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Event Notification Report for April 17, 2003








                    U.S. Nuclear Regulatory Commission

                              Operations Center



                              Event Reports For

                           04/16/2003 - 04/17/2003



                              ** EVENT NUMBERS **



39755  39756  39762  39764  39765  



+------------------------------------------------------------------------------+

|General Information or Other                     |Event Number:   39755       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| REP ORG:  TEXAS DEPARTMENT OF HEALTH           |NOTIFICATION DATE: 04/14/2003|

|LICENSEE:  ALBEMARELE CORPORATION               |NOTIFICATION TIME: 11:34[EDT]|

|    CITY:  PASADENA                 REGION:  4  |EVENT DATE:        04/11/2003|

|  COUNTY:                            STATE:  TX |EVENT TIME:        14:00[CDT]|

|LICENSE#:  L04072-000            AGREEMENT:  Y  |LAST UPDATE DATE:  04/14/2003|

|  DOCKET:                                       |+----------------------------+

|                                                |PERSON          ORGANIZATION |

|                                                |CLAUDE JOHNSON       R4      |

|                                                |JANET SCHLUETER      NMSS    |

+------------------------------------------------+                             |

| NRC NOTIFIED BY:  JAMES OGDEN                  |                             |

|  HQ OPS OFFICER:  RICH LAURA                   |                             |

+------------------------------------------------+                             |

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|NAGR                     AGREEMENT STATE        |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

+------------------------------------------------------------------------------+



                                   EVENT TEXT                                   

+------------------------------------------------------------------------------+

| TEXAS AGREEMENT STATE REPORT FOR FIRE DAMAGED THREE SOURCE HOLDERS           |

|                                                                              |

| "Fire detectors activated in the multi-Product Unit 1 on Friday afternoon,   |

| insulation and sheeting on the unit were damaged by the fire. Three Ohmart   |

| SH-F1 source holders were installed on the unit. Each source holder contains |

| a Cesium-137 source with an estimated activity of 120 millicuries each. The  |

| on-site fire department was notified and extinguished the fire. It was       |

| suspect that the gauges had been engulfed in the fire. However, after        |

| notification to Techstar, an on-site visit for inspection and verification   |

| determined that none of the gauges were burned in the fire but had been      |

| affected by the heat of the fire. It has been explained that the detectors   |

| were damaged. The Techstar firm confirms that all labels are intact and      |

| legible. A leak test was performed on each unit for gross contamination and  |

| a radiation survey and occupancy evaluation was performed. No contamination  |

| was detected. The ion chamber detectors will have to be replaced, as the     |

| greater part of the fire was on the detector side of the vessels. Techstar   |

| placed the three units shutters in the closed position until repairs to the  |

| facility can be made. Estimated time to repair the facility is approximately |

| 10 working days. After repair the ion detectors will be replaced and the     |

| gauges will be tested by Techstar."                                          |

|                                                                              |

| Notified NMSS EO (F. Brown)                                                  |

+------------------------------------------------------------------------------+



+------------------------------------------------------------------------------+

|General Information or Other                     |Event Number:   39756       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| REP ORG:  NV DIV OF RAD HEALTH                 |NOTIFICATION DATE: 04/14/2003|

|LICENSEE:  ACCLAIM MATERIAL TESTING AND INSPECTI|NOTIFICATION TIME: 13:05[EDT]|

|    CITY:  Las Vegas                REGION:  4  |EVENT DATE:        04/10/2003|

|  COUNTY:                            STATE:  NV |EVENT TIME:        17:30[PDT]|

|LICENSE#:  00-11-0470-01         AGREEMENT:  Y  |LAST UPDATE DATE:  04/15/2003|

|  DOCKET:                                       |+----------------------------+

|                                                |PERSON          ORGANIZATION |

|                                                |CLAUDE JOHNSON       R4      |

|                                                |JANET SCHLUETER      NMSS    |

+------------------------------------------------+                             |

| NRC NOTIFIED BY:  STAN MARSHALL                |                             |

|  HQ OPS OFFICER:  ERIC THOMAS                  |                             |

+------------------------------------------------+                             |

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|NAGR                     AGREEMENT STATE        |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

+------------------------------------------------------------------------------+



                                   EVENT TEXT                                   

+------------------------------------------------------------------------------+

| LOST MOISTURE DENSITY GAUGE                                                  |

|                                                                              |

| A Campbell Pacific Nuclear Model MC-DR1P s/n MD20200680 moisture/density     |

| gauge was lost out of a transport vehicle on 4/10/03.  The gauge contains 10 |

| millicuries of Cs-137 and 50 millicuries of Am-241:Be.  The gauge was not    |

| properly secured in the transport vehicle prior to transportation.           |

| Licensee's corrective actions included a meeting with all gauge users on     |

| 4/14/03, and issuing an orange cone to be put in the back of each transport  |

| vehicle to remind users to secure gauges before transport.  Local law        |

| enforcement was notified of this event.  The licensee may issue a violation  |

| letter for failure to follow procedures.                                     |

|                                                                              |

| Notified R4 DO (C. Johnson) and NMSS EO (F. Brown)                           |

|                                                                              |

| *****UPDATE ON 4/15/03 AT 10:40 FROM MARSHALL TO LAURA*****                  |

|                                                                              |

| The licensee called at 6:15 pm PDT to advise the gauge had been found on     |

| April 14 in the middle of the street in vicinity of where it had been lost.  |

| It had taken the finder some time to track down the owner of the gauge. The  |

| gauge case was missing but the gauge was reported to be undamaged.           |

|                                                                              |

| Notified the R4DO (Johnson) and NMSS (ESSIG).                                |

+------------------------------------------------------------------------------+



+------------------------------------------------------------------------------+

|Fuel Cycle Facility                              |Event Number:   39762       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT      |NOTIFICATION DATE: 04/16/2003|

|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 06:32[EDT]|

| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        04/15/2003|

|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        09:45[CDT]|

|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  04/16/2003|

|    CITY:  PADUCAH                  REGION:  3  +-----------------------------+

|  COUNTY:  McCRACKEN                 STATE:  KY |PERSON          ORGANIZATION |

|LICENSE#:  GDP-1                 AGREEMENT:  Y  |THOMAS KOZAK         R3      |

|  DOCKET:  0707001                              |TOM ESSIG            NMSS    |

+------------------------------------------------+                             |

| NRC NOTIFIED BY:  TOM WHITE                    |                             |

|  HQ OPS OFFICER:  MIKE RIPLEY                  |                             |

+------------------------------------------------+                             |

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|NBNL                     RESPONSE-BULLETIN      |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

+------------------------------------------------------------------------------+



                                   EVENT TEXT                                   

+------------------------------------------------------------------------------+

| BULLETIN 91-01 24 HOUR REPORT FOR CRITICALITY CONTROL                        |

|                                                                              |

| "At 0945 on 4/15/03, the Plant Shift Superintendent (PSS) was notified that  |

| SX/WA (Seal Exhaust/Wet Air) pump components were discovered outside the     |

| C-337 SX/WA FCA (Fissile Control Area) not properly tagged and spaced, as    |

| required by NCSA CAS-007.  Tagging of items removed from the SX/WA FCA       |

| ensure proper identification of potential fissile components requiring       |

| spacing controls.  Components include used oil solenoid valve, 3 inch elbow, |

| oil mist filter crushing tool, 3 gas ballast pipes and valves, oil level     |

| sight glass, oil or water flow sight glass and copper tubing.  The NRC       |

| Resident Inspector has been notified of this event."                         |

|                                                                              |

| SAFETY SIGNIFICANCE OF EVENTS:  While an approved analysis does exist for    |

| subcriticality of this upset condition, a control relied upon for double     |

| contingency was violated.                                                    |

|                                                                              |

| POTENTIAL CRITICALITY PATHWAYS INVOLVED:  In order for a criticality to be   |

| possible, a second independent and unlikely event would need to occur        |

| concurrently with the loss of spacing accident.                              |

|                                                                              |

| CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION, ETC):      |

| Double contingency is maintained by implementing controls on interaction and |

| an independent failure.                                                      |

|                                                                              |

| ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL:  Less than the safe |

| mass of uranium at plant maximum assay of 5.5  wt. % U235.                   |

|                                                                              |

| NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION   |

| OF THE FAILURES OR DEFICIENCIES:  The first leg of double contingency relies |

| on interaction. Components removed from a SX/WA FCA shall be spaced a        |

| minimum 2 feet, edge-to-edge from other potentially fissile material or      |

| components, the SX/WA components were spaced less than the required 2 foot   |

| spacing.  Therefore, the control on interaction was violated and the         |

| parameter was lost.                                                          |

|                                                                              |

| The second leg of double contingency is based on the subcriticality of the   |

| loss of spacing.  The improperly spaced components are of small size and     |

| limited uranium loading which are in a configuration that is bounded by      |

| calculations performed for the SX/WA station. Therefore, this leg of double  |

| contingency is maintained.                                                   |

|                                                                              |

| Since the interaction parameter was lost; therefore, the double contingency  |

| principle was not maintained.                                                |

|                                                                              |

| CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEMS AND WHEN EACH WAS IMPLEMENTED:  |

| See remediation guide.                                                       |

+------------------------------------------------------------------------------+



+------------------------------------------------------------------------------+

|Power Reactor                                    |Event Number:   39764       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| FACILITY: OCONEE                   REGION:  2  |NOTIFICATION DATE: 04/16/2003|

|    UNIT:  [1] [2] [3]               STATE:  SC |NOTIFICATION TIME: 14:14[EDT]|

|   RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-L|EVENT DATE:        04/16/2003|

+------------------------------------------------+EVENT TIME:        11:45[EDT]|

| NRC NOTIFIED BY:  RANDY TODD                   |LAST UPDATE DATE:  04/16/2003|

|  HQ OPS OFFICER:  ERIC THOMAS                  +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |THOMAS DECKER        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          Y       100      Power Operation  |100      Power Operation  |

|2     N          Y       100      Power Operation  |100      Power Operation  |

|3     N          Y       82       Power Operation  |82       Power Operation  |

+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   

+------------------------------------------------------------------------------+

| FITNESS FOR DUTY                                                             |

|                                                                              |

| "Event:  At 11:45 on April 16, 2003, the Oconee Medical Review Officer       |

| notified the affected individual of a confirmed positive test result         |

| following a random Fitness For Duty (FFD) screening test.  The confirmed     |

| positive was for alcohol.  The individual being tested is a Supervisor in    |

| the Radiation Protection Section.                                            |

|                                                                              |

| "Initial Safety Significance:  None:  There is no reason to believe there    |

| has been any adverse consequences from this event.  The employee had been in |

| meetings all morning until he reported for the random screening test.  This  |

| event is not considered to have impacted operation of the plant in any way.  |

|                                                                              |

| "Corrective Action(s):  The immediate action was to place the individual's   |

| security badge on FFD hold, which will deny access to the protected area.    |

| Also, the individual was referred for immediate assessment by the Employee   |

| Assistance Program counselor, who will determine the extent of additional    |

| actions."                                                                    |

|                                                                              |

| The licensee notified the NRC Resident Inspector.                            |

+------------------------------------------------------------------------------+



+------------------------------------------------------------------------------+

|Power Reactor                                    |Event Number:   39765       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| FACILITY: QUAD CITIES              REGION:  3  |NOTIFICATION DATE: 04/16/2003|

|    UNIT:  [] [2] []                 STATE:  IL |NOTIFICATION TIME: 15:46[EDT]|

|   RXTYPE: [1] GE-3,[2] GE-3                    |EVENT DATE:        04/16/2003|

+------------------------------------------------+EVENT TIME:        13:59[CDT]|

| NRC NOTIFIED BY:  MIKE WAGNER                  |LAST UPDATE DATE:  04/16/2003|

|  HQ OPS OFFICER:  ERIC THOMAS                  +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          ALERT                 |THOMAS KOZAK         R3      |

|10 CFR SECTION:                                 |BOB DENNIG           NRR     |

|AAEC 50.72(a) (1) (i)    EMERGENCY DECLARED     |CLAUDE JOHNSON       R4      |

|                                                |GILL                 DHS     |

|                                                |GARY BELCHER         FEMA    |

|                                                |SAL MORRONEN         DOE     |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|                                                   |                          |

|2     N          Y       100      Power Operation  |0        Hot Shutdown     |

|                                                   |                          |

+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   

+------------------------------------------------------------------------------+

| ALERT DECLARED                                                               |

|                                                                              |

| "At 1359 CDT, Quad Cities declared and ALERT condition on Unit 2.  This      |

| ALERT was declared due to a stuck open [power operated] relief valve (3B     |

| PORV).  A manual scram was initiated [at 1337 CDT].  Priorities include      |

| actions to close the 3B relief valve and to maximize Torus cooling.  Note    |

| that the ALERT was declared due to condition FA1 (relief valve stuck open    |

| and Torus temperature."                                                      |

|                                                                              |

| The reactor was scrammed due to a 95 deg F Torus temperature.  All rods      |

| fully inserted on the scram.  The Torus temperature peaked at 118 degrees F, |

| and then started to decrease due to Torus cooling.  The tech spec limit on   |

| Torus temperature is 110 deg F.  Cooldown rate exceeded 100 deg F per hour,  |

| and all MSIVs were closed to limit the cooldown rate.                        |

|                                                                              |

| The NRC Region III Incident response center was fully staffed at 1415 CDT.   |

| The NRC entered Monitoring mode at 1435 CDT, with Region III in the lead.    |

|                                                                              |

| * * * SUMMARY AT 1600 CDT ON 4/16/03 FROM DAVID WASNIACK (EXELON) TO NRC     |

| STAFF * * *                                                                  |

|                                                                              |

| Torus temperature now <110 deg F.  Expect to be in Mode IV by 1900 CDT.  In  |

| order to de-inert the Torus, must have Torus temperature <95 deg F, and have |

| shutdown cooling supplied to the core.  Anticipate 15-16 hours before the    |

| drywell can be accessed to attempt to manually shut the valve.               |

|                                                                              |

| The licensee has attempted to close the PORV from the control room via       |

| several means (switch and pulling control power fuses) and been              |

| unsuccessful.                                                                |

|                                                                              |

| * * * SUMMARY AT 1715 CDT ON 4/16/03 FROM DAVID WASNIACK TO NRC STAFF * * *  |

|                                                                              |

| The licensee is continuing plant and Torus cooldown, and anticipates         |

| terminating the ALERT when the plant is in Mode 4, at approximately 1900     |

| CDT.  Suspected cause of the PORV lifting is a failed pilot.                 |

|                                                                              |

| * * * SUMMARY AT 2130 CDT ON 4/16/03 FROM DAVID WASNIACK TO NRC STAFF * * *  |

|                                                                              |

| Shutdown cooling was established at 2104 CDT.  Current temperature 275 deg   |

| F, cooldown rate is 80 degrees per hour. At 2237 CDT, the licensee declared  |

| that Unit 2 was in Mode 4.                                                   |

|                                                                              |

| * * * SUMMARY AT 2245 CDT ON 4/16/03 FROM DAVID WASNIACK TO NRC STAFF * * *  |

|                                                                              |

| The NRC exited Monitoring mode at 2255 CDT.                                  |

|                                                                              |

| * * * SUMMARY AT 2340 CDT ON 4/16/03 FROM RALPH BASSETT  TO NRC STAFF * * *  |

|                                                                              |

| The licensee terminated the alert at 2251 CDT.  The plant is in Cold         |

| Shutdown Mode 4 with the RCS depressurized and less than 212 deg F.          |

| Notified DHS (Stucky), FEMA (Saunder), DOE (Rick) , USDA (L. Thomas), HHS    |

| (M. Miller), EPA (Flach), NRR EO (S. Black), HQ PAO (W. Beecher), R3 (S.     |

| Reynolds).                                                                   |

+------------------------------------------------------------------------------+





                    

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