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Event Notification Report for January 28, 2003






                    U.S. Nuclear Regulatory Commission

                              Operations Center



                              Event Reports For

                           01/27/2003 - 01/28/2003



                              ** EVENT NUMBERS **



39480  39538  39540  





!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!

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|Power Reactor                                    |Event Number:   39480       |

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| 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:  01/27/2003|

|  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  |

|                                                   |                          |

|                                                   |                          |

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                                   EVENT TEXT                                   

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| 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.                                     |

|                                                                              |

| * * * RETRACTED ON 1/27/03 AT 1714 EST BY DAVID BARNETT TO GERRY WAIG * * *  |

|                                                                              |

|                                                                              |

| "On 12/29/02 at 2330 CST, the Monticello nuclear power plant notified the    |

| NRC operations center of the #12 EDG being declared inoperable when          |

| personnel noted an equipment problem during surveillance testing. In         |

| addition, the #11 EDG was declared inoperable due to station Technical       |

| Specification required surveillance testing to prove operability of the #11  |

| EDG while the #12 EDG was inoperable. The report was made pursuant to        |

| 10CFR50.72(b)(3)(v) under Event Notification number 39480.                   |

|                                                                              |

| "Upon further review, Monticello is retracting the event reported based on   |

| the information in NUREG-1022, Rev. 2, page 56, which states, 'The following |

| types of events or conditions generally are not reportable under these       |

| conditions. Sub-item 3 states: removal of a system or part of a system from  |

| service as part of a planned evolution for maintenance or surveillance       |

| testing when done in accordance with an approved procedure and the plant's   |

| TS (unless a condition is discovered that could have prevented the system    |

| from performing its function).'                                              |

|                                                                              |

| "The station condition reported in Event Report #39480 was determined not to |

| be reportable based on the following:                                        |

| 1) #11 EDG was inoperable due to the performance of a surveillance test in   |

| accordance with the station's Technical Specifications and an approved       |

| procedure; and                                                               |

| 2) #11 EDG successfully passed the surveillance test to prove operability.   |

| Additionally, the required TS LCO action statement requiring plant shutdown  |

| was entered. The appropriate procedure was entered. However the station was  |

| not required to reduce power or initiate shutdown by inserting negative      |

| reactivity and additionally the shutdown was not imminent, since the #11 EDG |

| was confirmed to be operable."                                               |

|                                                                              |

| The licensee has notified the NRC Resident Inspector, State of Minnesota,    |

| and Local Government of this retraction.                                     |

|                                                                              |

| Notified R3DO (Mark Ring)                                                    |

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+------------------------------------------------------------------------------+

|Power Reactor                                    |Event Number:   39538       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| FACILITY: TURKEY POINT             REGION:  2  |NOTIFICATION DATE: 01/27/2003|

|    UNIT:  [3] [] []                 STATE:  FL |NOTIFICATION TIME: 10:05[EST]|

|   RXTYPE: [3] W-3-LP,[4] W-3-LP                |EVENT DATE:        01/27/2003|

+------------------------------------------------+EVENT TIME:        08:44[EST]|

| NRC NOTIFIED BY:  JEFF DEAL                    |LAST UPDATE DATE:  01/27/2003|

|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |KEN BARR             R2      |

|10 CFR SECTION:                                 |                             |

|ARPS 50.72(b)(2)(iv)(B)  RPS ACTUATION - CRITICA|                             |

|AESF 50.72(b)(3)(iv)(A)  VALID SPECIF SYS ACTUAT|                             |

|                                                |                             |

|                                                |                             |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|3     M/R        Y       100      Power Operation  |0        Hot Standby      |

|                                                   |                          |

|                                                   |                          |

+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   

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| UNIT 3 MANUALLY TRIPPED DUE TO LOW STEAM GENERATOR LEVELS                    |

|                                                                              |

| The following information was submitted via facsimile:                       |

|                                                                              |

| "Manual reactor trip on Unit 3 due to low steam generator levels caused by a |

| loss of instrument air pressure.  Instrument air pressure has been           |

| restored."                                                                   |

|                                                                              |

| Operators manually tripped Unit 3 following the loss of instrument air (IA)  |

| pressure which resulted in closing of the main feedwater regulating valves.  |

| IA can be supplied from one of four compressors;  two motor driven and two   |

| diesel driven.  When the operating motor driven air compressor breaker       |

| tripped, both diesel driven compressors received a start signal (the other   |

| motor driven compressor had been previously removed from service).  One of   |

| the diesel driven compressors failed to start while the other started and    |

| tripped.  IA pressure was restored by manually starting one of the diesel    |

| units.  The licensee has the cause of the IA loss under investigation.       |

|                                                                              |

| Following the manual reactor trip, all three turbine driven auxiliary        |

| feedwater pumps started as expected.  The licensee is in the process of      |

| restoring normal feedwater and returning the auxiliary feedwater pumps to    |

| standby.   The atmospheric steam dumps are currently in service to remove    |

| decay heat (no known primary-secondary leakage).  All control rods fully     |

| inserted.                                                                    |

|                                                                              |

| The licensee will notify the resident inspector and does not plan a press    |

| release.                                                                     |

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+------------------------------------------------------------------------------+

|Power Reactor                                    |Event Number:   39540       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| FACILITY: LASALLE                  REGION:  3  |NOTIFICATION DATE: 01/27/2003|

|    UNIT:  [] [2] []                 STATE:  IL |NOTIFICATION TIME: 17:40[EST]|

|   RXTYPE: [1] GE-5,[2] GE-5                    |EVENT DATE:        01/22/2003|

+------------------------------------------------+EVENT TIME:        21:51[CST]|

| NRC NOTIFIED BY:  HAROLD VINYARD               |LAST UPDATE DATE:  01/27/2003|

|  HQ OPS OFFICER:  MIKE RIPLEY                  +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |MARK RING            R3      |

|10 CFR SECTION:                                 |                             |

|AINV 50.73(a)(1)         INVALID SPECIF SYSTEM A|                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|                                                   |                          |

|2     N          N       0        Refueling        |0        Refueling        |

|                                                   |                          |

+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   

+------------------------------------------------------------------------------+

| INVALID AUTOMATIC START OF EMERGENCY DIESEL GENERATOR DURING TESTING         |

|                                                                              |

| "On January 22, 2003, at 2045 hours, with Unit 2 in Mode 5 (refuel), the 2B  |

| Emergency Diesel Generator (DG) automatically started during the performance |

| of a Unit 2 High Pressure Excess Flow Check Valve Operability Test. The      |

| apparent cause was an improper manipulation of instrument isolation valves   |

| during the test, which caused the associated Reactor Vessel Water Level      |

| Transmitters to sense a low level condition. This invalid low level signal   |

| resulted in the automatic actuation of the 2B DG (Div. III) which is the     |

| emergency power supply to the Unit 2 High Pressure Core Spray (HPCS) System. |

| The Unit 2 HPCS pump had been properly removed from service prior to the     |

| event and therefore did not actuate. This system actuation is reportable     |

| under 10CFR50.73 (a) (2) (iv) (A).                                           |

|                                                                              |

| "The 2B DG responded normally and reached normal speed and voltage. It was   |

| run both loaded and unloaded successfully, and was secured at 0238 on        |

| January 23, 2003.                                                            |

|                                                                              |

| "This report is being made in accordance with 10CFR50.73 (a) (1), which      |

| states that in the case of an invalid actuation reported under               |

| 10CFR50.73(a)2)(iv), other than an actuation of the RPS when the reactor is  |

| critical, the licensee may provide a telephone notification to the NRC       |

| operations center within 60 days after discovery of the event Instead of     |

| submitting a written LER."                                                   |

|                                                                              |

| The licensee notified the NRC resident inspector.                            |

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