U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
06/11/2003 - 06/12/2003
** EVENT NUMBERS **
39917 39918 39919 39920 39921 39922 39923 39924 39925
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39917 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 06/11/2003|
| UNIT: [] [2] [] STATE: FL |NOTIFICATION TIME: 02:26[EDT]|
| RXTYPE: [1] CE,[2] CE |EVENT DATE: 06/11/2003|
+------------------------------------------------+EVENT TIME: 01:30[EDT]|
| NRC NOTIFIED BY: JOE HESSLING |LAST UPDATE DATE: 06/11/2003|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |MARK LESSER R2 |
|10 CFR SECTION: | |
|ARPS 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 A/R Y 22 Power Operation |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AUTOMATIC TURBINE TRIP/REACTOR TRIP DUE TO HIGH HIGH STEAM GENERATOR WATER |
| LEVEL |
| |
| "On 06/11/03, Unit 2 Reactor tripped via Turbine Trip due to high-high |
| Steam Generator level. All Control Rods fully inserted. Unit stable in |
| Mode 3 (Hot Standby). Auxiliary Feedwater system was manually started and |
| currently maintaining steam generator levels. Investigation is in progress |
| to determine initial cause for loss of feed to the 2A Steam Generator from |
| its associated low power feedwater regulating valve." |
| |
| |
| Coming out of a refueling outage reactor power was at 30% when it was |
| noticed that main feedwater regulating valves were oscillating. Reactor |
| power was reduced to 20% and the low power feedwater regulating valves were |
| placed in service so testing of the main feedwater regulating valves could |
| be performed. During testing of the main feedwater regulating valves at |
| approximately 22% reactor power low power feedwater flow to the 2A Steam |
| Generator ceased. The dual indications for the low power feedwater |
| regulating valve indicated that the valve was open but Steam Generator 2A |
| water level was decreasing. Since main feedwater regulating valve was being |
| tested the 100% bypass low power feedwater regulating valve was opened. |
| Steam Generator water level began to increase rapidly so the valve was |
| closed. 2A Steam Generator level began to decrease so the 100% bypass low |
| power feedwater regulating valve was reopened. This time 2A Steam Generator |
| water level increase above 88% narrow range which caused an automatic |
| turbine trip. Since reactor power was greater than 15% the reactor |
| automatically tripped due to the turbine trip. All rods fully inserted into |
| the core. Since the reactor core had very little decay heat the main steam |
| isolation valves were closed and both motor driven auxiliary feedwater pumps |
| were manually started. Motor Driven Auxiliary Feedwater Pumps and Steam |
| Generator PORVs operation is maintaining the plant in a Hot Standby |
| condition. All emergency core cooling systems are fully operable and the |
| emergency diesel generators are fully operable if needed. The electrical |
| grid is stable. The licensee believes that the stem of the low power |
| feedwater regulating valve separated from the valve which in turn caused the |
| valve to close while still having dual indication that the low power |
| feedwater valve was open. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39918 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 06/11/2003|
| UNIT: [1] [] [] STATE: MA |NOTIFICATION TIME: 13:46[EDT]|
| RXTYPE: [1] GE-3 |EVENT DATE: 06/11/2003|
+------------------------------------------------+EVENT TIME: 08:10[EDT]|
| NRC NOTIFIED BY: FRANK CLIFFORD |LAST UPDATE DATE: 06/11/2003|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |CHRISTOPHER CAHILL R1 |
|10 CFR SECTION: |TERRY REIS NRR |
|ACOM 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
+------------------------------------------------------------------------------+
| INABILITY TO ACTIVATE EMERGENCY SIRENS DUE TO EQUIPMENT FAILURE |
| |
| "On June 11, 2003 at 0810 hours, the control room was notified that all |
| Prompt Alert and Notification System (PANS) sirens were inoperable. All |
| necessary notifications to local towns and MEMA (Massachusetts Emergency |
| Management Agency) have been made. A backup plan (route altering) is in |
| place in the event of an emergency at Pilgrim station. It was determined |
| that one of the sirens was transmitting a continuous radio signal to the |
| remaining sirens, preventing actuation. The faulty siren was isolated from |
| the system at 1125 hours." |
| |
| The licensee informed both state and local agencies and the NRC resident |
| inspector. |
| |
| This condition involving a different siren in the system occurred on |
| 6/10/03. See EN #39912. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39919 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 06/11/2003|
| UNIT: [1] [2] [] STATE: PA |NOTIFICATION TIME: 14:07[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 06/11/2003|
+------------------------------------------------+EVENT TIME: 12:17[EDT]|
| NRC NOTIFIED BY: GORDON ROBINSON |LAST UPDATE DATE: 06/11/2003|
| HQ OPS OFFICER: ARLON COSTA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |CHRISTOPHER CAHILL R1 |
|10 CFR SECTION: | |
|ASHU 50.72(b)(2)(i) PLANT S/D REQD BY TS | |
|AINA 50.72(b)(3)(v)(A) POT UNABLE TO SAFE SD | |
|AINB 50.72(b)(3)(v)(B) POT RHR INOP | |
|AINC 50.72(b)(3)(v)(C) POT UNCNTRL RAD REL | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
|2 N Y 100 Power Operation |98 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| CONTROLLED PLANT TS SHUTDOWN DUE TO LOSS OF HVAC SYSTEM |
| |
| "On 6/11/03 at 12:17, the 'A' Control Structure Chiller tripped. The 'B' |
| Control Structure Chiller was already inoperable for maintenance on the 'B' |
| Chiller Fans. With the loss of Control Structure HVAC System the ability to |
| maintain temperatures in various spaces including Relay rooms, Control Room |
| Floor Cooling and Emergency Switchgear rooms was lost. Units 1 and 2 |
| entered [Technical Specifications] TS 3.0.3 and a controlled shutdown of |
| both units were commenced at 13:15. The 'A' Chiller was restarted at 12:47 |
| and cooling was reestablished to the required areas, however the 'A' chiller |
| is not considered operable at this time. The 'B' Chiller was placed in |
| service and was declared operable at 13:20 [and the controlled shutdown of |
| both units were terminated]." |
| |
| "This constitutes a Tech Spec required shutdown and requires a 4-hr ENS |
| notification in accordance with 10 CFR 50.72(b)(2)(i). The failure also |
| requires an 8-hr ENS notification in accordance with 10 CFR |
| 50.72(b)(3)(v)(A-D) due to the loss of a safety function." |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39920 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 06/11/2003|
| UNIT: [1] [2] [] STATE: WI |NOTIFICATION TIME: 14:42[EDT]|
| RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 06/11/2003|
+------------------------------------------------+EVENT TIME: 12:45[CDT]|
| NRC NOTIFIED BY: DON POPP |LAST UPDATE DATE: 06/11/2003|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |DAVID HILLS R3 |
|10 CFR SECTION: | |
|DDDD 73.71(b)(1) SAFEGUARDS REPORTS | |
|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 |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| SECURITY REPORT INVOLVING A PLANT SECURITY OFFICER |
| |
| Discovery of criminal act involving individual granted access to the site. |
| Immediate compensatory measures taken upon discovery. The licensee informed |
| local law enforcement and the NRC resident inspector. Contact the |
| Headquarters Operations Officer for additional details. |
| |
| *** UPDATE ON 6/11/03 AT 2029 FROM D. POPP TO A. COSTA *** |
| |
| The non-licensed employee was determined to be under the influence of |
| alcohol during a "for cause" test. The individual's access to all NMC |
| facilities has been revoked. Contact the Headquarters Operations Officer |
| for additional details. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39921 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: GRAND GULF REGION: 4 |NOTIFICATION DATE: 06/11/2003|
| UNIT: [1] [] [] STATE: MS |NOTIFICATION TIME: 14:49[EDT]|
| RXTYPE: [1] GE-6 |EVENT DATE: 05/22/2003|
+------------------------------------------------+EVENT TIME: 08:02[CDT]|
| NRC NOTIFIED BY: JAMES OWENS |LAST UPDATE DATE: 06/11/2003|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |DAVID GRAVES R4 |
|10 CFR SECTION: | |
|AINV 50.73(a)(1) INVALID SPECIF SYSTEM A| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |50 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| INVALID ACTUATION AND VARIOUS SYSTEM ISOLATIONS DUE TO A FAILED RELAY |
| |
| "On May 22, 2003, at 0802 central time, while operating at 100 percent |
| power, Grand Gulf Nuclear Station experienced an invalid actuation of the |
| 'B' Containment, Drywell, and Auxiliary Building Isolation System. A failed |
| relay caused a fuse to blow which resulted in actuation of the isolation |
| logic for the 'B' Containment, Drywell, and Auxiliary Building Isolation |
| System. This event resulted in isolation of the Plant Service Water (PSW), |
| Plant Chilled Water (PCW), Drywell Chilled Water (DWCW), and Instrument Air |
| (IA) to the Auxiliary Building. The PSW isolation caused loss of Component |
| Cooling Water (CCW) in the Auxiliary Building and loss of Turbine Building |
| Cooling Water. Reactor power was reduced to approximately 50 percent as a |
| result of the loss of PSW." |
| |
| The licensee informed the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Other Nuclear Material |Event Number: 39922 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: CONSOLE ENERGY INC |NOTIFICATION DATE: 06/11/2003|
|LICENSEE: BUCHANAN MINE CONSOLIDATION COMPANY |NOTIFICATION TIME: 15:12[EDT]|
| CITY: MAVISDALE REGION: 2 |EVENT DATE: 06/04/2003|
| COUNTY: STATE: VA |EVENT TIME: [EDT]|
|LICENSE#: GENERAL AGREEMENT: N |LAST UPDATE DATE: 06/11/2003|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |MARK LESSER R2 |
| |CHRISTOPHER CAHILL R1 |
+------------------------------------------------+FRED BROWN NMSS |
| NRC NOTIFIED BY: JOE RICHARD |ROBERTA WARREN IAT |
| HQ OPS OFFICER: ARLON COSTA | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|BLO1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MISSING OR LOST GAUGE CONTAINING A RADIOACTIVE SOURCE |
| |
| A Texas Nuclear Product pipe mounted fixed gauge device, model 5202, Series |
| SG, serial number B174 containing a Cesium 137 (Cs-137), 500 millicuries |
| source (assay date of November 1984) could not be located in storage. The |
| gauge was removed from a pipe on the evening of 1/28/03 by an independent |
| contractor who placed the gauge in a temporary storage on the morning of |
| 1/29/03 at the Buchanan Mine Preparation Plant located in Mavisdale, |
| Virginia. The gauge was closed and pad locked before it was placed in the |
| small building storage room. The independent contractor and the plant |
| foreman looked for the gauge on 6/2/03 and could not locate it. They |
| continued looking for the gauge until 6/4/02 when they declared that it was |
| missing. The licensee has no reason to believe that the gauge left the |
| property, is retracing the steps of the gauge movement and is interviewing |
| their employees in an attempt to locate the gauge. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39923 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NORTH ANNA REGION: 2 |NOTIFICATION DATE: 06/11/2003|
| UNIT: [1] [] [] STATE: VA |NOTIFICATION TIME: 17:18[EDT]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 06/11/2003|
+------------------------------------------------+EVENT TIME: 14:53[EDT]|
| NRC NOTIFIED BY: J. W. JOHNSTONE |LAST UPDATE DATE: 06/11/2003|
| HQ OPS OFFICER: ARLON COSTA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |MARK LESSER R2 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
|AESF 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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 A/R Y 100 Power Operation |0 Hot Standby |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| REACTOR PROTECTION SYSTEM ACTUATION DUE TO MAIN TRANSFORMER LOCKOUT RELAY |
| TURBINE TRIP |
| |
| "At 1453 EDT on 6/11/03, Unit 1 experience a reactor trip due to a main |
| transformer lockout relay turbine trip. All equipment operated as designed. |
| 10 CFR 50.72(b)(2)(iv)(B). Main transformer 'C' appears to have an internal |
| fault, [and] may need to be replaced. All control rods inserted fully. |
| |
| "A valid actuation of the Auxiliary Feedwater System resulted, due to the |
| reactor trip. 10 CFR 50.72(b)(3)(iv)(A). The unit is stable, using main |
| feedwater and condenser steam dump [as a means of heat removal]. |
| |
| All safety-related systems are available except for Unit 1 Emergency Diesel |
| Generator which is out of service for maintenance. |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39924 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 06/11/2003|
| UNIT: [3] [] [] STATE: FL |NOTIFICATION TIME: 18:30[EDT]|
| RXTYPE: [3] B&W-L-LP |EVENT DATE: 06/11/2003|
+------------------------------------------------+EVENT TIME: 15:05[EDT]|
| NRC NOTIFIED BY: JOHN ADDISON |LAST UPDATE DATE: 06/11/2003|
| HQ OPS OFFICER: ARLON COSTA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |MARK LESSER R2 |
|10 CFR SECTION: | |
|ASHU 50.72(b)(2)(i) PLANT S/D REQD BY TS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO INOPERABLE CHILLERS |
| |
| "At 1409 on 6/11/03, both Control Complex Chillers were declared inoperable. |
| The inoperability resulted in an entry into ITS 3.0.3 due to the inability |
| to comply with ITS 3.7.18. At 1505 CR-3 [Crystal River Unit 3] began a |
| power decrease in compliance with the actions of ITS 3.0.3. This is a |
| 4-hour reportable event as required by 10 CFR 50.72(b)(2)(i). |
| |
| "At 1618 on 6/11/03 the operating Control Complex Chiller was declared |
| Operable and the actions of ITS 3.0.3 were exited. The plant has been |
| returned to full power operation. |
| |
| "The safety significance of this event was small. The Control Complex |
| cooling safety function was available through the use of existing procedures |
| and available alternate cooling methods. At 1456, an available Control |
| Complex Chiller was manually loaded and is currently providing all required |
| cooling to the control complex in automatic mode." |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39925 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WATTS BAR REGION: 2 |NOTIFICATION DATE: 06/12/2003|
| UNIT: [1] [] [] STATE: TN |NOTIFICATION TIME: 00:34[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 06/11/2003|
+------------------------------------------------+EVENT TIME: 23:45[EDT]|
| NRC NOTIFIED BY: MIKE EARLES |LAST UPDATE DATE: 06/12/2003|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |MARK LESSER R2 |
|10 CFR SECTION: | |
|ACOM 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
+------------------------------------------------------------------------------+
| GREATER THAN 30% OF THE OFFSITE NOTIFICATION SIRENS OUT OF SERVICE DUE TO |
| STORM |
| |
| Greater than 30% of the offsite prompt notification system sirens are out of |
| service due to storm related loss of power. Repairs are presently in |
| progress to restore power to the affected sirens (34 of 99). State and |
| Local agencies have been notified to implement compensatory measures if |
| required. |
| |
| The NRC Resident Inspector will be notified by the licensee. |
+------------------------------------------------------------------------------+
