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
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|Power Reactor |Event Number: 38474 |
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!!!!! This event is a security event. Contact HOO for details. !!!!!
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|Power Reactor |Event Number: 38475 |
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| 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 |
| | |
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EVENT TEXT
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| 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. |
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|General Information or Other |Event Number: 38476 |
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*** NOT FOR PUBLIC DISTRIBUTION ***
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| 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 |
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| NRC NOTIFIED BY: LYNCH REG 3/GULCZYNSKI | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
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EVENT TEXT
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| 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. |
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|Power Reactor |Event Number: 38477 |
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*** NOT FOR PUBLIC DISTRIBUTION ***
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| 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 | |
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| | |
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+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
| | |
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EVENT TEXT
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| 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. |
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|Power Reactor |Event Number: 38478 |
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*** NOT FOR PUBLIC DISTRIBUTION ***
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| 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| |
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| | |
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+-----+----------+-------+--------+-----------------+--------+-----------------+
|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 |
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EVENT TEXT
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| 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. |
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Page Last Reviewed/Updated Thursday, March 25, 2021