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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 37305 |
+------------------------------------------------------------------------------+
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| 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
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| 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. |
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|Power Reactor |Event Number: 37414 |
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+------------------------------------------------------------------------------+
| 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 |
+------------------------------------------------------------------------------+
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| 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
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| 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 |
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+------------------------------------------------------------------------------+
|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. |
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Page Last Reviewed/Updated Thursday, March 25, 2021