| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
10/12/2007 - 10/15/2007 ** EVENT NUMBERS ** |
 | Power Reactor | Event Number: 43705 | Facility: TURKEY POINT
Region: 2 State: FL
Unit: [ ] [4] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: EDDIE NEVILLE
HQ OPS Officer: JASON KOZAL | Notification Date: 10/10/2007
Notification Time: 05:35 [ET]
Event Date: 10/10/2007
Event Time: 00:00 [EDT]
Last Update Date: 10/12/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
BINOY DESAI (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 4 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text LOSS OF ERDADS AND ERDS LINK
"The Emergency Response and Data Acquisition System (ERDADS) was out of service at 0000 EST on 10/10/2007. This resulted in a loss of the ERDS link of plant data to the NRC. This is an 8-hour reportable event pursuant to 10CFR50.72(b)(3)(xiii) Major Loss of Assessment Capability. The cause of the loss appears to be a computer malfunction, there is no evidence of tampering. Follow-up notification to the NRC will be given once Unit 4 ERDS is returned to service."
As of 0515 ERDADS was available in the licensee control room, but the ERDS link was not available with the NRC.
The licensee notified the NRC Resident Inspector.
* * * UPDATE FROM NIELSEN TO HUFFMAN AT 1341 EDT ON 10/12/07 * * *
"Repairs are complete and the Unit 4 ERDADS system was tested Sat. at 1216 EDT on 10/12/07. The ERDS link of plant data to the NRC has been restored on Unit 4."
The licensee notified the NRC Resident Inspector. R2DO (Desai) notified. |
| Power Reactor | Event Number: 43717 | Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [1] [ ] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: PAUL CHRISTIANSEN
HQ OPS Officer: JOE O'HARA | Notification Date: 10/12/2007
Notification Time: 04:34 [ET]
Event Date: 10/11/2007
Event Time: 21:47 [EDT]
Last Update Date: 10/12/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
BINOY DESAI (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text LOSS OF ERDADS/SPDS DISPLAY
"On 10/11/2007 at 2147, the ERDADS SPDS displays for Unit 1 were discovered out of service, rendering the majority of process parameters and trends unreadable from the display screens in the control room, TSC, and EOF. This information was also not available to the NRC via the ERDS. However, the process parameters and alarm capabilities are available to operating personnel via redundant control room and plant instrumentation. Information regarding main steam line radiation monitoring, meteorological data, and information provided by the Qualified Safety Parameter Display System (QSPDS) (i.e. RCS sub cooling, reactor vessel level, and core exit temperature) is available on the ERDADS terminals and is also available to the NRC via the ERDS. The ERDS Link to the NRC from both Unit 1 and Unit 2 remains functional. Troubleshooting by the site maintenance and engineering personnel is ongoing. This Non-Emergency Notification is being made pursuant to 10CFR50.72(b)(3)(xiii) regarding loss of emergency assessment capability."
The licensee will notify the NRC Resident Inspector. |
| Power Reactor | Event Number: 43718 | Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: MATTHEW RASMUSSEN
HQ OPS Officer: JOE O'HARA | Notification Date: 10/12/2007
Notification Time: 11:07 [ET]
Event Date: 10/12/2007
Event Time: 08:02 [CDT]
Last Update Date: 10/12/2007 | 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
| Person (Organization):
BINOY DESAI (R2)
|
| 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 | Event Text AUTOMATIC REACTOR SCRAM DUE TO TURBINE TRIP
"At 0802 [CDT] on 10/12/2007 with Unit 1 at 100% power, an automatic reactor scram was received due to a turbine trip. Unit 2 and 3 were also at 100% power and were unaffected by the event. All expected PClS isolations, Group 2 (RHR Shutdown Cooling), Group 3 (RWCU), Group 6 (Ventilation), and Group 8 (TIP) were received along with the auto start of CREVs and 3 SBGT trains.
"This event is reportable as a 4-hour and 8-hour non-emergency notification along with a 60-day written report in accordance with 10 CFR50.72(b)(2)(iv)(B), 10 CFR 50.72(b)(3)(iv)(A) and 10 CFR 50.73(a)(2)(iv)(A) as 'any event or condition that results in valid actuation of RPS or PCIS'.
"All control rods fully inserted, the electrical grid is stable, the EDGs and ESF systems remain available, and decay heat is being removed via the Turbine Bypass Valves. The licensee notified the NRC Resident Inspector.
"The cause of the turbine trip is under investigation."
The 1D RHR pump is OOS for planned maintenance. Isolations occurred as a result of low reactor water level +2 inches.
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 43719 | Facility: MILLSTONE
Region: 1 State: CT
Unit: [ ] [ ] [3]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: RICH SADLER
HQ OPS Officer: BILL HUFFMAN | Notification Date: 10/12/2007
Notification Time: 14:52 [ET]
Event Date: 10/12/2007
Event Time: 13:30 [EDT]
Last Update Date: 10/12/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
WILLIAM COOK (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text UNANALYZED CONDITION AFFECTING FIRE SAFE SHUTDOWN
"During an engineering review it was discovered that for certain fire scenarios affecting the auxiliary building west motor control center - rod control room, the previously established fire safe shutdown strategy might not be successful. Specifically, for a fire in the west motor control center - rod control room, fire safe shutdown would be accomplished utilizing an unaffected charging pump. During an engineering review, a vulnerability was identified in which under certain circumstances the spurious closure of a charging pump suction valve could result in a loss of the running charging pump and the unavailability of the remaining charging pumps due to potential fire damage. The result is that all charging pumps could be affected by the fire and be unavailable to support fire safe shutdown in accordance with established procedures.
"Compensatory actions to minimize risk of fire in areas of concern are being implemented.
"This condition is being reported pursuant to 10 CFR 50.72(b)(3)(ii)(B).
"The NRC Resident Inspector has been notified." The licensee has also notified appropriate State and local authorities. |
| Power Reactor | Event Number: 43720 | Facility: QUAD CITIES
Region: 3 State: IL
Unit: [1] [2] [ ]
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: DARYL CLARK
HQ OPS Officer: JOHN MacKINNON | Notification Date: 10/12/2007
Notification Time: 18:02 [ET]
Event Date: 10/12/2007
Event Time: 16:04 [CDT]
Last Update Date: 10/12/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
PATTY PELKE (R3)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 97 | Power Operation | 97 | Power Operation | | 2 | N | Y | 96 | Power Operation | 96 | Power Operation | Event Text OFFSITE NOTIFICATION MADE DUE TO ELEVATED LEVELS OF TRITIUM
"This notification is being made pursuant to 10 CFR 50.72(b)(2)(xi) due to the fact that Exelon Nuclear has informed the Illinois Emergency Management Agency and Illinois Environmental Protection Agency of recent groundwater monitoring results at Quad Cities Station. This notification was made at 16:04 hours CDST on October 12, 2007.
"As part of the Station's continuing environmental monitoring and sampling program, new wells were recently installed on Station property to better characterize the known, on-site tritium plume previously identified during Exelon's fleetwide tritium study conducted in 2006. Samples from some of the new wells have indicated elevated levels of tritium requiring notification of the State of Illinois.
"Based on well data to date, the tritium in the groundwater is confined to Exelon property and poses no threat to public health or safety.
"The Station continues to track this issue by monitoring the existing wells, installing new wells for further assessment, and pursuing underground pipe integrity testing."
The NRC Resident Inspector was notified of this event by the licensee. |
| Other Nuclear Material | Event Number: 43721 | Rep Org: THOMAS, DEAN, & HOSKINGS
Licensee: THOMAS, DEAN, & HOSKINGS
Region: 4
City: GREAT FALLS State: MT
County:
License #:
Agreement: N
Docket:
NRC Notified By: ERLING JUEL
HQ OPS Officer: BILL HUFFMAN | Notification Date: 10/12/2007
Notification Time: 18:07 [ET]
Event Date: 10/12/2007
Event Time: [MDT]
Last Update Date: 10/12/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
| Person (Organization):
MICHAEL SHANNON (R4)
SCOTT FLANDERS (FSME)
| Event Text DAMAGED TROXLER MOISTURE DENSITY GAUGE
A Troxler moisture density gauge was damaged by construction equipment that backed up over the gauge after it had been placed on the ground in preparation for taking soil density measurements. The incident occurred at a Great Falls MT construction site. The source rod was still in the safe shielded position when run over. The gauge housing was damaged but there was no apparent damage to the gauge sources. The rod source was confirmed to still be present in the gauge. There was no contamination found. The damaged gauge was placed into its shipping container. The sources will be leaked tested prior to shipment to Troxler for repair. |
| Power Reactor | Event Number: 43722 | Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: MARTIN LICHTNER
HQ OPS Officer: JASON KOZAL | Notification Date: 10/13/2007
Notification Time: 05:15 [ET]
Event Date: 10/13/2007
Event Time: 02:20 [EDT]
Last Update Date: 10/13/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
| Person (Organization):
WILLIAM COOK (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 0 | Hot Shutdown | Event Text TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO INOPERABLE CONTROL RODS
"Susquehanna Unit 1 was being manually shutdown on 10/13/2007 for a planned maintenance outage to address control cell friction. Prior to the shutdown five control rods had been declared inoperable due to control cell friction. When reactor power was lowered to 10% at 0220, entry into Tech Spec 3.1.3 was required for 'One or more BPWS groups with four inoperable control rods'. The completion time for this specification is 4 hours. The inoperability of the control rods condition cannot be cleared in the specified time. This condition results in the unit being in a 'Shutdown Required By Technical Specifications'. The required action is to be in Mode 3 within 12 hours. The Shutdown required by Technical Specifications is reportable as a 4 hour Non-Emergency report under 10 CFR 50.72(b)(2)(i).
"Manual insertion of control rods will continue until all rods are fully inserted. Hot Shutdown is expected by 0800, 10/13/07.
"Shutdown activities will continue to place the unit in cold shutdown.
"A Press Release will be made concerning the planned maintenance outage."
The licensee notified the NRC Resident Inspector. | |