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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!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