Event Notification Report for September 29, 2005
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
09/28/2005 - 09/29/2005
Power Reactor
Event Number: 42024
Facility: MILLSTONE
Region: 1 State: CT
Unit: [] [] [3]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: FRED NYGARD
HQ OPS Officer: BILL HUFFMAN
Region: 1 State: CT
Unit: [] [] [3]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: FRED NYGARD
HQ OPS Officer: BILL HUFFMAN
Notification Date: 09/29/2005
Notification Time: 14:49 [ET]
Event Date: 09/29/2005
Event Time: 13:10 [EDT]
Last Update Date: 09/29/2005
Notification Time: 14:49 [ET]
Event Date: 09/29/2005
Event Time: 13:10 [EDT]
Last Update Date: 09/29/2005
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):
CHRISTOPHER CAHILL (R1)
CHRISTOPHER CAHILL (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | M/R | Y | 100 | Power Operation | 0 | Hot Standby |
MANUAL REACTOR TRIP DUE TO LOSS OF CIRCULATING WATER PUMPS
The licensee reported that high wind and wave action at the site has resulted in sea weed and related debris buildup at the Unit 3 intake structure. The traveling screens were unable to keep pace with the debris buildup and two out of six circulating water pumps tripped on high differential pressure across the traveling screens. Based on procedural requirements, the licensee is required to manually trip the plant due to the loss of the two circ water pumps. The reactor trip was characterized as uncomplicated with all systems functioning as required. All rods fully inserted. No primary or secondary relief valves lifted. Auxiliary feedwater automatically started as expected and is supplying cooling water to the steam generators. Decay heat is being discharged to the condenser via the turbine bypass valves. The plant is stable in hot standby at no-load temperature and pressure. The plant trip had no impact on Unit 2. The debris buildup on the Unit 2 intake is being monitored but is less of a problem due to the orientation of the Unit 2 intake structure.
The NRC Resident Inspector has been notified by the licensee. The licensee has also notified State and local authorities and has made a press release.
The licensee reported that high wind and wave action at the site has resulted in sea weed and related debris buildup at the Unit 3 intake structure. The traveling screens were unable to keep pace with the debris buildup and two out of six circulating water pumps tripped on high differential pressure across the traveling screens. Based on procedural requirements, the licensee is required to manually trip the plant due to the loss of the two circ water pumps. The reactor trip was characterized as uncomplicated with all systems functioning as required. All rods fully inserted. No primary or secondary relief valves lifted. Auxiliary feedwater automatically started as expected and is supplying cooling water to the steam generators. Decay heat is being discharged to the condenser via the turbine bypass valves. The plant is stable in hot standby at no-load temperature and pressure. The plant trip had no impact on Unit 2. The debris buildup on the Unit 2 intake is being monitored but is less of a problem due to the orientation of the Unit 2 intake structure.
The NRC Resident Inspector has been notified by the licensee. The licensee has also notified State and local authorities and has made a press release.
Power Reactor
Event Number: 42025
Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: DAVID ECKERT
HQ OPS Officer: BILL HUFFMAN
Region: 3 State: IA
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: DAVID ECKERT
HQ OPS Officer: BILL HUFFMAN
Notification Date: 09/29/2005
Notification Time: 18:13 [ET]
Event Date: 09/29/2005
Event Time: 15:34 [CDT]
Last Update Date: 09/29/2005
Notification Time: 18:13 [ET]
Event Date: 09/29/2005
Event Time: 15:34 [CDT]
Last Update Date: 09/29/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
DAVID HILLS (R3)
DAVID HILLS (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 96 | Power Operation | 96 | Power Operation |
HIGH PRESSURE COOLANT INJECTION (HPCI) DECLARED INOPERABLE
"During venting of the HPCI discharge line, a steady stream of water was not obtained. Venting was conducted for approximately 30 minutes.
"HPCI was declared inoperable as Surveillance Requirement SR 3.5.1.1 (for verifying ECCS injection subsystem piping is filled with water from the pump discharge valve to the injection valve) was unable to be satisfied.
"This unplanned HPCI System inoperability is reportable under 10 CFR 50.72(b)(3)(v)(D) as a single train failure that could have prevented the fulfillment of a safety function of structures or systems designed to mitigate the consequences of an accident."
The licensee stated that the cause of the venting problem is still under investigation. The HPCI inoperability places the licensee into a 14 day LCO.
The NRC resident has been notified.
"During venting of the HPCI discharge line, a steady stream of water was not obtained. Venting was conducted for approximately 30 minutes.
"HPCI was declared inoperable as Surveillance Requirement SR 3.5.1.1 (for verifying ECCS injection subsystem piping is filled with water from the pump discharge valve to the injection valve) was unable to be satisfied.
"This unplanned HPCI System inoperability is reportable under 10 CFR 50.72(b)(3)(v)(D) as a single train failure that could have prevented the fulfillment of a safety function of structures or systems designed to mitigate the consequences of an accident."
The licensee stated that the cause of the venting problem is still under investigation. The HPCI inoperability places the licensee into a 14 day LCO.
The NRC resident has been notified.
General Information or Other
Event Number: 42040
Rep Org: OHIO BUREAU OF RADIATION PROTECTION
Licensee: THELEN ASSOCIATES, INC.
Region: 3
City: CINCINNATI State: OH
County:
License #: OH31210310005
Agreement: Y
Docket:
NRC Notified By: STEPHEN JAMES
HQ OPS Officer: JOHN MacKINNON
Licensee: THELEN ASSOCIATES, INC.
Region: 3
City: CINCINNATI State: OH
County:
License #: OH31210310005
Agreement: Y
Docket:
NRC Notified By: STEPHEN JAMES
HQ OPS Officer: JOHN MacKINNON
Notification Date: 10/05/2005
Notification Time: 16:29 [ET]
Event Date: 09/29/2005
Event Time: 02:00 [EDT]
Last Update Date: 10/05/2005
Notification Time: 16:29 [ET]
Event Date: 09/29/2005
Event Time: 02:00 [EDT]
Last Update Date: 10/05/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
BRUCE BURGESS (R3)
E. WILLIAM BRACH (NMSS)
BRUCE BURGESS (R3)
E. WILLIAM BRACH (NMSS)
OHIO AGREEMENT STATE REPORT - PORTABLE DENSITY GAUGE DAMAGED
"Portable density gauge was damaged by [an] intoxicated driver while [the] gauge was in use at approximately 2:00 AM. Licensee personnel were able to retract [the] source rod into [the] damaged case. [The] shielding appeared to be intact. Readings on [the] damaged gauge at one meter with [the] rod retracted were 0.2 to 0.3 Mr/hr. [The] Gauge was placed in [a] transport case and returned to [the] licensee's storage location. Licensee performed [a] leak test and is awaiting results. Initial survey of [the] area around [the] damaged gauge indicated no contamination or evidence of leakage of [the] source. Gauge to be surveyed, packaged and prepared for shipment by local service provider (Cline Technical Services). Gauge is a Troxler Model 4640-B with 8 mCi (millicuries) Cs-137 source."
Corrective Action: Equipment returned to manufacturer for repair or disposal.
Manufacturer: Troxler Model Number: 4640-B Serial Number: 1122
Item Number: OH050006.
"Portable density gauge was damaged by [an] intoxicated driver while [the] gauge was in use at approximately 2:00 AM. Licensee personnel were able to retract [the] source rod into [the] damaged case. [The] shielding appeared to be intact. Readings on [the] damaged gauge at one meter with [the] rod retracted were 0.2 to 0.3 Mr/hr. [The] Gauge was placed in [a] transport case and returned to [the] licensee's storage location. Licensee performed [a] leak test and is awaiting results. Initial survey of [the] area around [the] damaged gauge indicated no contamination or evidence of leakage of [the] source. Gauge to be surveyed, packaged and prepared for shipment by local service provider (Cline Technical Services). Gauge is a Troxler Model 4640-B with 8 mCi (millicuries) Cs-137 source."
Corrective Action: Equipment returned to manufacturer for repair or disposal.
Manufacturer: Troxler Model Number: 4640-B Serial Number: 1122
Item Number: OH050006.