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Event Notification Report for August 2, 2001

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           08/01/2001 - 08/02/2001

                              ** EVENT NUMBERS **

38149  38179  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
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|Fuel Cycle Facility                              |Event Number:   38149       |
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| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 07/18/2001|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 13:05[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        07/17/2001|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        15:30[EDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  08/01/2001|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |BRUCE JORGENSEN      R3      |
|  DOCKET:  0707002                              |BRIAN SMITH          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  SALYERS                      |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|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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| HIGH PRESSURE FIRE WATER SPRINKLER SYSTEM DECLARED INOPERABLE                |
|                                                                              |
| On 7/17/01 at approximately 1530 hrs, the Plant Shift Superintendent (PSS)   |
| was notified that during a Fire Protection Engineering assessment/inspection |
| that High Pressure Fire Water (HPFW) sprinkler system #165 in the X-333      |
| Building contained five adjacent sprinkler heads with visible corrosion      |
| deposits.  Previous engineering reviews have concluded that the system under |
| this condition would not be capable of meeting the Technical Safety          |
| Requirements (TSR) to maintain operability.                                  |
|                                                                              |
| The PSS declared the affected sprinkler system inoperable and TSR required   |
| actions were implemented.                                                    |
|                                                                              |
| The NRC Resident Inspector was notified along with the DOE Representative.   |
|                                                                              |
| * * * RETRACTION ON 08/01/01 AT 1600 ET BY KURT SISLER TAKEN BY MACKINNON *  |
| * *                                                                          |
|                                                                              |
| This event is being retracted based upon engineering evaluation              |
| (EVAL-SE-2001-0321) approved on July 31, 2001.  Functional testing of these  |
| sprinkler heads was conducted.  The results showed that all these sprinkler  |
| heads would have operated when needed and performed their intended safety    |
| function.  R3DO (John Madera) & NMSS EO (Brian Smith) notified.              |
|                                                                              |
| The NRC resident inspector was notified of this retraction by the            |
| certificate holder.                                                          |
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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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