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
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 37879 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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 | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 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. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37880 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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 |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 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. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37882 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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 |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 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. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021