Event Notification Report for March 13, 2001
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
03/12/2001 - 03/13/2001
** EVENT NUMBERS **
37821 37826 37827 37828 37829 37830
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|Power Reactor |Event Number: 37821 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CALLAWAY REGION: 4 |NOTIFICATION DATE: 03/09/2001|
| UNIT: [1] [] [] STATE: MO |NOTIFICATION TIME: 20:46[EST]|
| RXTYPE: [1] W-4-LP |EVENT DATE: 03/09/2001|
+------------------------------------------------+EVENT TIME: 12:51[CST]|
| NRC NOTIFIED BY: GARY OLMSTEAD |LAST UPDATE DATE: 03/12/2001|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |WILLIAM JOHNSON R4 |
|10 CFR SECTION: | |
|*ESF 50.72(b)(3)(iv)(A) VALID SPECIF SYS ACTUAT| |
|*PRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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 |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LOSS OF BOTH CONTROL ROD DRIVE MOTOR GENERATORS CAUSES REACTOR TRIP |
| |
| During performance of work on the 'B' Rod Drive Motor Generator set, the |
| output breaker for 'A' Rod Drive Motor Generator set opened causing a loss |
| of power to the Rod Control System. The cause of the 'A' Rod Drive Motor |
| Generator set output breaker opening is being investigated. With a loss of |
| power, all rods were de-energized and inserted into the core. Rod K-10 |
| developed an alarm and the problem was determined to be a faulty circuit |
| card. The circuit card was replaced and the problem corrected. |
| |
| This event resulted in a Reactor Protection System (RPS) actuation, when |
| rods were inserted, an Over Temperature delta T (OTdeltaT) trip was |
| generated which generated the RPS actuation. After the RPS system actuated, |
| an Auxiliary Feedwater System actuation was generated. |
| |
| It was concluded this event is reportable per 10CFR50.72(b)(3)(iv)(A) |
| since: |
| (1) The actuation of the Reactor Protection System occurred after the rods |
| were at the bottom of the Reactor core (i.e. shut down) as indicated by |
| computer point alarm printout. |
| |
| The NRC Resident inspector was notified of this event by the licensee. |
| |
| * * * UPDATE 1500EST ON 3/12/01 FROM ROBERT BARTON TO S. SANDIN * * * |
| |
| The licensee is updating this report with the following information: |
| |
| "Update to the NRC Notification of Reactor Trip due to Loss of Both Rod |
| Drive Motor Generator Sets at Callaway Event Number 37821. |
| |
| "This 4-hour call is being made to the NRC 1) to inform the NRC that a |
| Notification was made to the Missouri Public Service Commission reporting |
| the Reactor Trip due to the loss of both Rod Drive Motor Generators which |
| resulted in an outage expected to last longer than 72 hours and 2) to |
| clarify information presented on March 9, 2001 concerning the Reactor Trip |
| due to a loss of electrical power to the Rod Control System at the Callaway |
| Plant. |
| |
| Time of Notification to NRC Ops Center 1400 |
| Event Number assigned by NRC 37821 |
| NRC staff contacted at Ops Center Steve |
| Sandin |
| Event Time (time of notification) |
| 1400 |
| Event Date (date of notification) |
| 3/12/0 1 |
| Mode/Power before event |
| 2/1 percent Reactor Power |
| Mode/Power after event |
| 2/1 percent Reactor Power |
| Event Classification |
| 10CFR50.72(b)(2)(xi) |
| Was NRC Resident notified |
| Yes |
| Was State notified |
| No |
| Was other local government agencies notified Yes |
| Is media press release planned No |
| Anything unusual or not understood about the event N/A |
| Did all systems function as required N/A |
| |
| "1) The following was reported to the Missouri PSC at 1248, 3/12/01: |
| |
| 'The following is a report to the Missouri Public Service Commission (MPSC) |
| involving a Reactor Trip due to a loss of both Rod Drive Motor Generators at |
| the Callaway Plant and is reportable under 4CSR240-20.080(3)(B) because the |
| outage is expected to last longer than 72 hours. |
| |
| 'At 1251 on March 9, 2001, work was commencing on one Rod Drive Motor |
| Generator when the alternate Rod Drive Motor Generator electrical output |
| breaker failed open. This caused the Reactor Control Rods to be de-energized |
| and insert into the Reactor core. Thc rod insertion shut the Reactor down |
| and the plant continues to remain shut down to support repairs on equipment |
| not related to the primary Reactor systems.' |
| |
| "2) On March 9, 2001, the NRC Ops Center was informed of the Reactor Trip at |
| Callaway that occurred because of a loss of both Rod Control Motor |
| Generators. During the notification, it was mentioned that the press had |
| been notified and a copy of the statement faxed to the NRC Ops Center also |
| reflected this. What was not covered was the time of the news release. The |
| news media was faxed a release at 1645 on 3/9/01. This information is being |
| supplied to ensure clarity that the NRC had been notified of a news release |
| within the required 4-hour time limit. |
| |
| "The NRC Resident Inspector was notified of this event by the licensee." |
| |
| Notified R4DO (Johnson). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37826 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MAINE YANKEE REGION: 1 |NOTIFICATION DATE: 03/12/2001|
| UNIT: [1] [] [] STATE: ME |NOTIFICATION TIME: 11:25[EST]|
| RXTYPE: [1] CE |EVENT DATE: 03/12/2001|
+------------------------------------------------+EVENT TIME: 10:30[EST]|
| NRC NOTIFIED BY: RON DOIRON |LAST UPDATE DATE: 03/12/2001|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |PETE ESELGROTH R1 |
|10 CFR SECTION: |FEMA, DOA, HHS FAX |
|*PRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION |EPA, DOT (VIA NRC) FAX |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Decommissioned |0 Decommissioned |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION DUE TO FUEL OIL SPILL |
| |
| The licensee notified the Maine Department of Environmental Protection (DEP) |
| about a fuel oil spill. The spill was from a fuel tank on a portable |
| compressor, at about 1015 EST the fuel line broke dumping about 30 gallons |
| on the ground. About 20 to 25 gallons went into the storm water system and |
| ended up in the adjacent cove. The licensee is working on containing the |
| spill on the water and has contained the balance of the spill on the ground. |
| The licensee has also notified the State Nuclear Inspector, the National |
| Response Center, and will notify NRC Region 1 Decommissioning Branch |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37827 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 03/12/2001|
| UNIT: [1] [] [] STATE: TX |NOTIFICATION TIME: 11:32[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/12/2001|
+------------------------------------------------+EVENT TIME: 00:45[CST]|
| NRC NOTIFIED BY: W. E. MOOKHOEK |LAST UPDATE DATE: 03/12/2001|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |WILLIAM JOHNSON R4 |
|10 CFR SECTION: | |
|HFIT 26.73 FITNESS FOR DUTY | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| A supervisor contractor was determined to be under the influence of alcohol |
| during a for cause fitness for duty test. The individuals access to the |
| protected area was terminated. |
| |
| Call HOO for further details. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37828 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COMANCHE PEAK REGION: 4 |NOTIFICATION DATE: 03/12/2001|
| UNIT: [] [2] [] STATE: TX |NOTIFICATION TIME: 16:23[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/12/2001|
+------------------------------------------------+EVENT TIME: 10:28[CST]|
| NRC NOTIFIED BY: MIKE SMITH |LAST UPDATE DATE: 03/12/2001|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |WILLIAM JOHNSON R4 |
|10 CFR SECTION: | |
|NONR OTHER UNSPEC REQMNT | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |85 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 24-HOUR VIOLATION OF LICENSEE CONDITION DUE TO EXCEEDING THERMAL POWER |
| LIMIT |
| |
| "License restriction of 3445 MWth for the unit was exceeded. Highest |
| reading N-16 power was 104.93%. Highest reading Nuclear Instrumentation |
| Power was approximately 97%. This event was initiated by a failure of Main |
| Turbine EHC fluid pressure switch, which closed [the] extraction steam |
| valves to [the] feedwater heaters. Unit has been stabilized at 85% Reactor |
| Power." |
| |
| Control Room Operators received a feedwater heater high level alarm alerting |
| them to the isolation of extraction steam to both the high and low pressure |
| feedwater heaters on both feedwater trains. The isolation of extraction |
| steam caused a decrease in feedwater temperature thus adding positive |
| reactivity which increased reactor thermal power. Operators responded |
| promptly by reducing turbine load. The licensee plans on replacing the |
| failed pressure switch and resuming full power operations. The licensee |
| informed the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37829 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 03/12/2001|
| UNIT: [1] [] [] STATE: LA |NOTIFICATION TIME: 16:59[EST]|
| RXTYPE: [1] GE-6 |EVENT DATE: 03/12/2001|
+------------------------------------------------+EVENT TIME: 08:31[CST]|
| NRC NOTIFIED BY: GEORGE TURNER |LAST UPDATE DATE: 03/12/2001|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |WILLIAM JOHNSON R4 |
|10 CFR SECTION: | |
|*COM 50.72(b)(3)(xiii) LOSS COMM/ASMT/RESPONSE| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LOSS OF VARIOUS COMMUNICATIONS CAPABILITIES DUE TO SEVERE WEATHER |
| |
| "Following a series of severe thunderstorms that passed through the Baton |
| Rouge area during the night it was discovered and reported to the Main |
| Control Room at 0831 that all offsite sirens, State and Local Hotlines, the |
| ESP Computer Notification System and Emergency Preparedness Radio were not |
| available. Commercial telephones and NRC ETS phone lines were available |
| during this period and continue to be available. The Offsite sirens were |
| transferred to the backup transmitter within 10 minutes of discovery and |
| restored as of 0828. As of 1500 hours, all but 2 State and Local Hotlines |
| were restored. Efforts to restore the remaining communications systems |
| continue." |
| |
| The licensee informed the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37830 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 03/12/2001|
| UNIT: [1] [] [] STATE: MN |NOTIFICATION TIME: 20:47[EST]|
| RXTYPE: [1] GE-3 |EVENT DATE: 03/12/2001|
+------------------------------------------------+EVENT TIME: 18:40[CST]|
| NRC NOTIFIED BY: JOLENE TEMPLE |LAST UPDATE DATE: 03/12/2001|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |GEOFFREY WRIGHT R3 |
|10 CFR SECTION: | |
|*UNA 50.72(b)(3)(ii)(B) UNANALYZED COND OP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNANALYZED CONDITION DUE TO AN INADEQUATE HELB BARRIER DURING A POSTULATED |
| FEEDWATER LINE BREAK |
| |
| "An unanalyzed plant condition may exist regarding a HELB barrier within the |
| turbine building. The HELB barrier in question separates two different |
| trains of essential 480 volt motor control centers and may be inadequate if |
| subjected." |
| |
| An Extent of Condition investigation of High Energy Line Break (HELB) |
| barriers determined that a barrier separating two adjacent areas (upper and |
| lower) in the turbine building may not withstand a 0.6 psid due to a |
| postulated heated feedwater line break. This could result in the loss of |
| both trains of equipment controlled by 480 volt MCCs. The licensee will |
| develop appropriate corrective action. |
| |
| The licensee informed the NRC resident inspector. |
+------------------------------------------------------------------------------+
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