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Event Notification Report for October 20, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           10/19/2000 - 10/20/2000

                              ** EVENT NUMBERS **

37440  37441  37442  

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|Power Reactor                                    |Event Number:   37440       |
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| FACILITY: QUAD CITIES              REGION:  3  |NOTIFICATION DATE: 10/19/2000|
|    UNIT:  [1] [] []                 STATE:  IL |NOTIFICATION TIME: 07:00[EDT]|
|   RXTYPE: [1] GE-3,[2] GE-3                    |EVENT DATE:        10/19/2000|
+------------------------------------------------+EVENT TIME:        05:30[CDT]|
| NRC NOTIFIED BY:  MCLENNAN                     |LAST UPDATE DATE:  10/19/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |ROGER LANKSBURY      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        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| MAIN STEAM LINE ISOLATION VALVES FAIL LOCAL LEAK RATE TEST                   |
|                                                                              |
| At 0530 CT on 10/19/00, the total maximum pathway leakage for all main steam |
| line isolation valves was determined by Local Leak Rate Testing to be in     |
| excess of Technical Specification 4.7.D.6 limit of < 46 scfh when tested at  |
| a test pressure of 25 psig.                                                  |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
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|Fuel Cycle Facility                              |Event Number:   37441       |
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| FACILITY: WESTINGHOUSE ELECTRIC CORPORATION    |NOTIFICATION DATE: 10/19/2000|
|   RXTYPE: URANIUM FUEL FABRICATION             |NOTIFICATION TIME: 08:53[EDT]|
| COMMENTS: LEU CONVERSION (UF6 to UO2)          |EVENT DATE:        10/18/2000|
|           COMMERCIAL LWR FUEL                  |EVENT TIME:        09:30[EDT]|
|                                                |LAST UPDATE DATE:  10/19/2000|
|    CITY:  COLUMBIA                 REGION:  2  +-----------------------------+
|  COUNTY:  RICHLAND                  STATE:  SC |PERSON          ORGANIZATION |
|LICENSE#:  SNM-1107              AGREEMENT:  Y  |CAUDLE JULIAN        R2      |
|  DOCKET:  07001151                             |BRIAN SMITH          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  JIM HEATH                    |                             |
|  HQ OPS OFFICER:  JOHN MacKINNON               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| FAILURE OF VAPORIZE LEVEL PROBE IN "3A" VAPORIZER                            |
|                                                                              |
| NRC BULLETIN 91-01 24 HOUR NOTIFICATION                                      |
|                                                                              |
| Periodic testing of the condensate level detection system in the 3A          |
| vaporizer steam chest determined that the system could not perform its       |
| intended function due to blockage in the system by loose debris.  Further    |
| investigation determined that paint flaked from the recently processed       |
| cylinder and collected in the bottom of the vaporizer.  However, the debris  |
| did not block the main condensate removal drain which allowed condensate to  |
| be removed from the vaporizer, so there was no condensate accumulation.      |
|                                                                              |
| The vaporizer bottom was cleaned and the level detection system was checked. |
| The system responded correctly.                                              |
|                                                                              |
| SAFETY SIGNIFICANCE OF EVENTS:                                               |
|                                                                              |
| No contingency occurred.  No accumulation of water in the bottom of the      |
| vaporizer occurred.  No SNM was involved.                                    |
|                                                                              |
| CONTROLLED PARAMETER:                                                        |
|                                                                              |
| Mass and moderator are the controlled parameters for the vaporizer.          |
|                                                                              |
| ESTIMATED AMOUNT, ENRICHMENT, FORM of LICENSED MATERIAL:                     |
|                                                                              |
| Cylinders heated in the vaporizer contain uranium hexafluoride gas with a    |
| uranium-235 enrichment less than 5.0 weight percent. No SNM  was involved in |
| this incident since uranium hexafluoride was contained at all times within   |
| the uranium hexafluoride piping system.                                      |
|                                                                              |
| NUCLEAR CRITICALITY SAFETY CONTROL(s) OR CONTROLLED SYSTEM(s) AND            |
| DESCRIPTION OF THE FAILURES OR DEFICIENCIES:                                 |
|                                                                              |
| The condensate level detection system in the 3A vaporizer was rendered       |
| inoperable as a result of a drain line that was blocked by debris which came |
| from the most recently processed cylinder.                                   |
|                                                                              |
| CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEMS AND WHEN EACH WAS IMPLEMENTED:  |
|                                                                              |
| The debris in the 3A vaporizer was removed and proper functioning of the     |
| level detection system was verified.  The 3A vaporizer was released for      |
| restart on October 19, 2000 at 0730 hours.  Other vaporizers not in use at   |
| the time of the incident were checked for proper functioning of the level    |
| detection system; each system responded correctly.   Other vaporizers in use |
| at the time were subject to increased-frequency checks to verify proper      |
| functioning of the condensate removal system; all vaporizers were draining   |
| properly.  In addition, the condensate level detection system for in-use     |
| vaporizers will be function-tested immediately after the uranium             |
| hexafluoride cylinder currently being processed is removed.                  |
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+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37442       |
+------------------------------------------------------------------------------+
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| FACILITY: WATERFORD                REGION:  4  |NOTIFICATION DATE: 10/19/2000|
|    UNIT:  [3] [] []                 STATE:  LA |NOTIFICATION TIME: 15:53[EDT]|
|   RXTYPE: [3] CE                               |EVENT DATE:        10/19/2000|
+------------------------------------------------+EVENT TIME:        13:40[CDT]|
| NRC NOTIFIED BY:  BRUCE PROCTOR                |LAST UPDATE DATE:  10/19/2000|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN PELLET          R4      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| BORIC ACID RESIDUE DISCOVERED ON REACTOR COOLANT SYSTEM INSTRUMENT NOZZLES   |
|                                                                              |
| "During a bare metal inspection of reactor coolant system hot leg instrument |
| nozzles, boric acid residue was found on two of the three mechanical nozzle  |
| seal assembly (MNSA) clamps installed during the previous refueling outage   |
| (3/99). The MNSA clamps were installed on previously identified leaking      |
| nozzles. The leakage from the clamps constitutes a reinitiation of RCS       |
| pressure boundary leakage, which is a degradation of the RCS pressure        |
| boundary."                                                                   |
|                                                                              |
| The NRC resident inspector has been informed of this notification by the     |
| licensee.                                                                    |
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