Event Notification Report for August 23, 2007
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
08/22/2007 - 08/23/2007
EVENT NUMBERS
43590435914358943587
Power Reactor
Event Number: 43590
Facility: BRAIDWOOD
Region: 3 State: IL
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: RALPH RICHARD
HQ OPS Officer: PETE SNYDER
Region: 3 State: IL
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: RALPH RICHARD
HQ OPS Officer: PETE SNYDER
Notification Date: 08/23/2007
Notification Time: 20:14 [ET]
Event Date: 08/23/2007
Event Time: 15:30 [CDT]
Last Update Date: 08/23/2007
Notification Time: 20:14 [ET]
Event Date: 08/23/2007
Event Time: 15:30 [CDT]
Last Update Date: 08/23/2007
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 50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION 50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
JULIO LARA (R3)
JULIO LARA (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 |
| 2 | M/R | Y | 100 | Power Operation | 0 | Hot Standby |
MANUAL REACTOR TRIP BECAUSE OF LOWERING CONDENSER VACUUM
"At 1530 hours on 8/23/07, Braidwood Station Unit 2 was manually tripped due to lowering condenser vacuum. The lowering condenser vacuum resulted from the trip of two circulating water pumps. The cause of the two circulating water pump tripping is under investigation. All control rods inserted and there were no complications during the trip and all systems functions as required. Following the unit trip, the Auxiliary Feedwater System actuated as expected to maintain steam generator level. At the time of the unit trip, the Braidwood Station area was experiencing severe thunderstorms.
"Additionally, at 1604 hours, 19 of 70 emergency sirens for the Braidwood Station were declared inoperable due to a loss of power from storms in the area. As of 1704 hours, 19 sirens (greater than 25%) remain inoperable. This event is considered a major loss of offsite response capability and applies to both Braidwood Station Unit 1 and Unit 2.
"These events are is being reported under:
(1) 10 CFR 50.72(b)(2)(iv)(B) as an event that results in the actuation of the reactor protection system (RPS) when the reactor is critical,
(2) 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of the PWR auxiliary feedwater system.
(3) 10 CFR 50.72(b)(3)(xiii) as a major loss of offsite response capability."
All safety buses remained powered by offsite power throughout this event. Emergency diesel generators are available if needed. No steam generator PORV's lifted as a result of the trip. Decay heat is being discharged to the condenser via the steam dumps.
The licensee informed the NRC Resident Inspector.
"At 1530 hours on 8/23/07, Braidwood Station Unit 2 was manually tripped due to lowering condenser vacuum. The lowering condenser vacuum resulted from the trip of two circulating water pumps. The cause of the two circulating water pump tripping is under investigation. All control rods inserted and there were no complications during the trip and all systems functions as required. Following the unit trip, the Auxiliary Feedwater System actuated as expected to maintain steam generator level. At the time of the unit trip, the Braidwood Station area was experiencing severe thunderstorms.
"Additionally, at 1604 hours, 19 of 70 emergency sirens for the Braidwood Station were declared inoperable due to a loss of power from storms in the area. As of 1704 hours, 19 sirens (greater than 25%) remain inoperable. This event is considered a major loss of offsite response capability and applies to both Braidwood Station Unit 1 and Unit 2.
"These events are is being reported under:
(1) 10 CFR 50.72(b)(2)(iv)(B) as an event that results in the actuation of the reactor protection system (RPS) when the reactor is critical,
(2) 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of the PWR auxiliary feedwater system.
(3) 10 CFR 50.72(b)(3)(xiii) as a major loss of offsite response capability."
All safety buses remained powered by offsite power throughout this event. Emergency diesel generators are available if needed. No steam generator PORV's lifted as a result of the trip. Decay heat is being discharged to the condenser via the steam dumps.
The licensee informed the NRC Resident Inspector.
Fuel Cycle Facility
Event Number: 43591
Facility: GENERAL ELECTRIC CO.
Region: 3 State: IL
Unit: [] [] []
RX Type: SPENT FUEL STORAGE FACILITY
NRC Notified By: STANLEY BOND
HQ OPS Officer: PETE SNYDER
Region: 3 State: IL
Unit: [] [] []
RX Type: SPENT FUEL STORAGE FACILITY
NRC Notified By: STANLEY BOND
HQ OPS Officer: PETE SNYDER
Notification Date: 08/23/2007
Notification Time: 22:20 [ET]
Event Date: 08/23/2007
Event Time: 18:50 [CDT]
Last Update Date: 08/23/2007
Notification Time: 22:20 [ET]
Event Date: 08/23/2007
Event Time: 18:50 [CDT]
Last Update Date: 08/23/2007
Emergency Class: UNUSUAL EVENT
10 CFR Section:
10 CFR Section:
Person (Organization):
JULIO LARA (R3)
TOM BLOUNT (IRD)
EDWIN HACKETT (FSME)
JULIO LARA (R3)
TOM BLOUNT (IRD)
EDWIN HACKETT (FSME)
UNUSUAL EVENT DECLARED DUE TO SEVERE WEATHER IN THE AREA
Per the site emergency plan, MOI's 202 and 233, at 1850 local time, the licensee declared an Unusual Event due to severe weather including tornado warnings. The licensee sheltered personnel onsite. No damage was sustained at the site. There was no radiological release. No offsite assistance was requested. At 1930 local time the licensee terminated the Unusual Event due to expiration of the tornado warnings.
The licensee notified state authorities.
Per the site emergency plan, MOI's 202 and 233, at 1850 local time, the licensee declared an Unusual Event due to severe weather including tornado warnings. The licensee sheltered personnel onsite. No damage was sustained at the site. There was no radiological release. No offsite assistance was requested. At 1930 local time the licensee terminated the Unusual Event due to expiration of the tornado warnings.
The licensee notified state authorities.
Power Reactor
Event Number: 43589
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: GORDY ROBINSON
HQ OPS Officer: STEVE SANDIN
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: GORDY ROBINSON
HQ OPS Officer: STEVE SANDIN
Notification Date: 08/23/2007
Notification Time: 15:54 [ET]
Event Date: 08/23/2007
Event Time: 13:00 [EDT]
Last Update Date: 08/23/2007
Notification Time: 15:54 [ET]
Event Date: 08/23/2007
Event Time: 13:00 [EDT]
Last Update Date: 08/23/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
JAMES DWYER (R1)
JAMES DWYER (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
OFFSITE NOTIFICATION INVOLVING A 70 GALLON DIESEL SPILL WITHIN 1 MILE OF THE SITE BOUNDARY
"On August 23, 2007, at 1300 EDT, the Susquehanna Control Room was notified of a diesel fuel oil spill from a ruptured saddle tank on a tanker truck. The truck was located within 1 mile of the site boundary, on company property, NOT within the plant protected area. Approximately 70 gallons of diesel fuel oil was spilled in the immediate vicinity of the parked truck and did not get into any waterway. The remainder of the fuel oil was pumped from the ruptured tank into a 55 gallon drum. The event did not meet thresholds for reporting to the state of Pennsylvania. However, the contractor (Rizzo Associates) performing the work made a courtesy call to the Department of Environmental Protection with subsequent notifications made to the Susquehanna control room. This 4 hour notification is made per 10CFR50.72(b)(2)(xi) for '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 clean-up plan was discussed with the DEP and is currently in progress. This incident had no impact to SSHS or its operating units."
The licensee informed the NRC Resident Inspector.
"On August 23, 2007, at 1300 EDT, the Susquehanna Control Room was notified of a diesel fuel oil spill from a ruptured saddle tank on a tanker truck. The truck was located within 1 mile of the site boundary, on company property, NOT within the plant protected area. Approximately 70 gallons of diesel fuel oil was spilled in the immediate vicinity of the parked truck and did not get into any waterway. The remainder of the fuel oil was pumped from the ruptured tank into a 55 gallon drum. The event did not meet thresholds for reporting to the state of Pennsylvania. However, the contractor (Rizzo Associates) performing the work made a courtesy call to the Department of Environmental Protection with subsequent notifications made to the Susquehanna control room. This 4 hour notification is made per 10CFR50.72(b)(2)(xi) for '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 clean-up plan was discussed with the DEP and is currently in progress. This incident had no impact to SSHS or its operating units."
The licensee informed the NRC Resident Inspector.
Power Reactor
Event Number: 43587
Facility: GRAND GULF
Region: 4 State: MS
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: ERNEST MATHES
HQ OPS Officer: PETE SNYDER
Region: 4 State: MS
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: ERNEST MATHES
HQ OPS Officer: PETE SNYDER
Notification Date: 08/23/2007
Notification Time: 15:20 [ET]
Event Date: 08/23/2007
Event Time: 13:54 [CDT]
Last Update Date: 08/23/2007
Notification Time: 15:20 [ET]
Event Date: 08/23/2007
Event Time: 13:54 [CDT]
Last Update Date: 08/23/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
20.1906(d)(2) - EXTERNAL RAD LEVELS > LIMITS
10 CFR Section:
20.1906(d)(2) - EXTERNAL RAD LEVELS > LIMITS
Person (Organization):
JEFFREY CLARK (R4)
JEFFREY CLARK (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 12 | Power Operation | 12 | Power Operation |
RECEIPT INSPECTION SURVEYS INDICATE RAD LEVELS GREATER THAN EXPECTED
"A package removed from the transport flatbed had a gamma dose rate of 224 [millirem per hour] on contact which exceeded the 10 CFR 71.47 limit, and is therefore reportable per 10 CFR 20.1906(d)(2).
"No issue with personnel exposure or a dose to public since the highest dose rate was found on the bottom of the package which was secured to the flatbed. No other limits were exceeded."
The licensee notified the NRC Resident Inspector.
"A package removed from the transport flatbed had a gamma dose rate of 224 [millirem per hour] on contact which exceeded the 10 CFR 71.47 limit, and is therefore reportable per 10 CFR 20.1906(d)(2).
"No issue with personnel exposure or a dose to public since the highest dose rate was found on the bottom of the package which was secured to the flatbed. No other limits were exceeded."
The licensee notified the NRC Resident Inspector.