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Event Notification Report for March 5, 2002

                         
                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           03/04/2002 - 03/05/2002

                              ** EVENT NUMBERS **

38477  38704  38748  38749  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
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|Power Reactor                                    |Event Number:   38477       |
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| FACILITY: PALISADES                REGION:  3  |NOTIFICATION DATE: 11/07/2001|
|    UNIT:  [1] [] []                 STATE:  MI |NOTIFICATION TIME: 19:47[EST]|
|   RXTYPE: [1] CE                               |EVENT DATE:        11/07/2001|
+------------------------------------------------+EVENT TIME:        14:14[EST]|
| NRC NOTIFIED BY:  DANIEL G. MALONE             |LAST UPDATE DATE:  03/04/2002|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |R3 IRC TEAM MANAGER  R3      |
|10 CFR SECTION:                                 |                             |
|AUNA 50.72(b)(3)(ii)(B)  UNANALYZED CONDITION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| HEAD LOSS CHARACTERISTICS OF CHECK VALVES GREATER THAN PREVIOUSLY
ASSUMED.   |
|                                                                              |
| On November 7, 2001, at approximately 1414 hours, with the plant in mode 5   |
| (cold shutdown), evaluation of preliminary results from mock-up testing of   |
| containment sump check valves determined that the head loss characteristics  |
| of the check valves are greater than previously assumed by calculations that |
| support the safety analyses.  The result of increased head loss through the  |
| containment sump check valves is reduced available net positive suction head |
| (NPSH) for the safety injection and containment spray pumps during           |
| recirculation mode following a loss of coolant accident (LOCA).  The reduced |
| available NPSH may have effected the ability of the pumps to satisfy their   |
| required design safety function during previous periods of plant operation.  |
| Recirculation mode operation of these pumps is required by Technical         |
| Specifications in Mode 3 (hot standby) and above.  Therefore, this condition |
| has no adverse implications for the present plant condition at Mode 5.       |
| Evaluation of test results is continuing.                                    |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
|                                                                              |
| * * * RETRACTED AT 1450 EST ON 03/04/02 BY DAN MALONE  TO GERRY WAIG* * *    |
|                                                                              |
| "Subsequent evaluation of the past operability of the pumps with the reduced |
| NPSH condition was concluded that the pumps were nonconforming but operable. |
| This conclusion was reached by crediting containment overpressure and actual |
| plant parameters, which increase available NPSH above that required for all  |
| pumps considering the most limiting postulated conditions.                   |
|                                                                              |
| "Since a determination of nonconforming but operable was reached for past    |
| operating conditions, there was no loss of a required safety function and no |
| significant impact on plant safety this condition was originally discovered  |
| and reported with the plant in Mode 5; and was corrected prior to plant      |
| restart by modifying plant equipment and procedures without further reliance |
| on crediting containment overpressure."                                      |
|                                                                              |
| Licensee notified the NRC Resident Inspector. Notified R3DO (John Madera).   |
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|Fuel Cycle Facility                              |Event Number:   38704       |
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| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT      |NOTIFICATION DATE: 02/16/2002|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 11:11[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        02/15/2002|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        22:00[CST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  03/04/2002|
|    CITY:  PADUCAH                  REGION:  3  +-----------------------------+
|  COUNTY:  McCRACKEN                 STATE:  KY |PERSON          ORGANIZATION |
|LICENSE#:  GDP-1                 AGREEMENT:  Y  |ANTON VEGEL          R3      |
|  DOCKET:  0707001                              |SUSAN FRANT          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  KEVIN BEASLEY                |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|OCBA 76.120(c)(2)        SAFETY EQUIPMENT FAILUR|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| SAFETY EQUIPMENT FAILURE - PROCESS GAS LEAK DETECTION FAILURE                |
|                                                                              |
| "At 2200 CST, on 02-15-02 the Plant Shift Superintendent (PSS) was notified  |
| of a failure of the Process Gas Leak Detector (PGLD) system in the C-333     |
| building.  During above atmospheric operation a PGLD alarm was received in   |
| the Area Control Room [ACR] on C-333 Unit 4 Cell 4.  An operator responded   |
| to the local cell panel to investigate according to the alarm response       |
| procedure.  Upon arriving at the cell panel the operator discovered that the |
| Ready light was not Illuminated on the PGLD panel.  At this time the         |
| operator attempted to test fire the PGLD system, however the system would    |
| not respond. The Front Line Mgr. and the PSS were immediately notified of    |
| the system failure.  At this time, required TSR 2.4.4.1 LCO continuous smoke |
| watches were put in place in the affected areas until repair of the system   |
| was completed.  Following replacement of the power supply by Instrument      |
| Maintenance and testing by Operations, ten Unit 4 Cell 4 PGLD system was     |
| declared operable by the PSS at 2340 CST. At this time the TSR required      |
| smoke watches were discontinued.                                             |
|                                                                              |
| "The PGLD system is designed to detect the leakage of process gas from the   |
| process system and is required to be operable while operating in Cascade     |
| Mode 2 (Above Atmospheric Pressure).  Due to the failure of this TSR         |
| required system; the PSS has determined that this is reportable as a 24 hour |
| Event Report.                                                                |
|                                                                              |
| "The NRC Resident inspector has been notified of this event."                |
|                                                                              |
| * * * RETRACTED AT 0346 EST ON 02/22/02 BY ERIC WALKER TO FANGIE JONES * * * |
|                                                                              |
|                                                                              |
| "This event has been retracted. Even though the power loss causes the system |
| to be incapable of annunciating additional alarms from this system in the    |
| ACR, the same is true when a PGLD head actuates in response to smoke. The    |
| system Is designed to alert operators of a release or loss of system power.  |
| Operator response and the initiation of a smoke watch provide the safety     |
| function after the initial alarm is annunciated. The NRC resident inspector  |
| has been notified of this update."                                           |
|                                                                              |
| The R3DO (Bruce Jorgensen) and NMSS EO (E. William Brach) have been          |
| notified.                                                                    |
|                                                                              |
| * * * UPDATED AT 1750 EST ON 3/4/02 BY TOM WHITE TO FANGIE JONES * * *       |
|                                                                              |
| "Following discussions with NRC Region III and the PGDP NRC Senior Resident  |
| Inspector. USEC has determined that a rescission of the retraction made on   |
| 2/21/02 will be necessary in response to NRC concerns related to this        |
| matter. Therefore, USEC hereby rescinds the subject retraction and will be   |
| submitting the written report required by 10CFR76.120(d)(2). The NRC Senior  |
| Resident Inspector has been notified of the rescission."                     |
|                                                                              |
| Notified the R3DO (John Madera) and NMSS EO (C. W. Reamer).                  |
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|Power Reactor                                    |Event Number:   38748       |
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| FACILITY: MCGUIRE                  REGION:  2  |NOTIFICATION DATE: 03/04/2002|
|    UNIT:  [1] [] []                 STATE:  NC |NOTIFICATION TIME: 10:13[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        03/04/2002|
+------------------------------------------------+EVENT TIME:        08:41[EST]|
| NRC NOTIFIED BY:  PHILLIP THOMPSON             |LAST UPDATE DATE:  03/04/2002|
|  HQ OPS OFFICER:  MIKE NORRIS                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |CAUDLE JULIAN        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  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     M/R        Y       100      Power Operation  |0        Hot Standby      |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| MANUAL REACTOR TRIP DUE TO LOSS OF FEEDWATER                                 |
|                                                                              |
| "Manual reactor trip due to falling level in 1A Steam Generator (S/G), (RPS  |
| Activation).  Level decrease occurred after the Feedwater Regulating Valve   |
| (FRV) for the 1A S/G failed closed upon loss of the normal and backup        |
| electrical power to the valve solenoid. After the reactor trip, the 1A S/G   |
| experienced a LO-LO Level Alarm which auto started both motor driven         |
| Auxiliary Feedwater pumps, (ESF Actuation).  All S/G levels are now at       |
| normal levels and Unit 1 is stable.  An investigation is in progress to      |
| determine the loss of electrical power to the FRV solenoid for the 1A S/G."  |
|                                                                              |
| The plant is dumping steam to the Main Condenser with no known               |
| Primary/Secondary leakage.  There was no actuation of primary safety valves. |
| All safety systems are operable and normal electrical distribution is        |
| available.                                                                   |
|                                                                              |
| The NRC Resident Inspector has been notified.                                |
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|Power Reactor                                    |Event Number:   38749       |
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| FACILITY: POINT BEACH              REGION:  3  |NOTIFICATION DATE: 03/04/2002|
|    UNIT:  [1] [2] []                STATE:  WI |NOTIFICATION TIME: 11:37[EST]|
|   RXTYPE: [1] W-2-LP,[2] W-2-LP                |EVENT DATE:        03/04/2002|
+------------------------------------------------+EVENT TIME:             [CST]|
| NRC NOTIFIED BY:  RICK ROBBINS                 |LAST UPDATE DATE:  03/04/2002|
|  HQ OPS OFFICER:  GERRY WAIG                   +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          UNUSUAL EVENT         |JOHN MADERA          R3      |
|10 CFR SECTION:                                 |CHRIS GRIMES         EO      |
|AAEC 50.72(a) (1) (i)    EMERGENCY DECLARED     |RICHARD WESSMAN      IRO     |
|                                                |JEFF GRANT           R3      |
|                                                |REGION V OSC         EPA     |
|                                                |BELCHER              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  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| UNUSUAL EVENT DUE TO UNCONTROLLED FLAMMABLE GAS LEAK ONSITE                  |
|                                                                              |
| At 0946 CST, 3/4/02, an Unusual Event was declared due to a non isolable     |
| leak on a propane tank.  The tank is approximately 500 to 750 gals, and is   |
| 55 % full.  The tank is leaking at the rate of 5% decrease every 20 minutes. |
| The tank  is 25 to 30 yards out in the Owner Controlled Area and a local     |
| area evacuation has been performed.  The Two Creek Fire Department is on the |
| scene.                                                                       |
|                                                                              |
| NRC Resident Inspector has been notified.                                    |
|                                                                              |
| At 1147 EST, NRC entered Monitoring for Normal Phase Mode.                   |
|                                                                              |
| ***EVENT UPDATED AT 1309 EST ON 3/4/02 BY MARK HANSON TO FANGIE JONES***     |
|                                                                              |
| At 1154 CST, Licensee terminated Unusual Event due to leak isolated.         |
|                                                                              |
| At 1310 EST, NRC exited monitoring for the Unusual Event.                    |
|                                                                              |
| Notified IRO (Holonich), R3DO (Madera), NRR (Grimes), PAO (Dricks), FEMA     |
| (Snyder).                                                                    |
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