U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
05/19/2003 - 05/20/2003
** EVENT NUMBERS **
39680 39850 39857 39858 39859 39860 39861 39862
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 39680 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CALLAWAY REGION: 4 |NOTIFICATION DATE: 03/19/2003|
| UNIT: [1] [] [] STATE: MO |NOTIFICATION TIME: 18:16[EST]|
| RXTYPE: [1] W-4-LP |EVENT DATE: 03/19/2003|
+------------------------------------------------+EVENT TIME: 11:04[CST]|
| NRC NOTIFIED BY: E. HENSEN |LAST UPDATE DATE: 05/19/2003|
| HQ OPS OFFICER: MIKE RIPLEY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |CLAUDE JOHNSON R4 |
|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 Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| HATCH MODIFICATION COULD HAVE IMPACTED COMPLETION OF A CONTROL ROOM |
| EVACUATION |
| |
| "At 1104, 3/19/03, while operating at 100% power, Callaway Plant discovered |
| that a modification performed on an equipment hatch impacted the ability to |
| complete a Control Room evacuation in the event of a fire. The modification |
| had installed a hatch in a floor penetration between elevations that had a |
| latching mechanism installed on the bottom side of the hatch but the |
| associated T-handle was not initially installed on top of the hatch. The |
| latch mechanism could still be operated from the top via a large opening in |
| the hatch where a ladder passed through the hatch. This modification could |
| have resulted in the inability to access the area and valves below the hatch |
| that would require manipulation during a Control Room evacuation. When |
| this problem was identified, a T-handle was installed on top of the hatch |
| for operating the latching mechanism and resolved the situation. |
| |
| "This event affects our commitment for the Control Room Fire Safe Shutdown |
| analysis and is being reported as an unanalyzed condition per |
| 10CFR50.72(b)(3)(ii)(B)." |
| |
| The licensee has notified the NRC Resident Inspector. |
| |
| Notified R4DO (C. Johnson) |
| |
| * * * RETRACTION ON 5/19/03 AT 1451 EDT FROM TIM HOLLAND TO E. THOMAS * * * |
| |
| "This event is being retracted. Upon further Engineering evaluation, it was |
| determined that there was sufficient time to allow using an alternate route |
| to access and operate the valve located on the elevation below the equipment |
| hatch. Thus this event did not represent an unanalyzed condition and is not |
| reportable." |
| |
| Notified R4DO (T. Pruett) |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 39850 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: TEXAS DEPARTMENT OF HEALTH |NOTIFICATION DATE: 05/15/2003|
|LICENSEE: BLAZER INDUSTRIAL RADIOGRAPHY |NOTIFICATION TIME: 12:18[EDT]|
| CITY: PASADENA REGION: 4 |EVENT DATE: 05/14/2003|
| COUNTY: STATE: TX |EVENT TIME: 18:48[CDT]|
|LICENSE#: LO4619 AGREEMENT: Y |LAST UPDATE DATE: 05/16/2003|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |WILLIAM JOHNSON R4 |
| |TOM ESSIG NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: HELEN WATKINS | |
| HQ OPS OFFICER: ERIC THOMAS | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| AGREEMENT STATE REPORT |
| |
| The licensee reported a potential overexposure to a radiographer who was |
| x-raying some pipes at a worksite. After completing a section of piping, |
| the radiographer should have cranked his source back in, but was interrupted |
| by another technician and left his work area. When he returned, the |
| radiographer changed out his film, and moved the guide tube to another |
| section of piping to begin more x-rays. At this point, he realized that his |
| survey meter had pegged high, and remembered that he had not cranked the |
| source back in prior to moving it. He proceeded to immediately crank the |
| source back to its fully shielded position. The exact time and distance |
| from the source for the radiographer's exposure is unknown, and the licensee |
| is attempting to re-create the scenario. |
| |
| The source was 26 Curies of Iridium 192, model number INC-32. The serial |
| number is unknown at this time. A preliminary investigation by the licensee |
| estimates the radiographer's exposure to 800-900 millirem whole body. There |
| is currently no exposure estimate for his hands/extremities. |
| |
| The radiographer's badge was sent off for processing. Results will be |
| reported on 5/16/03 to the NRC. The Texas Department of Health is sending |
| an additional inspector to the site to investigate. |
| |
| |
| * * * UPDATE ON 5/16/03 @ 1120 BY WATKINS TO GOULD * * * |
| |
| Blazer Industrial Radiography brought in a consultant to perform preliminary |
| dose calculations for the whole body and the right hand of the radiographer. |
| The results were 1.3R for the whole body and 37.1R for the right hand, |
| neither of which exceeds the annual regulatory limit. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39857 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 05/19/2003|
| UNIT: [1] [] [] STATE: MA |NOTIFICATION TIME: 05:57[EDT]|
| RXTYPE: [1] GE-3 |EVENT DATE: 05/19/2003|
+------------------------------------------------+EVENT TIME: 04:24[EDT]|
| NRC NOTIFIED BY: MARTIN MANPENFEL |LAST UPDATE DATE: 05/19/2003|
| HQ OPS OFFICER: HOWIE CROUCH +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |BRIAN MCDERMOTT R1 |
|10 CFR SECTION: |TERRY REIS NRR |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA|RICHARD WESSMAN IRO |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 A/R Y 3 Startup |0 Startup |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR SCRAM RESULTING IN PRIMARY CONTAINMENT AND REACTOR |
| BUILDING ISOLATIONS |
| |
| At 0424 EDT, during startup operations, the Main Turbine Bypass valves |
| unexpectedly opened and depressurized the reactor vessel. After |
| depressurization, the reactor level increased due to swell and caused an |
| automatic reactor scram. Additionally, there was a Reactor Building |
| Isolation Signal and Group I, II, and VI Primary Containment Isolation |
| Signal generated. Immediately after the automatic scram, five control rods |
| failed to insert into the core. Plant operations personnel performed |
| actions in accordance with their Emergency Operating Procedures to drive the |
| control rods into the core. According to the licensee, adequate shutdown |
| margin was always maintained. |
| |
| The plant electrical system is stable with plant equipment being powered |
| from offsite and the startup transformer. Reactor pressure and level are |
| being maintained via steam line drains to the main condenser. |
| |
| Troubleshooting of the Main Turbine Bypass valves/control system is in |
| progress. |
| |
| The licensee will be notifying the NRC Resident Inspector. |
| |
| * * * UPDATE ON 5/19/03 @ 0957 EDT FROM ERIC OLSON TO CROUCH * * * |
| |
| The following clarification of the above information was received from the |
| licensee via facsimile: |
| |
| "At 04:24 EDT, during startup operations, the Main Turbine Bypass Valves |
| failed open. At the beginning of the event reactor pressure was |
| approximately 880 psig. When the Main Turbine Bypass Valves opened, reactor |
| pressure lowered to approximately 820 psi and reactor water level swelled |
| (due to voiding) from 28 inches to approximately 55 inches. This resulted |
| in a Group I PCIS [Primary Containment Isolation Signal] being generated as |
| designed and automatically closing the MSIV's [Main Steam Isolation Valves]. |
| MSIV closure terminated the depressurization, however initiated an automatic |
| RPS [Reactor Protection System] signal as designed. Termination of |
| depressurization resulted in reactor level lowering to approximately 7 |
| inches which in turn initiated a Group II (Containment Isolation) and Group |
| VI (Reactor Water Cleanup Isolation) PCIS signals. All rods inserted during |
| the scram, however five control rods went beyond full in. Actions were |
| taken in accordance with EOP's [Emergency Operating Procedures] and plant |
| operating procedures to verify the five control rods were beyond full in. |
| This is an indication issue with control rods that can occur when a scram |
| signal is present and the Control Rod Drive System charging water flow |
| drives the control rods beyond the [zero] and full in reed switches. |
| |
| "The plant electrical system is stable with plant equipment being powered |
| from offsite power via the startup transformer. Reactor pressure is being |
| maintained by steam line drains to the main condenser. Reactor water level |
| is being maintained with normal feed and condensate system. |
| |
| "Troubleshooting of the Main Turbine Bypass Valve/Control system is in |
| progress. |
| |
| "The [NRC] Resident Inspector has been notified." |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39858 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: KEWAUNEE REGION: 3 |NOTIFICATION DATE: 05/19/2003|
| UNIT: [1] [] [] STATE: WI |NOTIFICATION TIME: 09:43[EDT]|
| RXTYPE: [1] W-2-LP |EVENT DATE: 05/19/2003|
+------------------------------------------------+EVENT TIME: 05:18[CDT]|
| NRC NOTIFIED BY: JONATHAN ROBB |LAST UPDATE DATE: 05/19/2003|
| HQ OPS OFFICER: HOWIE CROUCH +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |ANNE MARIE STONE R3 |
|10 CFR SECTION: | |
|ASHU 50.72(b)(2)(i) PLANT S/D REQD BY TS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |97 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| PLANT COMMENCED TECH SPEC REQUIRED SHUTDOWN |
| |
| The following information was received from the licensee via facsimile: |
| |
| "At 0323 [CDT] on May 19th an Individual Rod Position Indication (IRPI) of |
| control bank D exceeded 12 steps from its bank demand position. At 0418 an |
| additional IRPI of control bank D exceeded 12 steps from its bank demand |
| position, at which time the two IRPI indications were declared inoperable. |
| At 0518 the plant initiated a Standard Shutdown Sequence as required by the |
| plant's Technical Specifications (TS 3.10.f.2) since two IRPI's in a group |
| were out of service. At 0530 the two IRPI were within 12 steps of the bank |
| demand position and therefore the shutdown sequence was exited. Power is |
| being held at 97% to investigate. |
| |
| "This is a 4-hour. Notification made in accordance with |
| 10CFR50.72(b)(2)(i)." |
| |
| Initially, rod G-3 indication was greater than 12 steps from the bank demand |
| position. Then rod G-11 indication drifted greater than 12 steps from the |
| bank demand position. Currently, power in stable at 97% with G-3 indicating |
| 198 steps and G-11 indicating 204 steps and bank demand position at 202 |
| steps. |
| |
| The licensee has notified the NRC Resident Inspector. |
| |
| * * * UPDATE AT 1540 EDT ON 5/19/03 FROM JONATHAN ROBB TO E.THOMAS * * * |
| |
| Mr. Robb called back to clarify that IRPI indication deviated gradually from |
| bank rod position as the bank was withdrawn, and as power and Tavg were |
| increased. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39859 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 05/19/2003|
| UNIT: [1] [2] [] STATE: FL |NOTIFICATION TIME: 10:32[EDT]|
| RXTYPE: [1] CE,[2] CE |EVENT DATE: 05/19/2003|
+------------------------------------------------+EVENT TIME: 09:05[EDT]|
| NRC NOTIFIED BY: GEORGE TULLIDGE |LAST UPDATE DATE: 05/19/2003|
| HQ OPS OFFICER: HOWIE CROUCH +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |ROBERT HAAG R2 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION | |
|NONR OTHER UNSPEC REQMNT | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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 N 0 Refueling |0 Refueling |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MANATEE TRAPPED IN THE INTAKE CANAL |
| |
| The following information was received from the licensee via facsimile: |
| |
| "Notification being made due to a State Notification (Florida Fish and |
| Wildlife Commission - Bureau of Protected Species) at 0905 [EDT]. (10 CFR |
| 50.72 (b)(2)). |
| |
| "State notification made due to a Manatee trapped in the Intake Canal. The |
| animal appears to be in good condition and State personnel are [en route] to |
| assist in removal and release. |
| |
| "This notification includes requirements per St. Lucie Environmental |
| Protection Plan Technical Specifications, Appendix B, section 4.1. This is |
| a 72-hr notification for unusual occurrence of any species protected by the |
| Endangered Species Act of 1973." |
| |
| The licensee has notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Other Nuclear Material |Event Number: 39860 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: GIBRALTAR PLASTIC CORPORATION |NOTIFICATION DATE: 05/19/2003|
|LICENSEE: GIBRALTAR PLASTIC CORPORATION |NOTIFICATION TIME: 12:58[EDT]|
| CITY: LODI REGION: 1 |EVENT DATE: 05/19/2003|
| COUNTY: STATE: NJ |EVENT TIME: 09:30[EDT]|
|LICENSE#: 29-18454-02 AGREEMENT: N |LAST UPDATE DATE: 05/19/2003|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |ANTHONY DIMITRIADIS R1 |
| |THOMAS ESSIG NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: JERRY WIZA | |
| HQ OPS OFFICER: ARLON COSTA | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|BSUR 20.1906(d)(1) SURFACE CONTAM LEVELS >| |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| SURFACE CONTAMINATION LEVELS ON SOURCE IS GREATER THAN LIMITS |
| |
| The licensee was packaging eleven cesium sources for shipment to Adco |
| Services Incorporated. Upon surveying the sources, the contractor found |
| that one Cs-137 source, Model No.S-4, Serial No.485 indicated field testing |
| contaminations above 0.005 microcuries (exposure rate greater than 0.5 |
| mR/h). The source activity is believed to be approximately 10.2 |
| millicuries. This contaminated source will be packaged as dry waste in |
| certified type A containers and will be shipped for disposal . The cabinet |
| where the source was stored was contaminated and will also be packed and |
| shipped for disposal. |
| |
| The licensee contacted Region 1 (D. White). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Other Nuclear Material |Event Number: 39861 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: ILLINOIS DEPARTMENT OF NUC. SAFETY |NOTIFICATION DATE: 05/19/2003|
|LICENSEE: NELSON LEASING |NOTIFICATION TIME: 16:30[EDT]|
| CITY: WHEELING REGION: 3 |EVENT DATE: 05/17/2003|
| COUNTY: STATE: IL |EVENT TIME: 18:45[CDT]|
|LICENSE#: IL-01828-01 AGREEMENT: Y |LAST UPDATE DATE: 05/19/2003|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |ANNE MARIE STONE R3 |
| | |
+------------------------------------------------+ |
| NRC NOTIFIED BY: JOE KLINGER | |
| HQ OPS OFFICER: ARLON COSTA | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT - STOLEN TROXLER MOISTURE DENSITY GAUGE |
| |
| "On Saturday, May 17, at approximately 1845 hrs a Troxler moisture/density |
| gauge Model # 3440, serial no. 21948, was stolen from a licensee's locked |
| truck while it was parked in a parking lot at 105 N. Des Plaines, in |
| Chicago. The licensee's technician stopped on his way home from work at |
| this location and noticed, upon returning to his vehicle, that the rear hard |
| cover, locked hatch had been broken into. Upon further inspection, the |
| technician noticed that the locked and chained nuclear gauge had been taken. |
| Immediately following this discovery, the Chicago Police Department was |
| notified along with the licensee's Radiation Safety Officer/President, Scott |
| R. Nelson. Scott Nelson mobilized to the crime scene. En route he notified |
| the Illinois Department of Nuclear Safety's Radiological Duty Officer, Larry |
| Haskell. Upon arrival at the scene, Mr. Nelson informed the police of the |
| gauges operations, potential health issues and completed filing a police |
| report. It apparently was evident that the truck was broken into. The |
| police report number is HJ-369907. The station is Area 4." |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39862 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 05/20/2003|
| UNIT: [1] [] [] STATE: NJ |NOTIFICATION TIME: 02:47[EDT]|
| RXTYPE: [1] GE-2 |EVENT DATE: 05/20/2003|
+------------------------------------------------+EVENT TIME: 00:30[EDT]|
| NRC NOTIFIED BY: JEFF DOSTAL |LAST UPDATE DATE: 05/20/2003|
| HQ OPS OFFICER: HOWIE CROUCH +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |ANTHONY DIMITRIADIS R1 |
|10 CFR SECTION: |MICHAEL CASE NRR |
|ASHU 50.72(b)(2)(i) PLANT S/D REQD BY TS |RICHARD WESSMAN IRO |
| |SAM COLLINS NRR |
| |JIM WIGGINS R1 |
| |NEAL PERRY R1 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| PLANT SHUTDOWN REQUIRED BY TECHNICAL SPECIFICATIONS |
| |
| The plant experienced a trip of the "C" 4160 V electrical bus. This |
| condition required entry into multiple technical specifications the most |
| limiting being 3.3.D.5.B due to the loss of the capability to determine the |
| rate of identified containment leakage. This required the reactor to be |
| placed in a shutdown condition within the next 12 hours. |
| |
| The licensee believes that the cause of the "C" bus trip is a fault on the |
| bus that is indicated as a lockout, however, the specific fault is unknown |
| at this time and is under investigation. Due to the faulted bus, the |
| station's emergency diesel generator did not start and will not be able to |
| power any equipment on the "C" bus until the fault is repaired. Significant |
| safety equipment lost due to loss of the bus is as follows: |
| |
| Emergency Service Water pump and Containment spray system #1 |
| Service Water pump #1 |
| Reactor Building Closed Cooling pump #1 |
| Standby Gas Treatment system #1 |
| Core spray and Core spray booster pumps "A" & "D" (4 pumps total) |
| Standby Liquid Control pump #1 |
| Control Rod Drive pump #1 |
| |
| The plant is commencing the required shutdown and expect to be at 60% |
| reactor power by 0430 EDT. |
| |
| The licensee will be notifying the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
