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Event Notification Report for April 9, 2001

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           04/06/2001 - 04/09/2001

                              ** EVENT NUMBERS **

37895  37896  37897  37898  37899  37900  

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|Power Reactor                                    |Event Number:   37895       |
+------------------------------------------------------------------------------+
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| FACILITY: LASALLE                  REGION:  3  |NOTIFICATION DATE: 04/06/2001|
|    UNIT:  [] [2] []                 STATE:  IL |NOTIFICATION TIME: 13:27[EDT]|
|   RXTYPE: [1] GE-5,[2] GE-5                    |EVENT DATE:        04/06/2001|
+------------------------------------------------+EVENT TIME:        09:09[CDT]|
| NRC NOTIFIED BY:  D. COVEYOU                   |LAST UPDATE DATE:  04/06/2001|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MICHAEL JORDAN       R3      |
|10 CFR SECTION:                                 |                             |
|*RPS 50.72(b)(2)(iv)(B)  RPS ACTUATION - CRITICA|                             |
|*ESF 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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     A/R        Y       100      Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
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                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR SCRAM DUE TO BLOWN FUSE IN FEEDWATER CONTROL SYSTEM        |
|                                                                              |
| "This report is bring made per 10CFR50.72(b)(2)(iv)(B) RPS actuation, 4 hour |
| notification for Unit 2 and 10CFR50.72(b)(3)(iv)(A) System Actuation not     |
| including RPS, 8 hour notification for Units 1 and 2.                        |
|                                                                              |
| "At 0909, Friday 4-6-01, U-2 automatically scrammed. Initial investigations  |
| indicate that a blown fuse in the Feedwater control system caused the        |
| reactor Recirculation pumps to downshift. The resultant level swell caused   |
| reactor water level to reach the level 8 trip setpoint (plus 55 inches). The |
| main turbine tripped on the high reactor water level. The reactor scrammed   |
| due to the main turbine Stop Valves closure with reactor power above 25%     |
| power. All control rods fully inserted.                                      |
|                                                                              |
| "The Turbine driven reactor feedwater pumps tripped as designed. The Motor   |
| Driven Reactor Feedwater pump feed regulating valve locked out, the cause is |
| not known at this time. Reactor Core Isolation Cooling (RCIC) was initiated  |
| manually by the operators for reactor pressure and level control.            |
|                                                                              |
| "A primary containment level 2 isolation (primary containment cooling,       |
| containment monitoring. process sample, Unit 1 and 2 Reactor Building        |
| Ventilation. Unit 1 and 2 Standby Gas treatment initiation, Reactor water    |
| cleanup, reactor Recirculation hydraulic power units and others) occurred at |
| approximately minus 40 inches.                                               |
|                                                                              |
| "The lowest Reactor water level reached was minus 44 inches and was          |
| recovered to normal level utilizing RCIC. RCIC was operated in manual mode   |
| following erratic operation in automatic, the cause is not known at this     |
| time. System isolations have been restored with exception of reactor water   |
| cleanup on U-2.                                                              |
|                                                                              |
| "The station is taking action to investigate the cause of the blown fuse and |
| erratic RCIC operation."                                                     |
|                                                                              |
| The NRC resident inspector has been informed of this event by the licensee.  |
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+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   37896       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  MID WEST TESTING                     |NOTIFICATION DATE: 04/06/2001|
|LICENSEE:  MID WEST TESTING                     |NOTIFICATION TIME: 17:50[EDT]|
|    CITY:  HAZLEWOOD                REGION:  3  |EVENT DATE:        04/06/2001|
|  COUNTY:                            STATE:  MO |EVENT TIME:        15:00[CDT]|
|LICENSE#:  24-24619-02           AGREEMENT:  N  |LAST UPDATE DATE:  04/06/2001|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |MICHAEL JORDAN       R3      |
|                                                |LARRY CAMPER         NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  DAVID WEBER                  |                             |
|  HQ OPS OFFICER:  BOB STRANSKY                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|BAB1 20.2201(a)(1)(i)    LOST/STOLEN LNM>1000X  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LOST MOISTURE/DENSITY GAUGE                                                  |
|                                                                              |
| The licensee reported that a Humboldt Model HS-EZ moisture/density gauge     |
| (serial #3310) fell from the bed of a pickup truck in Hazlewood, MO. The     |
| device was not stored in its case at the time of the loss. The unit contains |
| one 11 millicurie Cs-137 source and one 44 millicurie Am-241/Be source.      |
|                                                                              |
| The licensee was unable to locate the gauge after retracing the route of the |
| vehicle. The licensee has contacted the local police department for          |
| assistance in recovering the gauge.                                          |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37897       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BEAVER VALLEY            REGION:  1  |NOTIFICATION DATE: 04/06/2001|
|    UNIT:  [] [2] []                 STATE:  PA |NOTIFICATION TIME: 20:46[EDT]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        04/06/2001|
+------------------------------------------------+EVENT TIME:        19:43[EDT]|
| NRC NOTIFIED BY:  JEFFREY SHIRE                |LAST UPDATE DATE:  04/07/2001|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          UNU                   |JACK MCFADDEN        R1      |
|10 CFR SECTION:                                 |CHRISTOPHER GRIMES   NRR     |
|*AEC 50.72(a) (1) (i)    EMERGENCY DECLARED     |RICHARD WESSMAN      IRO     |
|                                                |DAVID BARDON         FEMA    |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNUSUAL EVENT DECLARED DUE TO FIRE IN EXHAUST HOOD DUCTING                   |
|                                                                              |
| A fire occurred in an exhaust hood duct in the Unit 2 chemistry sample room  |
| during the processing of an oil sample. The fire was located inside the      |
| ducting. Offsite departments responded to the site. An Unusual Event was     |
| declared at 1943 EDT.  The fire was extinguished at 2022 EDT.   The NRC      |
| resident inspector has been informed of this event by the licensee.          |
|                                                                              |
| * * * UPDATE 0012EDT ON 4/7/01 FROM CARLOS CONTRERAS TO S. SANDIN * * *      |
|                                                                              |
| The licensee terminated the Unusual Event at 2300EDT on 4/6/01 based on the  |
| fact that the fire had been extinguished, current stable plant conditions,   |
| and adequate support staff availability.  The licensee informed state/local  |
| agencies and the NRC resident inspector.  Notified R1DO(McFadden),           |
| EO(Grimes) and FEMA(Bardon).                                                 |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37898       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: VOGTLE                   REGION:  2  |NOTIFICATION DATE: 04/07/2001|
|    UNIT:  [] [2] []                 STATE:  GA |NOTIFICATION TIME: 23:30[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        04/07/2001|
+------------------------------------------------+EVENT TIME:        21:23[EDT]|
| NRC NOTIFIED BY:  ROB DORMAN                   |LAST UPDATE DATE:  04/07/2001|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CAUDLE JULIAN        R2      |
|10 CFR SECTION:                                 |                             |
|*RPS 50.72(b)(2)(iv)(B)  RPS ACTUATION - CRITICA|                             |
|*ESF 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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     M/R        Y       46       Power Operation  |0        Hot Standby      |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MANUAL REACTOR TRIP DUE TO LOSS OF FEEDWATER FLOW                            |
|                                                                              |
| "While performing 14236-2, 'SGFPT A and B Trip TADOT [trip actuation device  |
| operational test]'  on SGFPT A, the link disabling the trip signal to the    |
| running SGFPT B was not fully opened, resulting in a trip of SGFPT B. The    |
| reactor was manually tripped due to no SGFPT's running. Both trains of the   |
| Reactor Protection System functioned as expected. A Feed Water Isolation was |
| received as expected from P4-Low Tavg. An Aux Feed Water Actuation Signal    |
| (AFWAS) was generated on the trip of both SGFPT's for both MDAFW pumps and   |
| on Lo-Lo Steam Generator level in two of four Steam Generators for the TDAFW |
| pump. The Steam Generator Blow Down system also Isolated properly on the     |
| AFWAS signal. The plant is currently stable in Mode 3. A shut down was in    |
| progress at the time of this event for a planned refueling outage. The       |
| refueling outage will continue as planned."                                  |
|                                                                              |
| The NRC resident inspector has been informed of this event by the licensee.  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37899       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAINT LUCIE              REGION:  2  |NOTIFICATION DATE: 04/08/2001|
|    UNIT:  [1] [2] []                STATE:  FL |NOTIFICATION TIME: 11:21[EDT]|
|   RXTYPE: [1] CE,[2] CE                        |EVENT DATE:        04/08/2001|
+------------------------------------------------+EVENT TIME:        11:15[EDT]|
| NRC NOTIFIED BY:  C. D. MARPLE                 |LAST UPDATE DATE:  04/08/2001|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CAUDLE JULIAN        R2      |
|10 CFR SECTION:                                 |                             |
|*PRE 50.72(b)(2)(xi)     OFFSITE NOTIFICATION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION INVOLVING A LOGGERHEAD TURTLE FOUND IN THE INTAKE       |
| CANAL                                                                        |
|                                                                              |
| "At 1115[EDT] on 4/8/01 a notification was made to the Florida Fish and      |
| Wildlife Conservation Commission regarding a live Loggerhead Turtle found in |
| the intake canal.  The turtle will be sent off site to a rehabilitation      |
| facility.  The notification to a state government agency requires            |
| notification to the NRC."                                                    |
|                                                                              |
| The licensee informed the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37900       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NINE MILE POINT          REGION:  1  |NOTIFICATION DATE: 04/08/2001|
|    UNIT:  [] [2] []                 STATE:  NY |NOTIFICATION TIME: 22:15[EDT]|
|   RXTYPE: [1] GE-2,[2] GE-5                    |EVENT DATE:        04/08/2001|
+------------------------------------------------+EVENT TIME:        16:15[EDT]|
| NRC NOTIFIED BY:  RICHARD LANGE                |LAST UPDATE DATE:  04/08/2001|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JACK MCFADDEN        R1      |
|10 CFR SECTION:                                 |                             |
|*INA 50.72(b)(3)(v)(A)   POT UNABLE TO SAFE SD  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| BOTH EMERGENCY DIESEL GENERATORS DECLARED INOPERABLE                         |
|                                                                              |
| "Both Division 1 and Division 2 standby diesel generators were declared      |
| inoperable. This report is being made per 10CFR50.72(b)(3)(v)(A), in that    |
| both standby diesels were in a condition such that they may not have been    |
| able to fulfill their intended safety function.                              |
|                                                                              |
| "The division 1 diesel generator was declared inoperable because both diesel |
| generator room exhaust fans were found rotating backwards.  The division 2   |
| diesel generator was declared inoperable due to one exhaust fan rotating     |
| backwards and the outside air temperature exceeding 72F. The cause of the   |
| fan blades' reverse rotation is under evaluation.  Reverse fan blade         |
| rotation may cause longer in-rush starting currents which could cause the    |
| fan motors to trip.                                                          |
|                                                                              |
| "With two diesel generators inoperable, the plant entered Technical          |
| Specification 3.8.1, a 2-hour shutdown Action Statement.                     |
|                                                                              |
| "Division 1 and 2 diesel room exhaust fans stopped rotating, and the outside |
| air temperature lowered to less than 72F The Technical Specification Action |
| Statements were exited. Periodic monitoring of the fans has been established |
| to address reoccurrence of the condition."                                   |
|                                                                              |
| The NRC resident inspector has been informed of this event by the licensee.  |
+------------------------------------------------------------------------------+