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
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36648 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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 |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 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. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 36649 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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 | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
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. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 36650 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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 | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 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. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36651 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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 |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 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. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|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 |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| INFORMATION CALL INVOLVING A NON-CREDIBLE PLANT THREAT. |
| |
| CONTACT THE NRC OPERATIONS CENTER FOR ADDITIONAL DETAILS. |
| |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021