| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
06/27/2012 - 06/28/2012 ** EVENT NUMBERS ** |
 | 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: 06/27/2012 | 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
* * * UPDATE FROM JEFF MCCONKEY TO PETE SNYDER ON 6/27/12 AT 1714 EDT * * *
The following update was received via fax:
"Pursuant to 10 CFR 21.21, Flowserve Corp is providing notification of the identification of a defect. This information was originally reported to the NRC Operations Center on 12/6/2011 (Event # 47505). This document is a follow-up to the interim Part 21 report.
"Nineteen of the twenty actuators identified in the interim report as potentially suspect have been returned to Limitorque for inspection of the spring pack. All nineteen of these actuators were returned from two different valve manufacturer's facilities and bad not been shipped to any utilities for installation. Six of the actuators returned from Velan Valve Corporation were found to contain defective springs. The spring packs were replaced and the actuators were returned to Velan Valve. The actuators returned from Weir Valve Corporation did not contain defective springs.
"The remaining actuator (serial number 917953) identified in the interim report which has not been returned to Limitorque is at Exelon Braidwood NGS. Exelon reported the following with regards to this actuator. The actuator is installed on a 36" quarter-turn MOV that is normally open and de-energized. This MOV has no safety related function to close. The MOV is position limit controlled and the valve functioned properly during operational testing after installation. Exelon Braidwood NGS is aware of the potential spring defect and plans to change the spring pack on this MOV at the first available maintenance cycle.
"Flowserve's investigation of this issue concluded that this was an isolated incident and that all defective components have been identified."
Notified R3DO (Valos) and Part 21 Group (e-mail). |
| Power Reactor | Event Number: 48051 | Facility: KEWAUNEE
Region: 3 State: WI
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP
NRC Notified By: DANIEL BACKUS
HQ OPS Officer: JOE O'HARA | Notification Date: 06/27/2012
Notification Time: 17:10 [ET]
Event Date: 06/27/2012
Event Time: 14:46 [CDT]
Last Update Date: 06/27/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
NICK VALOS (R3DO)
|
| 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 SUCTION PIPE VOIDING
"On 06/27/2012, it was identified that a void existed in the common suction header for Safety Injection. The void was of the size such that operability was maintained. However, this was nonconforming to the Kewaunee Power Station licensing basis.
"At 1446 on 06/27/2012, the Kewaunee Power Station declared both Safety Injection Train A and Safety Injection Train B Inoperable due to venting of the common suction line to remove the void. LCO 3.0.3 was entered as directed by LCO 3.5.2. ECCS Operating. This loss of safety function is reportable under 10CFR50.72(b)(3)(ii)(B).
"The void in question has been reduced to an acceptable size with the common Safety Injection suction piping full. Both Safety Injection Train A and Safety Injection Train B have been restored to Operable status and LCO 3.0.3 was exited at 1500 on 06/27/2012."
The condition was detected by ultrasonic testing as part of a surveillance for RHR pump and valve testing.
The NRC Resident Inspector has been notified. |
| Power Reactor | Event Number: 48052 | Facility: OYSTER CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-2
NRC Notified By: ANDREW ZUCHOWSKI
HQ OPS Officer: PETE SNYDER | Notification Date: 06/27/2012
Notification Time: 20:16 [ET]
Event Date: 06/27/2012
Event Time: 16:30 [EDT]
Last Update Date: 06/27/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
ANNE DeFRANCISCO (R1DO)
|
| 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 INADVERTENT ACTUATION OF AN EMERGENCY SIREN
"At 1630 EST, Exelon was notified by the NJ State OEM (Office of Emergency Management) that Oyster Creek Emergency Preparedness Siren #25, located in Harvey Cedars, NJ, was inadvertently actuated at 0209 EST and sounded for a period of 2-3 minutes. The siren was inadvertently actuated by Atlantic City Electric when restoring power to the siren. No actual plant emergency existed. Siren #25 and all other of the 42 sirens remain functional. No other reportability thresholds have been met or exceeded. State and local authorities were also notified."
The licensee will notify the NRC Resident Inspector. |
| Power Reactor | Event Number: 48053 | Facility: POINT BEACH
Region: 3 State: WI
Unit: [ ] [2] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: RUSS PARKER
HQ OPS Officer: JOHN SHOEMAKER | Notification Date: 06/28/2012
Notification Time: 01:06 [ET]
Event Date: 06/27/2012
Event Time: 20:46 [CDT]
Last Update Date: 06/28/2012 | 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):
NICK VALOS (R3DO)
|
| 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 100% LOAD REJECT
"Unit 2 Manual Reactor Trip was actuated due to indications of a 100% Load Rejection. The cause of the Load Rejection is not known at this time. All Control Rods are fully inserted. The RCS is being cooled by forced flow (reactor coolant pumps). Secondary heat sink is being provided by the condenser steam dumps utilizing the main feedwater system. The auxiliary feedwater system actuated based on low steam generator level, but has since been secured. There were no unexpected (inconsistent with nature of trip) pressure or level transients. Off site power remains available. No release occurred nor is ongoing. Emergency Core Cooling Systems did not actuate. No unexpected isolations occurred. Emergency Plan entry was not required."
The plant is stable at normal temperature and pressure. The electrical system is in a normal offsite power alignment. The Unit 2 Reactor Trip had no effect on Unit 1 which continues to operate at 100% power.
The licensee has notified the NRC Resident Inspector. | |