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Event Notification Report for April 5, 2001

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           04/04/2001 - 04/05/2001

                              ** EVENT NUMBERS **

37880  37887  37888  37889  37890  37891  

+------------------------------------------------------------------------------+
|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:  04/04/2001|
|  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.   |
|                                                                              |
| * * * UPDATE ON 04/03/01 AT 0653 ET BY RAUL MARTINEZ TAKEN BY MACKINNON * *  |
| *                                                                            |
|                                                                              |
| GREATER THAN 1 PERCENT OF STEAM GENERATOR # 4 TUBES FOUND TO BE POTENTIALLY  |
| DEFECTIVE.                                                                   |
|                                                                              |
| At approximately 0500 CT on 04/03/01 Comanche Peak discovered that more than |
| 1% (49 out of 4777 tubes) of the inspected tubes in Steam Generator # 4 are  |
| potentially defective.  The defective tubes are being evaluated to be        |
| removed from service.                                                        |
|                                                                              |
| This event meets the criteria of C-3 as described in the 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.                    |
|                                                                              |
| The licensee is presently inspecting Steam Generators 1 and 2.  R4DO (Linda  |
| Smith) notified.                                                             |
|                                                                              |
| The NRC Resident Inspector will be notified of this update by the licensee.  |
|                                                                              |
| ***** UPDATE AT 0015 EDT ON 04/04/01 FROM RAUL MARTINEZ TO LEIGH TROCINE     |
| *****                                                                        |
|                                                                              |
| GREATER THAN 1% OF THE INSPECTED STEAM GENERATOR #2 TUBES WERE FOUND TO BE   |
| POTENTIALLY DEFECTIVE.                                                       |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "At approximately 2237 [CDT] on [04/03/01,] Comanche Peak Unit 1 discovered  |
| that more than 1% of the inspected tubes in steam generator #2 [were]        |
| potentially defective.  The defective tubes are being evaluated to be        |
| removed from service."                                                       |
|                                                                              |
| "This event meets the criteria of C-3 as described in [...] Technical        |
| Specification section 5.5.9 and is being reported pursuant to the            |
| requirements of 10 CFR 50.72(b)(3)(ii)(A).  Additional data is being         |
| collected and will be analyzed to assist in determining the cause of the     |
| event."                                                                      |
|                                                                              |
| "[The total number] of inservice tubes in [steam generator] #2 = 4,476       |
| tubes.  [The total number] of tubes discovered defective at this time = 52   |
| tubes."                                                                      |
|                                                                              |
| The licensee plans to notify the NRC resident inspector.  The NRC operations |
| officer notified the R4DO (Linda Smith).                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37887       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DRESDEN                  REGION:  3  |NOTIFICATION DATE: 04/04/2001|
|    UNIT:  [] [2] []                 STATE:  IL |NOTIFICATION TIME: 02:19[EDT]|
|   RXTYPE: [1] GE-1,[2] GE-3,[3] GE-3           |EVENT DATE:        04/03/2001|
+------------------------------------------------+EVENT TIME:        23:58[CDT]|
| NRC NOTIFIED BY:  RON WIGGINS                  |LAST UPDATE DATE:  04/04/2001|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MICHAEL PARKER       R3      |
|10 CFR SECTION:                                 |                             |
|*RPS 50.72(b)(2)(iv)(B)  RPS ACTUATION - CRITICA|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     M/R        Y       27       Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MANUAL REACTOR SCRAM FROM 27% POWER DUE TO A RECIRULATION PUMP TRIP FOR      |
| UNKNOWN REASONS WHILE THE UNIT WAS IN SINGLE LOOP OPERATION                  |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "[The] unit was operating [in] single loop (2A [recirculation] pump          |
| operating) when the 2A [recirculation] pump tripped.  The [nuclear station   |
| operator] manually scrammed the unit as required by procedure.  During the   |
| event, Group II and III isolations were received.  All equipment operated as |
| expected.  [The] unit is [currently] stable in Mode 3.  Restart is being     |
| evaluated."                                                                  |
|                                                                              |
| The licensee stated that reactor vessel water level decreased to +5 inches   |
| and that the Group II and III isolation setpoint was +8 inches.  The Group   |
| II and III isolations have been reset, and ventilation has been restored.    |
|                                                                              |
| The normal reactor feedwater system is currently being utilized to supply    |
| water to the reactor vessel, and containment parameters are normal.  The     |
| steam dumps to the condenser were available but not needed.                  |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37888       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BROWNS FERRY             REGION:  2  |NOTIFICATION DATE: 04/04/2001|
|    UNIT:  [] [2] []                 STATE:  AL |NOTIFICATION TIME: 07:22[EDT]|
|   RXTYPE: [1] GE-4,[2] GE-4,[3] GE-4           |EVENT DATE:        04/03/2001|
+------------------------------------------------+EVENT TIME:        23:51[CDT]|
| NRC NOTIFIED BY:  DAVID TIDWELL                |LAST UPDATE DATE:  04/04/2001|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |KEN BARR             R2      |
|10 CFR SECTION:                                 |                             |
|*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          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| REACTOR SCRAM ON WEST SCRAM DISCHARGE VOLUME HIGH WATER LEVEL DUE TO         |
| APPARENT LEAKAGE THROUGH THE SCRAM VALVES                                    |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "During a refueling outage while picking up a hold order on the control rod  |
| drive system, water level in the scram discharge volume instrument volume    |
| started to rise from apparent leakage through the scram valves.  At 2351     |
| [CDT,] a reactor scram was received on the west scram [discharge volume]     |
| high water level.  All expected alarms and actuations were received.  All    |
| control rods were initially 'full in,' and no rod movement occurred."        |
|                                                                              |
| The licensee stated that there was nothing unusual or misunderstood and that |
| all systems functioned as required.  The licensee also stated that at the    |
| time of the event, work was being performed on the scram discharge volume    |
| drain valves which inhibited the ability to drain the scram discharge        |
| volume.                                                                      |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37889       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAINT LUCIE              REGION:  2  |NOTIFICATION DATE: 04/04/2001|
|    UNIT:  [1] [] []                 STATE:  FL |NOTIFICATION TIME: 10:50[EDT]|
|   RXTYPE: [1] CE,[2] CE                        |EVENT DATE:        04/04/2001|
+------------------------------------------------+EVENT TIME:        10:12[EDT]|
| NRC NOTIFIED BY:  DAVE WILLIAMS                |LAST UPDATE DATE:  04/04/2001|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          UNU                   |KEN BARR             R2      |
|10 CFR SECTION:                                 |TAD MARSH            NRR     |
|*AEC 50.72(a) (1) (i)    EMERGENCY DECLARED     |RICHARD WESSMAN      IRO     |
|                                                |GARY BELCHER         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                                                                  |
|                                                                              |
| "EMERGENCY PLAN ENTRY DUE TO CONTROL ROOM INDICATION OF REACTOR COOLANT      |
| SYSTEM LEAKAGE GREATER THAN 10 GPM.  IT APPEARS THAT SHUTDOWN COOLING RELIEF |
| VALVE V-3483 LIFTED WHILE ATTEMPTING TO PLACE '1A' TRAIN OF SHUTDOWN COOLING |
| IN SERVICE.  WHEN V-3481, HOT LEG SUCTION VALVE, WAS OPENED, APPROXIMATELY   |
| 300 GALLONS OF REACTOR COOLANT WAS DIVERTED TO A HOLDUP TANK OVER A PERIOD   |
| OF 2 MINUTES.  THE LEAK, ESTIMATED AT 150 GPM, WAS ISOLATED BY CLOSING HOT   |
| LEG SUCTION VALVE V-3480.  AN UNUSUAL EVENT WAS ENTERED AND TERMINATED       |
| IMMEDIATELY AT 1012 HOURS AS THE LEAK HAD BEEN TERMINATED AT THE TIME OF THE |
| NOTIFICATION.                                                                |
|                                                                              |
| "THIS EVENT IS SIMILAR TO EVENT #37882."                                     |
|                                                                              |
| RCS PRESSURE AND TEMPERATURE IS CURRENTLY 260 PSIG AND 250 DEGREES F,        |
| RESPECTIVELY.  THE RELIEF VALVE SETPOINT IS 330 PSIG.  FOLLOWING THE         |
| PREVIOUS EVENT, THE RELIEF VALVE V-3483 WAS REMOVED AND BENCH TESTED WITH NO |
| ABNORMALITIES RELATED TO THE SETPOINT PRESSURE FOUND.  PRESENTLY, THERE ARE  |
| TWO (2) RCPs RUNNING WITH A THIRD AVAILABLE AND THE "1B" SHUTDOWN COOLING    |
| TRAIN IN SERVICE.  THE LICENSEE PER A PROCEDURAL  REQUIREMENT INVOLVING LOW  |
| PRESSURE OPERATION OF THE RCPs (RCP SEAL PROTECTION) IS IN A 12 HOUR TIME    |
| PERIOD ENDING AT 1600 HOURS.  THE CURRENT PLANS ARE TO INCREASE RCS PRESSURE |
| TO GREATER THAN 350 PSIG.  BOTH STEAM GENERATORS ARE AVAILABLE TO REMOVE     |
| DECAY HEAT.  UNIT 1 HAS BEEN SHUTDOWN FOR APPROXIMATELY 50 HOURS.  AN EVENT  |
| RESPONSE TEAM HAS BEEN ASSEMBLED TO RECOMMEND APPROPRIATE CORRECTIVE ACTIONS |
| FOLLOWING COMPLETION OF AN INVESTIGATION.                                    |
|                                                                              |
| THE LICENSEE INFORMED STATE/LOCAL AGENCIES AND THE NRC RESIDENT INSPECTOR.   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   37890       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  ALABAMA RADIATION CONTROL            |NOTIFICATION DATE: 04/04/2001|
|LICENSEE:  JACKSON PAVING AND CONSTRUCTION, INC.|NOTIFICATION TIME: 17:32[EDT]|
|    CITY:  SCOTTSBORO               REGION:  2  |EVENT DATE:        04/04/2001|
|  COUNTY:                            STATE:  AL |EVENT TIME:        07:00[CDT]|
|LICENSE#:  1167                  AGREEMENT:  Y  |LAST UPDATE DATE:  04/04/2001|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |KEN BARR             R2      |
|                                                |LARRY CAMPER         NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  JAMES McNEES                 |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT CONCERNING STOLEN GAUGE                               |
|                                                                              |
| "On the morning of April 4, 2001, the Alabama Office of Radiation Control    |
| was advised that a CPN model AC-2 asphalt content gauge (serial number       |
| A29099099) had been stolen from the facilities of Jackson Paving and         |
| Construction, Inc. located in Scottsboro, AL. Jackson Paving and             |
| Construction, Inc. is authorized to possess and use the device under Alabama |
| Radioactive Material License No. 1167. The device contains 100 millicuries   |
| of Am-241/Be and the theft was discovered at approximately 7:00 am CDT on    |
| April 4, 2001. Along with the gauge, other items such as a generator,        |
| torches, radio, etc. were also stolen. The theft is being investigated by    |
| the Scottsboro City Police. The device was not in the transport container at |
| the time of the theft.                                                       |
|                                                                              |
| "The licensee's building located in Skyline, Alabama was also broken into    |
| and the two incidents may or may not be related. Local Emergency Management  |
| Agency personnel were advised to inform the Jackson County Sheriff and local |
| police that stolen radioactive devices are typically abandoned quickly by    |
| the thief because they have no sale value."                                  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   37891       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 04/04/2001|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 18:35[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        04/04/2001|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        08:27[EDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  04/04/2001|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |MICHAEL JORDAN       R3      |
|  DOCKET:  0707002                              |LARRY CAMPER         NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  JIM McCLEERY                 |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| NRC BULLETIN 91-01 24 HOUR REPORT                                            |
|                                                                              |
| The following is a portion of a faxed report:                                |
|                                                                              |
| "At 0827 Pressure in 33-5-4 was found to be 13.80 psia. The pressure         |
| requirement in 33-5-4 is 14 psia when not in a fluorinating environment as   |
| required in NCSA PLANT 333-15.A05. The Plant Shift Superintendent directed   |
| the facility to enter an anomalous condition. Pressure was regained in the   |
| equipment and the facility exited the anomalous condition."                  |
|                                                                              |
| "SAFETY SIGNIFICANCE OF EVENTS:"                                             |
|                                                                              |
| "Safety significance of this event is low. The deposit size in the cell is   |
| less than H/U=4 safe mass and the cell is isolated from the operating        |
| cascade. If the unbuffered condition were permitted to continue for a long   |
| period of time, the H/U of the deposit could eventually reach a maximum of   |
| 4. However, since the mass of the deposit is known to be less than or equal  |
| to the safe mass at H/U=4, a criticality could not occur."                   |
|                                                                              |
| "POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO[S] OF HOW           |
| CRITICALITY COULD OCCUR):"                                                   |
|                                                                              |
| "For a criticality to occur the deposit in the cell would have to be         |
| moderated the mass of the deposit would have to increase and the deposit     |
| would have to be reflected."                                                 |
|                                                                              |
| "CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION, ETC.):"   |
|                                                                              |
| "Mass and Moderation"                                                        |
|                                                                              |
| "ESTIMATED AMOUNT, ENRICHMENT FORM OF LICENSED MATERIAL (INCLUDE PROCESS     |
| LIMIT AND % WORST CASE OF CRITICAL MASS):"                                   |
|                                                                              |
| "The estimated enrichment of the cell is 1.27% U-235, the mass is less than  |
| safe mass."                                                                  |
|                                                                              |
| "NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION  |
| OF THE FAILURES OR DEFICIENCIES:"                                            |
|                                                                              |
| "The NCS control was a dry air buffer to >14 psia. The control was           |
| established by pressuring the cell to 16.5 psia. The cell was found to be at |
| 13.8 psia."                                                                  |
|                                                                              |
| "CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEM AND WHEN EACH WAS               |
| IMPLEMENTED:"                                                                |
|                                                                              |
| "The cell was restored to a pressure >14 psia at 0850."                      |
|                                                                              |
| Portsmouth personnel notified the NRC Resident Inspector and the DOE         |
| representative.                                                              |
+------------------------------------------------------------------------------+