| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
02/03/2010 - 02/04/2010 ** EVENT NUMBERS ** |
 | Power Reactor | Event Number: 45673 | Facility: FARLEY
Region: 2 State: AL
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: BILL ARENS
HQ OPS Officer: DONG HWA PARK | Notification Date: 02/03/2010
Notification Time: 03:14 [ET]
Event Date: 02/02/2010
Event Time: 20:15 [CST]
Last Update Date: 02/03/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
DAVID AYRES (R2DO)
|
| 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 TWO OF THREE TRAINS OF AUXILIARY FEED WATER DECLARED INOPERABLE
"On 2/2/10, at 1615 [CST], the Unit 1 TDAFW [Turbine Driven Auxiliary Feed Water] Pump was declared inoperable due to a high temperature identified on an electrical cable in the TDAFW UPS [Uninterrupted Power Supply]. The 1B Diesel Generator had previously been removed from service for scheduled maintenance. As required by the Diesel Generator LCO Required Action Statement, the Unit 1 'B' MDAFW [Motor Driven Auxiliary Feed Water] Pump was declared inoperable at 2015 [CST], on 2/2/10, due to the combination of its inoperable emergency power supply and inoperable redundant equipment. This resulted in two of three trains of Auxiliary Feed Water being inoperable. Because two out of the three trains of AFW [Auxiliary Feed Water] are required to meet flow requirements for limiting design basis accidents, this represents a condition that could have prevented the fulfillment of a safety function.
"Repairs to the electrical cable were immediately initiated. At 2216 [CST], on 2/2/10, the Unit 1 TDAFW Pump was returned to operable status, allowing the 1B MDAFW Pump to be declared operable, and restoring the safety function."
The licensee determined that the high temperature in the electrical cable was caused by a high resistance between the lug and cable connection.
The licensee will notify the NRC Resident Inspector. |
| Power Reactor | Event Number: 45675 | Facility: SOUTH TEXAS
Region: 4 State: TX
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BILLY HERZOG
HQ OPS Officer: HOWIE CROUCH | Notification Date: 02/03/2010
Notification Time: 16:38 [ET]
Event Date: 02/03/2010
Event Time: 13:44 [CST]
Last Update Date: 02/03/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
| Person (Organization):
VINCENT GADDY (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 30 | Power Operation | Event Text TECHNICAL SPECIFICATION SHUTDOWN REQUIRED DUE TO CONTROL ROD OUT OF ALIGNMENT
"A shutdown of South Texas Project Unit 1 was initiated at 13:44 hours [CST] on February 3, 2010. When in Action b.2. of Technical Specification (TS) 3.1.3.1, 'Moveable Control Assemblies Group Height,' a second control rod, B-12, in Shutdown Bank A was declared inoperable when the rod came out of alignment with the remainder of the rods within its bank. The second control rod came out of alignment during the performance of Surveillance Requirement 4.1.3.1.2; a surveillance to determine operability by movement of the rod.
"For the above condition, Action c. of TS 3.1.3.1 was entered. When the requirements of the action could not be met, South Texas Project Unit 1 entered TS 3.0.3. and a plant shutdown was initiated.
"Prior to initiation of this event, South Texas Project Unit 1 was in Action b.2 [of TS 3.1.3.1] with rod C-5 of Shutdown Bank D trippable but inoperable due to causes other than addressed by Action a. The inoperable rod, C-5, was aligned within 12 steps of the remainder of the rods within its group and the rod sequence and insertion limits as specified in the Core Operating Limits Report were being maintained."
At the time of this report, South Texas Project Unit 1 was at 30% power and decreasing. The plant will enter Mode 3, Hot Shutdown, at approximately 1800 CST. Shutdown was initiated when rod B-12 could not be aligned within 12 steps of the remainder of rods within its bank as specified in Action c. of TS 3.1.3.1.
The licensee has notified the NRC Resident Inspector.
* * * UPDATE FROM BOB SCARBOROUGH TO HOWIE CROUCH @ 2220 EST ON 2/03/10 * * *
"At 1730 [CST] during performance of the Unit 1 shutdown, control rod H-2 in Bank 1C inserted from 246 steps, as indicated by the digital rod-position indication system, to 234 steps indicated without a demand signal applied to the control bank. The group step counter remained at 249 steps with no other rods in Bank 1C indicating movement.
"The shutdown continued normally from that point. Control rod H-2 stepped with the rest on the rods in the bank down to zero steps. All control rods in Unit 1 are at zero steps. The shutdown rods are currently withdrawn."
The licensee has notified the NRC Resident Inspector. Notified R4DO (Gaddy). |
| Power Reactor | Event Number: 45676 | Facility: CLINTON
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: JIM PETERSON
HQ OPS Officer: JOHN KNOKE | Notification Date: 02/03/2010
Notification Time: 17:11 [ET]
Event Date: 02/03/2010
Event Time: 11:00 [CST]
Last Update Date: 02/03/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
| Person (Organization):
DAVID HILLS (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 3 | Startup | 4 | Startup | Event Text FEEDWATER CHECK VALVE LEAK RATE EXCEEDED TECHNICAL SPECIFICATION REQUIREMENT
"At 1100 [CST] on February 3, 2010, it was discovered that a primary containment local leak rate test performed on feedwater check valve 1B21-F032B exceeded its acceptance criteria. Technical Specification Surveillance Requirement (SR) 3.6.1.3.11 requires that the combined leakage rate for both primary containment feedwater penetrations to be less than or equal to 2 gallons per minute. The measured leakage for 1B21-F032B was reported to be 2.5 gallons per minute (gpm). Operations immediately declared 1B21-F032B inoperable and initiated action to close the feedwater inlet shutoff valve 1B21-F065B to isolate the affected penetration. At 1136 [CST], 1B21-F065B was closed and its breaker was turned off to comply with TS 3.6.1.3, Condition C required actions.
"At 1447 [CST], the Feedwater Leakage Control System (FWLCS) was declared inoperable in accordance with LCO 3.6.1.9 and the plant entered a 30-day action to restore FWLCS to an operable condition.
"After performance of a line flush, plans are underway to attempt to re-perform the local leak rate test for the feedwater check valve, 1B21-F032B. If unsuccessful, further corrective actions will be taken.
"The NRC Senior Resident has been informed." | |