| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
12/06/2011 - 12/07/2011 ** EVENT NUMBERS ** |
 | Power Reactor | Event Number: 47499 | Facility: TURKEY POINT
Region: 2 State: FL
Unit: [3] [4] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: ROBERT STRUSINSKI
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 12/06/2011
Notification Time: 09:51 [ET]
Event Date: 12/06/2011
Event Time: 09:30 [EST]
Last Update Date: 12/06/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
BINOY DESAI (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | | 4 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text TECHNICAL SUPPORT CENTER NON-FUNCTIONAL DUE TO PLANNED MAINTENANCE
"Between December 6, 2011 and January 13, 2012, a sequence of activities are planned that will render the Technical Support Center (TSC) non-functional at times by removing the emergency ventilation system from service. These activities are being performed in support of planned preventive maintenance and extended power uprate facility upgrades. In preparation for these emergency ventilation system outages, the TSC emergency responders were notified that if an emergency occurred during these outages the Emergency Coordinator and the TSC staff involved with classification, notification and PARS should report to the control room. All other TSC personnel should report to the Operational Support Center. The duration for each of these TSC outages is expected to be less than 24 hours. The NRC Operations Center will be provided an update to this notification when the TSC emergency ventilation has been removed from service and following restoration for each time period. This 8 hour notification in accordance with 10 CFR 50.72(b)(3)(xiii)."
The licensee notified the NRC Resident Inspector, and State and local governments. |
| Power Reactor | Event Number: 47500 | Facility: VERMONT YANKEE
Region: 1 State: VT
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: KEVIN MURPHY
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 12/06/2011
Notification Time: 10:15 [ET]
Event Date: 10/11/2011
Event Time: 16:29 [EST]
Last Update Date: 12/06/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
| Person (Organization):
CHRISTOPHER CAHILL (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | Event Text LOSS OF VITAL AC POWER WHILE SHUTDOWN
"This 60-day telephone notification is being made pursuant to 10CFR50.73(a)(2)(iv)(A) and 10CFR50.73(a)(1) to describe an invalid actuation of a containment heat removal system.
"On October 11, 2011, with the reactor shutdown for refueling, a partial loss of vital AC power was experienced which resulted in a loss of shutdown cooling as well as PCIS group 2, 3, 4, and 5 half isolations. The actuation was determined to be invalid as it occurred because a breaker supplying power to the 'A' vital AC was manually opened, resulting in actuation of the associated PCIS logic circuitry. The Group 4 actuation resulted in a complete isolation of the single train Residual Heat Removal shutdown cooling suction path. The shutdown cooling path was isolated for approximately 12 minutes resulting in a coolant temperature increase of approximately 2 degrees F. At the time of the event, the reactor cavity was flooded with the spent fuel pool gates removed and the normal fuel pool cooling system in operation to provide reactor cavity cooling. Based on this, there was no impact on public health and safety."
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 47501 | Facility: ROBINSON
Region: 2 State: SC
Unit: [2] [ ] [ ]
RX Type: [2] W-3-LP
NRC Notified By: RAY BUZARD
HQ OPS Officer: STEVE SANDIN | Notification Date: 12/06/2011
Notification Time: 13:54 [ET]
Event Date: 12/06/2011
Event Time: 09:00 [EST]
Last Update Date: 12/06/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
RANDY MUSSER (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text LOSS OF EMERGENCY ASSESSMENT CAPABILITY
"At 0900 hours EST, on December 6, 2011, Emergency Preparedness personnel determined that the Unusual Event and Alert EAL criteria for the Liquid Waste Disposal Effluent could not be achieved due to the monitor range capability. Specifically, the R-18 effluent monitor instrument range has a maximum range of 1.0E+06 with the alarm set at 1.0E+06. The UE and Alert criteria, which are 2 times the alarm and 200 times the alarm respectively, both exceed the instrument range.
"The NRC Resident Inspector has been notified."
This condition has existed for some time (at least three years) and was discovered during a review of the Operating Experience database involving a similar condition reported by Crystal River-3. The licensee maintains the ability to perform grab samples of the liquid effluent for assessment. |
| Power Reactor | Event Number: 47502 | Facility: CLINTON
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: ED TIEDEMANN
HQ OPS Officer: STEVE SANDIN | Notification Date: 12/06/2011
Notification Time: 17:07 [ET]
Event Date: 12/06/2011
Event Time: 13:06 [CST]
Last Update Date: 12/06/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
RICHARD SKOKOWSKI (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | Event Text LOSS OF COMMUNICATIONS CAPABILITY DUE TO A MAJOR CABLE CUT
"On 12/06/2011 at approximately 1306 CST, a major offsite underground communications line was severed, cutting telephone lines to Clinton Power Station. The lost communications include the Health Physics Network (HPN), Emergency Notification System (ENS) and the ability to send Emergency Response Data System (ERDS) data to the NRC. Alternate communications have been established with the NRC and other agencies.
This event is reportable due to the major loss of emergency assessment capability per 10CFR50.72 (b)(3)(xiii). The time to repair the lines and restore communications is unknown at this time.
The NRC Resident Inspector has been notified.
* * * UPDATE AT 1624 EST ON 12/6/11 FROM BOB RUSH TO S. SANDIN * * *
The communication lines have been repaired and HPN, ENS, and ERDS have been restored. Notified R3DO (Skokowski). |
| Part 21 | Event Number: 47505 | Rep Org: FLOWSERVE LIMITORQUE ACTUATORS
Licensee: FLOWSERVE LIMITORQUE ACTUATORS
Region: 1
City: LYNCHBURG State: VA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: JEFF McCONKEY
HQ OPS Officer: STEVE SANDIN | Notification Date: 12/06/2011
Notification Time: 16:43 [ET]
Event Date: 12/05/2011
Event Time: [EST]
Last Update Date: 12/06/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
| Person (Organization):
CHRISTOPHER CAHILL (R1DO)
RANDY MUSSER (R2DO)
RICHARD SKOKOWSKI (R3DO)
NEIL OKEEFE (R4DO)
PART 21 via email ()
| Event Text LIMITORQUE PART 21 NOTIFICATION INTERIM REPORT - POTENTIAL DEFECTIVE PART IN SMB-0 HEAVY SPRING PACK
The following information was received via fax:
Background: During in-house production testing of Limitorque SMB-0 actuators, test lab personnel
reported an inability to maintain consistent torque output at the various torque switch settings. Investigation revealed that the actuator torque spring pack assembly had lost preload during the test. Component inspection determined that the loss of preload was due to disc springs that had experienced an excessive permanent relaxation of free height during actuator testing.
Components Affected: Only SMB/SB/SBD-0 actuators with heavy spring pack assemblies shipped between September 15, 2011 and November 7, 2011 could possibly be affected. No parts orders for SMB/SB/SBD-0 replacement heavy spring packs were built in this time period.
Potential Impact on Safety Related Operation: A significant loss of preload on the actuator torque spring pack assembly could result in the actuator producing insufficient output torque thereby affecting proper valve function.
Cause and Corrective Action: Communications with the spring manufacturer revealed that Limitorque was shipped a single lot of springs that were not in accordance with our parts requirements. These springs were incorrectly shipped to Limitorque due to a manufacturer backorder on our normally requested product. Vendor controls have been implemented to prevent reoccurrence of this issue. Limitorque has identified the problem springs and purged them from inventory.
On November 14, 2011 Limitorque notified all affected customers who received the actuators which shipped during the time period identified above. The serial numbers and locations of the potentially affected actuators are provided in the table below. Limitorque has requested that the actuator spring packs be returned for detailed inspection and replacement if needed.
After inspection of the spring pack assembly of all actuators listed below, Flowserve-Limitorque will issue a follow-up to this interim report on or before February 3, 2012.
Affected Customers/Locations:
Customer - Velan Valve Corp.
Location of Actuator - Velan Valve, Montreal
Limitorque Order No. 110309.001
Quantity - 6
Actuator Serial # 909476-909481
Customer - Velan Valve Corp.
Location of Actuator - Velan Valve, Montreal
Limitorque Order No. 115055.001
Quantity - 1
Actuator Serial # 926332
Customer - Weir Valve Corp.
Location of Actuator - Weir Valve, Ipswich, MA
Limitorque Order No. 106839.008
Quantity - 4
Actuator Serial # 911621-911624
Customer - Weir Valve Corp.
Location of Actuator - Weir Valve, Ipswich, MA
Limitorque Order No. 106839.009
Quantity - 4
Actuator Serial # 911625-911628
Customer - Weir Valve Corp.
Location of Actuator - Weir Valve, Ipswich, MA
Limitorque Order No. 106930.012
Quantity - 4
Actuator Serial # 912769-912772
Customer - Areva NP
Location of Actuator - Exelon, Braidwood NGS
Limitorque Order No. 112724.001
Quantity - 1
Actuator Serial # 917953 | |