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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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                                   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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