Event Notification Report for June 4, 2001
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
06/01/2001 - 06/04/2001
** EVENT NUMBERS **
38043 38045 38046 38047 38048
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|Power Reactor |Event Number: 38043 |
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| FACILITY: DUANE ARNOLD REGION: 3 |NOTIFICATION DATE: 06/01/2001|
| UNIT: [1] [] [] STATE: IA |NOTIFICATION TIME: 11:43[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 04/30/2001|
+------------------------------------------------+EVENT TIME: 23:13[CDT]|
| NRC NOTIFIED BY: JOHN KARRICK |LAST UPDATE DATE: 06/01/2001|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |MARK RING R3 |
|10 CFR SECTION: | |
|AINV 50.73(a)(1) INVALID SPECIF SYSTEM A| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
| | |
| | |
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EVENT TEXT
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| INVALID SPECIFIED SYSTEM ACTUATION |
| |
| On April 30, 2001, during a refueling outage and with the primary |
| containment open for personnel access, an unexpected Group III Primary |
| Containment Isolation System (PCIS, EIIS code: JM) actuation occurred. |
| Operators were attempting to remove 24 VDC battery chargers from service |
| (1D51 and 1D52). The section of the procedure used de-energized the whole |
| Division I 24 VDC bus. As a result, the Offgas system radiation monitor |
| (RM4116A) was the de-energized causing an invalid Group III PCIS isolation. |
| |
| This actuation is considered a complete isolation for a Group III signal. |
| |
| The components of the system that were in service at the time of the |
| actuation operated as designed upon receipt of the isolation signal. |
| |
| The licensee notified the NRC resident inspector. |
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|Power Reactor |Event Number: 38045 |
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| FACILITY: COLUMBIA GENERATING STATIREGION: 4 |NOTIFICATION DATE: 06/01/2001|
| UNIT: [2] [] [] STATE: WA |NOTIFICATION TIME: 19:53[EDT]|
| RXTYPE: [2] GE-5 |EVENT DATE: 06/01/2001|
+------------------------------------------------+EVENT TIME: 14:02[PDT]|
| NRC NOTIFIED BY: MYRON BAIRD |LAST UPDATE DATE: 06/01/2001|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: |DALE POWERS R4 |
|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 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| INADVERTENT LOSS OF POWER TO A SAFETY BUS |
| |
| "At 1402 PST, with Columbia Generating Station in Mode 5, a loss of 230 KV |
| offsite source (startup transformer) occurred. This resulted in a loss of |
| voltage to the Div 2 safety related bus (SM-8) which was automatically |
| reenergized by the 115 KV offsite source (backup transformer). All plant |
| systems and components responded as expected. No core alterations were in |
| progress. SM-8 was inoperable but energized at the time of the event due to |
| planned outage maintenance. There was no challenge to the plant shutdown |
| safety plan as a result of this loss of offsite power. The loss of power |
| was a result of a lightning strike offsite on the Bonneville Power |
| Administration (BPA) electrical grid. Restoration of the 230 KV source is |
| pending repairs to damage on the BPA grid. This notification is being made |
| pursuant to 10CFR50.72(b)(3)(iv)(B)(8). This is a valid actuation of an |
| Emergency AC electrical power system." |
| |
| The licensee notified the NRC Resident Inspector. |
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|Fuel Cycle Facility |Event Number: 38046 |
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| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 06/02/2001|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 14:16[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 06/02/2001|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 01:55[CDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 06/02/2001|
| CITY: PADUCAH REGION: 3 +-----------------------------+
| COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION |
|LICENSE#: GDP-1 AGREEMENT: Y |MARK RING R3 |
| DOCKET: 0707001 |LARRY CAMPER NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: MIKE UNDERWOOD | |
| HQ OPS OFFICER: FANGIE JONES | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NONR OTHER UNSPEC REQMNT | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| SAFETY SYSTEM ACTUATION |
| |
| "At 0155 on 06-02-01 the Plant Shift Superintendent (PSS) was notified of an |
| activation of the High Voltage UF6 Release Detection System at the C-315 |
| Tails Withdrawal Building. An Instrument Mechanic was walking down job in |
| preparation for connecting a safety sample buggy to valve SW-53. In order |
| to verify which instrument line was the correct one to connect to the buggy, |
| the mechanic moved the quarter inch copper line. The mechanic reported that |
| the line broke and he saw smoke come from the area. Personnel in the area |
| evacuated to the Area Control Room (ACR) and the Plant Emergency Squad was |
| notified. Subsequent to the release, UF6 Detector heads YE-10-2-6 and |
| YE-10-2-7 alarmed in the ACR. Detector head YE-10-2-6 is a TSR required Q |
| component. The Plant Emergency Squad mitigated the release and the area was |
| turned over to Operations. |
| |
| "High volume air samples and wipe samples by Health Physics personnel |
| indicate no widespread radiological contamination. Contamination was |
| confined to the immediate area at the broken instrument line. Precautionary |
| urine samples submitted by the two employees near the release indicated |
| fluoride uptakes below plant recall limits of 5 mg/L. Analysis for uranium |
| uptake indicated one employee's results were below detectable limits. The |
| other employee's results indicated an uptake 7.3 �g U/L, which is above the |
| plant recall limit of 5.0 �g U/L but below the restriction limit of 40 �g |
| U/L. A follow-up urinalysis will be performed upon this employee upon his |
| return to work at 1900 hours on 6-2-01. |
| |
| "This safety system actuation is reportable to the NRC as required by Safety |
| Analysis Report, section 6.9, table 1 criteria J.2, Safety System actuation |
| due to a valid signal as a 24-hour event notification, |
| |
| "The NRC Resident inspector has been notified of this event. |
| |
| "PGDP Problem Report No. ATR-01-2653; PGDP Event Report No. PAD-2001-022; |
| Event Worksheet Responsible Division: Operations" |
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|Power Reactor |Event Number: 38047 |
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| FACILITY: SEABROOK REGION: 1 |NOTIFICATION DATE: 06/02/2001|
| UNIT: [1] [] [] STATE: NH |NOTIFICATION TIME: 18:03[EDT]|
| RXTYPE: [1] W-4-LP |EVENT DATE: 06/02/2001|
+------------------------------------------------+EVENT TIME: 15:30[EDT]|
| NRC NOTIFIED BY: DENNIS BEMIS |LAST UPDATE DATE: 06/02/2001|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |ERIC REBER R1 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(xi) 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 |
| | |
| | |
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EVENT TEXT
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| OFFSITE NOTIFICATION TO STATE |
| |
| The licensee notified the state public service commission concerning an |
| injured employee who will spend the night in the hospital. A watch stander |
| fell off a ladder. No contamination involved. |
| |
| The licensee intends to notify the NRC Resident Inspector. |
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|Other Nuclear Material |Event Number: 38048 |
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| REP ORG: COMPUTALOG WIRELINE SERVICES |NOTIFICATION DATE: 06/03/2001|
|LICENSEE: COMPUTALOG WIRELINE SERVICES |NOTIFICATION TIME: 21:41[EDT]|
| CITY: FORT WORTH REGION: 4 |EVENT DATE: 06/03/2001|
| COUNTY: STATE: TX |EVENT TIME: 15:30[CDT]|
|LICENSE#: 42-26891-01 AGREEMENT: Y |LAST UPDATE DATE: 06/03/2001|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |DALE POWERS R4 |
| |LARRY CAMPER NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: ERIC ROSENMANN | |
| HQ OPS OFFICER: JOHN MacKINNON | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| DENSITY MEASURING DEVICE FELL INTO THE GULF OF MEXICO. DIVERS WILL RETRIEVE |
| IT MONDAY MORNING. |
| |
| A density measuring device stripped off its wireline an fell into the Gulf |
| of Mexico. The well is between 25 to 50 miles offshore from New Orleans. |
| Chevron Oil owns the Well. Well # 1 in the Gulf of Mexico is located at |
| OCSG 13982. The density measuring device contains a 17mCi cesium-137 source |
| and the source is double encapsulated within another holder. The density |
| measuring device is approximately 1.688 inches in diameter and 40 feet long. |
| The device is at a depth of 123 feet of water on a hard bottom next to the |
| well head (light ocean currents in the area). The make of the density |
| measuring device is a Gammatron, Model "CSV", and its serial number is |
| "V948". A special diving crew will go down in the morning to retrieve the |
| density measuring device. The diving crew has been briefed that they will |
| be retrieving a radioactive source. |
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Page Last Reviewed/Updated Thursday, March 25, 2021