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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