEL RADWASTE INCINERATOR FIRE EVENT AT FRAMATOME | | | | "At approximately 0630 hrs. a cardboard waste box, containing about 9.75 | | grams of U-235, was being fed into the low level rad waste incinerator. The | | box entered into the feed box area of the incinerator and the outer door | | closed, however the inner door, separating the feed box from the | | incinerator, only partially opened and prevented the waste box from being | | fed into the incinerator. The waste box caught fire in the feed box area | | which resulted in damage to the primary HEPA filter and associated | | pre-filter for the feed box and incinerator shroud (located just above and | | directly downstream of the feed box area). The final HEPA filters remained | | undamaged. The ventilation duct upstream of the final HEPA filters is | | equipped with a fire deluge system, which remained unactivated indicating | | the temperature seen by the final filters was below the deluge system | | activation temperature (less than 180 degrees F). The fire self-extinguished | | when the inner door was fully closed and the waste box and contents were | | consumed. There was no unusual release of radioactive material from the | | facility as demonstrated by stack air sample results and samples taken from | | the roof and surroundings. The two employees in the facility were checked | | and no detectable contamination, and only minimal (less than .1 DAC hrs.) | | exposure occurred. An Incident Investigation Board (IIB) has been convened. | | The equipment is currently shutdown and will remain down until the IIB | | report is complete and appropriate corrective actions are completed." | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 39603 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 02/20/2003| | UNIT: [] [2] [] STATE: IL |NOTIFICATION TIME: 17:32[EST]| | RXTYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 02/18/2003| +------------------------------------------------+EVENT TIME: 10:16[CST]| | NRC NOTIFIED BY: KEITH TABER |LAST UPDATE DATE: 02/20/2003| | HQ OPS OFFICER: ERIC THOMAS +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |JOHN MADERA R3 | |10 CFR SECTION: | | |AINV 50.73(a)(1) INVALID SPECIF SYSTEM A| | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | |2 N N 0 Refueling |0 Refueling | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INVALID SPECIFIED SYSTEM ACTUATION | | | | "On February 18, 2003, at 1016 hours, with Unit 2 in Mode 5 (refuel), the 2B | | Emergency Diesel Generator (DG), automatically started during the | | restoration from the reactor vessel hydrostatic leakage test. The apparent | | cause was a spurious pressure spike sensed at instrument rack 2H22-P004 | | while opening the reactor vessel head vent valves. This pressure spike | | caused the associated reactor vessel water level transmitters to sense a low | | level condition. This invalid low level signal resulted in the automatic | | actuation of the 2B DG (Div. III) which is the emergency power supply to the | | Unit 2 High Pressure Core Spray (HPCS) system. The Unit 2 HPCS pump control | | switch had been placed in the pull to lock position as part of the procedure | | controls for the hydrostatic leakage test and therefore did not actuate. | | This system actuation is reportable under 10 CFR 50.73 (a)(2)(iv)(A). | | | | "The 2B DG responded normally and reached normal speed and voltage. It was | | run both loaded and unloaded successfully, and was secured at 1042 on | | February 18, 2003. | | | | "This report is being made in accordance with 10 CFR 50.73 (a)(1), which | | states that in the case of an invalid actuation reported under 10 CFR | | 50.73(a)(2)(iv), other than an actuation of the RPS when the reactor is | | critical, the licensee may provide a telephone notification to the NRC | | Operations Center within 60 days after discovery of the event instead of | | submitting a written LER." | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 39604 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 02/20/2003| | UNIT: [2] [] [] STATE: MI |NOTIFICATION TIME: 17:38[EST]| | RXTYPE: [2] GE-4 |EVENT DATE: 02/20/2003| +------------------------------------------------+EVENT TIME: 18:00[EST]| | NRC NOTIFIED BY: GREGORY MILLER |LAST UPDATE DATE: 02/20/2003| | HQ OPS OFFICER: RICH LAURA +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |JOHN MADERA R3 | |10 CFR SECTION: | | |ACOM 50.72(b)(3)(xiii) LOSS COMM/ASMT/RESPONSE| | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |2 N Y 100 Power Operation |100 Power Operation | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ERDS OUT OF SERVICE FOR PLANNED OUTAGE AT FERMI 2 | | | | "The safety parameter display system (SPDS) is being removed from service to | | perform planned upgrades to the system. The removal of the SPDS affects the | | transmission of data for the emergency response data system (ERDS). The SPDS | | will be deactivated at approximately 1800 hours on February 20, 2003, and | | will not be returned to service until the end of April 2003. During this | | period, the primary plant indicators that supply the SPDS, in conjunction | | with the other indication and communication systems available to the plant | | operations staff will be used for emergency response if needed. This | | condition is reportable in accordance with 10CFR50.72(b)(3)(xiii). The | | Senior Resident Inspector, appropriate Region III and NRR Staff members, | | have been briefed on this modification." | | | | The NRC Resident Inspector was notified. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Fuel Cycle Facility |Event Number: 39605 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 02/20/2003| | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 17:59[EST]| | COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 02/20/2003| | 6903 ROCKLEDGE DRIVE |EVENT TIME: 15:30[EST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 02/20/2003| | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION | |LICENSE#: GDP-2 AGREEMENT: N |JOHN MADERA R3 | | DOCKET: 0707002 |ROBERT PIERSON NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: GARY SAYLERS | | | HQ OPS OFFICER: ERIC THOMAS | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | NON-WORK RELATED DEATH OF PLANT EMPLOYEE | | | | "On 2-20-03 at 1530 hours, the Occupational safety and Health Administration | | (OSHA) was notified of a non-occupational related employee death. The | | reporting requirement, 29 CFR 1904.39(b)(5), specifically requires employers | | to notify OSHA when an employee death occurs within thirty (30) days of a | | heart attack which occurred on plant premises. This is not classified as a | | work related event. | | | | "This is being reported in accordance with UE2-RA-RE1030 'Nuclear Regulatory | | Event Reporting,' notification made to another government agency." | | | | This worker had two previous heart attacks. He complained to co-workers of | | chest pains during a break on 2/17/03. On his way to the site medical | | facility, he began to feel chest pains and was taken to the local hospital. | | He died on the morning of 2/20/03 of heart failure. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 39608 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 02/21/2003| | UNIT: [1] [] [] STATE: MA |NOTIFICATION TIME: 02:30[EST]| | RXTYPE: [1] GE-3 |EVENT DATE: 02/21/2003| +------------------------------------------------+EVENT TIME: 00:25[EST]| | NRC NOTIFIED BY: ENGLAND |LAST UPDATE DATE: 02/21/2003| | HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |CLIFFORD ANDERSON R1 | |10 CFR SECTION: | | |ASHU 50.72(b)(2)(i) PLANT S/D REQD BY TS | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N Y 100 Power Operation |70 Power Operation | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR IS BEING SHUT DOWN DUE TO ONE RECIRCULATION LOOP BEING INOPERABLE | | | | "On 2/20/03 @ 0525 PNPS experienced a trip/lockout of 1 of their 2 Recirc MG | | sets. This caused Reactor Power to decrease to 70% of rated. All other | | safety and nonsafety plant equipment functioned normally after the Recirc | | MG trip. Due to our Facility Operating Licenses PNPS entered an Active LCO | | for One Recirculation Loop Inoperable. The License states, 'The Reactor | | shall not be operated with one reciculation loop out of service for more | | than 24 hours. With the reactor operating, the plant shall be placed in a | | hot shutdown condition within 24 hours unless the loop is sooner returned to | | service'. | | | | After extensive trouble shooting activities PNPS decided that the loop will | | not be returned to service in the required time frame and has commenced a | | normal shutdown to hot shutdown condition on 2/21/03 @ 0025. Reactor | | Power at the time of commencement of shutdown was 37%." | | | | The licensee believes the cause was due to a field lead braking off the | | slip rings. Estimated down time is 5 to 8 days. | | | | | | The NRC Resident Inspector was notified and the licensee may notify the | | media. | +------------------------------------------------------------------------------+
Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021