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Event Notification Report for February 2, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           02/01/2000 - 02/02/2000

                              ** EVENT NUMBERS **

36648  36649  36650  36651  36652  

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|Power Reactor                                    |Event Number:   36648       |
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| FACILITY: SAINT LUCIE              REGION:  2  |NOTIFICATION DATE: 02/01/2000|
|    UNIT:  [1] [2] []                STATE:  FL |NOTIFICATION TIME: 09:27[EST]|
|   RXTYPE: [1] CE,[2] CE                        |EVENT DATE:        02/01/2000|
+------------------------------------------------+EVENT TIME:        07:40[EST]|
| NRC NOTIFIED BY:  STEVE MERRILL                |LAST UPDATE DATE:  02/01/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CAUDLE JULIAN        R2      |
|10 CFR SECTION:                                 |                             |
|APRE 50.72(b)(2)(vi)     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 TO THE FLORIDA DEPARTMENT OF THE ENVIRONMENT INVOLVING A GREEN  |
| SEA TURTLE FOUND IN THE INTAKE CANAL                                         |
|                                                                              |
| "AT APPROXIMATELY 0740 EST ON 2/1/00, A JUVENILE GREEN SEA TURTLE WAS        |
| RESCUED FROM THE PLANT'S INTAKE CANAL.  THE TURTLE WAS ALIVE BUT IN NEED OF  |
| REHABILITATION.  AS REQUIRED BY THE PLANT'S SEA TURTLE PERMIT, THE FLORIDA   |
| DEPARTMENT OF ENVIRONMENTAL PROTECTION WAS NOTIFIED OF THE EVENT."           |
|                                                                              |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR.                            |
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|General Information or Other                     |Event Number:   36649       |
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| REP ORG:  TEXAS BUREAU OF RAD CONTROL          |NOTIFICATION DATE: 02/01/2000|
|LICENSEE:  TECHNICAL WELDING LABORATORY INC     |NOTIFICATION TIME: 17:42[EST]|
|    CITY:  PASADENA                 REGION:  4  |EVENT DATE:        01/18/2000|
|  COUNTY:                            STATE:  TX |EVENT TIME:             [CST]|
|LICENSE#:  L02187                AGREEMENT:  Y  |LAST UPDATE DATE:  02/01/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |CLAUDE JOHNSON       R4      |
|                                                |JOE HOLONICH         NMSS    |
+------------------------------------------------+FRANK CONGEL         IRO     |
| NRC NOTIFIED BY:  TIM HOPKINS (by fax)         |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|BAE1 20.2202(b)(1)       PERS OVEREXPOSURE      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| TEXAS INCIDENT #7568 - RADIOGRAPHER RECEIVED A 1999 ANNUAL EXPOSURE OF 5.01  |
| REM                                                                          |
|                                                                              |
| On 01/18/00 the licensee received its film badge report from Atomic Energy   |
| Industrial Laboratory showing that an employee had exceeded the allowable    |
| occupational dose limit of 5 rems for the year ending 12/31/99.  In          |
| following the Technical Welding Laboratory (TWL) radiation safety program    |
| and their operating and emergency procedures, the employee was notified of   |
| his exposure.  In addition, he was brought into the office and reviewed      |
| TWL's ALARA program to ensure that he understands his responsibilities       |
| according to Texas State regulations and TWL's operating and emergency       |
| procedures.                                                                  |
|                                                                              |
| After interviewing the employee and listening to his explanation of possible |
| causes for the amount of radiation he received, it was determined that the   |
| employee needs to pay more attention to ALARA concerns in the future.        |
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|General Information or Other                     |Event Number:   36650       |
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| REP ORG:  IL DEPARTMENT OF NUCLEAR SAFETY      |NOTIFICATION DATE: 02/01/2000|
|LICENSEE:  UNKNOWN                              |NOTIFICATION TIME: 18:00[EST]|
|    CITY:                           REGION:  3  |EVENT DATE:        01/28/2000|
|  COUNTY:                            STATE:  IL |EVENT TIME:             [CST]|
|LICENSE#:  GL#9223308            AGREEMENT:  Y  |LAST UPDATE DATE:  02/01/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |TONY VEGEL           R3      |
|                                                |JOE HOLONICH         NMSS    |
+------------------------------------------------+FRANK CONGEL         IRO     |
| NRC NOTIFIED BY:  STEVE COLLINS (by E MAIL)    |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| MISSING THICKNESS GAUGE CONTAINING RADIOACTIVE SOURCE                        |
|                                                                              |
| The individual responsible for a Generally Licensed device reported on       |
| 01/28/00 that he noticed the device containing a radioactive source was      |
| missing from the facility.  The device was removed by some unauthorized      |
| person or persons.  He noticed it missing when he attempted to perform a     |
| test for leakage.  The Illinois company changed ownership within the last    |
| two weeks.  The facility location and most personnel remain the same.  The   |
| radioactive source was registered with the Illinois Department of Nuclear    |
| Safety on 09/05/96 (GL #9223308).  The source is 150 mCi of Am-241 in a NDC  |
| Model 103 thickness gauge with serial number 11300.  This device was used to |
| measure thickness of plastic film.  The device is stainless steel            |
| approximately eight inches long and 1-1/4 to 1-1/2 inches in diameter.  The  |
| SS&D sheet (CA0471D102B) indicates a maximum radiation level of 5 mR/hour at |
| one foot with the shutter open and 185 mR/hour near contact with the shutter |
| open.  With the shutter closed, the maximum radiation level is 0.1 mR/hour   |
| at one inch and less than 0.75 mR/hour near contact.                         |
|                                                                              |
| The individual had searched the entire plant on 01/28/00, including the      |
| roof, in an attempt to locate the device.  A police report has been filed.   |
|                                                                              |
| On 02/01/00, IL Department of Nuclear Safety staff personnel performed       |
| surveys in an attempt to locate the device and its source but did not find   |
| them.                                                                        |
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+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36651       |
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| FACILITY: WNP-2                    REGION:  4  |NOTIFICATION DATE: 02/01/2000|
|    UNIT:  [2] [] []                 STATE:  WA |NOTIFICATION TIME: 18:49[EST]|
|   RXTYPE: [2] GE-5                             |EVENT DATE:        02/01/2000|
+------------------------------------------------+EVENT TIME:        12:25[PST]|
| NRC NOTIFIED BY:  J. McBRIDE                   |LAST UPDATE DATE:  02/01/2000|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CLAUDE JOHNSON       R4      |
|10 CFR SECTION:                                 |                             |
|AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| A condition that alone could have caused the loss of initiation capability   |
| of an engineered safety feature.                                             |
|                                                                              |
| At 1038 PST on 01/31/00, the division 2 low condenser vacuum main steam      |
| isolation initiation channel B was found to trip at approximately 2.4 inches |
| Hg vacuum during the performance of plant technical specification            |
| surveillance test.  This was less than the plant technical specification     |
| allowable value of greater than or equal to 7.2 inches Hg vacuum.  The       |
| channel was declared inoperable and entry into plant technical specification |
| limiting condition of operation (LCO) 3.3.6.1.A was made for the channel.    |
| Channel B was then adjusted to plant technical specification tolerance per   |
| approved plant procedures and returned to service.  LCO 3.3.6.1.A was then   |
| exited at 1135 PST on 01/31/00.                                              |
|                                                                              |
| At 1310 PST on 01/31/00, the division 2 low condenser vacuum main steam      |
| isolation initiation channel D was found to trip at approximately 2.8 inches |
| Hg vacuum during the performance of a plant technical specification          |
| surveillance test.  This was less than the plant technical specification     |
| allowable value of greater than or equal to 7.2 inches Hg vacuum.  The       |
| channel was declared inoperable and entry into plant technical specification |
| LCO 3.3.6.1.A was made for the channel.  Channel D was then adjusted to      |
| plant technical specification tolerance per approved plant procedures and    |
| returned to service.  LCO 3.3.6.1.A was then exited at 1335 PST on           |
| 01/31/00.                                                                    |
|                                                                              |
| A problem evaluation request was initiated on 01/31/00 to investigate the    |
| cause of the setpoint problem. Preliminary investigation determined that on  |
| 11/10/99 the pressure switches had been miscalibrated during the previous    |
| surveillance due to a calibration equipment problem.  The division 1 low     |
| condenser vacuum main steam isolation initiation pressure switch setpoints   |
| were verified to be in compliance with plant technical specifications.       |
|                                                                              |
| At 1225 PST on 02/01/00, plant system engineering determined, based on       |
| engineering judgement, that a loss of engineered safety feature initiation   |
| capability had occurred since the time that the pressure switches were       |
| miscalibrated and informed the control room staff.  The control room staff   |
| performed an independent review and concurred with the assessment.           |
| Investigation into the cause of this condition will continue.                |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
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+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36652       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: THREE MILE ISLAND        REGION:  1  |NOTIFICATION DATE: 02/01/2000|
|    UNIT:  [1] [] []                 STATE:  PA |NOTIFICATION TIME: 23:26[EST]|
|   RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP            |EVENT DATE:        02/01/2000|
+------------------------------------------------+EVENT TIME:        22:24[EST]|
| NRC NOTIFIED BY:  BLAIR                        |LAST UPDATE DATE:  02/01/2000|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |TONY DIMITRIADIS     R1      |
|10 CFR SECTION:                                 |FRANK CONGEL         IRO     |
|NINF                     INFORMATION ONLY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| INFORMATION CALL INVOLVING A NON-CREDIBLE PLANT THREAT.                      |
|                                                                              |
| CONTACT THE NRC OPERATIONS CENTER FOR ADDITIONAL DETAILS.                    |
|                                                                              |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR.                            |
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