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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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| 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        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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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 ÁRem/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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| 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    |
|                                                   |                          |
|                                                   |                          |
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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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| 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     |
|                                                   |                          |
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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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