Event Notification Report for August 14, 2003
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
08/13/2003 - 08/14/2003
EVENT NUMBERS
4007140072400734007440075400634006440065400664006740068400694007040061
Power Reactor
Event Number: 40071
Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: HELKER
HQ OPS Officer: JOHN MacKINNON
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: HELKER
HQ OPS Officer: JOHN MacKINNON
Notification Date: 08/14/2003
Notification Time: 17:15 [ET]
Event Date: 08/14/2003
Event Time: 16:35 [EDT]
Last Update Date: 08/15/2003
Notification Time: 17:15 [ET]
Event Date: 08/14/2003
Event Time: 16:35 [EDT]
Last Update Date: 08/15/2003
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
GLENN MEYER (R1)
STUART RICHARDS (NRR)
HYMAN (FEMA)
GLENN MEYER (R1)
STUART RICHARDS (NRR)
HYMAN (FEMA)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 100 | Power Operation | 0 | Hot Shutdown |
UNUSUAL EVENT DECLARED DUE TO LOSS OF OFFSITE POWER GREATER THAN 15 MINUTES.
Automatic reactor scram due to a loss of offsite power. All rods fully inserted into the core. All emergency core cooling systems are operating properly and the emergency diesel generators are operating properly.
NRC Resident Inspector was notified of this event by the licensee.
*****UPDATE 8/15/03 AT 0145 TO LAURA*****
Offsite electrical power was restored. The licensee exited the Unusual Event at 0123. Notified R1IRC and FEMA(Heyman).
Automatic reactor scram due to a loss of offsite power. All rods fully inserted into the core. All emergency core cooling systems are operating properly and the emergency diesel generators are operating properly.
NRC Resident Inspector was notified of this event by the licensee.
*****UPDATE 8/15/03 AT 0145 TO LAURA*****
Offsite electrical power was restored. The licensee exited the Unusual Event at 0123. Notified R1IRC and FEMA(Heyman).
Power Reactor
Event Number: 40072
Facility: FITZPATRICK
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: TIM PAGE
HQ OPS Officer: JOHN MacKINNON
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: TIM PAGE
HQ OPS Officer: JOHN MacKINNON
Notification Date: 08/14/2003
Notification Time: 17:17 [ET]
Event Date: 08/14/2003
Event Time: 16:26 [EDT]
Last Update Date: 08/15/2003
Notification Time: 17:17 [ET]
Event Date: 08/14/2003
Event Time: 16:26 [EDT]
Last Update Date: 08/15/2003
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED 50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED 50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
GLENN MEYER (R1)
STUART RICHARDS (NRR)
HYMAN (FEMA)
GLENN MEYER (R1)
STUART RICHARDS (NRR)
HYMAN (FEMA)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 100 | Power Operation | 0 | Hot Shutdown |
UNUSUAL EVENT DECLARED DUE TO A LOSS OF OFFSITE POWER.
Automatic reactor scram due to a loss of offsite power. All rods fully inserted into the core. All emergency core cooling systems and the emergency diesel generators are operating properly.
NRC Resident Inspector was notified of this event by the licensee.
*****UPDATE ON 8/15/03 AT 0035 FROM PAGE TO LAURA*****
Reactor vessel pressure is 93 psig. Plant electrical loads have been shifted back to offsite power and the EDGs were secured. The licensee exited the Unusual Event at 0039. The licensee tentatively plans to remain shutdown for a brief period to do some maintenance work.
Notified R1IRC and FEMA(Hyman).
* * * UPDATE ON 08/15/03 @ 1539 BY HALLIDAY TO GOULD * * *
This updated is being provided to note a correction to the previously submitted time information and provide additional clarification of information that did not get captured. The automatic reactor scram occurred due to a generator load rejection. All rods fully inserted into the core, all emergency core cooling systems and the emergency diesel generators operated properly.
The incorrect "event time" was communicated to the NRC during the initial notification (at 1717 hours) and subsequent updates. The event time listed was "1611" hours EDT. This was the actual time of the loss of offsite power. The declaration of the Unusual Event was at "1626" hours EDT, based on EAL 6.1.1, Loss of power to transformers T2/T3 for greater than 15 minutes (loss of offsite power).
In addition, the initial notification of the Unusual Event was also used to document two reporting requirements under 10CFR50.72. Specifically, 10CFR50.72(b)(2)(iv)(B) for actuation of the reactor protection system (RPS) when the reactor is critical, and 10CFR50.72(b)(3)(iv)(A) for valid actuation of systems listed in paragraph (b)(3)(iv)(B). Various system actuations occurred as a result of the loss of offsite power.
The NRC Resident Inspector was notified along with state and local agencies.
Notified Reg 1 RDO(Meyer)
Automatic reactor scram due to a loss of offsite power. All rods fully inserted into the core. All emergency core cooling systems and the emergency diesel generators are operating properly.
NRC Resident Inspector was notified of this event by the licensee.
*****UPDATE ON 8/15/03 AT 0035 FROM PAGE TO LAURA*****
Reactor vessel pressure is 93 psig. Plant electrical loads have been shifted back to offsite power and the EDGs were secured. The licensee exited the Unusual Event at 0039. The licensee tentatively plans to remain shutdown for a brief period to do some maintenance work.
Notified R1IRC and FEMA(Hyman).
* * * UPDATE ON 08/15/03 @ 1539 BY HALLIDAY TO GOULD * * *
This updated is being provided to note a correction to the previously submitted time information and provide additional clarification of information that did not get captured. The automatic reactor scram occurred due to a generator load rejection. All rods fully inserted into the core, all emergency core cooling systems and the emergency diesel generators operated properly.
The incorrect "event time" was communicated to the NRC during the initial notification (at 1717 hours) and subsequent updates. The event time listed was "1611" hours EDT. This was the actual time of the loss of offsite power. The declaration of the Unusual Event was at "1626" hours EDT, based on EAL 6.1.1, Loss of power to transformers T2/T3 for greater than 15 minutes (loss of offsite power).
In addition, the initial notification of the Unusual Event was also used to document two reporting requirements under 10CFR50.72. Specifically, 10CFR50.72(b)(2)(iv)(B) for actuation of the reactor protection system (RPS) when the reactor is critical, and 10CFR50.72(b)(3)(iv)(A) for valid actuation of systems listed in paragraph (b)(3)(iv)(B). Various system actuations occurred as a result of the loss of offsite power.
The NRC Resident Inspector was notified along with state and local agencies.
Notified Reg 1 RDO(Meyer)
Power Reactor
Event Number: 40073
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [3] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: FINUCAH
HQ OPS Officer: JOHN MacKINNON
Region: 1 State: NY
Unit: [2] [3] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: FINUCAH
HQ OPS Officer: JOHN MacKINNON
Notification Date: 08/14/2003
Notification Time: 18:49 [ET]
Event Date: 08/14/2003
Event Time: 16:25 [EDT]
Last Update Date: 08/14/2003
Notification Time: 18:49 [ET]
Event Date: 08/14/2003
Event Time: 16:25 [EDT]
Last Update Date: 08/14/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
GLENN MEYER (R1)
GLENN MEYER (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | N | 0 | Hot Shutdown | 0 | Hot Shutdown |
| 3 | N | N | 0 | Hot Shutdown | 0 | Hot Shutdown |
EMERGENCY SIRENS LOST IN FOUR COUNTIES
Emergency sirens lost in four counties due to a loss of power. At approximately 1830 hours power starting to be returned to the sirens.
NRC Resident Inspector notified of this event by the licensee.
Emergency sirens lost in four counties due to a loss of power. At approximately 1830 hours power starting to be returned to the sirens.
NRC Resident Inspector notified of this event by the licensee.
Power Reactor
Event Number: 40074
Facility: GINNA
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: Roy Gillow
HQ OPS Officer: JOHN MacKINNON
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: Roy Gillow
HQ OPS Officer: JOHN MacKINNON
Notification Date: 08/14/2003
Notification Time: 20:07 [ET]
Event Date: 08/14/2003
Event Time: 16:11 [EDT]
Last Update Date: 08/14/2003
Notification Time: 20:07 [ET]
Event Date: 08/14/2003
Event Time: 16:11 [EDT]
Last Update Date: 08/14/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
GLENN MEYER (R1)
GLENN MEYER (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
REACTOR TRIP/AUXILIARY FEEDWATER ACTUATION
Received grid disturbance that caused reactor trip at 1611. The trip occurred due to over temperature delta set point being reached from load swings experienced on the generator. Subsequently in the recovery process, the Auxiliary Feedwater Pumps auto started from a signal from the Main Feedwater Pumps being secured. As a result of grid problems it was noted that Ginna did not meet the required number of emergency sirens (greater than 25% of sirens without power).
NRC Resident Inspector was notified of this event by the licensee.
Received grid disturbance that caused reactor trip at 1611. The trip occurred due to over temperature delta set point being reached from load swings experienced on the generator. Subsequently in the recovery process, the Auxiliary Feedwater Pumps auto started from a signal from the Main Feedwater Pumps being secured. As a result of grid problems it was noted that Ginna did not meet the required number of emergency sirens (greater than 25% of sirens without power).
NRC Resident Inspector was notified of this event by the licensee.
Power Reactor
Event Number: 40075
Facility: FERMI
Region: 3 State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: KEVIN DAHM
HQ OPS Officer: CHAUNCEY GOULD
Region: 3 State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: KEVIN DAHM
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 08/14/2003
Notification Time: 20:08 [ET]
Event Date: 08/14/2003
Event Time: 16:10 [EDT]
Last Update Date: 08/15/2003
Notification Time: 20:08 [ET]
Event Date: 08/14/2003
Event Time: 16:10 [EDT]
Last Update Date: 08/15/2003
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
SONIA BURGESS (R3)
STUART RICHARDS (NRR)
HYMAN (FEMA)
SONIA BURGESS (R3)
STUART RICHARDS (NRR)
HYMAN (FEMA)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | A/R | Y | 100 | Power Operation | 0 | Hot Shutdown |
PLANT ENTERED AN NOUE DUE TO THE LOSS OF OFF SITE POWER
The reactor scrammed from 100% power due to fluctuations occurring on the main generator and a loss of off site power. All rods fully inserted and all MSIV's closed. Reactor level is being maintained in the normal band of 173 to 214 inches using RCIC. Reactor pressure is being controlled via SRV's in lo-lo set mode between 905 and 1017 psig. Isolations occurred as expected for level 2 and level 3. HPCI and RCIC started on level 2 signal. HPCI has been shutdown but is available. All 4 EDG's started and loaded.
The NRC Resident Inspector was notified.
* * * UPDATE ON 08/15/03 AT 1754EDT BY ERIC SORG TAKEN BY MACKINNON * * *
Unusual Event terminated at 1348 EDT on 08/15/03.
R3DO (Sonia Burgess), NRR EO (Stu Richards) & FEMA (Bob Caldwell) notified.
The reactor scrammed from 100% power due to fluctuations occurring on the main generator and a loss of off site power. All rods fully inserted and all MSIV's closed. Reactor level is being maintained in the normal band of 173 to 214 inches using RCIC. Reactor pressure is being controlled via SRV's in lo-lo set mode between 905 and 1017 psig. Isolations occurred as expected for level 2 and level 3. HPCI and RCIC started on level 2 signal. HPCI has been shutdown but is available. All 4 EDG's started and loaded.
The NRC Resident Inspector was notified.
* * * UPDATE ON 08/15/03 AT 1754EDT BY ERIC SORG TAKEN BY MACKINNON * * *
Unusual Event terminated at 1348 EDT on 08/15/03.
R3DO (Sonia Burgess), NRR EO (Stu Richards) & FEMA (Bob Caldwell) notified.
Power Reactor
Event Number: 40063
Facility: PERRY
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: JOE KOTAR
HQ OPS Officer: JOHN MacKINNON
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: JOE KOTAR
HQ OPS Officer: JOHN MacKINNON
Notification Date: 08/14/2003
Notification Time: 16:33 [ET]
Event Date: 08/14/2003
Event Time: 16:10 [EDT]
Last Update Date: 08/15/2003
Notification Time: 16:33 [ET]
Event Date: 08/14/2003
Event Time: 16:10 [EDT]
Last Update Date: 08/15/2003
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
SONIA BURGESS (R3)
STUART RICHARDS (NRR)
HYMAN (FEMA)
SONIA BURGESS (R3)
STUART RICHARDS (NRR)
HYMAN (FEMA)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 100 | Power Operation | 0 | Hot Shutdown |
UNUSUAL EVENT DECLARED DUE TO LOSS OF OFFSITE POWER GREATER THAN 15 MINUTES.
Automatic reactor scram due to a loss of offsite power. All rods fully inserted. Supplying power to vital buses via emergency diesel generators. All system operating properly.
NRC Resident Inspector was notified of the event by the licensee.
* * * UPDATE ON 08/15/03 @ 2007 BY STRACH TO GOULD * * *
The NOUE was terminated at 1952. Off site power was restored and the emergency diesels secured.
Notified FEMA (Austin), Reg 3 RDO (Burgess) and EO (Richards)
Automatic reactor scram due to a loss of offsite power. All rods fully inserted. Supplying power to vital buses via emergency diesel generators. All system operating properly.
NRC Resident Inspector was notified of the event by the licensee.
* * * UPDATE ON 08/15/03 @ 2007 BY STRACH TO GOULD * * *
The NOUE was terminated at 1952. Off site power was restored and the emergency diesels secured.
Notified FEMA (Austin), Reg 3 RDO (Burgess) and EO (Richards)
Power Reactor
Event Number: 40064
Facility: PALISADES
Region: 3 State: MI
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: VANDENALLE
HQ OPS Officer: CHAUNCEY GOULD
Region: 3 State: MI
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: VANDENALLE
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 08/14/2003
Notification Time: 17:10 [ET]
Event Date: 08/14/2003
Event Time: 16:07 [EDT]
Last Update Date: 08/14/2003
Notification Time: 17:10 [ET]
Event Date: 08/14/2003
Event Time: 16:07 [EDT]
Last Update Date: 08/14/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
SONIA BURGESS (R3)
SONIA BURGESS (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
POWER GRID DISTURBANCE OCCURRED RESULTING IN A MOMENTARY DROP IN VOLTAGE
At 1607 EDT a significant electrical power grid disturbance occurred resulting in a momentary drop in voltage at the site, including both 2400 VAC safety busses 1C and 1D. The reduced voltage on the 2400VAC safety busses caused both emergency diesel generators to auto start, but not load. The plant is stable at pre-event conditions.
The NRC Resident Inspector was notified.
At 1607 EDT a significant electrical power grid disturbance occurred resulting in a momentary drop in voltage at the site, including both 2400 VAC safety busses 1C and 1D. The reduced voltage on the 2400VAC safety busses caused both emergency diesel generators to auto start, but not load. The plant is stable at pre-event conditions.
The NRC Resident Inspector was notified.
Power Reactor
Event Number: 40065
Facility: OYSTER CREEK
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-2
NRC Notified By: CIGANIK
HQ OPS Officer: CHAUNCEY GOULD
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-2
NRC Notified By: CIGANIK
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 08/14/2003
Notification Time: 18:16 [ET]
Event Date: 08/14/2003
Event Time: 16:11 [EDT]
Last Update Date: 08/14/2003
Notification Time: 18:16 [ET]
Event Date: 08/14/2003
Event Time: 16:11 [EDT]
Last Update Date: 08/14/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
GLENN MEYER (R1)
GLENN MEYER (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 100 | Power Operation | 0 | Hot Shutdown |
REACTOR SCRAM FROM 100% POWER DUE TO OFF SITE ELECTRICAL GRID INSTABILITY
Reactor scram from 100% due to off site electrical grid instability, but did not lose off site power. Reactor conditions at 1730 are normal reactor water level, reactor pressure 850-1000psig, MSIV's closed and all recirc pumps are off and reactor is in hot shutdown with all rods inserted.
The NRC Resident Inspector
Reactor scram from 100% due to off site electrical grid instability, but did not lose off site power. Reactor conditions at 1730 are normal reactor water level, reactor pressure 850-1000psig, MSIV's closed and all recirc pumps are off and reactor is in hot shutdown with all rods inserted.
The NRC Resident Inspector
Power Reactor
Event Number: 40066
Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [] [2] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: MORAN
HQ OPS Officer: CHAUNCEY GOULD
Region: 1 State: NY
Unit: [] [2] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: MORAN
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 08/14/2003
Notification Time: 17:34 [ET]
Event Date: 08/14/2003
Event Time: 17:00 [EDT]
Last Update Date: 08/15/2003
Notification Time: 17:34 [ET]
Event Date: 08/14/2003
Event Time: 17:00 [EDT]
Last Update Date: 08/15/2003
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
GLENN MEYER (R1)
HYMAN (FEMA)
STUART RICHARDS (NRR)
GLENN MEYER (R1)
HYMAN (FEMA)
STUART RICHARDS (NRR)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | A/R | Y | 100 | Power Operation | 0 | Hot Shutdown |
NOUE WAS DECLARED AT 1700 DUE TO LOSS OF OFFSITE POWER
The plant lost offsite power due to grid disturbance which resulted in a reactor trip from 100% power. The NOUE was declared because of loss of offsite power was greater than 15 minutes.
The NRC Resident Inspector was notified.
*****UPDATE ON 8/15/03 AT 0805 FROM MORAN TO LAURA*****
All offsite power lines are available. The electrical power grid is stable. The licensee terminated the Unusual Event at 0730.
Notified R1 IRC, FEMA (D. Sullivan) and DHS (W. Hall)
The plant lost offsite power due to grid disturbance which resulted in a reactor trip from 100% power. The NOUE was declared because of loss of offsite power was greater than 15 minutes.
The NRC Resident Inspector was notified.
*****UPDATE ON 8/15/03 AT 0805 FROM MORAN TO LAURA*****
All offsite power lines are available. The electrical power grid is stable. The licensee terminated the Unusual Event at 0730.
Notified R1 IRC, FEMA (D. Sullivan) and DHS (W. Hall)
Power Reactor
Event Number: 40067
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: MARK COX
HQ OPS Officer: JOHN MacKINNON
Region: 1 State: NY
Unit: [2] [] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: MARK COX
HQ OPS Officer: JOHN MacKINNON
Notification Date: 08/14/2003
Notification Time: 16:39 [ET]
Event Date: 08/14/2003
Event Time: 16:25 [EDT]
Last Update Date: 08/15/2003
Notification Time: 16:39 [ET]
Event Date: 08/14/2003
Event Time: 16:25 [EDT]
Last Update Date: 08/15/2003
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED 50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED 50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
GLENN MEYER (R1)
STUART RICHARDS (NRR)
HYMAN (FEMA)
GLENN MEYER (R1)
STUART RICHARDS (NRR)
HYMAN (FEMA)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
UNUSUAL EVENT DECLARED DUE TO LOSS OF OFFSITE POWER GREATER THAN 15 MINUTES.
Automatic reactor scram due to a loss of offsite power. All rods fully inserted. Supplying power to vital buses via emergency diesel generators. All systems operating properly.
NRC Resident Inspector was notified of the event by the licensee.
* * * UPDATE 2340EDT ON 8/14/03 FROM ANDY MIHALIK TO S.SANDIN * * *
The following information was provided as an update:
"RPS Actuation (loss of flow) due to loss of offsite power. Auto actuation of AFW in response to the unit trips. Auto start & load of Emergency Diesel Generators in response to the loss of offsite power."
The licensee informed the state/local authorities and the NRC resident inspector. Notified R1IRC.
*****UPDATE ON 8/15/03 AT 0226 FROM CELENTANO TO GOTT*****
The licensee exited the Unusual Event at 0210 upon confirmation of a stable off-site power.
Notified R1 IRC and FEMA(Heyman).
Automatic reactor scram due to a loss of offsite power. All rods fully inserted. Supplying power to vital buses via emergency diesel generators. All systems operating properly.
NRC Resident Inspector was notified of the event by the licensee.
* * * UPDATE 2340EDT ON 8/14/03 FROM ANDY MIHALIK TO S.SANDIN * * *
The following information was provided as an update:
"RPS Actuation (loss of flow) due to loss of offsite power. Auto actuation of AFW in response to the unit trips. Auto start & load of Emergency Diesel Generators in response to the loss of offsite power."
The licensee informed the state/local authorities and the NRC resident inspector. Notified R1IRC.
*****UPDATE ON 8/15/03 AT 0226 FROM CELENTANO TO GOTT*****
The licensee exited the Unusual Event at 0210 upon confirmation of a stable off-site power.
Notified R1 IRC and FEMA(Heyman).
Power Reactor
Event Number: 40068
Facility: GINNA
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: PAUL HARRIS
HQ OPS Officer: JOHN MacKINNON
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: PAUL HARRIS
HQ OPS Officer: JOHN MacKINNON
Notification Date: 08/14/2003
Notification Time: 16:46 [ET]
Event Date: 08/14/2003
Event Time: 16:12 [EDT]
Last Update Date: 08/14/2003
Notification Time: 16:46 [ET]
Event Date: 08/14/2003
Event Time: 16:12 [EDT]
Last Update Date: 08/14/2003
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
GLENN MEYER (R1)
STUART RICHARDS (NRR)
HYMAN (FEMA)
GLENN MEYER (R1)
STUART RICHARDS (NRR)
HYMAN (FEMA)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
UNUSUAL EVENT DECLARED DUE TO LOSS OF OFFSITE POWER GREATER THAN 15 MINUTES.
Automatic reactor trip due to a loss of offsite power. All rods fully inserted into the core. All emergency systems operated as expected.
NRC Resident Inspector was of this event by the licensee.
* * * UPDATE 0510EDT ON 8/15/03 FROM McCOY TO S.SANDIN * * *
Unit exited the UE at 2108EDT on 8/14/03 after restoration of offsite power. The licensee informed state.local agencies and the NRC resident inspector. Notified R1IRC and FEMA(Hyman).
Automatic reactor trip due to a loss of offsite power. All rods fully inserted into the core. All emergency systems operated as expected.
NRC Resident Inspector was of this event by the licensee.
* * * UPDATE 0510EDT ON 8/15/03 FROM McCOY TO S.SANDIN * * *
Unit exited the UE at 2108EDT on 8/14/03 after restoration of offsite power. The licensee informed state.local agencies and the NRC resident inspector. Notified R1IRC and FEMA(Hyman).
Power Reactor
Event Number: 40069
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [] [3] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: MESSINA
HQ OPS Officer: JOHN MacKINNON
Region: 1 State: NY
Unit: [] [3] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: MESSINA
HQ OPS Officer: JOHN MacKINNON
Notification Date: 08/14/2003
Notification Time: 16:50 [ET]
Event Date: 08/14/2003
Event Time: 16:23 [EDT]
Last Update Date: 08/15/2003
Notification Time: 16:50 [ET]
Event Date: 08/14/2003
Event Time: 16:23 [EDT]
Last Update Date: 08/15/2003
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED 50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION 50.72(b)(2)(i) - PLANT S/D REQD BY TS
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED 50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION 50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
GLENN MEYER (R1)
STUART RICHARDS (NRR)
HYMAN (FEMA)
GLENN MEYER (R1)
STUART RICHARDS (NRR)
HYMAN (FEMA)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | A/R | Y | 100 | Power Operation | 0 | Hot Shutdown |
UNUSUAL EVENT DECLARED DUE TO LOSS OF OFFSITE POWER GREATER THAN 15 MINUTES.
Automatic reactor scram due to a loss of offsite power. All rods fully inserted. Supplying power to vital buses via emergency diesel generators. All systems operating properly.
NRC Resident Inspector was notified of the event by the licensee.
* * * UPDATE 2340EDT ON 8/14/03 FROM ANDY MIHALIK TO S.SANDIN * * *
The following information was provided as an update:
"RPS Actuation (loss of flow) due to loss of offsite power. Auto actuation of AFW in response to the unit trips. Auto start & load of Emergency Diesel Generators in response to the loss of offsite power. Unit 3 also experienced a second AFW auto start during the event. Unit 3 also entered Tech Spec LCO 3.0.3 for loss of two offsite circuits and one EDG inoperable. #31 EDG was declared inoperable when its associated Fuel oil storage tank inventory decreased below required."
The licensee informed the state/local authorities and the NRC resident inspector. Notified R1IRC.
*****UPDATE ON 8/15/03 AT 0226 FROM CELENTANO TO GOTT*****
The licensee exited the Unusual Event at 0210 upon confirmation of a stable off-site power.
Notified R1 IRC and FEMA(Heyman).
Automatic reactor scram due to a loss of offsite power. All rods fully inserted. Supplying power to vital buses via emergency diesel generators. All systems operating properly.
NRC Resident Inspector was notified of the event by the licensee.
* * * UPDATE 2340EDT ON 8/14/03 FROM ANDY MIHALIK TO S.SANDIN * * *
The following information was provided as an update:
"RPS Actuation (loss of flow) due to loss of offsite power. Auto actuation of AFW in response to the unit trips. Auto start & load of Emergency Diesel Generators in response to the loss of offsite power. Unit 3 also experienced a second AFW auto start during the event. Unit 3 also entered Tech Spec LCO 3.0.3 for loss of two offsite circuits and one EDG inoperable. #31 EDG was declared inoperable when its associated Fuel oil storage tank inventory decreased below required."
The licensee informed the state/local authorities and the NRC resident inspector. Notified R1IRC.
*****UPDATE ON 8/15/03 AT 0226 FROM CELENTANO TO GOTT*****
The licensee exited the Unusual Event at 0210 upon confirmation of a stable off-site power.
Notified R1 IRC and FEMA(Heyman).
Power Reactor
Event Number: 40070
Facility: DAVIS BESSE
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] B&W-R-LP
NRC Notified By: DON BONDY
HQ OPS Officer: JOHN MacKINNON
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] B&W-R-LP
NRC Notified By: DON BONDY
HQ OPS Officer: JOHN MacKINNON
Notification Date: 08/14/2003
Notification Time: 16:54 [ET]
Event Date: 08/14/2003
Event Time: 16:10 [EDT]
Last Update Date: 08/15/2003
Notification Time: 16:54 [ET]
Event Date: 08/14/2003
Event Time: 16:10 [EDT]
Last Update Date: 08/15/2003
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
SONIA BURGESS (R3)
STUART RICHARDS (NRR)
HYMAN (FEMA)
SONIA BURGESS (R3)
STUART RICHARDS (NRR)
HYMAN (FEMA)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
UNUSUAL EVENT DECLARED DUE TO A LOSS OF OFFSITE POWER.
All systems operated as expected. Decay Heat pumps are available if needed.
NRC Resident Inspector was notified of this event by the licensee.
* * * UPDATE ON 08/15/03 @ 1942 BY LEISURE TO GOULD * * *
The plant exited the NOUE at 1940 on 08/15/03. The grid is stable, the plant is on off site power and the emergency diesels are in standby.
Notified FEMA (Steindurf), Reg 3 RDO (S. Burgess) and EO (S. Richards)
All systems operated as expected. Decay Heat pumps are available if needed.
NRC Resident Inspector was notified of this event by the licensee.
* * * UPDATE ON 08/15/03 @ 1942 BY LEISURE TO GOULD * * *
The plant exited the NOUE at 1940 on 08/15/03. The grid is stable, the plant is on off site power and the emergency diesels are in standby.
Notified FEMA (Steindurf), Reg 3 RDO (S. Burgess) and EO (S. Richards)
Power Reactor
Event Number: 40061
Facility: KEWAUNEE
Region: 3 State: WI
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: ETHAN TREPTOW
HQ OPS Officer: RICH LAURA
Region: 3 State: WI
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: ETHAN TREPTOW
HQ OPS Officer: RICH LAURA
Notification Date: 08/14/2003
Notification Time: 10:57 [ET]
Event Date: 08/14/2003
Event Time: 09:10 [CDT]
Last Update Date: 08/14/2003
Notification Time: 10:57 [ET]
Event Date: 08/14/2003
Event Time: 09:10 [CDT]
Last Update Date: 08/14/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE 50.72(b)(2)(xi) - OFFSITE NOTIFICATION
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE 50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
SONIA BURGESS (R3)
SONIA BURGESS (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
EP SIRENS OUT OF SERVICE IN KEWAUNEE COUNTY
"At 0910 on August 14, It was reported to the Control Room that all thirteen Kewaunee County sirens had a communications problem that rendered them out of service. The percent siren coverage population lost is 68.52%. The State and County have been notified of the siren failures. The siren vendor has been contacted to begin troubleshooting the problem.
"This is being reported under 10 CFR 50.72(b)(3)(xiii) as any event that results in a major loss of emergency assessment capability, offsite response capability, or offsite communications capability (loss of greater than 50% of emergency sirens). It is also being reported under 10 CFR 50.72(b)(2)(xi) as any event or situation, related to the health and safety of the public or onsite personnel, or protection of the environment, for which a news release is planned or notification to other government agencies has been or will be made."
The NRC resident inspector was notified.
"At 0910 on August 14, It was reported to the Control Room that all thirteen Kewaunee County sirens had a communications problem that rendered them out of service. The percent siren coverage population lost is 68.52%. The State and County have been notified of the siren failures. The siren vendor has been contacted to begin troubleshooting the problem.
"This is being reported under 10 CFR 50.72(b)(3)(xiii) as any event that results in a major loss of emergency assessment capability, offsite response capability, or offsite communications capability (loss of greater than 50% of emergency sirens). It is also being reported under 10 CFR 50.72(b)(2)(xi) as any event or situation, related to the health and safety of the public or onsite personnel, or protection of the environment, for which a news release is planned or notification to other government agencies has been or will be made."
The NRC resident inspector was notified.