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Event Notification Report for April 3, 2001

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           04/02/2001 - 04/03/2001

                              ** EVENT NUMBERS **

37879  37880  37882  

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|Fuel Cycle Facility                              |Event Number:   37879       |
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| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT      |NOTIFICATION DATE: 04/02/2001|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 03:42[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        04/01/2001|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        01:45[CST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  04/02/2001|
|    CITY:  PADUCAH                  REGION:  3  +-----------------------------+
|  COUNTY:  McCRACKEN                 STATE:  KY |PERSON          ORGANIZATION |
|LICENSE#:  GDP-1                 AGREEMENT:  Y  |MICHAEL JORDAN       R3      |
|  DOCKET:  0707001                              |PATRICIA HOLAHAN     NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  W. F. CAGE                   |                             |
|  HQ OPS OFFICER:  JOHN MacKINNON               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| NRC BULLETIN 91-01,  24 HOUR NOTIFICATION INVOLVING REFRIGERANT-114 (R-114)  |
| NOT IMMEDIATELY SAMPLED TO DETERMINE MOISTURE CONTENT                        |
|                                                                              |
| On 03/31/01, R-114 was transferred from a rail car to the C-335 R-114 drain  |
| tank.  Following the transfer from the rail car it was determined that the   |
| C-335 R-114 drain tank was over the desired fill level and the decision was  |
| made to transfer the R-114 from the drain tank to C-335 Unit 4 Cell 9 R-114  |
| system.  The R-114 transfer to C-335 Unit 4 Cell 9 from the C-335 drain tank |
| was completed at 1740 CST on 03/31/01.  Following the 1900 shift change on   |
| 03/31/01 the C-335 building personnel questioned if the R-114 in C-335 Unit  |
| 4 Cell 9 should be sampled for moisture.  A review of the independent assay  |
| verification for C-335 Unit 4 Cell 9 revealed the assay was greater than 1   |
| wt% U235 assay and at 0145 CST on 04/01/01 it was determined that moisture   |
| sampling was required and the Plant Shift Superintendent was notified.  NCSA |
| CAS-011 requires that if R-114 is transferred to a cell that is above        |
| 1wt%U235 assay, the R-114 in the cell must be immediately sampled to         |
| determine the moisture content. Since the time between the transfer of the   |
| R-114 to the cell and the actual sampling was determined to not meet the     |
| NCSA requirement of immediate sampling and is therefore an NCS violation.    |
|                                                                              |
| SAFETY SIGNIFICANCE OF THE EVENT:                                            |
|                                                                              |
| Although a time limit to determine moisture is not possible, the control     |
| requires sampling to start immediately as defined in the TSR.  Sampling was  |
| delayed in violation of the control procedure.                               |
|                                                                              |
| POTENTIAL CRITICALITY PATHWAYS INVOLVED:                                     |
|                                                                              |
| In order for criticality to be possible, the following sequence must occur:  |
| Wet R-114 must leak into the process gas portion of the system which         |
| contains a larger that critical mass fissile deposit.  Sufficient time to    |
| enable the hydrogen of the deposit must pass and the deposit must be in a    |
| critical geometry for criticality to be possible.                            |
|                                                                              |
| CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION, ETC.):     |
|                                                                              |
| Double contingency for this scenario is established by implementing two      |
| controls on moderation.                                                      |
|                                                                              |
| ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS AND |
| % CASE CRITICAL MASS):                                                       |
|                                                                              |
| 1.5185 wt%U235                                                               |
|                                                                              |
| NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION   |
| OF THE FAILURES OR DEFICIENCIES:                                             |
|                                                                              |
| The first leg of double contingency is based on immediately sampling of      |
| R-114 for water content.  Actual moisture content was within acceptable      |
| specifications but the sample was not taken in accordance with the time      |
| requirement for control.  Specifically the control requires immediate        |
| sampling upon completion of the addition of R-114.                           |
|                                                                              |
| CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEMS AND WHEN EACH WAS IMPLEMENTED:  |
|                                                                              |
|                                                                              |
| The R-114 was sampled at 0300 on 04/1/01 with the moisture level determined  |
| to be within specifications.                                                 |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the Certificate     |
| Holder.                                                                      |
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|Power Reactor                                    |Event Number:   37880       |
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| FACILITY: COMANCHE PEAK            REGION:  4  |NOTIFICATION DATE: 04/02/2001|
|    UNIT:  [1] [] []                 STATE:  TX |NOTIFICATION TIME: 06:53[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        04/02/2001|
+------------------------------------------------+EVENT TIME:        04:02[CST]|
| NRC NOTIFIED BY:  BEAUDIN                      |LAST UPDATE DATE:  04/02/2001|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |DAVE LOVELESS        R4      |
|10 CFR SECTION:                                 |                             |
|*DEG 50.72(b)(3)(ii)(A)  DEGRAD COND DURING OP  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| GREATER THAN 1 PERCENT OF STEAM GENERATOR # 3 TUBES FOUND TO  BE POTENTIALLY |
| DEGRADED.                                                                    |
|                                                                              |
| At approximately 0402 CT on 04/02/01, Comanche Peak discovered that more     |
| than 1% (52 out of 4772 tubes) of the inspected tubes in Steam Generator # 3 |
| are potentially degraded.  The degraded tubes are being evaluated to be      |
| removed from service.  This event meets the criteria of C-3 as described in  |
| their Technical Specification section 5.5.9.  Additional data is being       |
| collected and will be analyzed to assist in determining the cause of the     |
| event.  An LER will be issued to further document this issue.  The other     |
| three Steam Generator tubes are being inspected.                             |
|                                                                              |
| The NRC Resident Inspector will be notified of this event by the licensee.   |
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|Power Reactor                                    |Event Number:   37882       |
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| FACILITY: SAINT LUCIE              REGION:  2  |NOTIFICATION DATE: 04/02/2001|
|    UNIT:  [1] [] []                 STATE:  FL |NOTIFICATION TIME: 17:35[EDT]|
|   RXTYPE: [1] CE,[2] CE                        |EVENT DATE:        04/02/2001|
+------------------------------------------------+EVENT TIME:        17:10[EDT]|
| NRC NOTIFIED BY:  DAVE WILLIAMS                |LAST UPDATE DATE:  04/02/2001|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          UNU                   |EDWARD MCALPINE      R2      |
|10 CFR SECTION:                                 |JOHN ZWOLINSKI       NRR     |
|*AEC 50.72(a) (1) (i)    EMERGENCY DECLARED     |RICHARD WESSMAN      IRO     |
|                                                |AUSTIN               FEMA    |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Hot Shutdown     |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| REACTOR COOLANT SYSTEM LEAKAGE >10 GPM AS OBSERVED FROM CONTROL ROOM         |
| INDICATIONS                                                                  |
|                                                                              |
| The licensee was in the process of placing the '1A' train of shutdown        |
| cooling system in service, when relief valve V-3483 lifted.  Opening V-3481, |
| shutdown cooling hotleg suction valve, caused pressurizer level to decrease  |
| about 4% in 5 minutes which corresponds to about 80 gpm.  The leak was       |
| terminated when V-3481 was closed.  The Unusual Event was declared and       |
| terminated at 1710 EDT when the leak was isolated.                           |
|                                                                              |
| The licensee intends to notify the NRC Resident Inspector and has notified   |
| the State of Florida.                                                        |
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