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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        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 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       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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                                   
+------------------------------------------------------------------------------+
| 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       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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                                   
+------------------------------------------------------------------------------+
| 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"                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38047       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 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.                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   38048       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 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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