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Event Notification Report for June 6, 2002

                         
                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           06/05/2002 - 06/06/2002

                              ** EVENT NUMBERS **

38956  38965  38966  38967  

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|General Information or Other                     |Event Number:   38956       |
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| REP ORG:  OR DEPT OF HEALTH RAD PROTECTION     |NOTIFICATION DATE:
05/31/2002|
|LICENSEE:  US AIR FORCE                         |NOTIFICATION TIME: 17:28[EDT]|
|    CITY:                           REGION:  4  |EVENT DATE:        05/30/2002|
|  COUNTY:  HOOD RIVER                STATE:  OR |EVENT TIME:        14:00[PDT]|
|LICENSE#:                        AGREEMENT:  Y  |LAST UPDATE DATE:  05/31/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |GARY SANBORN         R4      |
|                                                |E. WILLIAM BRACH     NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  KEVIN SIEBERT                |                             |
|  HQ OPS OFFICER:  MIKE NORRIS                  |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NINF                     INFORMATION ONLY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| LOSS OF LICENSED NUCLEAR MATERIAL IN HELICOPTER ACCIDENT                     |
|                                                                              |
| An Air Force Pave Hawk Helicopter crashed approximately 800 feet from the    |
| summit of Mount Hood.  Each of the 4 rotors contains a 500 microcurie Sr-90  |
| source.  More information will follow as it becomes available.               |
|                                                                              |
| The State will be contacting R4.                                             |
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|Fuel Cycle Facility                              |Event Number:   38965       |
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| FACILITY: WESTINGHOUSE ELECTRIC CORPORATION    |NOTIFICATION DATE:
06/05/2002|
|   RXTYPE: URANIUM FUEL FABRICATION             |NOTIFICATION TIME: 13:10[EDT]|
| COMMENTS: LEU CONVERSION (UF6 to UO2)          |EVENT DATE:        06/05/2002|
|           COMMERCIAL LWR FUEL                  |EVENT TIME:        10:45[EDT]|
|                                                |LAST UPDATE DATE:  06/05/2002|
|    CITY:  COLUMBIA                 REGION:  2  +-----------------------------+
|  COUNTY:  RICHLAND                  STATE:  SC |PERSON          ORGANIZATION |
|LICENSE#:  SNM-1107              AGREEMENT:  Y  |BRIAN BONSER         R2      |
|  DOCKET:  07001151                             |DOUG BROADDUS        NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  B. W. WALLACE                |                             |
|  HQ OPS OFFICER:  LEIGH TROCINE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| NRC BULLETIN 91-01 RESPONSE -- FAILURE TO MAINTAIN A DOUBLE CONTINGENCY     
|
| INVOLVING MATERIAL TRANSFER INTO THE ERBIA MODCON AREA WITHOUT
MOISTURE      |
| RESULTS (24-Hour Report)                                                     |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "Facility                                                                    |
| Westinghouse Electric Company, Commercial Fuel Fabrication Facility,         |
| Columbia SC, low enriched ([<=]5.0 wt. % U-235) PWR fuel fabricator for      |
| commercial light water reactors.                                             |
| License:  SNM-1107."                                                         |
|                                                                              |
| "Time and Date of Event                                                      |
| Approximately 10:45 hours, Wednesday, June 5, 2002."                         |
|                                                                              |
| "Reason for Notification                                                     |
| Thirteen packs of oxidized U3O8 were improperly transferred into the Erbia   |
| Modcon area without proper moisture analysis results."                       |
|                                                                              |
| "Summary of Process                                                          |
| UO2 powder is oxidized to U3O8 to be used as addback in powder blends.       |
| After staying in an oven at a high temperature for over one hour, the        |
| material is screened and put into polypaks.  Each pack is sampled for        |
| moisture and stored pending results of the moisture analysis.  Then the      |
| material is bar code scanned and transferred into the Modcon area using a    |
| polypak elevator interlocked with the moisture analysis results."            |
|                                                                              |
| "As-Found Condition                                                          |
| A summary of the as-found conditions is as follows:                          |
| *  Thirteen packs of material were found to have been taken into the Modcon  |
| area via a freight elevator, bypassing the bar code scanning interlock.  The |
| packs did not have moisture analysis results completed and posted.           |
| *  The packs were immediately removed from the area, and the Nuclear         |
| Criticality Safety (NCS) function was immediately notified.                  |
| *  The material in question was oxidized U3O8, visually dry."                |
|                                                                              |
| "Double Contingency Protection                                               |
| Double contingency protection for the erbia blender and bulk containers is   |
| based on moderation control, that is, (1) prevent greater than 20.48 liters  |
| of water equivalent from becoming available to the mixer or container, and   |
| (2) prevent 20.48 liters of water equivalent from entering the mixer or      |
| container.  It was determined that double contingency protection was         |
| bypassed because, for the 13 packs involved, there were no effective         |
| controls to prevent material with undocumented moisture from being brought   |
| into the Modcon area.  It is also noted that at no time was greater than the |
| safety limit of moderator involved.  Therefore, the incident requires        |
| 24-hour notification in accordance with Westinghouse Operating License (SNM- |
| 1107), paragraph 3.7.3(c.5)."                                                |
|                                                                              |
| "Summary of Activity                                                         |
| *  The packs were immediately removed from the area, and the Nuclear         |
| Criticality Safety (NCS) function was immediately notified.                  |
| *  The Erbia Process Engineer stopped all erbia powder blending              |
| operations."                                                                 |
|                                                                              |
| "Conclusions                                                                 |
| *  There was a loss of double contingency protection.                        |
| *  At no time was greater than a safe limit of moderator involved.           |
| *  At no time was criticality possible.                                      |
| *  At no time was there any risk to the health or safety of any employee or  |
| member of the public.  No exposure to hazardous material was involved.       |
| *  The Incident Review Committee (IRC) determined that this is a safety      |
| significant incident in accordance with governing procedures.  A causal      |
| analysis will be performed."                                                 |
|                                                                              |
| The licensee reported that the information provided via facsimile (and       |
| quoted above) does NOT contain sensitive information.                        |
|                                                                              |
| The licensee notified an onsite NRC Region 2 inspector (Bill Gloersen) and   |
| plans to notify the NRC Region 2 office (Manuel Crespo) and NMSS (Dennis     |
| Morey).                                                                      |
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|Fuel Cycle Facility                              |Event Number:   38966       |
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| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT      |NOTIFICATION DATE: 06/05/2002|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 13:18[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        06/04/2002|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        14:20[CDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  06/05/2002|
|    CITY:  PADUCAH                  REGION:  3  +-----------------------------+
|  COUNTY:  McCRACKEN                 STATE:  KY |PERSON          ORGANIZATION |
|LICENSE#:  GDP-1                 AGREEMENT:  Y  |SONIA BURGESS        R3      |
|  DOCKET:  0707001                              |DOUG BROADDUS        NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  B.  W. WALLACE               |                             |
|  HQ OPS OFFICER:  LEIGH TROCINE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| NRC BULLETIN 91-01 RESPONSE -- FAILURE TO MAINTAIN A DOUBLE CONTINGENCY     
|
| INVOLVING TWO CONTROLS ON THE MASS PARAMETER (24-Hour Report)                |
|                                                                              |
| The following text is a portion of a facsimile received from Paducah         |
| personnel:                                                                   |
|                                                                              |
| "A container of improperly exempted uranium hexafluoride compressor parts    |
| was discovered in the C-333 process building which had not been              |
| characterized for storage as a group, in violation of the governing Nuclear  |
| Criticality Safety Approval NCSA GEN-010.  NCSA GEN-010 requires individual  |
| items to be either spaced or grouped.  Grouping is allowed if mass           |
| requirements are met.  These items were not identified as GEN-010 items and  |
| had been stored as an unanalyzed group.  The purpose of the GEN-010          |
| requirement is to ensure that only safe mass items/groups are handled."      |
|                                                                              |
| "The NRC Resident Inspector has been notified of this event."                |
|                                                                              |
| "PGDP Assessment and Tracking Report No. ATR-02-2713; PGDP Event Report No.  |
| PAD-2002-017, Event Worksheet 38966"                                         |
|                                                                              |
| "Responsible Division:  Engineering"                                         |
|                                                                              |
| "SAFETY SIGNIFICANCE OF EVENTS:"                                             |
|                                                                              |
| "Double contingency was not maintained because the independent determination |
| of mass had not been performed.  The independent determination of mass has   |
| since been performed and [was] found to be less than the maximum safe        |
| mass."                                                                       |
|                                                                              |
| "POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO(S) OF HOW           |
| CRITICALITY COULD OCCUR:"                                                    |
|                                                                              |
| "In order for a criticality to be possible, more than a critical mass would  |
| need to be accumulated in an unsafe geometry."                               |
|                                                                              |
| "CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION,
ETC.):"   |
|                                                                              |
| "The controlled parameter is mass."                                          |
|                                                                              |
| "ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE
PROCESS    |
| LIMIT AND % WORST CASE CRITICAL MASS):"                                      |
|                                                                              |
| "A non-destructive analysis was conducted and determined the mass of U235 in |
| the parts was less than 91 grams; the always-safe mass at the assay involved |
| is [    ] grams of U235."                                                    |
|                                                                              |
| "NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND
DESCRIPTION  |
| OF THE FAILURES OR DEFICIENCIES:"                                            |
|                                                                              |
| "Double contingency is maintained by implementing two controls on the mass   |
| parameter."                                                                  |
|                                                                              |
| "The first leg of double contingency is based on determining the mass of the |
| group.  The mass was not determined during the legacy characterization       |
| process.  Therefore, the control was violated."                              |
|                                                                              |
| "The second leg of double contingency is based on independently determining  |
| the mass of the group.  The mass was not determined during the legacy        |
| characterization process; therefore, the control was violated.  Since there  |
| are two controls on one parameter, the mass parameter was not maintained and |
| double contingency was not maintained."                                      |
|                                                                              |
| "Since double contingency is based on two controls on one parameter, double  |
| contingency was not maintained."                                             |
|                                                                              |
| "CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEMS AND WHEN EACH WAS            
 |
| IMPLEMENTED:"                                                                |
|                                                                              |
| "Use the independent NDA results in conjunction with approved plant          |
| procedures to establish and post these items as a GEN-010 group."            |
|                                                                              |
| Paducah personnel reported that the information provided via facsimile (and  |
| quoted above) does NOT contain sensitive information.                        |
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|Power Reactor                                    |Event Number:   38967       |
+------------------------------------------------------------------------------+
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| FACILITY: COOK                     REGION:  3  |NOTIFICATION DATE: 06/06/2002|
|    UNIT:  [1] [] []                 STATE:  MI |NOTIFICATION TIME: 02:51[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        06/05/2002|
+------------------------------------------------+EVENT TIME:        23:00[EDT]|
| NRC NOTIFIED BY:  DUANE COBB                   |LAST UPDATE DATE:  06/06/2002|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          UNUSUAL EVENT         |JAMES CREED          R3      |
|10 CFR SECTION:                                 |STUART RICHARDS      NRR     |
|AAEC 50.72(a) (1) (i)    EMERGENCY DECLARED     |JOSEPH HOLONICH      IRO     |
|                                                |DEPUY                FEMA    |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Hot Shutdown     |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
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| UNIT 1 DECLARED AN UNUSUAL EVENT DUE TO RCS LEAKAGE > 25 GPM DURING         
|
| SURVEILLANCE TESTING                                                         |
|                                                                              |
| "D.C. Cook Unit One declares entry and exit of an Unusual Event due to       |
| Reactor Coolant System leakage of greater than 25 gallons per minute. On     |
| June 5 @ 23:00 while performing an 18 month surveillance [1-IHP-4030-102-017 |
| 'Pressurizer PORV/Actuation Channel Calibration with Valve Operation'] on    |
| the Pressurizer Power Operated Relief Valves (PORVs) an unblocked PORV       |
| lifted and discharged to the Pressure Relief Tank (PRT) for approximately 15 |
| seconds. This lifting discharged approximately 100 gallons to the PRT. The   |
| Initiating Condition for this Unusual Event is Reactor Coolant System        |
| leakage greater than 25 gallons per minute.                                  |
|                                                                              |
| "The plant is and was in Mode 4. Conditions remain stable after manual       |
| isolation of the PORV with the Control Switch of the Block Valve by the      |
| assisting Reactor Operator."                                                 |
|                                                                              |
| The licensee attributed this occurrence to the recently revised procedure    |
| identified above which did not address blocking the other PORVs during       |
| testing.  The licensee informed state and local agencies and the NRC         |
| Resident Inspector.                                                          |
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