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Event Notification Report for August 3, 2001

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           08/02/2001 - 08/03/2001

                              ** EVENT NUMBERS **

38179  38180  38181  38182  38183  

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|Power Reactor                                    |Event Number:   38179       |
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| FACILITY: PRAIRIE ISLAND           REGION:  3  |NOTIFICATION DATE: 08/01/2001|
|    UNIT:  [1] [] []                 STATE:  MN |NOTIFICATION TIME: 09:05[EDT]|
|   RXTYPE: [1] W-2-LP,[2] W-2-LP                |EVENT DATE:        08/01/2001|
+------------------------------------------------+EVENT TIME:        07:01[CDT]|
| NRC NOTIFIED BY:  BRUCE ANDERSON               |LAST UPDATE DATE:  08/02/2001|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |PATRICK HILAND       R3      |
|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     A/R        Y       100      Power Operation  |0        Hot Standby      |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| AUTOMATIC REACTOR TRIP DUE TO NEGATIVE FLUX RATE                             |
|                                                                              |
| The unit automatically tripped from 100%; the first out annunciator was Flux |
| Rate Reactor Trip.  Immediately following the trip, the rod position         |
| indicator showed that five control rods did not insert completely. The stuck |
| control rods indicated 15-20 steps out from bottom. Operators entered their  |
| reactor trip/safety injection emergency procedure (1E0), but were able to    |
| transition to the trip recovery procedure (1ES0.1). One of the stuck control |
| rods subsequently indicated full insertion. The unit is currently stable in  |
| Mode 3. Operators are emergency borating the reactor per 1ES0.1 a total of   |
| 1000 gallons (250 gallons per stuck rod). The licensee is continuing their   |
| trip recovery.  Preliminary investigation indicates a problem with the rod   |
| control system may have led to one or more dropped control rods.             |
|                                                                              |
| The NRC resident inspector has been informed of this event by the licensee.  |
|                                                                              |
| * * * UPDATE 1025 EDT 8/1/01 FROM DAMMANN TAKEN BY JONES * * *               |
|                                                                              |
| The licensee reported that the auxiliary feedwater (AFW) system (pumps 11    |
| and 12) automatically actuated on steam generator low-low level following    |
| the trip, as expected.  In addition, two of the stuck rods are now           |
| indicating full insertion. The NRC resident inspector has been informed of   |
| this update.                                                                 |
|                                                                              |
| * * * UPDATE 1624 EDT 08/01/01 FROM GOSMAN TAKEN BY MACKINNON * * *          |
|                                                                              |
| After interviewing the Reactor Operators it was determined that 6 rod bottom |
| lights did not immediately come on after the reactor trip.  Also a media     |
| press release will be made concerning this event.  R3DO (John Madera)        |
| notified.                                                                    |
|                                                                              |
| The NRC resident inspector was notified of this update by the licensee.      |
|                                                                              |
| * * * UPDATE 0431 EDT 8/2/01 FROM IRVIN TAKEN BY STRANSKY * * *              |
|                                                                              |
| "Investigation into the cause of the reactor trip has determined that        |
| control rods associated with Rod Control Power Cabinet 2AC began to insert   |
| into the core. As designed, the reactor protection system actuated to insert |
| the remaining control rods.                                                  |
|                                                                              |
| "In accordance with procedures, operators verified the reactor had safely    |
| shutdown. However, indicator lights for six of twenty-nine individual        |
| control rods did not indicate that the rods had fully inserted. This         |
| situation is addressed in the reactor trip procedure and the operators       |
| responded appropriately by borating to compensate.                           |
|                                                                              |
| "Control rod drop testing has been performed and has verified that all       |
| control rods fully inserted. Individual rod position indication calibration  |
| check is in progress."                                                       |
|                                                                              |
| The NRC resident inspector will be informed of this update by the licensee.  |
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|Other Nuclear Material                           |Event Number:   38180       |
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| REP ORG:  NTH CONSULTANTS                      |NOTIFICATION DATE: 08/02/2001|
|LICENSEE:  NTH CONSULTANTS                      |NOTIFICATION TIME: 08:49[EDT]|
|    CITY:  FARMINGTON HILLS         REGION:  3  |EVENT DATE:        08/02/2001|
|  COUNTY:                            STATE:  MI |EVENT TIME:        07:50[EDT]|
|LICENSE#:  21-14894-01           AGREEMENT:  N  |LAST UPDATE DATE:  08/02/2001|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |JOHN MADERA          R3      |
|                                                |BRIAN SMITH          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  JIM CARSONS                  |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|BAB1 20.2201(a)(1)(i)    LOST/STOLEN LNM>1000X  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| STOLEN TROXLER MOISTURE DENSITY GAUGE                                        |
|                                                                              |
| The licensee reported a missing (presumed stolen) Troxler moisture density   |
| gauge, model #3401 serial #14236.  The gauge was discovered missing from the |
| bed of a pickup where it had been locked in its case and the case cabled to  |
| the truck.  The gauge contains 2 sources, one of approximately 8 mCi Cs-137  |
| and the other 40 mCi Am-241:Be.  The licensee intends to make a police       |
| report and is retracing the trucks route from the work site back to the      |
| driver's home located in Farmington Hills, MI.                               |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38181       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: QUAD CITIES              REGION:  3  |NOTIFICATION DATE: 08/02/2001|
|    UNIT:  [] [2] []                 STATE:  IL |NOTIFICATION TIME: 10:07[EDT]|
|   RXTYPE: [1] GE-3,[2] GE-3                    |EVENT DATE:        08/02/2001|
+------------------------------------------------+EVENT TIME:        08:23[CDT]|
| NRC NOTIFIED BY:  TOM OSELAND                  |LAST UPDATE DATE:  08/02/2001|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          UNUSUAL EVENT         |JOHN MADERA          R3      |
|10 CFR SECTION:                                 |PAT MADDEN           NRR     |
|AAEC 50.72(a) (1) (i)    EMERGENCY DECLARED     |JOSEPH HOLONICH      IRO     |
|ARPS 50.72(b)(2)(iv)(B)  RPS ACTUATION - CRITICA|MARK RING            R3      |
|AESF 50.72(b)(3)(iv)(A)  VALID SPECIF SYS ACTUAT|JAMES DYER           R3      |
|                                                |STEINDURF            FEMA    |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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     |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNUSUAL EVENT DECLARED DUE TO LOSS OF OFFSITE POWER FOLLOWING LIGHTNING      |
| STRIKE                                                                       |
|                                                                              |
| At 0823 CDT, the licensee declared an Unusual Event due to a lightning       |
| strike on or near the Unit 2 main transformer which caused a fire in the     |
| transformer and a loss of offsite power to the unit. Both emergency diesel   |
| generators (the Unit 2 and swing EDGs) started and loaded.  An automatic     |
| reactor scram occurred and all control rods inserted following the scram.    |
| The unit is currently in Hot Shutdown with decay heat being removed via the  |
| safety/relief valves and reactor vessel water level control being maintained |
| using the safe shutdown makeup pump and the reactor core isolation cooling   |
| (RCIC) system.                                                               |
|                                                                              |
| Offsite firefighting assistance was requested to combat the fire, which has  |
| since been extinguished. The licensee is currently in the process of         |
| restoring offsite power to the unit. The electrical transient did not        |
| significantly affect the operation of Unit 1.                                |
|                                                                              |
| The NRC resident inspector has been informed by the licensee.                |
|                                                                              |
| HOO NOTE: The NRC senior resident inspector notified the NRC Operations      |
| Center of this event at 0933 EDT. The agency entered the monitoring phase of |
| normal mode at 1003 EDT.                                                     |
|                                                                              |
| * * * UPDATE 1220EDT ON 8/2/01 FROM FOSTER (REGION 3 IRC) TO S. SANDIN * *   |
| *                                                                            |
|                                                                              |
| Region 3 has secured from Monitoring at 1120CDT based on current plant       |
| conditions and the licensee's on-going restoration of offsite power.         |
| Notified IRO(Holonich).                                                      |
|                                                                              |
| * * * UPDATE 1253EDT ON 8/2/01 FROM CHRISSOTIMOS TO S. SANDIN * * *          |
|                                                                              |
| Unit 2 exited the Unusual Event at 1147CDT.  The following information was   |
| provided via fax:                                                            |
|                                                                              |
| "The Unit 2 and 1/2 [Swing] Emergency Diesel Generators Auto Started on the  |
| ESF signal. Group II and III isolations were received as expected. Local     |
| Fire Department assisted in fire activities and extinguished transformer     |
| fire. RCIC and the Safe Shutdown Makeup Pump were manually initiated to      |
| provide level control. Relief valves were manually operated to control       |
| pressure.  At 1048 CDT Transformer 22 power was restored and is providing    |
| loads to Unit 2. Both EDG's have been shutdown. The Illinois Emergency       |
| Management Agency has been notified of the Hazmat spill from the transformer |
| fire.                                                                        |
|                                                                              |
| "A courtesy call was also made to the National Response Center for a         |
| potential of a Hazmat spill into the Mississippi River [NRC Incident Report  |
| # 575186].                                                                   |
|                                                                              |
| "The Unusual Event was terminated at 1147 CDT."                              |
|                                                                              |
| The licensee is in the process of informing state/local agencies and has     |
| informed the NRC resident inspector.  Notified R3DO(Madera), EO(Madden),     |
| IRO(Holonich), EDO(Bergman) and FEMA(Caldwell).                              |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   38182       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT      |NOTIFICATION DATE: 08/02/2001|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 18:10[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        08/02/2001|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        12:38[CDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  08/02/2001|
|    CITY:  PADUCAH                  REGION:  3  +-----------------------------+
|  COUNTY:  McCRACKEN                 STATE:  KY |PERSON          ORGANIZATION |
|LICENSE#:  GDP-1                 AGREEMENT:  Y  |JOHN MADERA          R3      |
|  DOCKET:  0707001                              |LARRY CAMPER         NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  M. C. PITTMAN                |                             |
|  HQ OPS OFFICER:  STEVE SANDIN                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NONR                     OTHER UNSPEC REQMNT    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 24-HOUR REPORT INVOLVING A SAFETY SYSTEM ACTUATION DUE TO A VALID SIGNAL     |
|                                                                              |
| "At 1250 on 08/02/01, the PSS office was notified that a High Autoclave      |
| Steam Pressure alarm was received on the C-337A  autoclave position 2 west   |
| Autoclave Steam Pressure Control System (SPCS). The SPCS system is required  |
| to be operable while feeding in mode 5 according to TSR 2.2.3.3. The         |
| autoclave was in Mode 5 at the time of the actuation. The indications were   |
| checked according to the alarm response procedure and the alarm was          |
| determined to be a valid signal. The autoclave was removed from service and  |
| the Steam Pressure Control System was declared inoperable by the Plant Shift |
| Superintendent.                                                              |
|                                                                              |
| "This safety system actuation is reportable to the NRC as required by Safety |
| Analysis Report, section 6.9, table 1, criteria J.2, Safety System actuation |
| due to a valid signal as a 24-hour event notification.                       |
|                                                                              |
| "The NRC Senior Resident Inspector has been notified of this event."         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38183       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT             REGION:  1  |NOTIFICATION DATE: 08/02/2001|
|    UNIT:  [] [3] []                 STATE:  NY |NOTIFICATION TIME: 19:17[EDT]|
|   RXTYPE: [2] W-4-LP,[3] W-4-LP                |EVENT DATE:        08/02/2001|
+------------------------------------------------+EVENT TIME:        15:00[EDT]|
| NRC NOTIFIED BY:  TIM RIEGER                   |LAST UPDATE DATE:  08/02/2001|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |CLIFFORD ANDERSON    R1      |
|10 CFR SECTION:                                 |HERB BERKOW          NRR     |
|AUNA 50.72(b)(3)(ii)(B)  UNANALYZED CONDITION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|3     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNANALYZED CONDITION INVOLVING SEISMIC EVENT DISCOVERED DURING ENGINEERING   |
| REVIEW                                                                       |
|                                                                              |
| "On August 2, 2001, at approximately 1500 hours, Engineering notified        |
| operations that the Service Water (SW) System may not meet analyzed flow     |
| requirements after a seismic event as a result of a system re-alignment      |
| change implemented June 4, 2001. The SWS re-alignment change placed an 8     |
| inch non-seismic SW line on the essential SW header. The SWS was originally  |
| analyzed for a seismic event with the break of a 10 inch non-seismic SW      |
| line. The change evaluation concluded that this configuration was bounding   |
| for the alignment. The assessment of the alignment change did not adequately |
| consider the effects of the seismic event. After a review of the change,     |
| Engineering judged that the SWS would not meet system design flow            |
| requirement after a seismic event with two out of three pumps due to the     |
| failure of both non-seismic lines that were aligned as a result of the       |
| change. Operations initiated realignment of the 8 inch SW line back to the   |
| non-essential header which was completed at 1640 hours. Engineering is       |
| performing evaluations but judged that the SWS would have met flow           |
| requirements for plant shutdown with three SW pumps operable after a seismic |
| event with no random single failure (three pumps operable)."                 |
|                                                                              |
| The licensee will inform the NRC resident inspector.                         |
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