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Event Notification Report for October 10, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           10/06/2000 - 10/10/2000

                              ** EVENT NUMBERS **

37305  37414  37415  37416  37417  37418  37419  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37305       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FITZPATRICK              REGION:  1  |NOTIFICATION DATE: 09/11/2000|
|    UNIT:  [1] [] []                 STATE:  NY |NOTIFICATION TIME: 12:42[EDT]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        09/11/2000|
+------------------------------------------------+EVENT TIME:        11:45[EDT]|
| NRC NOTIFIED BY:  MARK ABRAMSKI                |LAST UPDATE DATE:  10/06/2000|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JAMES TRAPP          R1      |
|10 CFR SECTION:                                 |                             |
|AOUT 50.72(b)(1)(ii)(B)  OUTSIDE DESIGN BASIS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OUTSIDE DESIGN BASIS - STATION BATTERY CALCULATIONS                          |
|                                                                              |
| An engineering review of voltage drop calculations for station battery       |
| systems (A & B) has identified an error in the assumed value for the current |
| rating for the starting coil on the A & B ESW pump motor starter.  The       |
| starting coil is actually rated for 44 amps vs. 6 amps as originally         |
| assumed.  This discrepancy results in a calculated terminal voltage at the   |
| coil below that stated on the name plate.  This condition is considered to   |
| be outside the design basis of the plant.                                    |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
|                                                                              |
| * * * RETRACTION on 10/06/00 at 1059 ET by Abramski taken by MacKinnon * *   |
| *                                                                            |
|                                                                              |
| Subsequent testing has determined that there would in fact be sufficient     |
| terminal voltage at the starting coil of the A & B ESW Pump motor starters   |
| during a postulated Loss of Offsite Power.  Therefore the plant was not      |
| outside its design basis and this event is being retracted.  R1DO (Linville) |
| notified                                                                     |
|                                                                              |
| The NRC Resident Inspector was notified of this retraction by the licensee.  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37414       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAINT LUCIE              REGION:  2  |NOTIFICATION DATE: 10/06/2000|
|    UNIT:  [1] [2] []                STATE:  FL |NOTIFICATION TIME: 09:47[EDT]|
|   RXTYPE: [1] CE,[2] CE                        |EVENT DATE:        10/06/2000|
+------------------------------------------------+EVENT TIME:        09:20[EDT]|
| NRC NOTIFIED BY:  DAVE WILLIAMS                |LAST UPDATE DATE:  10/06/2000|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |LEONARD WERT         R2      |
|10 CFR SECTION:                                 |                             |
|APRE 50.72(b)(2)(vi)     OFFSITE NOTIFICATION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION -                                                       |
|                                                                              |
| THE LICENSEE NOTIFIED THE FLORIDA FISH & WILDLIFE CONSERVATION COMMISSION    |
| ABOUT A LIVE LOGGERHEAD SEA TURTLE THAT WAS FOUND IN THE INTAKE NET.  THE    |
| TURTLE WILL BE SENT OFF FOR REHABILITATION.                                  |
|                                                                              |
| THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   37415       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  WA DIVISION OF RADIATION PROTECTION  |NOTIFICATION DATE: 10/06/2000|
|LICENSEE:  TRANSALTA CENTRALIA MINING, LLC      |NOTIFICATION TIME: 19:45[EDT]|
|    CITY:  CENTRALIA                REGION:  4  |EVENT DATE:        10/05/2000|
|  COUNTY:                            STATE:  WA |EVENT TIME:             [PDT]|
|LICENSE#:  WN-I0241-1            AGREEMENT:  Y  |LAST UPDATE DATE:  10/06/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |DAVE LOVELESS        R4      |
|                                                |M. WAYNE HODGES      NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  TERRY FRAZEE (EMAIL)         |                             |
|  HQ OPS OFFICER:  STEVE SANDIN                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT - SOURCE DETACHED FROM DRIVE ROD                      |
|                                                                              |
| "The licensee notified the WA Department of Health, Division of Radiation    |
| Protection (WDOH), of an additional mechanical failure involving the same    |
| Ronan Engineering Company Model SA-4 gauging device which suffered           |
| a 'source disconnect' as reported in event #WA-00-046.  The device is        |
| specifically licensed for density process measurements and uses a Cesium 137 |
| sealed source, Amersham Model CDC.711M not to exceed 74 gigabecquerels (2    |
| curies).  The source is normally mounted at the end of a source rod,         |
| approximately six feet long.  In this particular model version, the source   |
| rod consists of two screw-together extensions (approximately two and a half  |
| feet each) which screw into the same diameter source holder (approximately   |
| half a foot long).  When operating, the rod with source is lowered through   |
| the shielded storage position, into the integral and enclosed dry well tube. |
| When not in operation, the rod with source is raised to place the source     |
| into a safe position inside the main shielding.  On September 13, the top    |
| screw connection came unscrewed apparently due to prolonged mechanical       |
| vibration.  This 'disconnect' was repaired and the gauge returned to         |
| operation on September 18.  At the same time the lower screw connection was  |
| found to be partially unscrewed as well.  Both connections were opened,      |
| cleaned, coated with 'Lok-tite' and tightened.                               |
|                                                                              |
| "On October 5, during routine 'end of shift' return of the source to the     |
| shielded position, the source rod snapped off at the lower screw connection. |
| The operator was able to quickly grab the exposed end of the source holder   |
| and prevent the source from falling to the bottom of the dry well.  The      |
| source was successfully locked out in the shielded storage position.         |
| Examination of the source rod indicates that the male screw connector        |
| sheared off at its juncture with the main body of the rod section.  The      |
| cause of this additional failure is under investigation.  The manufacturer   |
| is working on a retrofit for all four gauges of this type at this licensee's |
| facility.  Department staff will be present during the retrofit."            |
|                                                                              |
| HOO NOTE:  See event #37353                                                  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37416       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WATTS BAR                REGION:  2  |NOTIFICATION DATE: 10/06/2000|
|    UNIT:  [1] [] []                 STATE:  TN |NOTIFICATION TIME: 21:19[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        10/06/2000|
+------------------------------------------------+EVENT TIME:        19:39[EDT]|
| NRC NOTIFIED BY:  BENJAMIN HUNT                |LAST UPDATE DATE:  10/06/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |LEONARD WERT         R2      |
|10 CFR SECTION:                                 |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       13       Power Operation  |13       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUTOSTART OF AUXILIARY FEEDWATER PUMPS WHILE PREPARING TO ROLL THE MAIN      |
| TURBINE                                                                      |
|                                                                              |
| "At 1939 hours on 10/6/2000, with the reactor in mode 1 at 13 % power,       |
| preparations to roll the Main Turbine for Main Turbine testing, the 'B' Main |
| Feedwater Pump tripped on low condenser vacuum.  'A' Main Feedwater Pump was |
| not in service, and 'B' Main Feedwater Pump was supplying all Steam          |
| Generators.                                                                  |
|                                                                              |
| "Off Normal Instruction (AOI-16) was entered and the Standby Main Feedwater  |
| Pump was started to supply all Steam Generators, the reactor was maintained  |
| at 13 % power. All Auxiliary Feedwater Pumps started upon receipt of the ESF |
| signal (loss of both Main Feedwater Pumps).                                  |
|                                                                              |
| "This is Reportable event under 10 CFR 50.72(b)(2)(ii) and 50.73(a)(2)(iv),  |
| any event or condition that results in a manual or automatic actuation of    |
| any engineered safety feature (ESF)."                                        |
|                                                                              |
| The licensee informed the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   37417       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT      |NOTIFICATION DATE: 10/08/2000|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 17:59[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        10/08/2000|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        05:18[CDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  10/08/2000|
|    CITY:  PADUCAH                  REGION:  3  +-----------------------------+
|  COUNTY:  McCRACKEN                 STATE:  KY |PERSON          ORGANIZATION |
|LICENSE#:  GDP-1                 AGREEMENT:  Y  |JOHN MADERA          R3      |
|  DOCKET:  0707001                              |M. WAYNE HODGES      NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  J.M. UNDERWOOD               |                             |
|  HQ OPS OFFICER:  STEVE SANDIN                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NCFR                     NON CFR REPORT REQMNT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 24-HOUR  REPORT INVOLVING A SAFETY SYSTEM ACTUATION DUE TO FAILURE OF        |
| FREEZER/SUBLIMER INLET VALVE TO CLOSE                                        |
|                                                                              |
| "At 0518 on 10/8/00 the PSS office was notified that the C-333 Unit 4 Cell 9 |
| freezer/sublimer (F/S) 'B' valve had failed to close following completion of |
| a high-high weight safety system trip test. The F/S high-high weight trip    |
| actuated due to accumulation of UF6 in the vessel caused by the failure of   |
| the  'B' valve. The F/S high-high weight trip system is required to be       |
| operable while in modes F/S 1 and F/S 3 per TSR 2.4.3.1. The F/S high-high   |
| weight trip actuated within the specified limiting control settings of TSR   |
| 2.4.3.1. The F/S 'B' valve was manually closed, the F/S was declared         |
| inoperable and the excess UF6 was removed from the vessel. The F/S was       |
| placed in mode F/S 6 (out of service).                                       |
|                                                                              |
| "The safety system actuation is reportable to the NRC as required by Safety  |
| Analysis Report section 6.9, table 1,  criteria J.2, Safety System actuation |
| due to a valid signal as a 24-hour event notification.                       |
|                                                                              |
| "The NRC Resident inspector has been notified of this event."                |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37418       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HOPE CREEK               REGION:  1  |NOTIFICATION DATE: 10/08/2000|
|    UNIT:  [1] [] []                 STATE:  NJ |NOTIFICATION TIME: 18:11[EDT]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        10/08/2000|
+------------------------------------------------+EVENT TIME:        16:20[EDT]|
| NRC NOTIFIED BY:  DAN BOYLE                    |LAST UPDATE DATE:  10/08/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JAMES LINVILLE       R1      |
|10 CFR SECTION:                                 |                             |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       99       Power Operation  |99       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| "B" REACTOR RECIRC PUMP MOTOR GENERATOR OVERSPEED STOPS FOUND SET HIGH       |
| (NON-CONSERVATIVE) DURING SURVEILLANCE TESTING                               |
|                                                                              |
| "During the performance of the 18 month surveillance requirement to          |
| demonstrate operability of the reactor recirc pump motor set scoop tube      |
| mechanical and electrical stop overspeed setpoints to be less than or equal  |
| to 109% and 107%, respectively, the 'B' MG set stops were found              |
| non-conservatively high.  The magnitude of offset has not been calculated as |
| of this time, but the setpoints have been readjusted to their proper         |
| settings as of 1732 hours this date.                                         |
|                                                                              |
| "The potential impact of this condition would be a function of the reactor   |
| recirc pump 'runaway' transient.  If that analyzed transient were to have    |
| occurred, the potential existed for the flow dependent minimum critical      |
| power ratio to have been exceeded.  This could result in exceeding the       |
| safety limit (MCPR) under those postulated conditions.                       |
|                                                                              |
| "Evaluation of the potential cause of the improper settings is under way."   |
|                                                                              |
| The licensee will inform the NRC resident inspector and the Lower Alloways   |
| Creek Township.                                                              |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37419       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SALEM                    REGION:  1  |NOTIFICATION DATE: 10/09/2000|
|    UNIT:  [1] [] []                 STATE:  NJ |NOTIFICATION TIME: 01:03[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        10/09/2000|
+------------------------------------------------+EVENT TIME:        00:42[EDT]|
| NRC NOTIFIED BY:  TIM PRZEKOP                  |LAST UPDATE DATE:  10/09/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          UNU                   |JAMES LINVILLE       R1      |
|10 CFR SECTION:                                 |CHRISTOPHER GRIMES   NRR     |
|AAEC                                            |CHARLES MILLER       IRO     |
|                                                |CANUPP               FEMA    |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| HYDRAZINE LEAK IN TURBINE BUILDING.                                          |
|                                                                              |
| Salem Unit 1 declared an Unusual Event at 0042 based on ammonia smell in     |
| Unit 1 Turbine Building.  Area was evacuated - no personnel were working in  |
| the area.  It appears as though hydrazine leaked from a chemical addition    |
| tank due to a failure of a chemical transfer pump.  Loss prevention          |
| personnel verified no one in area.  Air samples  all less than 1ppm          |
| hydrazine.  Odor is dissipating.  Abnormal Operating Procedure for Toxic Gas |
| Release has been implemented and Control Room Ventilation placed in Fire     |
| Outside Control Room Alignment.  Unit 1 remained at 100%.  No safeguards     |
| activated or needed.  All safeguards equipment  is available .   Hydrazine   |
| was contained in a dike and directed to chemical waste.  Air sampling will   |
| continue until spill is cleaned up and no odor remains.  State and local     |
| Counties notified.                                                           |
|                                                                              |
| The NRC Resident Inspector will be notified of this event by the licensee.   |
|                                                                              |
| * * * Update on 10/09/00 at 0502 ET by Przekop taken by MacKinnon * * *      |
|                                                                              |
| Unusual Event terminated at 0500 ET.  All hydrazine was cleaned up (25 to 50 |
| gallons).  State & local counties will be notified by the licensee.  R1DO    |
| (Linville), NRR EO (Grimes), IRO (Miller), & FEMA (Canupp) notified.  DOE,   |
| USDA, HHS and DOT(EPA) notified via fax.                                     |
|                                                                              |
| The NRC Resident Inspector will be notified by the licensee of the           |
| termination of the Unusual Event.                                            |
+------------------------------------------------------------------------------+