Event Notification Report for March 20, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
03/17/2000 - 03/20/2000
** EVENT NUMBERS **
36703 36806 36807 36808 36809 36810 36811 36812 36813
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36703 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 02/17/2000|
| UNIT: [] [2] [] STATE: CA |NOTIFICATION TIME: 10:39[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 02/16/2000|
+------------------------------------------------+EVENT TIME: 07:59[PST]|
| NRC NOTIFIED BY: MICHAEL CRAIG |LAST UPDATE DATE: 03/17/2000|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CHARLES MARSCHALL R4 |
|10 CFR SECTION: | |
|NLTR LICENSEE 24 HR REPORT | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| LICENSEE 24-HOUR REPORT DUE TO EXCEEDENCE OF LICENSED POWER LIMIT |
| |
| "On February 16, 2000, at 0759 PST Diablo Canyon Power Plant (DCPP) exceeded |
| the Operating License reactor core power of 3411 megawatts by greater than 2 |
| percent. At 0757 PST with Unit 2 at nominal full reactor power a load |
| transient bypass (LTB) signal was initiated diverting main feedwater around |
| the normal feedwater heaters into the steam generators. During the resultant |
| sudden temperature decrease, reactor power peaked at 103.8% and exceeded the |
| nominal full power for a total of six minutes. |
| |
| "The transient was initiated by utility maintenance personnel during the |
| scheduled performance of instrumentation calibration of circuits associated |
| with the LTB. Technicians performing a calibration inadvertently disturbed |
| an input circuit creating an invalid LTB initiate signal. |
| |
| "The feedwater temperature was rapidly reduced approximately 45 to 50 |
| degrees F. The Final Safety Analysis Report Update Chapter 15, 'Accident |
| Analyses,' Condition II, 'Faults of Moderate Frequency,' Section 15.2.11, |
| 'Sudden Feedwater Temperature Reduction,' provides bounding analysis for |
| this event. The FSAR Update concludes that for temperature drops of less |
| than 73 degrees F that the reactor will remain in operation and the reactor |
| will not go below the minimum DNBR. FSAR Update Section 15.2.11.1 analysis |
| specifically identifies the inadvertent actuation of the LTB as an |
| initiating event bound by the analysis.) |
| |
| "The DCPP Unit 2 Operating License DPR-82, Condition 2.C(1) authorizes PG&E |
| to operate Unit 2 at reactor core power levels not in excess of 3411 |
| megawatts thermal (100% rated power). DPR-82, Condition 2.G, 'Reporting,' |
| requires Emergency Notification System reporting within 24 hours and a |
| written followup report within 30 day in accordance with the procedures |
| described in 10 CFR 50.73(b), (c), and (e). This event will be reported as |
| Licensee Event Report (LER) 2-00-001." |
| |
| ************** UPDATE AT 1328 EST ON 03/17/00 FROM RICH LUCKETT TO LEIGH |
| TROCINE ************** |
| |
| The licensee is retracting this event notification because the NRC had |
| rescinded the requirement to make this report and because the licensee had |
| not received it. On 02/24/00, the NRC issued a letter identifying that |
| Operating License DPR-82, as modified by License Amendment No. 120 on |
| 02/03/00, was not properly issued to the correct license. Consequently, the |
| reporting requirement identified was incorrect, and a report was not |
| required. |
| |
| The licensee notified the NRC resident inspector. The NRC operations |
| officer notified the R4DO (Graves). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36806 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: ARKANSAS NUCLEAR REGION: 4 |NOTIFICATION DATE: 03/16/2000|
| UNIT: [1] [] [] STATE: AR |NOTIFICATION TIME: 18:05[EST]|
| RXTYPE: [1] B&W-L-LP,[2] CE |EVENT DATE: 03/16/2000|
+------------------------------------------------+EVENT TIME: 14:00[CST]|
| NRC NOTIFIED BY: ALAN SMITH |LAST UPDATE DATE: 03/17/2000|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |DAVID GRAVES R4 |
|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 |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| STATE NOTIFICATION REGARDING A PERSONNEL MEDICAL EMERGENCY |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "Arkansas Nuclear One Unit 1 declared a personnel emergency at 1400 [CST] on |
| 03/16/00 due to a contract employee becoming disoriented while performing a |
| routine task on top of an overhead crane that is located outside of the |
| power block. The individual had performed this task previously without |
| incident. The on-site Emergency Medical Team was activated to provide |
| assistance, and the Pope County Emergency Rescue was requested via 911 to |
| provide assistance in the safe removal of the individual from the crane. |
| The individual was subsequently transported to St. Mary's Regional Medical |
| Center for evaluation via local ambulance service. The individual was |
| conscious and in a stable condition following removal from the crane. This |
| event may result in news coverage." |
| |
| The licensee notified the State and the NRC resident inspector. |
| |
| HOO NOTE: This report was updated to reflect notification of the State of |
| Arkansas. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 36807 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: THE FOXBORO COMPANY |NOTIFICATION DATE: 03/17/2000|
|LICENSEE: THE FOXBORO COMPANY |NOTIFICATION TIME: 09:46[EST]|
| CITY: FOXBORO REGION: 1 |EVENT DATE: 03/17/2000|
| COUNTY: STATE: MA |EVENT TIME: [EST]|
|LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 03/17/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |LAURIE PELUSO R1 |
| |JOHN JACOBSON R3 |
+------------------------------------------------+VERN HODGE (by fax) NRR |
| NRC NOTIFIED BY: GEORGE JOHNSON | |
| HQ OPS OFFICER: DICK JOLLIFFE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|CCCC 21.21 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| PART 21 REPORT - LOSS OF GASKET SEAL INTEGRITY ON FOXBORO TRANSMITTER |
| DISPLAY COVERS |
| |
| The Foxboro Company has identified a potential defect with certain Foxboro |
| transmitter display covers manufactured between August 1997 and June 1999. |
| These display covers may not be in compliance with the requirements of leech |
| 1P65 nor NEMA Type-4 Environmental Protection, CENELEC (flameproof), CSA and |
| FM (explosion proof) electrical classification requirements are also |
| affected. |
| |
| A Foxboro investigation was initiated upon the return of a commercial grade |
| display cover which was reported to have lost seal integrity. This |
| investigation found that an unauthorized manufacturing process change |
| occurred between August 4, 1997 (date code 9732) and March 12, 1999 (date |
| code 9911) which allowed an interrupted seal on some portion of the covers |
| manufactured, compromising the environmental and electrical protection |
| requirements. |
| |
| Foxboro is taking immediate action to notify all customers who purchased |
| this product from The Foxboro Company during the time period affected and to |
| provide replacement covers. |
| |
| Indian Point Unit 3 and Cook Units 1 and 2 may be affected by this problem. |
| |
| Foxboro plans to submit a written report to the NRC on this 10 CFR Part 21 |
| Report. |
| |
| (Call the NRC operations center for contact information.) |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36808 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 03/17/2000|
| UNIT: [] [2] [] STATE: NY |NOTIFICATION TIME: 14:15[EST]|
| RXTYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 03/17/2000|
+------------------------------------------------+EVENT TIME: 10:20[EST]|
| NRC NOTIFIED BY: GREG PITTS |LAST UPDATE DATE: 03/17/2000|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |LAURIE PELUSO R1 |
|10 CFR SECTION: | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N N 0 Refueling |0 Refueling |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LOSS OF TWO DIVISION 2 SERVICE WATER SYSTEM (SWP) PUMPS WHILE ONE DIVISION 1 |
| PUMP WAS OUT OF SERVICE |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "At time 1020 hours on 03-17-00, Nine Mile Point Unit 2 entered Special |
| Operating Procedure (SOP) N2-SOP-11 for loss of service water. |
| Specifically, the Division 2 SWP pumps 2SWP*P1B [and] 2SWP*P1D tripped due |
| to a low flow condition. Operations personnel were restoring the Service |
| Water System (SWP) in accordance with procedure N2-PM-@12, attachment 2, to |
| align Division 1, following the Division 1 AC electrical bus outage. A lead |
| was re-landed in the Division 1 SWP logic. A failed component in this |
| Division 1 SWP logic caused the safety-related to non-safety-related |
| isolation valves to isolate. 2SWP*P1C remained in service when the Division |
| 2 pumps tripped. Subsequently, [the] SWP system was restored to a [one] |
| pump per division line-up. Investigation of the failed Division 1 logic |
| component continues at this time." |
| |
| The licensee stated that 2SWP*P1D was restored to service within |
| approximately 20 minutes and that no fuel moves (as part of a fuel shuffle) |
| were ongoing at the time of the event. |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Other Nuclear Material |Event Number: 36809 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: U.S. ARMY |NOTIFICATION DATE: 03/17/2000|
|LICENSEE: U.S. ARMY |NOTIFICATION TIME: 15:53[EST]|
| CITY: ROCK ISLAND REGION: 3 |EVENT DATE: 03/17/2000|
| COUNTY: STATE: IL |EVENT TIME: 12:00[CST]|
|LICENSE#: 12-00722-06 AGREEMENT: Y |LAST UPDATE DATE: 03/17/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |JOHN JACOBSON R3 |
| |AL BELISLE R2 |
+------------------------------------------------+DON COOL NMSS |
| NRC NOTIFIED BY: JEFF HAVENNER |CHARLES MILLER IRO |
| HQ OPS OFFICER: LEIGH TROCINE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| DISCOVERY THAT AN M43A1 CHEMICAL AGENT DETECTOR CELL MODULE CONTAINING 250 |
| �Ci OF AMERICIUM-241 HAD BEEN MISSING FROM FT. BRAGG (NORTH CAROLINA) SINCE |
| APRIL 1996 |
| |
| Late yesterday afternoon (03/16/00), representatives from Ft. Bragg, North |
| Carolina, requested the U.S. Army in Rock Island, Illinois, to help trace |
| files for documentation regarding a cell module that was discovered to be |
| missing from an M43A1 chemical agent detector. (The cell module contained |
| 250 �Ci of americium-241.) The most recent documentation found related to |
| the missing cell module indicated that it was last seen at Ft. Bragg in |
| April of 1996. More recent paperwork has not yet been found. The licensee |
| determined this event to reportable at approximately 1200 CST today |
| (03/17/00). |
| |
| The licensee hypothesized that the M43A1 chemical agent detector may have |
| been turned into a maintenance unit at some point. If the device tested |
| with bad air flow, the maintenance unit could have replaced several items |
| including the cell module. At this time, it is believed that the cell |
| module in question may have been removed (without any paperwork) and that |
| the device may have been returned without a replacement cell module |
| installed. |
| |
| The licensee stated that there does not appear to be any likelihood that the |
| general public will get involved with this issue. The licensee plans to |
| submit a 30-day written report to the NRC Region 3 office. |
| |
| (Call the NRC operations officer for licensee contact information.) |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36810 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 03/17/2000|
| UNIT: [1] [] [] STATE: IL |NOTIFICATION TIME: 16:52[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/17/2000|
+------------------------------------------------+EVENT TIME: 15:15[CST]|
| NRC NOTIFIED BY: TERRENCE DORAZIO |LAST UPDATE DATE: 03/17/2000|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN JACOBSON R3 |
|10 CFR SECTION: | |
|AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 66 Power Operation |66 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AS-FOUND TEST VALUES FOR 8 OF 20 MAIN STEAM SAFETY VALVES WERE OUT OF |
| TOLERANCE HIGH. |
| |
| The preliminary results on the analysis of testing of the main steam safety |
| valves indicates that the plant was operating outside the design bases. A |
| hypothetical turbine trip and loss of load accident would have exceeded the |
| design limit for secondary side pressure. The limit for pressure is 1318.5 |
| psig, and preliminary analysis shows a pressure of 1354 psig. The main |
| steam safety valves have since been set to within 1% of the tolerance of the |
| required setpoints for all 20 valves. This action of resetting the valves |
| returned the plant to within the design basis. |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36811 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 03/17/2000|
| UNIT: [1] [] [] STATE: AZ |NOTIFICATION TIME: 20:26[EST]|
| RXTYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 03/17/2000|
+------------------------------------------------+EVENT TIME: 17:30[MST]|
| NRC NOTIFIED BY: BRAD ROBINSON |LAST UPDATE DATE: 03/18/2000|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |DAVID GRAVES R4 |
|10 CFR SECTION: | |
|AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| DISCOVERY OF NON-CONSERVATIVE RODDED RADIAL PEAKING FACTORS IN THE CORE |
| PROTECTION CALCULATORS AND CORE OPERATING LIMIT SUPERVISORY SYSTEM FOR |
| GROUPS 5 AND P |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "On 03/17/00 at approximately 1730 MST, Palo Verde Engineering determined |
| that Non-conservative Rodded Radial Peaking Factors were installed in the |
| Unit 1 Core Protection Calculators (CPC) and Core Operating Limit |
| Supervisory System for Group 5 and Group P. During the course of normal |
| operations, Group 5 could be inserted into the core in order to compensate |
| for Axial Shape Index. With the current values of Rodded Radial Peaking |
| Factors, Group 5 may be outside of its design basis. Control room operators |
| have been briefed on contingency actions to prevent the unit from operating |
| outside the design basis. At this time, only Unit 1 is impacted, and the |
| investigation is continuing." |
| |
| The licensee plans to notify the NRC resident inspector. |
| |
| |
| * * * UPDATE AT 0009 ON 3/18/00, BY BANKS RECEIVED BY WEAVER * * * |
| |
| "On 3/17/00 at 2122, conservative Rodded Radial Peaking Factors were |
| installed in unit 1, Core Protection Calculators (CPCs channels A, B, & C) |
| and Core Operating Limit Supervisory System for Group 5 and Group P. CPC |
| channel D remains out of service for an un-related issue, however, before |
| the channel is placed back into service, the new conservative Rodded Radial |
| Peaking Factor will be installed." |
| |
| The licensee informed the NRC resident inspector of this update. The |
| Operations Center notified the R4DO(Graves). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36812 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 03/19/2000|
| UNIT: [1] [] [] STATE: NC |NOTIFICATION TIME: 23:31[EST]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 03/19/2000|
+------------------------------------------------+EVENT TIME: 20:00[EST]|
| NRC NOTIFIED BY: MARK SCHALL |LAST UPDATE DATE: 03/19/2000|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |AL BELISLE R2 |
|10 CFR SECTION: | |
|ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| DISCOVERY OF REACTOR COOLANT SYSTEM LEAKAGE ON THE WITHDRAWAL LINE WELDS OF |
| THREE CONTROL ROD DRIVE MECHANISMS DURING HYDRO TESTING |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "EVENT: During [the performance of procedure] OPT-80. 1, Reactor Pressure |
| Vessel ASME Vessel ASME Section XI Pressure Test, reactor coolant system |
| (RCS) pressure boundary leakage was observed on the withdrawal line welds of |
| three control rod drive mechanisms (CRDM). The following CRDMS were noted |
| with leakage: CRDM 06-15 (10 drops/minute at 1030 psig), CRDM 30-15 (20 |
| drops/minute at 1030 psig) and CRDM 14-19 (20 drops/minute at 1030 psig). |
| This leakage is outside the acceptance standard of zero leakage per ASME |
| Section XI, Table IWB-3410-1." |
| |
| "INITIAL SAFETY SIGNIFICANCE EVALUATION: Minimal; the leakage is well |
| within the capacity of available injection systems." |
| |
| "CORRECTIVE ACTION(S): The CRDMs will be removed, and the affected areas |
| repaired prior to reactor startup." |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36813 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CATAWBA REGION: 2 |NOTIFICATION DATE: 03/20/2000|
| UNIT: [] [2] [] STATE: SC |NOTIFICATION TIME: 05:02[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/20/2000|
+------------------------------------------------+EVENT TIME: 04:15[EST]|
| NRC NOTIFIED BY: DON BRADELY |LAST UPDATE DATE: 03/20/2000|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |AL BELISLE R2 |
|10 CFR SECTION: | |
|AMED 50.72(b)(2)(v) OFFSITE MEDICAL | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N N 0 Refueling |0 Refueling |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OFFSITE TRANSPORTATION OF A POTENTIALLY CONTAMINATED WORKER |
| |
| "A vendor support employee was injured due to a fall (approximately 6 to 8 |
| feet) in Unit 2 lower containment. The individual was supporting reactor |
| coolant pump work. Due to injuries, the individual could not be fully |
| frisked for contamination. Until further determination, individual is |
| considered potentially contaminated and is being transported offsite to the |
| local medical facility." |
| |
| The licensee will notify the NRC resident inspector. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021