Event Notification Report for November 8, 2003
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 11/07/2001 - 11/08/2001 ** EVENT NUMBERS ** 38474 38475 38476 38477 38478 +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 38474 | +------------------------------------------------------------------------------+ *** NOT FOR PUBLIC DISTRIBUTION *** +------------------------------------------------------------------------------+ !!!!! This event is a security event. Contact HOO for details. !!!!! +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 38475 | +------------------------------------------------------------------------------+ *** NOT FOR PUBLIC DISTRIBUTION *** +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 11/07/2001| | UNIT: [1] [2] [] STATE: FL |NOTIFICATION TIME: 10:32[EST]| | RXTYPE: [1] CE,[2] CE |EVENT DATE: 11/07/2001| +------------------------------------------------+EVENT TIME: 09:00[EST]| | NRC NOTIFIED BY: KORTH |LAST UPDATE DATE: 11/07/2001| | HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |R2 IRC TEAM MANAGER R2 | |10 CFR SECTION: | | |APRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | NOTIFICATION OF THE RECOVERY OF A DEAD GREEN TURTLE FROM THE PLANT'S INTAKE | | CANAL | | | | A dead green turtle was recovered from the plants intake canal where it | | apparently drowned near the 5" barrier net. The licensee notified the | | Florida Department of Environmental Protection as required by the plant's | | sea turtle permit. | | | | The NRC Resident Inspector was notified. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |General Information or Other |Event Number: 38476 | +------------------------------------------------------------------------------+ *** NOT FOR PUBLIC DISTRIBUTION *** +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: ILLINOIS DEPT OF NUCLEAR SAFETY |NOTIFICATION DATE: 11/07/2001| |LICENSEE: |NOTIFICATION TIME: 17:00[EST]| | CITY: CHICAGO REGION: 3 |EVENT DATE: 11/07/2001| | COUNTY: STATE: IL |EVENT TIME: [CST]| |LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 11/07/2001| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |R3 IRC TEAM MANAGER R3 | | |DON COOL NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: LYNCH REG 3/GULCZYNSKI | | | HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE STATE OF ILLINOIS REPORTED A SOURCE BEING FOUND AT A SCRAPYARD | | | | The source of the elevated readings was traced to a metallic right circular | | cylinder, approximately 1 inch long and 1/8 inch in diameter. There were no | | visible markings, color codings, or other identifications on this object. | | Measured exposure rates were 110 mR/hour at 3" and 13 mR/hour at 12". The | | object was placed into the finger of a nitrile glove and further surveys | | were performed. Mr. Labkon's(the individual who recovered the scrap metal) | | hands and gloves were surveyed and were found to be free of contamination. | | The Styrofoam cup which had held the source and the storage room were also | | surveyed and found to be free of contamination. | | | | A gamma spectrum was obtained using the Microspec-2 portable multichannel | | analyzer, serial number 94006. The spectrum showed no discernible | | photopeak. Spectral data are included with this report. | | | | The source/nitrile glove finger were placed into a Syncor threaded pig. The | | exposure rate at near contact with the pig was measured at 25 �Rem/hour. | | | | Based on the data available, this source would be either a strong beta | | emitter, or a very low energy gamma emitter, such as 241-Am. In order to | | determine whether this source may have been manufactured as a neutron | | source, a neutron measurement was performed on November 1, 2001. Using a | | Health Physics Instruments Model REM 500 neutron meter, serial number 00203, | | and taking a standard one minute count for each determination, the following | | readings were obtained: | | | | Configuration Reading (mRem/hour) Reading | | (neutrons/minute) | | Background 0.000 0 | | 4" from unshielded | | source 3.21 330 | | | | at near contact | | with the stainless | | steel shield with | | the source inside 0.448 2 | | | | | | Based on the available data, considering the possibilities of an 241-Am-Be | | source, a 239-Pu-Be source, or a 226-Ra-Be source, the most likely | | possibility is an 241-Am-Be source, with a calculated activity of 4 mCi. | | | | The source was returned to a safe shielded position and locked within their | | source storage room. Pending satisfactory disposal of this source, this | | matter may be considered closed. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 38477 | +------------------------------------------------------------------------------+ *** NOT FOR PUBLIC DISTRIBUTION *** +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PALISADES REGION: 3 |NOTIFICATION DATE: 11/07/2001| | UNIT: [1] [] [] STATE: MI |NOTIFICATION TIME: 19:47[EST]| | RXTYPE: [1] CE |EVENT DATE: 11/07/2001| +------------------------------------------------+EVENT TIME: 14:14[EST]| | NRC NOTIFIED BY: DANIEL G. MALONE |LAST UPDATE DATE: 11/07/2001| | HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |R3 IRC TEAM MANAGER R3 | |10 CFR SECTION: | | |AUNA 50.72(b)(3)(ii)(B) UNANALYZED CONDITION | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N N 0 Cold Shutdown |0 Cold Shutdown | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HEAD LOSS CHARACTERISTICS OF CHECK VALVES GREATER THAN PREVIOUSLY ASSUMED. | | | | On November 7, 2001, at approximately 1414 hours, with the plant in mode 5 | | (cold shutdown), evaluation of preliminary results from mock-up testing of | | containment sump check valves determined that the head loss characteristics | | of the check valves are greater than previously assumed by calculations that | | support the safety analyses. The result of increased head loss through the | | containment sump check valves is reduced available net positive suction head | | (NPSH) for the safety injection and containment spray pumps during | | recirculation mode following a loss of coolant accident (LOCA). The reduced | | available NPSH may have effected the ability of the pumps to satisfy their | | required design safety function during previous periods of plant operation. | | Recirculation mode operation of these pumps is required by Technical | | Specifications in Mode 3 (hot standby) and above. Therefore, this condition | | has no adverse implications for the present plant condition at Mode 5. | | Evaluation of test results is continuing. | | | | The NRC Resident Inspector was notified of this event by the licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 38478 | +------------------------------------------------------------------------------+ *** NOT FOR PUBLIC DISTRIBUTION *** +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 11/07/2001| | UNIT: [] [2] [] STATE: IL |NOTIFICATION TIME: 21:31[EST]| | RXTYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 11/07/2001| +------------------------------------------------+EVENT TIME: 20:04[CST]| | NRC NOTIFIED BY: DEAGLE |LAST UPDATE DATE: 11/07/2001| | HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |R3 IRC TEAM MANAGER R3 | |10 CFR SECTION: | | |ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | |2 A/R Y 8 Power Operation |0 Hot Shutdown | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC REACTOR SCRAM | | | | Reactor power level was at 8% after coming out of a refueling outage when a | | 1/2 scram signal was received. Approximately 2 minutes after receiving the | | 1/2 scram signal, while investigating the cause of the 1/2 scram signal, | | another 1/2 scram signal was received which initiated a fully reactor scram | | from 8% reactor power. All rods fully inserted into the core. The initial | | shrink of reactor vessel water level from plus 30 inches to plus 10 inches | | was due to the reactor scram. Group 2, drywell isolation valves, and Group | | 3, reactor water cleanup, isolations were caused by reactor vessel water | | level decreasing. Main Steam Isolation Valves were closed to maintain | | control of reactor vessel pressure, very little decay heat in the core. | | Reactor pressure is currently 562psi and reactor feed pumps are maintaining | | proper reactor vessel water level. All emergency core cooling systems are | | fully operable if needed. The emergency diesel generators are fully | | operable if needed and the electrical grid is stable. The licensee at this | | time does not know what signal initiated the 1/2 scram signals. | | Investigation is in progress. | | | | The NRC Resident Inspector will be notified by the licensee of this event. | +------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021