| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
11/23/2010 - 11/24/2010 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 46196 | Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: SETH BELL
HQ OPS Officer: STEVE SANDIN | Notification Date: 08/22/2010
Notification Time: 00:15 [ET]
Event Date: 08/21/2010
Event Time: 17:00 [CDT]
Last Update Date: 11/24/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
GEOFFREY MILLER (R4DO)
|
| 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 ONE TRAIN ECCS DECLARED INOPERABLE DUE TO VOID IN "A" RHR HEAT EXCHANGER
"On 8/21/10 at 1700 [CDT] with the Unit in Mode 1, 100% power, Engineering personnel provided information to the Control Room that a known void in the 'A' Residual Heat Removal (RHR) heat exchanger could move from the heat exchanger to other locations in the Emergency Core Cooling System (ECCS). The analysis provided by a vendor indicates that during a specific RCS leak scenario with a failure of the A' RHR Pump, our [Unit 1] piping configuration could potentially allow the void to be swept from the 'A' RHR heat exchanger and be transported to the 'A' Centrifugal Charging Pump (CCP) and 'A' Safety Injection Pump (SIP) while in the cold leg recirculation mode of operation. This condition results in one train of ECCS being inoperable. The ECCS safety function is maintained due to redundant and interconnecting piping, in both injection and recirculation phases of operation.
"The NRC Resident has been informed."
The licensee declared one train of ECCS inoperable placing Unit 1 in the 72-hour Technical Specification [TS] 3.5.2, Condition A, Action A.1. Corrective actions are on going to remove the void and exit the TS Action Statement.
* * * RETRACTION FROM RICK HUBBARD TO JOHN SHOEMAKER ON 11/24/10 AT 12:24 EST * * *
"Additional information has been obtained by Engineering. The largest void identified in the 'A' RHR heat exchanger would not prevent the RHR system from performing its safety function. Hydraulic analysis models of this void moving through the system have shown that no pressure pulses will occur that could challenge the structural integrity of the system. The model results also show that ingestion of the void by the higher head ECCS pumps during the ECCS recirculation mode has no adverse affect on the ECCS high head pumps and they would remain capable of performing their safety function.
"As a result, this event is not reportable per 50.72(b)(3)(ii)(B). This event is being retracted."
The licensee notified the NRC Resident Inspector. R4DO (Lantz) has been notified. |
| Other Nuclear Material | Event Number: 46432 | Rep Org: VA CARIBBEAN HEALTHCARE ADMIN.
Licensee: DEPARTMENT OF VETERAN AFFAIRS, NATIONAL HEALTH PHYSICS PROG.
Region:
City: SAN JUAN State:
County: PUERTO RICO
License #:
Agreement: N
Docket:
NRC Notified By: THOMAS HUSTON
HQ OPS Officer: JOHN SHOEMAKER | Notification Date: 11/23/2010
Notification Time: 14:24 [ET]
Event Date: 10/31/2010
Event Time: [EST]
Last Update Date: 11/23/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(ii) - LOST/STOLEN LNM>10X
| Person (Organization):
DON JACKSON (R1DO)
BILLY DICKSON (R3DO)
GLENDA VILLAMAR (FSME)
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text VA CARRABEAN HEALTH CARE SYSTEM IN SAN JUAN, PUERTO RICO - LOST TRITIUM EXIT SIGNS
The Department of Veterans Affairs, Veterans Health Administration, National Health Physics Program reported the loss of generally licensed devices (self-illuminating tritium exit signs).
"This report is required by 10 CFR 31.5(a)(10) and 10 CFR 20.2201(a)(1). Four (4) tritium exit signs are declared to be missing by the VA Caribbean Healthcare System, San Juan, Puerto Rico. The signs had been possessed under general licensing provisions of 10 CFR 31.5.
"The signs were model number SLXTU1RB15 manufactured by Foreverlite, Inc., and contained about 9.5 curies of tritium each. The signs had been removed from use by the facility earlier this year [March 19, 2010] and placed into temporary storage at the facility pending transfer to an authorized recipient. There are no indications that the signs were damaged or that these circumstances have resulted in any radiation exposure to individuals.
"A 30-day written report of the event will be provided to the NRC as required in 10 CFR 20.2201(a)(2)."
It was not determined the signs were missing until October 2010. A thorough search was conducted but failed to locate the missing signs. |
| Power Reactor | Event Number: 46433 | Facility: FERMI
Region: 3 State: MI
Unit: [2] [ ] [ ]
RX Type: [2] GE-4
NRC Notified By: MARK EGHIGIAN
HQ OPS Officer: DONALD NORWOOD | Notification Date: 11/23/2010
Notification Time: 14:53 [ET]
Event Date: 11/23/2010
Event Time: 11:45 [EST]
Last Update Date: 11/23/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
BILLY DICKSON (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown | Event Text OTHER GOVERNMENT AGENCY NOTIFICATION DUE TO SEWAGE LEAK
"On 11/23/10 at 1145 EST, a verbal report to the Michigan Department of Natural Resources & Environment (MDNRE) was made relating to a sewage leak to the ground from the Training Building restrooms. The onsite Facilities Maintenance Journeyman discovered mud and stones while clearing a drain to relieve a blockage. An immediate repair of the broken drain is being implemented. The plant is currently in Mode 4, in Refueling Outage 14 (RF14). Since a verbal report was made to the MDNRE, this is considered a News Release / Notification of Other Government Agency, and is reportable under 10CFR50.72(b)(2)(xi)."
The licensee notified the NRC Resident Inspector. The licensee also notified the Monroe County Health Department. |
| Power Reactor | Event Number: 46434 | Facility: SURRY
Region: 2 State: VA
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: JERRY ASHLEY
HQ OPS Officer: PETE SNYDER | Notification Date: 11/23/2010
Notification Time: 15:31 [ET]
Event Date: 10/26/2010
Event Time: 23:56 [EDT]
Last Update Date: 11/23/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
| Person (Organization):
DANIEL RICH (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown | Event Text INVALID ACTUATION OF HIGH CONSEQUENCE LIMITING SAFEGUARDS AND SAFETY INJECTION SYSTEMS
"This telephone notification is being made for an invalid actuation under 10 CFR 50.73(a)(2)(iv)(A) following the reporting guidance of 10 CFR 50.73(a)(1).
"With Unit 1 at cold shutdown (about 105 degrees Fahrenheight and depressurized), an invalid actuation of the Unit 1 'A' train of the High Consequence Limiting Safeguards (HI CLS) system and Unit 1 'A' train of the Safety Injection (SI) system occurred at 23:56 during setup for 'H' Bus Logic Testing. Plant systems and components responding to the HI CLS and SI 'A' train signals started and functioned successfully as designed (with the exception of those systems and components procedurally rendered inoperable due to the RCS being below 350 degrees Fahrenheight and 450 psig). The HI CLS and SI 'A' trains were reset and the affected systems were restored to their pre-event configurations.
"Specific trains and systems that actuated for the 'A' train of HI CLS and SI are described below:
"- With the unit at cold shutdown, one high head pump was running (the two redundant pump controls were in the pull to lock position in compliance with Technical Specifications). The 'A' train High Head Safety Injection motor operated valves re-aligned such that the running high head pump provided flow to the RCS cold legs from the Refueling Water Storage Tank (RWST). During this time the pressurizer level increased from approximately 23 percent to about 42 percent.
"- Auxiliary Feedwater (AFW) Pump motor operated valves opened but no flow was delivered to the steam generators since the AFW pumps were in pull to lock.
"- The 'A' train containment isolation valves closed, isolating the 'A' Residual Heat Removal (RHR) heat exchanger. However, shutdown cooling was previously aligned to the 'B' train RHR and therefore shutdown cooling was uninterrupted. Containment isolation valves were later restored to a normal alignment.
"- One train of Auxiliary Ventilation actuated and was restored to normal after the Safety Injection signal was reset.
"- Emergency Diesel Generator (EDG) No. 1 started but did not load since its associated Emergency Bus remained energized by offsite power. The EDG was stopped and returned to automatic.
"An apparent cause evaluation is in progress."
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 46435 | Facility: HARRIS
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP
NRC Notified By: KIMBERLY BASS
HQ OPS Officer: DONALD NORWOOD | Notification Date: 11/23/2010
Notification Time: 15:35 [ET]
Event Date: 11/10/2010
Event Time: 00:24 [EST]
Last Update Date: 11/23/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
| Person (Organization):
DANIEL RICH (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Hot Standby | 0 | Hot Standby | Event Text TELEPHONE NOTIFICATION IN LIEU OF WRITTEN LER - INVALID ACTUATION OF MOTOR DRIVEN AUXILIARY FEEDWATER PUMP
"Event: Invalid actuation of the 'B' Motor Driven Auxiliary Feedwater (MDAFW) pump.
"Report Type: This 60-day telephone notification is being made under 10CFR50.73(a)(2)(iv)(A) and 10CFR50.73(a)(1).
"Description: On November 10, 2010, the 'A' Main Feedwater Pump (MFP) was started per plant operating procedures. When the 'A' MFP was started, there was a partial activation of the Auxiliary Feedwater System with the start of the 'B' MDAFW.
"The plant was in Mode 3 after completing refueling outage 16 during this event. Actual plant conditions and parameters did not exist that required an automatic start of the 'B' MDAFW pump. Therefore, this actuation is classified as invalid. The system started and functioned successfully.
"This invalid actuation was entered into the corrective action program as NCR-432566."
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 46436 | Facility: FERMI
Region: 3 State: MI
Unit: [2] [ ] [ ]
RX Type: [2] GE-4
NRC Notified By: JIM KONRAD
HQ OPS Officer: DONALD NORWOOD | Notification Date: 11/24/2010
Notification Time: 16:00 [ET]
Event Date: 11/24/2010
Event Time: 15:15 [EST]
Last Update Date: 11/26/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
BILLY DICKSON (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown | Event Text SAFETY PARAMETER DISPLAY SYSTEM AND EMERGENCY RESPONSE DATA SYSTEM OUT OF SERVICE FOR PLANNED MAINTENANCE
"On 11/24/10 at 1515 EST, the Safety Parameter Display System (SPDS) and Emergency Response Data System (ERDS) were removed from service to support activities for a planned maintenance outage on the UPS vital bus power supply. The duration of work is expected to be approximately 48 hours. During this time, the majority of the Control Room indications remain available to the plant staff, and will be used for emergency response, if needed. Information will be communicated to the NRC using other available communication systems, if needed. The plant is currently in Mode 4, and will remain in Mode 4, for the duration of the SPDS and ERDS unavailability. Since the unavailability will last greater than 8 hours, this is considered a Loss of Emergency Assessment Capability, and reportable under 10CFR50.72(b)(3)(xiii).
"Followup notification will be made when SPDS and ERDS have been restored."
The licensee notified the NRC Resident Inspector.
* * * UPDATE AT 1850 EST ON 11/26/10 FROM JIM KONRAD TO S. SANDIN * * *
"Update to Event #46436: On 11/26/10 at 1733 EST, regarding Safety Parameter Display System (SPDS) and Emergency Response Data System (ERDS) systems removed from service to support planned maintenance on the UPS vital bus power supply.
"Planned work which resulted in the loss of SPDS and ERDS is complete. All Emergency Assessment Capabilities have been restored."
The licensee informed the NRC Resident Inspector. Notified R3DO (Dickson). |
| Power Reactor | Event Number: 46437 | Facility: CRYSTAL RIVER
Region: 2 State: FL
Unit: [3] [ ] [ ]
RX Type: [3] B&W-L-LP
NRC Notified By: EDDIE RIFFLE
HQ OPS Officer: HOWIE CROUCH | Notification Date: 11/24/2010
Notification Time: 17:43 [ET]
Event Date: 11/24/2010
Event Time: 15:50 [EST]
Last Update Date: 11/24/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
DANIEL RICH (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | N | 0 | Refueling | 0 | Refueling | Event Text OFFSITE NOTIFICATION DUE TO RELEASE OF AN OILY MIXTURE TO DISCHARGE CANAL
"During maintenance activities at Crystal River Unit 3, approximately 25 to 30 gallons of an oily water mixture was pumped from a manway/vault. A small amount of this mixture was inadvertently discharged to a storm drain that leads to the Crystal River Unit 3 outfall (discharge canal). There was a slight sheen observed at the outfall as approximately 1/2 cup of the mixture entered the outfall area. This is reportable under 40CFR110 due to a light sheen observed on the site discharge canal. Crystal River Environmental Specialists responded to the spill with a combination of sand bags, floating sorbent boom, as well as sorbent pads. After deployment of the sand bags, floating sorbent booms, and securing the pumping activities, the spill status was confirmed as ceased and contained. Notifications will be made to the Florida Department of Environmental Protection State Warning Point and the National Response Center. This is 4-hour reportable per 10 CFR 50.72(b)(2)(xi) as a situation related to protection of environment, for which government agencies will be notified."
The substance discharged appears to be some sort of motor oil. Prior to pumping, a sample of the liquid was analyzed and did not contain any radioactive nuclides. The licensee has notified the NRC Resident Inspector. | |