Event Notification Report for April 9, 2001
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
04/06/2001 - 04/09/2001
** EVENT NUMBERS **
37895 37896 37897 37898 37899 37900
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37895 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 04/06/2001|
| UNIT: [] [2] [] STATE: IL |NOTIFICATION TIME: 13:27[EDT]|
| RXTYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 04/06/2001|
+------------------------------------------------+EVENT TIME: 09:09[CDT]|
| NRC NOTIFIED BY: D. COVEYOU |LAST UPDATE DATE: 04/06/2001|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MICHAEL JORDAN R3 |
|10 CFR SECTION: | |
|*RPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
|*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/R Y 100 Power Operation |0 Hot Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR SCRAM DUE TO BLOWN FUSE IN FEEDWATER CONTROL SYSTEM |
| |
| "This report is bring made per 10CFR50.72(b)(2)(iv)(B) RPS actuation, 4 hour |
| notification for Unit 2 and 10CFR50.72(b)(3)(iv)(A) System Actuation not |
| including RPS, 8 hour notification for Units 1 and 2. |
| |
| "At 0909, Friday 4-6-01, U-2 automatically scrammed. Initial investigations |
| indicate that a blown fuse in the Feedwater control system caused the |
| reactor Recirculation pumps to downshift. The resultant level swell caused |
| reactor water level to reach the level 8 trip setpoint (plus 55 inches). The |
| main turbine tripped on the high reactor water level. The reactor scrammed |
| due to the main turbine Stop Valves closure with reactor power above 25% |
| power. All control rods fully inserted. |
| |
| "The Turbine driven reactor feedwater pumps tripped as designed. The Motor |
| Driven Reactor Feedwater pump feed regulating valve locked out, the cause is |
| not known at this time. Reactor Core Isolation Cooling (RCIC) was initiated |
| manually by the operators for reactor pressure and level control. |
| |
| "A primary containment level 2 isolation (primary containment cooling, |
| containment monitoring. process sample, Unit 1 and 2 Reactor Building |
| Ventilation. Unit 1 and 2 Standby Gas treatment initiation, Reactor water |
| cleanup, reactor Recirculation hydraulic power units and others) occurred at |
| approximately minus 40 inches. |
| |
| "The lowest Reactor water level reached was minus 44 inches and was |
| recovered to normal level utilizing RCIC. RCIC was operated in manual mode |
| following erratic operation in automatic, the cause is not known at this |
| time. System isolations have been restored with exception of reactor water |
| cleanup on U-2. |
| |
| "The station is taking action to investigate the cause of the blown fuse and |
| erratic RCIC operation." |
| |
| The NRC resident inspector has been informed of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Other Nuclear Material |Event Number: 37896 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: MID WEST TESTING |NOTIFICATION DATE: 04/06/2001|
|LICENSEE: MID WEST TESTING |NOTIFICATION TIME: 17:50[EDT]|
| CITY: HAZLEWOOD REGION: 3 |EVENT DATE: 04/06/2001|
| COUNTY: STATE: MO |EVENT TIME: 15:00[CDT]|
|LICENSE#: 24-24619-02 AGREEMENT: N |LAST UPDATE DATE: 04/06/2001|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |MICHAEL JORDAN R3 |
| |LARRY CAMPER NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: DAVID WEBER | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LOST MOISTURE/DENSITY GAUGE |
| |
| The licensee reported that a Humboldt Model HS-EZ moisture/density gauge |
| (serial #3310) fell from the bed of a pickup truck in Hazlewood, MO. The |
| device was not stored in its case at the time of the loss. The unit contains |
| one 11 millicurie Cs-137 source and one 44 millicurie Am-241/Be source. |
| |
| The licensee was unable to locate the gauge after retracing the route of the |
| vehicle. The licensee has contacted the local police department for |
| assistance in recovering the gauge. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37897 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 04/06/2001|
| UNIT: [] [2] [] STATE: PA |NOTIFICATION TIME: 20:46[EDT]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 04/06/2001|
+------------------------------------------------+EVENT TIME: 19:43[EDT]|
| NRC NOTIFIED BY: JEFFREY SHIRE |LAST UPDATE DATE: 04/07/2001|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: UNU |JACK MCFADDEN R1 |
|10 CFR SECTION: |CHRISTOPHER GRIMES NRR |
|*AEC 50.72(a) (1) (i) EMERGENCY DECLARED |RICHARD WESSMAN IRO |
| |DAVID BARDON FEMA |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNUSUAL EVENT DECLARED DUE TO FIRE IN EXHAUST HOOD DUCTING |
| |
| A fire occurred in an exhaust hood duct in the Unit 2 chemistry sample room |
| during the processing of an oil sample. The fire was located inside the |
| ducting. Offsite departments responded to the site. An Unusual Event was |
| declared at 1943 EDT. The fire was extinguished at 2022 EDT. The NRC |
| resident inspector has been informed of this event by the licensee. |
| |
| * * * UPDATE 0012EDT ON 4/7/01 FROM CARLOS CONTRERAS TO S. SANDIN * * * |
| |
| The licensee terminated the Unusual Event at 2300EDT on 4/6/01 based on the |
| fact that the fire had been extinguished, current stable plant conditions, |
| and adequate support staff availability. The licensee informed state/local |
| agencies and the NRC resident inspector. Notified R1DO(McFadden), |
| EO(Grimes) and FEMA(Bardon). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37898 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: VOGTLE REGION: 2 |NOTIFICATION DATE: 04/07/2001|
| UNIT: [] [2] [] STATE: GA |NOTIFICATION TIME: 23:30[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/07/2001|
+------------------------------------------------+EVENT TIME: 21:23[EDT]|
| NRC NOTIFIED BY: ROB DORMAN |LAST UPDATE DATE: 04/07/2001|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CAUDLE JULIAN R2 |
|10 CFR SECTION: | |
|*RPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
|*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 M/R Y 46 Power Operation |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MANUAL REACTOR TRIP DUE TO LOSS OF FEEDWATER FLOW |
| |
| "While performing 14236-2, 'SGFPT A and B Trip TADOT [trip actuation device |
| operational test]' on SGFPT A, the link disabling the trip signal to the |
| running SGFPT B was not fully opened, resulting in a trip of SGFPT B. The |
| reactor was manually tripped due to no SGFPT's running. Both trains of the |
| Reactor Protection System functioned as expected. A Feed Water Isolation was |
| received as expected from P4-Low Tavg. An Aux Feed Water Actuation Signal |
| (AFWAS) was generated on the trip of both SGFPT's for both MDAFW pumps and |
| on Lo-Lo Steam Generator level in two of four Steam Generators for the TDAFW |
| pump. The Steam Generator Blow Down system also Isolated properly on the |
| AFWAS signal. The plant is currently stable in Mode 3. A shut down was in |
| progress at the time of this event for a planned refueling outage. The |
| refueling outage will continue as planned." |
| |
| The NRC resident inspector has been informed of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37899 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 04/08/2001|
| UNIT: [1] [2] [] STATE: FL |NOTIFICATION TIME: 11:21[EDT]|
| RXTYPE: [1] CE,[2] CE |EVENT DATE: 04/08/2001|
+------------------------------------------------+EVENT TIME: 11:15[EDT]|
| NRC NOTIFIED BY: C. D. MARPLE |LAST UPDATE DATE: 04/08/2001|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CAUDLE JULIAN R2 |
|10 CFR SECTION: | |
|*PRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Cold Shutdown |0 Cold Shutdown |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION INVOLVING A LOGGERHEAD TURTLE FOUND IN THE INTAKE |
| CANAL |
| |
| "At 1115[EDT] on 4/8/01 a notification was made to the Florida Fish and |
| Wildlife Conservation Commission regarding a live Loggerhead Turtle found in |
| the intake canal. The turtle will be sent off site to a rehabilitation |
| facility. The notification to a state government agency requires |
| notification to the NRC." |
| |
| The licensee informed the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37900 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 04/08/2001|
| UNIT: [] [2] [] STATE: NY |NOTIFICATION TIME: 22:15[EDT]|
| RXTYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 04/08/2001|
+------------------------------------------------+EVENT TIME: 16:15[EDT]|
| NRC NOTIFIED BY: RICHARD LANGE |LAST UPDATE DATE: 04/08/2001|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JACK MCFADDEN R1 |
|10 CFR SECTION: | |
|*INA 50.72(b)(3)(v)(A) POT UNABLE TO SAFE SD | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| BOTH EMERGENCY DIESEL GENERATORS DECLARED INOPERABLE |
| |
| "Both Division 1 and Division 2 standby diesel generators were declared |
| inoperable. This report is being made per 10CFR50.72(b)(3)(v)(A), in that |
| both standby diesels were in a condition such that they may not have been |
| able to fulfill their intended safety function. |
| |
| "The division 1 diesel generator was declared inoperable because both diesel |
| generator room exhaust fans were found rotating backwards. The division 2 |
| diesel generator was declared inoperable due to one exhaust fan rotating |
| backwards and the outside air temperature exceeding 72�F. The cause of the |
| fan blades' reverse rotation is under evaluation. Reverse fan blade |
| rotation may cause longer in-rush starting currents which could cause the |
| fan motors to trip. |
| |
| "With two diesel generators inoperable, the plant entered Technical |
| Specification 3.8.1, a 2-hour shutdown Action Statement. |
| |
| "Division 1 and 2 diesel room exhaust fans stopped rotating, and the outside |
| air temperature lowered to less than 72�F The Technical Specification Action |
| Statements were exited. Periodic monitoring of the fans has been established |
| to address reoccurrence of the condition." |
| |
| The NRC resident inspector has been informed of this event by the licensee. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021