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Event Notification Report for December 31, 2002



                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           12/30/2002 - 12/31/2002

                              ** EVENT NUMBERS **

39406  39474  39478  39480  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
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|Power Reactor                                    |Event Number:   39406       |
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| FACILITY: DRESDEN                  REGION:  3  |NOTIFICATION DATE: 11/26/2002|
|    UNIT:  [] [2] []                 STATE:  IL |NOTIFICATION TIME: 08:24[EST]|
|   RXTYPE: [1] GE-1,[2] GE-3,[3] GE-3           |EVENT DATE:        11/26/2002|
+------------------------------------------------+EVENT TIME:        03:42[CST]|
| NRC NOTIFIED BY:  BRUCE FRANZEN                |LAST UPDATE DATE:  12/30/2002|
|  HQ OPS OFFICER:  ERIC THOMAS                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |JAMES CREED          R3      |
|10 CFR SECTION:                                 |                             |
|AIND 50.72(b)(3)(v)(D)   ACCIDENT MITIGATION    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       97       Power Operation  |97       Power Operation  |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| UNIT 2 HPCI SYSTEM DECLARED INOPERABLE                                       |
|                                                                              |
| Unit 2 HPCI (High Pressure Coolant Injection) system was declared inoperable |
| at 0342 [CST] due to a failed relay for the MGU (Motor Gear Unit) flow       |
| control circuit.  The relay is normally energized when the MGU is at the     |
| High Speed Stop and is utilized to de-energize the motor gear unit when a    |
| limit switch is reached to prevent damage to the MGU motor.  The resultant   |
| failure affects HPCI such that the MGU will not function from a signal       |
| generated by the Flow Indicating Controller.  HPCI can be operated manually  |
| from [the] Control Room.                                                     |
|                                                                              |
| The Resident Inspector was notified of this event.                           |
|                                                                              |
| *** EVENT RETRACTION FROM ROBERT BROCH TO ARLON COSTA ON 12/30/02 AT 1326    |
| ***                                                                          |
|                                                                              |
| "On November 26, 2002 at 0724 CST, Dresden Station made an ENS Notification  |
| (EN 39406) regarding a High Pressure Coolant Injection inoperability due to  |
| a failed relay for the Motor Gear Unit (MGU) flow control circuit. It was    |
| reported that the failed relay affected HPCI such that the MGU would not     |
| function from a signal generated by the Flow Indicating Controller. The MGU  |
| was capable of being operated from the Control Switch in the Control Room at |
| all times. The condition was reported, in accordance with 10 CFR             |
| 50.72(b)(3)(v)(D), as reduction in accident mitigation capability.           |
|                                                                              |
| "Upon further evaluation of the issue, the following conclusions were        |
| reached: In the event that HPCI would have automatically initiated following |
| the failure of the relay, the Motor Speed Changer (MSC) would have run to    |
| the High Speed Stop (HSS). When the turbine reached 4000 rpm and flow        |
| increased the MGU would have remained at the HSS. Therefore, HPCI would have |
| continued to operate at 4000 rpm and maximum injection flow (>5000 gpm)      |
| until the system restored reactor water level to +48" (at which point the    |
| turbine trips) or the Control Room Operator took manual control. It is       |
| important to note at this point that even if the flow controller circuitry   |
| is operational, the system would have responded in the same manner described |
| above. If no operator action was assumed following the relay failure, HPCI   |
| would have increased reactor water level to the high water trip for break    |
| sizes within its capability.                                                 |
|                                                                              |
| "NUREG 1022 states that the intent of the 10 CFR 50.72 and 50 .73 reporting  |
| criteria is to capture events where there would have been a failure of a     |
| safety system to properly complete a safety function. In the above described |
| condition, the HPCI system was still capable to perform its intended safety  |
| function. The system would have automatically started on an initiation       |
| signal, come up to speed (4000 rpm), and provided >5000 gpm to the reactor   |
| vessel. Additionally, the restart capability of the system was not affected  |
| by the relay failure. Therefore, the system would have operated long enough  |
| to complete its intended safety function as defined in the safety analysis   |
| report.                                                                      |
|                                                                              |
| "Based on the above evaluation, HPCI was capable of performing its functions |
| as specified in the Technical Specifications, the safety analysis report and |
| met all of the operability requirements specified by the plant licensing     |
| basis.                                                                       |
| Based on these conclusions, EN #39406 is being retracted.                    |
|                                                                              |
| The NRC Resident Inspector and the R3DO(Lanksbury) were notified.            |
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+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   39474       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  COLORADO DEPT OF HEALTH              |NOTIFICATION DATE: 12/26/2002|
|LICENSEE:  SCHLUMBERGER TECHNOLOGIES CORP.      |NOTIFICATION TIME: 11:35[EST]|
|    CITY:  RIFLE                    REGION:  4  |EVENT DATE:        12/26/2002|
|  COUNTY:                            STATE:  CO |EVENT TIME:        08:30[MST]|
|LICENSE#:  039-01                AGREEMENT:  Y  |LAST UPDATE DATE:  12/26/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |LINDA HOWELL         R4      |
|                                                |SUSAN FRANT (email)  NMSS    |
+------------------------------------------------+FRED BROWN (email)   NMSS    |
| NRC NOTIFIED BY:  TIM G. BONZER                |                             |
|  HQ OPS OFFICER:  ARLON COSTA                  |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AGREEMENT STATE NOTIFICATION OF IRRETRIEVABLE  WELL-LOGGING SOURCE           |
|                                                                              |
| Timothy Bonzer of the Colorado Radiation Services notified the NRC           |
| Operations Center via fax on 12/26/02 at 1135 EST on an incident involving   |
| an abandoned well-logging source assembly at a gas well near Rifle, Colorado |
| by Schlumberger Technologies Corp. The sources (Cs and AmBe) were lost at    |
| approximately the 8,000 ft level and efforts to retrieve the sources were    |
| unsuccessful. They had taken the necessary measures to deflect any future    |
| attempt to drill in the same location and will place a stainless steel       |
| warning placard at the surface. They intended to abandon the sources and are |
| still planning to use the well for the production of natural gas.            |
|                                                                              |
| The Colorado Emergency Management organization is cognizant of this          |
| incident.                                                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39478       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COMANCHE PEAK            REGION:  4  |NOTIFICATION DATE: 12/30/2002|
|    UNIT:  [1] [2] []                STATE:  TX |NOTIFICATION TIME: 15:51[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        12/30/2002|
+------------------------------------------------+EVENT TIME:        14:15[CST]|
| NRC NOTIFIED BY:  DAVE BUTLER                  |LAST UPDATE DATE:  12/30/2002|
|  HQ OPS OFFICER:  MIKE RIPLEY                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |WILLIAM JOHNSON      R4      |
|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  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LOSS OF OFFSITE EMERGENCY SIRENS DUE TO LIGHTNING STRIKES                    |
|                                                                              |
| All emergency sirens (66 of 66) serving Hood and Somervell Counties, TX are  |
| out of service due to lightning strikes on communications repeater           |
| equipment.  The licensee has notified the Hood and Somervell County Sheriff  |
| Departments and will be notifying the NRC resident inspector.  Repair crews  |
| are responding and expect to make repairs within about 4 hours.              |
|                                                                              |
| ***UPDATE on 12/31/02 at 0113ET by Don Cerny taken by MacKinnon****          |
|                                                                              |
| All sirens were returned to service December 31, 2002 at midnight.   NRC     |
| R4DO (Bill Johnson) notified.                                                |
|                                                                              |
| The NRC Resident Inspector will be contacted by the licensee of this update. |
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+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39480       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MONTICELLO               REGION:  3  |NOTIFICATION DATE: 12/31/2002|
|    UNIT:  [1] [] []                 STATE:  MN |NOTIFICATION TIME: 01:34[EST]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        12/30/2002|
+------------------------------------------------+EVENT TIME:        20:10[CST]|
| NRC NOTIFIED BY:  JAMES McKAY                  |LAST UPDATE DATE:  12/31/2002|
|  HQ OPS OFFICER:  RICH LAURA                   +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |ROGER LANKSBURY      R3      |
|10 CFR SECTION:                                 |                             |
|AINB 50.72(b)(3)(v)(B)   POT RHR INOP           |                             |
|AINA 50.72(b)(3)(v)(A)   POT UNABLE TO SAFE SD  |                             |
|AINC 50.72(b)(3)(v)(C)   POT UNCNTRL RAD REL    |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| MONTICELLO INITIATED TS REQUIRED PLANT SHUTDOWN DUE TO INOPERABILITY OF BOTH |
| EDGs                                                                         |
|                                                                              |
| "With #12 EDG inoperable due to a maintenance issue [on 12/29/02 at 2330     |
| CST] , it is required to test #11 EDG within 24 hours. Testing causes #11    |
| EDG to be inoperable, therefore both EDGs are inoperable requiring [the      |
| initiation of] a plant shutdown per T.S. 3.9.B.3.a.2 and a non-emergency     |
| notification per 10 CFR 50.72/8 hour.  #11 EDG subequently tested operable   |
| and the plant exited T.S. shutdown requirement at 2300 on 12/30/02."         |
|                                                                              |
| The licensee stated that the period of time both EDGs were inoperable was    |
| from 2010 to 2300 on 12/30/02.  The inoperablity of the #12 EDG was due to   |
| an equipment problem with the DC fuel oil pump.  After fixing the DC fuel    |
| oil pump on the #12 EDG, the EDG was restarted and the "failure-to-start"    |
| alarm lit  and the "cranking" alarm lit and stayed in for 5 minutes.   The   |
| licensee is currently evaluating these problems.  The #12 EDG remains in a 7 |
| day limiting LCO action statement.  The #11 EDG started and tested           |
| satisfactorily with no problems. The inoperability of the #11 EDG was due to |
| some of the set up conditions for testing when the EDG is considered to be   |
| inoperable per procedure.                                                    |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
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