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Event Notification Report for December 8, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           12/07/2000 - 12/08/2000

                              ** EVENT NUMBERS **

37574  37575  37576  37577  37578  

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|Fuel Cycle Facility                              |Event Number:   37574       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: GLOBAL NUCLEAR FUEL - AMERICAS       |NOTIFICATION DATE: 12/07/2000|
|   RXTYPE: URANIUM FUEL FABRICATION             |NOTIFICATION TIME: 11:43[EST]|
| COMMENTS: LEU CONVERSION (UF6 TO UO2)          |EVENT DATE:        12/06/2000|
|           LEU FABRICATION                      |EVENT TIME:        19:00[EST]|
|           LWR COMMERICAL FUEL                  |LAST UPDATE DATE:  12/07/2000|
|    CITY:  WILMINGTON               REGION:  2  +-----------------------------+
|  COUNTY:  NEW HANOVER               STATE:  NC |PERSON          ORGANIZATION |
|LICENSE#:  SNM-1097              AGREEMENT:  Y  |PAUL FREDRICKSON     R2      |
|  DOCKET:  07001113                             |JOHN HICKEY          NMSS    |
+------------------------------------------------+BRIAN SMITH          NMSS    |
| NRC NOTIFIED BY:  PAULSON                      |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| 24-HOUR NRC 91-01 BULLETIN REPORT INVOLVING LOSS OF MASS AND DENSITY         |
| CONTROLS IN TWO CARRYOVER STORAGE TANKS                                      |
|                                                                              |
| "At approximately 1900 hours on December 6, 2000 GNF-A Operations identified |
| that two tanks, believed to                                                  |
| be empty, contained liquid bearing very low concentrations of uranium. The   |
| tanks involved are V-109B and V-                                             |
| 113.                                                                         |
|                                                                              |
| "The total mass of uranium involved is 282 grams U, well below the           |
| established safe mass limit of 22,036 grams U at 5% enrichment. No unsafe    |
| condition existed.                                                           |
|                                                                              |
| "The accumulation occurred due to carryover via a common Vent Off-Gas (VOG)  |
| system from V-104 to the two tanks found to contain liquid. The independent  |
| mass and density controls on V-104 remained fully functional. The potential  |
| for carryover via the VOG system was not anticipated and represents an       |
| unanalyzed condition.                                                        |
|                                                                              |
| "The solution in both V-109B and V-113 was sampled and pumped back into      |
| V-104 under the direction of Nuclear Safety. The total solution volume in    |
| V-109B was 2960 gallons with a concentration of 22 ppm U (~247 grams U). The |
| total solution volume in V-113 was 1,507 gallons with a concentration of 6.1 |
| ppm U (~35 grams U). The VOG header has been isolated to prevent             |
| reoccurrence. Investigation and additional corrective actions are pending.   |
|                                                                              |
| "This event is reported pursuant to NRC Bulletin 91-01 (within 24 hours) due |
| to identification of an unanalyzed condition involving less than a safe mass |
| of uranium."                                                                 |
|                                                                              |
| SAFETY SIGNIFICANCE OF EVENTS:                                               |
|                                                                              |
| Low safety significance - low concentration                                  |
|                                                                              |
| POTENTIAL CRITICALITY PATHWAYS INVOLVED BRIEF SCENARIO(S) OF HOW CRITICALITY |
| COULD OCCUR):                                                                |
|                                                                              |
| Multiple failure modes required before a criticality accident could occur.   |
| Incident involves less than a safe mass of uranium.                          |
|                                                                              |
| CONTROLLED PARAMETER(S) (MASS, MODERATION, GEOMETRY, CONCENTRATION, ETC.):   |
|                                                                              |
| Mass: V-104 process vessel limited to safe mass by upstream active           |
| engineered controls on uranium concentration in material feed (independent   |
| uranium monitor and pipe detector NDA measurement).                          |
| Density: independent differential pressure density control tied to           |
| particulate removal (centrifugation) and air sparging.                       |
|                                                                              |
| ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS     |
| LIMIT AND % WORST BASE CRITICAL MASS):                                       |
|                                                                              |
| Affected equipment Contained < 300 grams of uranium (total). Established     |
| safe heterogeneous mass limit for U02 enriched to 5% is 25 kgs (or 22. 036   |
| grams U).                                                                    |
|                                                                              |
| NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION   |
| OF THE FAILURES OR DEFICIENCIES:                                             |
|                                                                              |
| The 4-inch overflow line located on tank V-104 beneath the VOG header failed |
| to prevent carryover into the VOG header.                                    |
|                                                                              |
| CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEMS AND WHEN EACH WAS IMPLEMENTED:  |
|                                                                              |
| 1. Solution in V-109B and V-113 sampled for U concentration, results         |
| acceptable.                                                                  |
|                                                                              |
| 2. Solution in V-109B and V-113 pumped back into V-104; VOG header tie-in    |
| blank flanged to prevent reoccurrence.                                       |
|                                                                              |
| 3. Investigation and additional corrective actions pending.                  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37575       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: OCONEE                   REGION:  2  |NOTIFICATION DATE: 12/07/2000|
|    UNIT:  [1] [] []                 STATE:  SC |NOTIFICATION TIME: 14:29[EST]|
|   RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-L|EVENT DATE:        11/07/2000|
+------------------------------------------------+EVENT TIME:             [EST]|
| NRC NOTIFIED BY:  RANDY TODD                   |LAST UPDATE DATE:  12/07/2000|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |PAUL FREDRICKSON     R2      |
|10 CFR SECTION:                                 |BRIAN SMITHN         NMSS    |
|BAB2 20.2201(a)(1)(ii)   LOST/STOLEN LNM>10X    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LOSS OF A RADIOACTIVE CALIBRATION SOURCE CONTAINING 0.022 MICROCURIES OF     |
| AMERICIUM-241                                                                |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "[...]  This is a non-emergency event being reported in accordance with 10   |
| CFR 20.2201(a)(2)(i) which references [10 CFR] 50.72.  The event did not     |
| directly affect operation of Oconee unit(s) 1, 2, or 3."                     |
|                                                                              |
| "[...]  This report is categorized under 10 CFR 20.2201(a)(1)(ii)."          |
|                                                                              |
| "[...]  Description of event:"                                               |
|                                                                              |
| "On [11/07/00,] a radioactive calibration source, designated as ONS-1075,    |
| was recognized as missing inside the Oconee restricted area.  Following an   |
| unsuccessful search, it was classified as lost.  [10 CFR] Part 20 requires a |
| telephone report to the NRC Operations Center within 30 days from the date   |
| of loss of this quantity of licensed material.  In addition, 10 CFR          |
| 20.2201(b) requires a written report within 30 days following the telephone  |
| report.  The written report will be submitted within that period."           |
|                                                                              |
| "Description of the lost licensed material[:]"                               |
|                                                                              |
| "The lost calibration source was a 47 mm glass fiber filter material         |
| impregnated with 0.022 microcurie[s] of [Am]-241, covered with mylar and     |
| contained in a stainless steel planchet.  This quantity is 22 times the 10   |
| CFR [Part] 20, Appendix C quantity.  For comparison, the average home smoke  |
| detector contains a source of approximately 1 microcurie."                   |
|                                                                              |
| "Circumstances under which the loss occurred[:]"                             |
|                                                                              |
| "On 10/30/00[,] an individual used the source used to calibrate a radiation  |
| measuring device.  Prior to returning the source to its storage location,    |
| the individual, who was experiencing elevated blood pressure, was relieved   |
| from duty and was referred to his personal physician.  On 11/07/00, after    |
| being released to return to work by his physician, the individual resumed    |
| the calibration process and noted the absence of the calibration source."    |
|                                                                              |
| "Probable disposition of licensed material[:]"                               |
|                                                                              |
| "Following a search and investigation associated with the missing            |
| calibration source (see below), it was concluded that the most probable      |
| disposition of the lost source was inadvertent disposal as dry active        |
| waste."                                                                      |
|                                                                              |
| "Exposures of individuals to radiation[:]"                                   |
|                                                                              |
| "No individuals are believed to have been exposed to this material.  A dose  |
| assessment assuming a hypothetical maximally exposed individual concluded    |
| that external exposure would be negligible, and internal dose would be 49    |
| mRem CEDE if ingested or 11.4 Rem CEDE if inhaled.  Given the probable       |
| disposition and physical characteristics of this source, it is unlikely that |
| this source was ingested or inhaled; therefore, it is not considered         |
| credible that any individual could receive the maximum calculable dose from  |
| this source."                                                                |
|                                                                              |
| "Action taken to recover the material[:]"                                    |
|                                                                              |
| "On 11/07/00[,] the individual conducted a search of the source's storage    |
| area and all reasonable areas where the source would be used in order to     |
| continue the calibration.  When the source was not found, the individual     |
| notified his supervisor, and the search was expanded to include the          |
| individual's office area and some personal effects.  Because the calibration |
| source is very similar in appearance to common samples used to quantify      |
| removable surface radioactive contamination, it was suspected that the       |
| calibration source had been mistakenly discarded as sample waste.  No dry    |
| active waste shipments had been made during the elapsed time between         |
| 10/30/2000, when the source was last known to have been used, and 11/7/00,   |
| when the search was conducted.  However, a significant amount of waste had   |
| accumulated at the collection point.  This waste was visually searched, but  |
| the source was not located."                                                 |
|                                                                              |
| "Measures that have been, or will be, adopted to ensure against a recurrence |
| of the loss of licensed material[:]"                                         |
|                                                                              |
| "This type of calibration source is similar in appearance to routine samples |
| prepared for counting in the detector.  Oconee will pursue a method for      |
| better marking of these sources to minimize the possibility of a source      |
| being visually mistaken for a waste sample."                                 |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
|                                                                              |
| NOTE:  The licensee stated that Oconee Unit 1 was operating at 100% power at |
| the time of the event (on 11/07/00).  However, the Unit 1 is currently       |
| defueled as part of a planned refueling outage.                              |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   37576       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  HUNT VALVE COMPANY, INC.             |NOTIFICATION DATE: 12/07/2000|
|LICENSEE:  HUNT VALVE COMPANY, INC.             |NOTIFICATION TIME: 19:19[EST]|
|    CITY:  SALEM                    REGION:  3  |EVENT DATE:        12/06/2000|
|  COUNTY:                            STATE:  OH |EVENT TIME:             [EST]|
|LICENSE#:                        AGREEMENT:  Y  |LAST UPDATE DATE:  12/07/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |MICHAEL PARKER       R3      |
|                                                |KEVIN RAMSEY (fax)   NMSS    |
+------------------------------------------------+VERN HODGE (fax)     NRR     |
| NRC NOTIFIED BY:  WAYNE ALDRICH (via fax)      |                             |
|  HQ OPS OFFICER:  LEIGH TROCINE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|CCCC 21.21               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 10 CFR PART 21 REPORT OF A DEVIATION - IDENTIFICATION OF A DEFECT WITH A     |
| COMPONENT ON VALVE ASSEMBLIES SUPPLIED TO USEC                               |
|                                                                              |
| The following text is a portion of a facsimile received from Hunt Valve      |
| Company, Inc.:                                                               |
|                                                                              |
| "We have discovered a material failure within our manufacturing process for  |
| the 1" UF-6 valves manufactured in accordance with ANSI N14.1.  During our   |
| normal visual inspection[,] a few packing nuts were noted to have cracks     |
| located on the hex flats.  These cracked packing nuts have been isolated to  |
| heat codes AXP and AFD."                                                     |
|                                                                              |
| "These valves were manufactured and shipped against contract No. 566948 for  |
| USEC.  Our records indicate that we have shipped Lot Serial [Nos.] 200027-36 |
| through 200027-40 containing the heat code AXP packing nuts, and Lot Serial  |
| [Nos.] 200027-5 [and] 200027-19 through 200027-35 containing heat code AFD.  |
| The total number of valves included in these shipments is 2,300 of which     |
| 1,300 are known to be from the affected heat codes (see attached table).     |
| All other inventory has been accounted for and isolated.  These valves have  |
| been located at USEC and are being returned to Hunt Valve for replacement    |
| nuts."                                                                       |
|                                                                              |
| "We are currently undergoing an investigation to determine the source of the |
| defect but feel compelled to inform you by this communication of our         |
| preliminary findings. [...]."                                                |
|                                                                              |
| "Heat Code                                                   Lot Serial      |
| [No.]               Date Shipped             Quantity                        |
| (Total Supplied)                                                             |
|                                                                              |
| AXP (735 pcs)                                                   200027-36    |
| 11/22/00                     97                                              |
| 200027-37                     11/22/00                    100                |
| (233 in stock 12/4/00)                                       200027-38       |
| 11/22/00                   100                                               |
| (100 on a shipment in shipping)                        200027-39             |
| 11/22/00                    100                                              |
| 200027-40                     11/22/00                    100                |
|                                                                              |
| AFD (972 pcs)                                                   200027-5     |
| 5/31/00                       10                                             |
| 200027-19                      8/14/00                         9             |
| (294 in stock 12/4/00)                                       200027-20       |
| 8/14/00                         7                                            |
| 200027-21                      8/31/00                       30              |
| 200027-22                      8/31/00                       44              |
| 200027-23                      8/31/00                       39              |
| 200027-24                      8/31/00                       33              |
| 200027-25                      8/31/00                       29              |
| 200027-26                      10/5/00                       53              |
| 200027-27                      10/5/00                       52              |
| 200027-28                      10/5/00                       67              |
| 200027-29                      10/5/00                       54              |
| 200027-30                      10/5/00                       62              |
| 200027-31                      11/3/00                       58              |
| 200027-32                      11/3/00                       45              |
| 200027-33                      11/3/00                       23              |
| 200027-34                      11/3/00                       35              |
| 200027-35                      11/3/00                       28"             |
|                                                                              |
| (Call the NRC operations officer for contact information).                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   37577       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  WA DIVISION OF RADIATION PROTECTION  |NOTIFICATION DATE: 12/07/2000|
|LICENSEE:  PACIFIC TECHNICAL INDUSTRIES         |NOTIFICATION TIME: 20:10[EST]|
|    CITY:  Bellevue                 REGION:  4  |EVENT DATE:        12/07/2000|
|  COUNTY:                            STATE:  WA |EVENT TIME:             [PST]|
|LICENSE#:  WN-IR053-1            AGREEMENT:  Y  |LAST UPDATE DATE:  12/07/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |BLAIR SPITZBERG      R4      |
|                                                |THOMAS ESSIG         NMSS    |
+------------------------------------------------+CHARLES MILLER       IRO     |
| NRC NOTIFIED BY:  TERRY C. FRAZEE (Fax)        |                             |
|  HQ OPS OFFICER:  LEIGH TROCINE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT REGARDING THE DISCOVERY THAT A PACIFIC TECHNICAL      |
| INDUSTRIES RADIOGRAPHER'S  EXPOSURE  EXCEEDED 5 REM ANNUAL LIMIT             |
|                                                                              |
| The following text is a portion of a facsimile received from WA Department   |
| of Health (DOH), Division of Radiation Protection:                           |
|                                                                              |
| "This is notification of an event in Washington state as reported to the WA  |
| Department of Health, Division of Radiation Protection."                     |
|                                                                              |
| "STATUS:  new"                                                               |
|                                                                              |
| "Licensee:  Pacific Technical Industries"                                    |
|                                                                              |
| "City and state:  Bellevue, WA"                                              |
|                                                                              |
| "License number:  WN-1R053-1"                                                |
|                                                                              |
| "Type of license:  Industrial radiography"                                   |
|                                                                              |
| "Date of event:  November 2000"                                              |
|                                                                              |
| "Location of Event:  Bellevue, WA"                                           |
|                                                                              |
| "ABSTRACT (where, when, how, why; cause, contributing factors, corrective    |
| actions, consequences, DOH on-site investigation; media attention)[:]  An    |
| industrial radiographer has exceeded the annual exposure limit of 5 rem.     |
| The licensee was notified by the dosimetry service on September 27 that the  |
| radiographer had received 4.3 rem through August 2000.  The Department       |
| mailed a copy of [Information Notice] IN 2000-15 to all radiography          |
| licensees on October 26.  Upon receipt of the Information Notice, the        |
| licensee was prompted to review the radiographer's daily pocket dosimeter    |
| records and at that time determined that the total dose was already likely   |
| to be 5.1 rem.  The radiographer was immediately reassigned to non-radiation |
| work, the dosimeter was sent for processing, and the Department was          |
| notified.  On December 7, the licensee reported the results of the dosimetry |
| as received from the dosimetry service.  The radiographer had received 5.217 |
| rem.  The licensee indicated that the radiographer had received more         |
| exposure than usual due to a heavy workload in confined spaces such as tanks |
| and other vessels where getting in and out was difficult or even hazardous.  |
| The relatively short exposure times involved led the radiographer to remain  |
| in the confined space hut as far as practical from the source and crank      |
| handle.  The licensee is being cited for failure to control the exposure of  |
| the radiographer."                                                           |
|                                                                              |
| "What is the notification or reporting criteria involved?  WAC 246-22l-010   |
| Occupational limits for adults."                                             |
|                                                                              |
| "Activity and Isotope(s) involved:  Curie amounts of Ir-192"                 |
|                                                                              |
| "Overexposure?  (Number of workers/members of public; dose estimate; body    |
| part receiving dose; consequence)[:]  One radiographer received 5.217 rem    |
| whole body exposure; 5.210 rem to the lens; and 5.248 rem shallow dose."     |
|                                                                              |
| (Call the NRC operations officer for contact information.)                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37578       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HATCH                    REGION:  2  |NOTIFICATION DATE: 12/07/2000|
|    UNIT:  [1] [2] []                STATE:  GA |NOTIFICATION TIME: 23:35[EST]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        12/07/2000|
+------------------------------------------------+EVENT TIME:        22:55[EST]|
| NRC NOTIFIED BY:  GUY GRIFFIS                  |LAST UPDATE DATE:  12/07/2000|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |PAUL FREDRICKSON     R2      |
|10 CFR SECTION:                                 |                             |
|AARC 50.72(b)(1)(v)      OTHER ASMT/COMM INOP   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LOSS OF THE PROMPT NOTIFICATION SYSTEM                                       |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "A complete loss of the prompt notification system has occurred [at 2255],   |
| which [is] considered to be a major loss of offsite notification capability. |
| The prompt notification system is a NOAA weather radio system [out of        |
| Jacksonville, Florida]."                                                     |
|                                                                              |
| The licensee stated that people are currently being dispatched to work on    |
| the problem and that the system was returned to service at 2335.             |
|                                                                              |
| The licensee notified applicable state and local officials and plans to      |
| notify the NRC resident inspector.                                           |
+------------------------------------------------------------------------------+