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Event Notification Report for June 11, 2002

                         
                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           06/10/2002 - 06/11/2002

                              ** EVENT NUMBERS **

38975  38976  38977  38978  

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|General Information or Other                     |Event Number:   38975       |
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| REP ORG:  ROTORK CONTROLS, INC                 |NOTIFICATION DATE: 06/10/2002|
|LICENSEE:  ROTORK CONTROLS, INC                 |NOTIFICATION TIME: 13:11[EDT]|
|    CITY:  ROCHESTER                REGION:  1  |EVENT DATE:        06/10/2002|
|  COUNTY:                            STATE:  NY |EVENT TIME:             [EDT]|
|LICENSE#:                        AGREEMENT:  Y  |LAST UPDATE DATE:  06/10/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |VERN HODGE           NRR     |
|                                                |                             |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  KAREN BLACK                  |                             |
|  HQ OPS OFFICER:  RICH LAURA                   |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|CCCC 21.21               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| PART 21 ON ROTORK NA1 ACTUATOR                                               |
|                                                                              |
| The name of the manufacturer is Rotork Controls, Inc.  The defective         |
| components the Rotork NA1 type electric Valve Actuators fitted with an       |
| Add-on-Pak 1 (AOP1) Assembly which was manufactured between 1978 and October |
| 2001 and have a safety function used for end of travel indication.  The      |
| problem is that moulded components within the AOP1 assembly cannot be        |
| confirmed to the same specifications as those originally tested and          |
| qualified at Wyle in 1978.  No list of affected plants was available at this |
| time.                                                                        |
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|Other Nuclear Material                           |Event Number:   38976       |
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| REP ORG:  STATE OF MONTANA -  RSO              |NOTIFICATION DATE: 06/10/2002|
|LICENSEE:  ROCKY MOUNTAIN LABRATORIES           |NOTIFICATION TIME: 16:04[EDT]|
|    CITY:  HAMILTON                 REGION:  4  |EVENT DATE:        05/28/2002|
|  COUNTY:                            STATE:  MT |EVENT TIME:        08:30[MDT]|
|LICENSE#:  25-01202-01           AGREEMENT:  N  |LAST UPDATE DATE:  05/28/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |ANTHONY GODY         R4      |
|                                                |FRED BROWN           NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  DIANNE HUHTANEN              |                             |
|  HQ OPS OFFICER:  RICH LAURA                   |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|BLO1 20.2201(a)(1)(i)    LOST/STOLEN LNM>1000X  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| LOST/MISSING  RADIOACTIVE MATERIAL AT ROCKY MOUNTAIN LABS                    |
|                                                                              |
| The Montana State RSO reported that Rocky Mountain Laboratories located in   |
| Hamilton, Montana is missing approximately 12 millicuries of Sulfur-35.      |
| This material is a low energy beta emitter which is used for biological      |
| research including protein mapping.  The material was in the form of pellets |
| and was in the bottom of microfuge tubes which were wrapped in a double bag. |
| The bag was last seen in building 1, room 102, on May 24, 2002 at 17:00.     |
| The material was discovered missing at 8:00 am on May 28, 2002.  A search    |
| was conducted and also waste streams were checked.                           |
|                                                                              |
| The State of Montana notified the NRC Region IV (Christy Maier).             |
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|Fuel Cycle Facility                              |Event Number:   38977       |
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| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT      |NOTIFICATION DATE: 06/10/2002|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 20:55[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        06/09/2002|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        23:55[CDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  06/10/2002|
|    CITY:  PADUCAH                  REGION:  3  +-----------------------------+
|  COUNTY:  McCRACKEN                 STATE:  KY |PERSON          ORGANIZATION |
|LICENSE#:  GDP-1                 AGREEMENT:  Y  |JAMES CREED          R3      |
|  DOCKET:  0707001                              |THOMAS ESSIG         NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  KEN BEASLEY                  |                             |
|  HQ OPS OFFICER:  RICH LAURA                   |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| NRC BULLETIN 91-01 CRITICALITY CONTROLS AT PADUCAH PLANT                     |
|                                                                              |
| "At 0045 CDT, on 6-10-02 The Plant Shift Superintendent (PSS) was notified   |
| that a violation of criticality controls had been discovered in the C-337    |
| process building. C-337 Unit #2 Cell #2 was isolated from the cascade and in |
| the process of being evacuated without an independent verification that a    |
| known R-114 coolant leak did not exist, in violation of NCSA CAS-002. The    |
| building Front Line Manager checked documentation to see if any other        |
| evolutions had taken place without completing this verification. C-337 Unit  |
| #1 Cell #2 was also discovered isolated and evacuated to a UF6 negative      |
| without an independent verification that a known R-114 coolant leak did not  |
| exist, in violation of NCSA CAS-002. The purpose of this check is to         |
| determine actions when transitioning to different moderation controls, i.e.  |
| removal of fluorinating environment to R-114 and RCW controls. The subject   |
| independent verification and coolant sampling were subsequently performed    |
| with successful results. These actions re-established double contingency     |
| within four hours of the time of discovery. Due to the loss of double        |
| contingency and the re-establishment of NCS controls, this event is being    |
| report as a 24-Hr. Event Report. The NRC Resident inspector has been         |
| notified of this event.                                                      |
|                                                                              |
| "SAFETY SIGNIFICANCE: Significant R-114 leaks to process gas systems should  |
| be readily apparent, however no checks for leaks were performed. Both        |
| controls were violated and double contingency was not maintained.            |
|                                                                              |
| "POTENTIAL CRITICALITY PATHWAYS INVOLVED: In order for a criticality to      |
| occur, an R-114 leak to the process gas system would have to occur. In       |
| addition, the R-114 would have to contain an unacceptable amount of moisture |
| and the moisture would have to be absorbed in a deposit of unsafe mass.      |
|                                                                              |
| "CONTROLLED PARAMETERS: Double contingency is maintained by implementing two |
| controls on moderation.                                                      |
|                                                                              |
| "NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(s) AND
DESCRIPTION  |
| OF THE FAILURES OR DEFICIENCIES: The first leg of double contingency is      |
| based on ensuring wet R-114 coolant does not moderate existing uranium       |
| deposits. NCSA CAS.002 requires that prior to the initial evacuation of UF6, |
| a check be made to determine if a known R-114 to process leak exists. This   |
| check was not performed and the control was violated. Until the check was    |
| performed successfully, the process condition was not maintained and double  |
| contingency was not maintained. The second leg of double contingency is      |
| based on independent verification that a known R-114 leak into the process   |
| gas system does not exist. This independent check was not performed          |
| violating the control. Until the check was independently performed           |
| successfully, the process condition was not maintained and double            |
| contingency was not maintained. Since double contingency is based on two     |
| controls on one parameter and both controls were violated, double            |
| contingency was not maintained."                                             |
|                                                                              |
| The NRC Resident Inspector was notified of this event.                       |
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|Power Reactor                                    |Event Number:   38978       |
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| FACILITY: FT CALHOUN               REGION:  4  |NOTIFICATION DATE: 06/11/2002|
|    UNIT:  [1] [] []                 STATE:  NE |NOTIFICATION TIME: 00:26[EDT]|
|   RXTYPE: [1] CE                               |EVENT DATE:        06/10/2002|
+------------------------------------------------+EVENT TIME:        21:20[CDT]|
| NRC NOTIFIED BY:  RICH LOWERY                  |LAST UPDATE DATE:  06/11/2002|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |ANTHONY GODY         R4      |
|10 CFR SECTION:                                 |                             |
|NONR                     OTHER UNSPEC REQMNT    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| BUS GROUND ON HOUSE SERVICE TRANSFORMER 4160V VITAL BUS TRANSFORMER   
      |
|                                                                              |
| At 2120 CT Ft. Calhoun Station control room received an alarm indicating a   |
| T1A3 4160V Bus Ground on house service transformer 4160V vital bus 1A3       |
| transformer.  Licensee referenced ARP and plant AOP's 31 and 32, for all     |
| 4160V buses fed from 22KV and Loss of 4160V bus power.  Subsequent securing  |
| of possible 4160V bus loads did not isolate the ground.  Subsequently        |
| transferred 4160V bus 1A3 feed from 4160V transformer T1A3 to 22KV           |
| Transformer T1A1.  Alarm and ground indications went away upon transfer.     |
| Per Technical Specification 2.7.(2) b Nuclear Regulatory Commission          |
| Operations Control Center shall be notified within 4 hours of transformer    |
| inoperability.  System Engineering and Electrical Support Staff are on site  |
| investigating. Plant is in a severe thunderstorm warning until 2300 CT.      |
| Diesel operability has been verified.                                        |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
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