Event Notification Report for August 31, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           08/30/2000 - 08/31/2000

                              ** EVENT NUMBERS **

37273  37274  37275  37276  37277  

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|Other Nuclear Material                           |Event Number:   37273       |
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| REP ORG:  U.S. ARMY                            |NOTIFICATION DATE: 08/30/2000|
|LICENSEE:  U.S. ARMY                            |NOTIFICATION TIME: 10:01[EDT]|
|    CITY:  ROCK ISLAND              REGION:  3  |EVENT DATE:        08/23/2000|
|  COUNTY:                            STATE:  IL |EVENT TIME:             [CDT]|
|LICENSE#:  12-00722-06           AGREEMENT:  Y  |LAST UPDATE DATE:  08/30/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |MELVYN LEACH         R3      |
|                                                |BRIAN SMITH          NMSS    |
+------------------------------------------------+CAUDLE JULIAN        R2      |
| NRC NOTIFIED BY:  JEFF HAVENNER                |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|BAB2 20.2201(a)(1)(ii)   LOST/STOLEN LNM>10X    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| MISSING M43A1 CHEMICAL AGENT DETECTOR                                        |
|                                                                              |
| The licensee reported that one M43A1 chemical agent detector, containing 250 |
| �Ci of Am-241, had been lost during a training exercise at Camp Shelby,      |
| Mississippi.   The Alabama National Guard was conducting a class, removed    |
| the cell containing the chemical agent detector which apparently was not     |
| replaced.  This was discovered when the assembly was sent in for the         |
| detector to be leak checked.  An investigation has looked for the missing    |
| detector and is still looking for it.                                        |
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+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   37274       |
+------------------------------------------------------------------------------+
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| REP ORG:  QSL INSPECTION                       |NOTIFICATION DATE: 08/30/2000|
|LICENSEE:  QSL INSPECTION                       |NOTIFICATION TIME: 11:30[EDT]|
|    CITY:  TRAINER                  REGION:  1  |EVENT DATE:        08/29/2000|
|  COUNTY:  DELAWARE                  STATE:  PA |EVENT TIME:        14:00[EDT]|
|LICENSE#:  37-28085-01           AGREEMENT:  N  |LAST UPDATE DATE:  08/30/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |PETE ESELGROTH       R1      |
|                                                |BRIAN SMITH          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  LANGE                        |                             |
|  HQ OPS OFFICER:  JOHN MacKINNON               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|IBBF 30.50(b)(2)(ii)     EQUIP DISABLED/FAILS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 30 CURIE IRIDIUM-192 SOURCE'S  PIG TAIL DISCONNECTED FROM ITS DRIVE CABLE.   |
|                                                                              |
| Event was reported by the Radiation Safety Officer for QSL Inspection.       |
|                                                                              |
| Disconnect of a Sentinel Amersham 660 exposure device occurred in Bensalem,  |
| Pa., yesterday afternoon.  After completing an exposure it was discovered    |
| that the source had become  disconnected from its drive cable and it could   |
| not be retracted back to its storage position.  The pig tail had become      |
| disconnected from the drive cable.  The licensee shielded the source and     |
| retrieved it.  Maximum reading of the radiographers pocket dosimetry devices |
| was 130 mRem (the radiographers actual exposure in retrieving the 30 curie   |
| Ir-192 source was less than 130 mRem because he had been wearing the same    |
| pocket dosimetry devices during other radiography shots) .   On              |
| investigation the licensee found that the drive cable selector ring was worn |
| (connects the drive cable to the pig tail).  The licensee has taken all of   |
| their 30 exposure controls and 27 devices out of service and is inspecting   |
| them for any problems.  The licensee notified NRC Region 1, John Kinneman,   |
| of this event.                                                               |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   37275       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  EATON CUTLER-HAMMER                  |NOTIFICATION DATE: 08/30/2000|
|LICENSEE:  EATON CUTLER-HAMMER                  |NOTIFICATION TIME: 15:06[EDT]|
|    CITY:  WARRENDALE               REGION:  1  |EVENT DATE:        07/31/2000|
|  COUNTY:                            STATE:  PA |EVENT TIME:             [EDT]|
|LICENSE#:                        AGREEMENT:  N  |LAST UPDATE DATE:  08/30/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |PETE ESELGROTH       R1      |
|                                                |CAUDLE JULIAN        R2      |
+------------------------------------------------+MELVYN LEACH         R3      |
| NRC NOTIFIED BY:  LAURENCE PATTERSON           |CHUCK PAULK          R4      |
|  HQ OPS OFFICER:  LEIGH TROCINE                |VERN HODGE (via fax) NRR     |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|CCCC 21.21               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 10 CFR PART 21 NOTIFICATION REGARDING THE POTENTIAL FAILURE OF               |
| EATON-CUTLER-HAMMER DS-206 CIRCUIT BREAKERS TO CLOSE ON DEMAND               |
|                                                                              |
| The following text is a portion of a facsimile received from Eaton           |
| Cutler-Hammer Nuclear Programs personnel:                                    |
|                                                                              |
| "The following information is provided pursuant to the requirements of 10    |
| CFR Part 21 to report a potential safety concern.  This issue concerns the   |
| possibility for malfunction of the Eaton Cutler-Hammer DS-206 circuit        |
| breakers due to 'shock-out' of Direct Trip Actuators (DTA).  Shock-out is    |
| defined as the unwarranted or undesired change in the state of a DTA from    |
| the normally un-tripped state to a tripped state.  Shock-out occurs as a     |
| result of shock caused by the circuit breaker cycling from the open position |
| to the closed position.  The shock force is supplied by the closing springs  |
| striking the bottom plate of the breaker frame during the breaker closing    |
| operation.  The result of shock-out is that the DTA trips immediately,       |
| returning the breaker to an open condition, which is neither required nor    |
| desired."                                                                    |
|                                                                              |
| "[Eaton Cutler-Hammer Nuclear Programs (C-HNP)] has determined that the root |
| cause of DTA shock-out in DS-206 breakers is the replacement of operating    |
| mechanisms and/or closing springs with new operating mechanisms and/or new   |
| closing springs, as part of the standard reconditioning process.  DTA        |
| shock-out has not been observed in vintage DS-206 breakers that are          |
| reconditioned in accordance with C-HNP procedures, which does not include    |
| the replacement of operating mechanisms and/or closing springs as part of    |
| the standard reconditioning process.  The standard C-HNP reconditioning      |
| process DOES include installation of design upgrades."                       |
|                                                                              |
| "To eliminate the possibility of shock-out, when the DS-206 breaker          |
| reconditioning process includes installation of a new operating mechanism    |
| and/or closing springs, C-HNP recommends the installation of a modified      |
| bottom plate to eliminate transmission of shock to the DTA.  A modified      |
| bottom plate has been designed, [and] tested and is being seismically        |
| qualified by C-HNP."                                                         |
|                                                                              |
| "This deficiency was identified and determined to be of a chronic reportable |
| nature on approximately July 31, 2000."                                      |
|                                                                              |
| "The installed base of the C-HNP supplied operating mechanisms and closing   |
| springs is limited to a single utility and plant, Tennessee Valley Authority |
| Sequoyah Nuclear Plant.  C-HNP does not know where operating mechanisms and  |
| closing springs, procured commercially by third party dedicators, may have   |
| been installed in safety-related applications."                              |
|                                                                              |
| (Contact the NRC operations officer for supplier contact information.)       |
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+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37276       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MONTICELLO               REGION:  3  |NOTIFICATION DATE: 08/30/2000|
|    UNIT:  [1] [] []                 STATE:  MN |NOTIFICATION TIME: 17:18[EDT]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        08/30/2000|
+------------------------------------------------+EVENT TIME:        15:05[CDT]|
| NRC NOTIFIED BY:  KEVIN PEDERSON               |LAST UPDATE DATE:  08/30/2000|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MELVYN LEACH         R3      |
|10 CFR SECTION:                                 |                             |
|ADAS 50.72(b)(2)(i)      DEG/UNANALYZED COND    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| FAILURE OF A MAIN STEAM LINE DRAIN PRIMARY CONTAINMENT ISOLATION VALVE TO    |
| COMPLETELY OPEN DUE TO LOOSE TORQUE SWITCH WIRE CONNECTIONS                  |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "During plant shutdown, primary containment isolation valve MO-2373 failed   |
| to properly function.  The failure was caused by loose torque switch wire    |
| connections which caused a failure of the valve to completely open.          |
| Improper electrical connections could have prevented full closure of the     |
| valve.  Therefore, the valve was determined to be inoperable prior to the    |
| repair.  ([The] valve has been repaired.)  The safety function of the        |
| redundant primary containment isolation valve was available."                |
|                                                                              |
| The licensee plans to notify the NRC resident inspector.                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   37277       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT      |NOTIFICATION DATE: 08/31/2000|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 05:30[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        08/30/2000|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        16:10[CDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  08/31/2000|
|    CITY:  PADUCAH                  REGION:  3  +-----------------------------+
|  COUNTY:  McCRACKEN                 STATE:  KY |PERSON          ORGANIZATION |
|LICENSE#:  GDP-1                 AGREEMENT:  Y  |MELVYN LEACH         R3      |
|  DOCKET:  0707001                              |BRIAN SMITH          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  -                            |                             |
|  HQ OPS OFFICER:  STEVE SANDIN                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|OCBA 76.120(c)(2)(i)     ACCID MT EQUIP FAILS   |                             |
|OCBB 76.120(c)(2)(ii)    EQUIP DISABLED/FAILS   |                             |
|OCBC 76.120(c)(2)(iii)   REDUNDANT EQUIP INOP   |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AREA CONTROL ROOM (ACR) ALARM POWER LOST DUE TO A FAILURE IN THE POWER       |
| TRANSFER SWITCH                                                              |
|                                                                              |
| "At 1610 on 08-30-00 the PSS was informed of a C-331 CAAS Cluster J Trouble  |
| alarm. Investigation of trouble alarm revealed that C-331 CAAS Horns         |
| solenoids had lost DC power. The C-331 ACR DC alarm power was lost due to    |
| the failures in the power transfer switch. Contacts fused together and a     |
| solenoid failed which allowed the transfer switch to reposition to the mid   |
| (no power) position and prevented repositioning to the emergency power       |
| position.  Since the CAAS horns did not have power,  they were unable to     |
| perform the intended safety function, rendering the system inoperable for    |
| audibility. The system is required to be operable according to TSR 2.4.4.7.b |
| for the current mode of operation. The horns were without power (inoperable) |
| for approximately 30 minutes until the transfer switch was physically forced |
| to the emergency power position.                                             |
|                                                                              |
| This event is reportable under 10 CFR 76.120(c)(2) as an event in which      |
| equipment required by the TSR is disabled or fails to function as designed.  |
|                                                                              |
| The NRC Resident Inspector has been notified of this event.                  |
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