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
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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: 04/04/2001|
| 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
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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. |
| |
| * * * 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). |
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|Power Reactor |Event Number: 37887 |
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| 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
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| 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. |
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|Power Reactor |Event Number: 37888 |
+------------------------------------------------------------------------------+
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| 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. |
+------------------------------------------------------------------------------+
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|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. |
+------------------------------------------------------------------------------+
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|General Information or Other |Event Number: 37890 |
+------------------------------------------------------------------------------+
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| 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
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| 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." |
+------------------------------------------------------------------------------+
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|Fuel Cycle Facility |Event Number: 37891 |
+------------------------------------------------------------------------------+
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| 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
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| 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. |
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