Event Notification Report for December 30, 2002
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|Power Reactor |Event Number: 39475 |
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| FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 12/28/2002|
| UNIT: [1] [2] [] STATE: WI |NOTIFICATION TIME: 14:38[EST]|
| RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 12/28/2002|
+------------------------------------------------+EVENT TIME: 12:28[CST]|
| NRC NOTIFIED BY: ROBERT W. ADAMS |LAST UPDATE DATE: 12/28/2002|
| HQ OPS OFFICER: ARLON COSTA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |ANNE MARIE STONE R3 |
|10 CFR SECTION: | |
|ACOM 50.72(b)(3)(xiii) LOSS COMM/ASMT/RESPONSE| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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 |
| | |
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EVENT TEXT
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| LOSS OF COMMUNICATION WITH OFFSITE EMERGENCY RESPONSE FACILITY |
| |
| Lost power to Emergency Operations Facility (EOF) at approximately 1228 CST |
| on 12/28/02. The power outage is likely caused by a car/pole accident at Hwy |
| 42 and Nuclear Rd. Repairs to the pole are expected to be complete by 1500 |
| CST today (12/28/02). The Licensee has phone cell communications capability |
| with the EOF if needed. |
| |
| The NRC Resident Inspector has been notified. |
| |
| *** UPDATE FROM DEAN RAASCH TO ARLON COSTA ON 12/28/02 AT 1649 EST *** |
| |
| "Subsequent to the first notification it was discovered that the ENS phone |
| lines from both the Control Room and TSC were also lost. |
| |
| "Power was restored to the EOF at 1515 CST. ENS phones are also restored at |
| this time." |
| |
| The Licensee notified the NRC Resident Inspector. |
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|Power Reactor |Event Number: 39476 |
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| FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 12/29/2002|
| UNIT: [2] [] [] STATE: MI |NOTIFICATION TIME: 02:56[EST]|
| RXTYPE: [2] GE-4 |EVENT DATE: 12/29/2002|
+------------------------------------------------+EVENT TIME: 00:10[EST]|
| NRC NOTIFIED BY: KEVIN DAHM |LAST UPDATE DATE: 12/29/2002|
| HQ OPS OFFICER: RICH LAURA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |ANNE MARIE STONE R3 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2 M/R Y 75 Power Operation |0 Hot Shutdown |
| | |
| | |
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EVENT TEXT
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| MANUAL SCRAM AT FERMI 2 DUE TO INABILITY TO DRIVE CONTROL RODS |
| |
| "The reactor was being shut down from 100% due to a low output voltage |
| condition from Master Power Unit |
| (MPU) 3. Power was lowered using core flow to 75%. The low MPU 3 voltage |
| allowed selection of control rods |
| but would not allow control rods to be inserted. On Sunday, December 29, |
| 2002 at 0010 hours, the reactor [was manually] scrammed from 75% power. |
| |
| "Reactor level is stable in the normal band (197 inches). Reactor Level 3 |
| (173 inches) was reached and level was restored to normal. |
| |
| "No ECCS systems actuated. No safety/relief valves opened. All systems |
| functioned normally. Reactor level is being maintained using feed water |
| through the startup level control valve. Cool down is through the main |
| turbine bypass valves to the main condenser. The following Level 3 |
| isolations occurred as expected: |
| |
| Group 4 - RHR Shutdown Cooling and Head Spray |
| Group 13 - Drywell Sumps |
| Group 15 - Traversing Incore Probe Systems |
| |
| "NRC Senior Resident Inspector has been notified. |
| |
| "This report is being made in accordance with 10 CFR 50.72(b)(2)(iv)(B), Any |
| event that results in actuation of the reactor protection system (RPS) when |
| the reactor is critical." |
| |
| The licensee also indicated that all control rods properly scrammed into the |
| core. |
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|Fuel Cycle Facility |Event Number: 39477 |
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| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 12/29/2002|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 13:27[EST]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 12/28/2002|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 15:20[CST]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 12/29/2002|
| CITY: PADUCAH REGION: 3 +-----------------------------+
| COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION |
|LICENSE#: GDP-1 AGREEMENT: Y |ANNE MARIE STONE R3 |
| DOCKET: 0707001 |SUSAN FRANT NMSS |
+------------------------------------------------+JOSEPH HOLONICH DIRO |
| NRC NOTIFIED BY: T. E. WHITE | |
| HQ OPS OFFICER: ARLON COSTA | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|OSAF 76.120(c)(2) SAFETY EQUIPMENT FAILUR| |
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| | |
| | |
| | |
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EVENT TEXT
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| SAFETY EQUIPMENT FAILURE |
| |
| "At 1515 CST, on 12-28-02 the Plant Shift Superintendent (PSS) was notified |
| that the power for C-746Q1 facility was being returned to the normal supply. |
| The C-746Q1 CAAS system power was being supplied via a portable generator to |
| maintain CAAS operability. As part of this evolution, the CAAS system power |
| was to be transferred back to normal as well by repositioning a knife switch |
| and disconnecting the portable generator. When the knife switch was |
| repositioned, C-746Q1 CAAS Cluster AD Trouble alarm was received (expected |
| alarm) but did not immediately clear (unexpected response). When the |
| building was entered, the building area lights were illuminated, the UPS |
| POWER ON light was extinguished and the HORN POWER ON light was illuminated. |
| The CAAS UPS had the Battery Status light flashing and the Load Status light |
| illuminated. At 1520, the UPS ON/Standby switch was manipulated in an |
| attempt to reenergize the UPS since the assumption was that there was power |
| to the UPS. This inappropriate action de-energized the UPS, extinguished the |
| HORN POWER ON light and the CAAS horn power was lost. This caused a loss of |
| CAAS Audibility for C-746Q1 end TSR LCO 2.6.4.1b was immediately entered. |
| There were no fissile material operations in progress end all of the |
| personnel in the affected area had a radio in constant communication with |
| the Central Control Facility satisfying the required actions of TSR |
| 2.6.4.1b. Upon further investigation it was determined that the knife switch |
| had not been fully engaged in the normal power position and no power was |
| available to the UPS as indicated by the extinguished UPS POWER ON light. At |
| 1530 the knife switch was exercised end fully engaged in the normal power |
| position. The UPS POWER ON light illuminated, the UPS was reenergized and |
| CAAS Horn light illuminated reestablishing CAAS audibility and TSR 2.6.4.1b |
| was exited. |
| |
| "The events reportable as a 24 hour event, as required by 10 |
| CFR76.120(c)(2)(i); An event in which equipment is disabled of fails to |
| function as designed when the equipment is required by TSR to prevent |
| releases, prevent exposures to radiation end radioactive materials exceeding |
| specified limits, mitigate the consequences of an accident, or restore this |
| facility to a pre-established safe condition after an accident. The |
| equipment was required by TSR to be available and operable and no redundant |
| equipment was available to perform the required safety function. |
| |
| "The NRC Resident Inspector has been notified of this event." |
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Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021