| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
11/06/2009 - 11/09/2009 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 45471 | Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: TICONA POLYMERS, INC
Region: 4
City: BISHOP State: TX
County:
License #: L-02441
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: JOHN KNOKE | Notification Date: 10/30/2009
Notification Time: 14:26 [ET]
Event Date: 09/22/2009
Event Time: [CDT]
Last Update Date: 11/06/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
DALE POWERS (R4DO)
ANGELA MCINTOSH (FSME)
| Event Text AGREEMENT STATE REPORT - STUCK SHUTTER ON GAUGE
The following was received via e-mail:
"On October 30, 2009, the Agency [Texas Department of State Health Services] was notified by the licensee that they were reporting a stuck gauge event. The licensee stated that they realized that they needed to report the event after they reviewed a letter sent out by this Agency regarding the reporting of stuck shutters on gauges. The stuck shutter was found during a routine inspection on September 22, 2009. The gauge is stuck in the open position, which is the normal operating position for this gauge. Dose rates in the area were measured and found to be normal. The gauge is a Thermo Fisher model SH-F2 containing a 100 millicurie Cesium (Cs) - 137. The gauge is installed on the side of a vessel and does not pose any additional risk to their workers. The Licensee has contacted a repair service to repair the shutter. This Agency will provide additional information as it is received."
Texas Incident number I-8683
* * * UPDATE AT 1116 EST ON 11/06/2009 TO SIMPSON FROM ART TUCKER * * *
The following update was provided by the State via e-mail:
"The gauge manufacturer was incorrectly identified as Thermo Fisher. The manufacturer is Ohmart/VEGA."
The R4DO (Hay) and FSME (McIntosh) were notified. |
| General Information or Other | Event Number: 45477 | Rep Org: FLOWSERVE
Licensee: FLOWSERVE
Region: 1
City: RALEIGH State: NC
County:
License #:
Agreement: Y
Docket:
NRC Notified By: ROBERT BARRY
HQ OPS Officer: ERIC SIMPSON | Notification Date: 11/06/2009
Notification Time: 11:34 [ET]
Event Date: 11/06/2009
Event Time: [EST]
Last Update Date: 11/06/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
| Person (Organization):
MICHAEL KUNOWSKI (R3DO)
JOHN THORP (e-mail) ()
O.TABATABAI (e-mail) ()
| Event Text PART 21 REPORT - POTENTIAL FAILURE OF BONNET VALVE
The following is quoted selectively from the text of the original Part 21 notification received from Flowserve via fax:
"On September 8, 2009, Flowserve Corporation was notified by Exelon-LaSalle Nuclear Power Station of a failure which occurred and was initially communicated via Flowserve Complaint Report #4914.
"The Referenced Complaint Report describes an anomaly with a Size 3/4 Figure 848Y bolted bonnet valve at the LaSalle Nuclear Power Station.
"The subject valve was in service at the time of disassembly. The disassembly revealed that the disk nut, which captures the valve stem in the valve main disk, had separated from the main disk.
"The valve in question is a manually operated, non-active valve. The safety function of this valve is to retain system pressure. This safety function was not affected by separation of the stem nut from the valve disk.
"However, other Figure 848 valves may have different safety related functions that could be affected by this type of failure.
"[Flowserve has determined that] the Nuclear Industry needs to be notified concerning the potential defect and encouraged to inspect the operation of their valves, especially if they have a safety-related function in the plant that may be adversely affected.
"The valves affected are Size 2 and smaller Edward Figure 848 valves manufactured by Rockwell International at the Sulphur Springs, Texas, and the Raleigh, North Carolina, manufacturing facilities prior to 1991. These valves may be tagged 'Rockwell', 'Rockwell Edward' or 'Edward'. The valves affected have the old design stem/disk assembly.
"Valves with Figure Number A848 incorporate the new design stem/disk connection and are not affected. The total number of valves affected and their installed locations are not known."
The original report contains more technical details and information. |
| Power Reactor | Event Number: 45482 | Facility: COOPER
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: ROY GILES
HQ OPS Officer: DONG HWA PARK | Notification Date: 11/06/2009
Notification Time: 23:22 [ET]
Event Date: 11/06/2009
Event Time: 19:30 [CST]
Last Update Date: 11/06/2009 | 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):
MICHAEL HAY (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | M/R | Y | 20 | Power Operation | 0 | Hot Shutdown | Event Text MANUAL REACTOR TRIP DUE TO AN UNISOLABLE LEAK ON THE TURBINE HIGH PRESSURE FLUID SYSTEM
"On November 6, 2009, at 1930 CST the reactor was manually scrammed following a manual trip of the Main Turbine due to an un-isolable leak on the Turbine High Pressure Fluid System (TGF). The RO [Reactor Operator] scrammed the reactor when [reactor vessel water] level lowered below 12 inches on the Narrow Range Instruments. All Control Rods fully inserted and a Group 2 Isolation occurred when level reached 3 inches on the Narrow Range Instruments. Reactor level lowered to approximately 22 inches on the Wide Range Instruments and was recovered in a slow and deliberate manner in order to minimize the effect on the cool down rate because of low levels of decay heat in the fuel. The Reactor Feed System was used to initially recover level. At 2043, the plant was in Mode 3 with the inboard MSIVs manually closed and level and pressure being controlled by RCIC. The MSIVs were closed to minimize the cool down rate and RCIC was started manually for level and pressure control. The Main Condenser remained available throughout the evolution and condenser vacuum is currently being maintained by the Mechanical Vacuum Pumps.
"The Group 2 Isolation was verified with no discrepancies and was reset at approximately 2010.
"All equipment operated as expected and there were no difficulties encountered during the evolution.
"The TGF System has been secured and is in the process of being tagged out for repair."
The licensee has notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 45483 | Facility: ROBINSON
Region: 2 State: SC
Unit: [2] [ ] [ ]
RX Type: [2] W-3-LP
NRC Notified By: LARRY SMITH
HQ OPS Officer: JOE O'HARA | Notification Date: 11/06/2009
Notification Time: 23:36 [ET]
Event Date: 11/06/2009
Event Time: 22:02 [EST]
Last Update Date: 11/06/2009 | 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):
GERALD MCCOY (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | M/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text MANUAL REACTOR TRIP DUE TO FEED REG VALVE CLOSURE
"A Manual Reactor Trip was initiated due to closure of Main Feedwater Regulating Valve 'A' with Steam Generator 'A' Level at 35% narrow range and lowering with a Steam Flow / Feed Flow mismatch present. Both Motor Driven Auxiliary Feedwater Pumps (MDAFW) and the Steam Driven Auxiliary Feedwater Pump (SDAFW) auto-started as required based on low Steam Generator Water Levels. All systems responded normally and plant operators have stabilized the unit in Mode 3."
There were no complications. All rods inserted during the trip. Decay heat is being removed via steam dumps to condensers.
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 45484 | Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: ERIC FRANKE
HQ OPS Officer: DONG HWA PARK | Notification Date: 11/07/2009
Notification Time: 12:57 [ET]
Event Date: 11/07/2009
Event Time: 07:25 [PST]
Last Update Date: 11/07/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
| Person (Organization):
MICHAEL HAY (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | M/R | Y | 52 | Power Operation | 0 | Hot Shutdown | Event Text MANUAL REACTOR SCRAM DUE TO A MAIN TURBINE DIGITAL ELECTRO-HYDRAULIC CONTROL SYSTEM LEAK
"At 0725 hours, a manual scram was inserted due to a Main Turbine Digital Electro-Hydraulic (DEH) control system leak and anticipated turbine trip on loss of DEH tank level. Initial investigation identified a DEH leak at the area of the Quad-Voter hydraulic trip subsystem on the high pressure turbine.
"All rods fully inserted, main steam isolation valves (MSIVs) remained open, no safety/relief valves (SRVs) opened, and all other safety systems operated as designed. Reactor water level was restored and maintained with the Reactor Feedwater and Condensate systems during the post-scram transient within normal operating bands. Reactor pressure was controlled using main steam drain lines. A normal cooldown to the condenser is in progress. Offsite power is available. All three emergency diesel generators are operable and available."
The plant was operating at 52% for planned maintenance. All safety systems remain available.
The licensee has notified the NRC Resident Inspector. | |