Event Notification Report for April 15, 2002
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
04/12/2002 - 04/15/2002
** EVENT NUMBERS **
38707 38844 38848 38849 38850 38851 38852 38853 38854
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 38707 |
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| FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 02/19/2002|
| UNIT: [] [2] [] STATE: PA |NOTIFICATION TIME: 01:27[EST]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 02/18/2002|
+------------------------------------------------+EVENT TIME: 18:15[EST]|
| NRC NOTIFIED BY: JAMES WITTER |LAST UPDATE DATE: 04/12/2002|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |JAMES TRAPP R1 |
|10 CFR SECTION: | |
|AINA 50.72(b)(3)(v)(A) POT UNABLE TO SAFE SD | |
|AINB 50.72(b)(3)(v)(B) POT RHR INOP | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
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EVENT TEXT
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| BOTH EMERGENCY DIESEL GENERATORS INADVERTENTLY MADE INOPERABLE
|
| |
| "On 02/18/02, at 1815 hours, the licensee discovered that the Beaver Valley |
| Unit 2 #1 Emergency Diesel Generator had been rendered inoperable |
| inadvertently, by the posting of a clearance at 1408 hours on 2/14/02. The |
| #2 Emergency Diesel Generator had previously been removed from service for |
| maintenance activities. Upon discovery that the #1 Emergency Diesel |
| Generator was inoperable, action was immediately initiated to restore the #1 |
| Emergency Diesel Generator to Operable status. These actions were completed |
| and the #1 Emergency Diesel Generator was restored to Operable status at |
| 1830 hrs on 02/18/02. |
| |
| "The #1 Diesel Generator was rendered inoperable at 1406 hrs on 02/14/02. |
| During the period of inoperability, the licensee conducted core alterations |
| including core reload during the ongoing ninth refueling outage. During the |
| affected period, there were no challenges to the offsite power sources, and |
| core cooling was maintained. Investigation into this event is ongoing. |
| |
| "This event is being reported under 10CFR50.72(v)(A) and 10CFR50.72(v)(B) as |
| a loss of Safe Shutdown Capability, and RHR Capability, respectively. There |
| were no radiological releases associated with this event," |
| |
| The licensee intends to notify the NRC Resident Inspector. |
| |
| * * * RETRACTION 1314 4/12/2002 FROM TOM COTTER TAKEN BY BOB STRANSKY * * * |
| |
| "Subsequent review and analysis of the event identified that the Unit 2 #1 |
| Emergency Diesel Generator (EDG) retained its capability to fulfil its |
| safety function. During the time that the potential transformer fuses were |
| inadvertently removed from the Unit 2 #1 EDG, the EDG would still have |
| started and accelerated to proper speed and output voltage if a station loss |
| of offsite power had occurred. However, the output breaker would not have |
| automatically closed and the EDG would not have automatically supplied |
| emergency AC power to the Unit 2 A train emergency bus. Control room |
| indications, powered by station DC sources, would have confirmed that the |
| EDG was running at rated speed. Following station procedures, operations |
| personnel would have attempted to locally close the A train EDG output |
| breaker. The EDG output breaker would have closed, the EDG sequencer would |
| have then have been automatically energized, and the required emergency |
| loads would have been automatically sequenced on to the A train emergency |
| bus. It is conservatively estimated that this action would have been |
| completed within approximately 20-30 minutes. Unit 2 Residual Heat Removal |
| (RHR) pumps are not automatically loaded onto an emergency bus for any |
| postulated station loss of offsite power and would have to be manually |
| loaded onto an emergency bus after a EDG is started. The estimated time |
| frame to close the EDG output breaker and to load the RHR pump onto the EDG |
| in this condition for a postulated loss of offsite power showed no |
| significant adverse Unit results. Therefore, the EDG retained its capability |
| to fulfill its safety function. |
| |
| "This event will be reported as a Licensee Event Report pursuant to |
| 10CFR50.73(a)(2)(i)(B)." |
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|General Information or Other |Event Number: 38844 |
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| REP ORG: TEXAS DEPARTMENT OF HEALTH |NOTIFICATION DATE: 04/10/2002|
|LICENSEE: TECHNICAL WELDING LAB INC |NOTIFICATION TIME: 16:29[EDT]|
| CITY: HOUSTON REGION: 4 |EVENT DATE: 04/10/2002|
| COUNTY: HARRIS STATE: TX |EVENT TIME: 04:00[CDT]|
|LICENSE#: L-02187 AGREEMENT: Y |LAST UPDATE DATE: 04/10/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |KRISS KENNEDY R4 |
| |JOHN HICKEY NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: TEXAS DEPT OF HEALTH BRC | |
| HQ OPS OFFICER: GERRY WAIG | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| OVEREXPOSURE TO GAMMA RADIATION |
| |
| The following is taken from a facsimile report: |
| |
| "A radiographer was [radiographing] welds on a vessel shooting with a 35 |
| curie Co-60 source and entered the vessel to change the source location |
| without cranking the source into the shielded position. The radiographer has |
| been taken for blood samples which will be repeated in 72 hours. Initial |
| calculations indicate a possible whole body exposure of 70 rems. Further |
| information forthcoming after investigation scheduled for May 14." |
| |
| The Texas Incident Number for this event is I-7882. |
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|Other Nuclear Material |Event Number: 38848 |
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| REP ORG: BRISTOL-MYERS SQUIBB |NOTIFICATION DATE: 04/12/2002|
|LICENSEE: BRISTOL-MYERS SQUIBB RADIOPHARMACEUTI|NOTIFICATION TIME:
16:15[EDT]|
| CITY: RIO TIADRIS REGION: 2 |EVENT DATE: 04/12/2002|
| COUNTY: STATE: PR |EVENT TIME: [EDT]|
|LICENSE#: 52-25361-01MD AGREEMENT: N |LAST UPDATE DATE: 04/12/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |KEN BARR R2 |
| |FRED BROWN NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: FRANCIS ROY | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|BAD1 20.2202(a)(1) PERS OVEREXPOSURE/TEDE | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| POTENTIAL OVEREXPOSURE OF EXTREMITIES |
| |
| While investigating high ring dosimeter readings for two radiopharmacists |
| involved in dispensing doses of Tc-99m, the licensee discovered that these |
| individuals may have exceeded their occupational dose limits to the |
| extremities for 2001. Ring dosimeter readings of 30-40 rem were recorded for |
| the individuals. During followup investigations, a certified health |
| physicist, using fingertip dosimetry, determined that the individuals were |
| receiving fingertip doses 3 to 7 times higher than those recorded on the |
| ring dosimeters. Therefore, the individuals may have exceeded the annual |
| occupational dose limit of 50 rem to the extremities. |
| |
| The licensee will be providing a report to NRC Region II next week. |
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|General Information or Other |Event Number: 38849 |
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| REP ORG: WYLE LABORATORIES |NOTIFICATION DATE: 04/12/2002|
|LICENSEE: WYLE LABORATORIES |NOTIFICATION TIME: 17:05[EDT]|
| CITY: HUNTSVILLE REGION: 2 |EVENT DATE: 04/12/2002|
| COUNTY: STATE: AL |EVENT TIME: [CDT]|
|LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 04/12/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |VERN HODGE (FAX) NRR |
| | |
+------------------------------------------------+ |
| NRC NOTIFIED BY: EDWARD SMITH (FAX) | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|CCCC 21.21 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| 10 CFR PART 21 REPORT |
| |
| "Pursuant to the 10 CFR Part 21 requirements, this letter notifies the NRC |
| of a Potential Part 21 condition. |
| |
| "An error in irradiation dose units is identified in the attached letter |
| from Georgia Tech letter dated March 15, 2002, which was received by Wyle on |
| April 11, 2002. The error applies to all equipment irradiated with the |
| cobalt-60 sources in the Georgia Tech hot cell from 7/24/1997 to 7/6/2001. |
| Georgia Tech reported radiation doses in units of rads-air (absorbed dose in |
| air) instead of Roentgens. Since one Roentgen is equal to 0.877 rad, the |
| actual dose is less than the reported value. |
| |
| "Wyle will perform an evaluation to determine |
| "1. Wyle projects that include irradiation with the cobalt-60 sources in the |
| Georgia Tech hot cell from 7/24/1997 to 7/6/2001. |
| "2. The actual dose absorbed by equipment in said projects. |
| "3. Whether the actual dose in said projects envelops the customer-specified |
| requirements. |
| |
| "Wyle Laboratories has the capability and chooses to perform the evaluation |
| to determine if a defect exists. It is the responsibility to Wyle |
| Laboratories to inform the purchaser(s), and any affected licensees. |
| |
| "Wyle will complete the specified evaluation of the circumstances within |
| sixty (60) days of discovery of the potential defect. The NRC will be |
| provided a copy of Wyle's evaluation report." |
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|Power Reactor |Event Number: 38850 |
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| FACILITY: VOGTLE REGION: 2 |NOTIFICATION DATE: 04/12/2002|
| UNIT: [1] [2] [] STATE: GA |NOTIFICATION TIME: 17:37[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/12/2002|
+------------------------------------------------+EVENT TIME: 08:38[EDT]|
| NRC NOTIFIED BY: KENNY MIDDLEBROOKS |LAST UPDATE DATE: 04/12/2002|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |KEN BARR R2 |
|10 CFR SECTION: | |
|HFIT 26.73 FITNESS FOR DUTY | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Hot Standby |0 Hot Standby |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| FITNESS FOR DUTY REPORT |
| |
| A contract supervisor tested positive for alcohol use during a for-cause |
| test. The individual's site access has been terminated. Contact the NRC |
| Operations Center for additional information. |
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|Power Reactor |Event Number: 38851 |
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| FACILITY: ARKANSAS NUCLEAR REGION: 4 |NOTIFICATION DATE: 04/12/2002|
| UNIT: [1] [] [] STATE: AR |NOTIFICATION TIME: 18:26[EDT]|
| RXTYPE: [1] B&W-L-LP,[2] CE |EVENT DATE: 04/12/2002|
+------------------------------------------------+EVENT TIME: 16:36[CDT]|
| NRC NOTIFIED BY: JAMES CRABILL |LAST UPDATE DATE: 04/12/2002|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |KRISS KENNEDY R4 |
|10 CFR SECTION: | |
|DDDD 73.71 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
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| SECURITY REPORT |
| |
| Safeguards system degradation related to detection. Immediate compensatory |
| measures taken upon discovery. Contact the NRC Operations Center for |
| additional details. The NRC resident inspector will be informed of this |
| event by the licensee. |
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|Power Reactor |Event Number: 38852 |
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| FACILITY: TURKEY POINT REGION: 2 |NOTIFICATION DATE: 04/13/2002|
| UNIT: [3] [4] [] STATE: FL |NOTIFICATION TIME: 14:51[EDT]|
| RXTYPE: [3] W-3-LP,[4] W-3-LP |EVENT DATE: 04/13/2002|
+------------------------------------------------+EVENT TIME: 13:17[EDT]|
| NRC NOTIFIED BY: MATUSZEWSKI |LAST UPDATE DATE: 04/13/2002|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |KEN BARR R2 |
|10 CFR SECTION: | |
|ACOM 50.72(b)(3)(xiii) LOSS COMM/ASMT/RESPONSE| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3 N Y 100 Power Operation |100 Power Operation |
|4 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| LOSS OF ERDADS/ERDS |
| |
| The licensee reported that the Emergency Response Data Acquisition and |
| Display System (ERDADS) and Emergency Response Data System (ERDS) became |
| inoperable due to the loss of both trains of the Data Link System. The |
| licensee is currently attempting to restore the DLS. The NRC resident |
| inspector will be informed of this notification by the licensee. |
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|Power Reactor |Event Number: 38853 |
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| FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 04/14/2002|
| UNIT: [1] [2] [] STATE: GA |NOTIFICATION TIME: 16:25[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 04/14/2002|
+------------------------------------------------+EVENT TIME: 12:00[EDT]|
| NRC NOTIFIED BY: A. DEES |LAST UPDATE DATE: 04/14/2002|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |KEN BARR R2 |
|10 CFR SECTION: | |
|AMED 50.72(b)(3)(xii) OFFSITE MEDICAL | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| POTENTIALLY CONTAMINATED PERSON TRANSPORTED OFFSITE BY AMBULANCE.
|
| |
| This report is being made to communicate the transportation of a potentially |
| radioactive contaminated person to an offsite medical facility for treatment |
| under 10CFR 50.72 (b)(3)(xii). At 1138 EDT the Unit 1 Control Room was |
| notified that an individual had fallen on the Refueling Floor striking her |
| head on the floor. The First Responders and Health Physics personnel |
| responded to attend the individual and requested that the injured person be |
| transported offsite to the Appling General Hospital in Baxley, Ga. At 1200 |
| EDT the individual was transported offsite via ambulance. The individual |
| left offsite prior to the initial onsite survey for radioactive |
| contamination had been completed. This report is being made since there was |
| a potential for contamination. The initial survey was completed at the |
| hospital and it was determined that neither the individual nor any clothing |
| was contaminated. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
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|Power Reactor |Event Number: 38854 |
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| FACILITY: SEQUOYAH REGION: 2 |NOTIFICATION DATE: 04/15/2002|
| UNIT: [] [2] [] STATE: TN |NOTIFICATION TIME: 02:59[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/15/2002|
+------------------------------------------------+EVENT TIME: 00:16[EDT]|
| NRC NOTIFIED BY: SIMMONS |LAST UPDATE DATE: 04/15/2002|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |KEN BARR R2 |
|10 CFR SECTION: | |
|AESF 50.72(b)(3)(iv)(A) VALID SPECIF SYS ACTUAT| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N N 0 Hot Standby |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| PLANT HAD ESF ACTUATION RESULTING IN AUTOMATIC REPOSITIONING OF AUX
|
| FEEDWATER VALVES. |
| |
| |
| Unit 2 was in mode 3 and stable following the completion of a preplanned |
| shutdown for a refueling outage. The aux feedwater was in service at the |
| time of this actuation. The AFW Level Control Valves had been throttled, |
| the "B" Main Feedwater Pump reset and Feedwater Isolation (FWI) reset to |
| accordance with procedures. The RCS Tavg drifted above 550�F. When the |
| RCS Tavg dropped below 550�F, a FWI signal was generated causing the reset |
| Main Feedwater Pump to trip and the Aux Feedwater valves to reposition open. |
| The Aux Feedwater pumps were already running. An investigation is |
| ongoing. |
| |
| The NRC Resident Inspector was notified. |
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