| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
06/14/2013 - 06/17/2013 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 49089 | Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: THE METHODIST HOSPITAL
Region: 4
City: State: TX
County: HOUSTON
License #: 00457
Agreement: Y
Docket:
NRC Notified By: CHRIS MOORE
HQ OPS Officer: CHARLES TEAL | Notification Date: 06/04/2013
Notification Time: 13:33 [ET]
Event Date: 06/03/2013
Event Time: [CDT]
Last Update Date: 06/14/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
BLAIR SPITZBERG (R4DO)
FSME EVENT RESOURCE (EMAI)
| Event Text AGREEMENT STATE REPORT - SOURCE RETRACTION FAILURE
The following was received from the State of Texas via email:
"On June 3, 2013, the Agency [State of Texas] was notified by the licensee that on June 3, 2013, a medical event had occurred. The licensee reported a source retraction failure with a Novoste Beta-Cath intravascular brachytherapy system containing a 45.1 mCi strontium - 90 source. When the treatment was completed, upon source retraction, the source got stuck in another area of the blood vessel roughly 5 cm away from the treatment site for 1 minute.
"The unintended absorbed dose to that area of the vessel is in the range of 5-6 Gy. The source open in air time was roughly 3 seconds from being retracted from the patient before being secured in a bail out box. Personnel exposure issues or concerns are not expected, however, dosimeters will be assessed. A technical representative was notified and during the next several days will inspect the system and assist in packaging the system for return shipment back to the manufacturer. Additional information will be provided as it is received in accordance with SA-300."
A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.
* * * UPDATE FROM CHRIS MOORE TO PETE SNYDER AT 1118 EDT ON 6/14/13 * * *
The following updated information was provided from the State of Texas via email:
"The Methodist Hospital reported an equipment failure that involved a source retraction during an intravascular brachytherapy treatment performed on 6/3/2013. The intravascular brachytherapy system (Best Vascular Beta-Cath A1000 series) contained a 1.67 GBq (45.1 mCi) Sr-90 source. When the treatment was completed and upon source retraction, the source became stuck in another area of the blood vessel approximately 5 cm from the treatment site for one minute. The unintended absorbed dose to the area of the aortic arch was approximately 40 cGy at 10 mm on the wall of the arch. A technical representative was notified and will inspect the system within the next several days and assist in packaging the system for return to the manufacturer."
The State of Texas determined that this event is no longer classified a medical event and has been updated to equipment failure.
Notified R4DO (Gepford) and FSME Events Resource email.
Texas Incident #: I-9088 |
| Agreement State | Event Number: 49093 | Rep Org: PA BUREAU OF RADIATION PROTECTION
Licensee: CROZIER CHESTER MEDICAL CENTER
Region: 1
City: UPLAND State: PA
County:
License #: PA-0061
Agreement: Y
Docket:
NRC Notified By: JOSEPH MELNIC
HQ OPS Officer: HOWIE CROUCH | Notification Date: 06/06/2013
Notification Time: 10:32 [ET]
Event Date: 06/04/2013
Event Time: 10:30 [EDT]
Last Update Date: 06/06/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
ART BURRITT (R1DO)
FSME EVENTS RESOURCE (EMAI)
| Event Text AGREEMENT STATE REPORT - ADMINISTERED DOSE LESS THAN DESCRIBED DOSE
The following information was obtained from the Commonwealth of Pennsylvania via facsimile:
"On June 5, 2013 the licensee informed the Department's [PA Department of Environmental Protection] Southeast Regional Office of the Medical Event. The event is reportable within 24 hours per 10 CFR 35.3045(a)(1)(i).
"Event Description: At approximately 10:30 a.m. [EDT] on June 4, 2013 the SIR-Sphere procedure took place leading to a microcatheter becoming occluded. The licensee replaced catheters and based on residual measurements of original catheter the patient received 57% of the intended dose.
"Cause of the Event: Microcatheter became occluded.
"Actions: The licensee is aware of the requirements to notify the patient and referring physician. A reactive inspection will be scheduled and conducted."
PA Event Report ID No.: PA130014
A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient. |
| Agreement State | Event Number: 49097 | Rep Org: ALABAMA RADIATION CONTROL
Licensee: UNIVERSITY OF SOUTH ALABAMA MEDICAL CENTER
Region: 1
City: State: AL
County:
License #:
Agreement: Y
Docket:
NRC Notified By: MYRON RILEY
HQ OPS Officer: VINCE KLCO | Notification Date: 06/06/2013
Notification Time: 16:39 [ET]
Event Date: 06/04/2013
Event Time: 15:45 [CDT]
Last Update Date: 06/06/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
ART BURRITT (R1DO)
FSME RESOURCES (EMAI)
| Event Text AGREEMENT STATE REPORT - EXPOSURE TO AN EMBRYO GREATER THAN 500 MILLIREM
The following information was received by facsimile:
"On June 4, 2013, the Radiation Safety Officer for the University of South Alabama, Mobile, Alabama, notified the Alabama Office of Radiation Control of a fetal/embryo dose that was in excess of 500 millirem.
"On April 2, 2013, a 30 [year old] female was referred to the University of South Alabama Medical Center for treatment of symptomatic hyperthyroidism via Sodium Iodide-131. The patient was interviewed regarding pregnancy by the authorized user and a blood test was collected for qualitative serum hCG testing. After a negative pregnancy testing and the patient's statements, the patient was given 15 millicuries of Sodium Iodide-131. The patient was also counseled to avoid pregnancy for six months.
"On May 30, 2013, eight weeks and two days later, the patient reported to her physician a positive pregnancy diagnosis by her OB/GYN physician. The patient reported that her OB/GYN physician determined that she was in the tenth week of pregnancy. This would place the patient approximately 10 days pregnant at the time of administration."
Alabama Incident: 13-27 |
| Agreement State | Event Number: 49098 | Rep Org: OK DEQ RAD MANAGEMENT
Licensee: BUILDING AND EARTH SCIENCES
Region: 4
City: PONCA CITY State: OK
County: USA
License #: OK-31032-01
Agreement: Y
Docket:
NRC Notified By: KEVIN SAMPSON
HQ OPS Officer: DANIEL MILLS | Notification Date: 06/07/2013
Notification Time: 09:48 [ET]
Event Date: 06/07/2013
Event Time: [CDT]
Last Update Date: 06/09/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
BLAIR SPITZBERG (R4DO)
FSME EVENTS RESOURCE (EMAI)
ILTAB (EMAI)
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text AGREEMENT STATE REPORT - MISSING TROXLER GAUGE
The following was received from the State of Oklahoma via email:
"Building and Earth Sciences has reported that a Troxler Model 3430 (S/N 36097) was stolen from a location in Ponca City, OK. The case was in the back of a truck and some time during the night it was opened and the gauge removed. The RSO is on the way to the site now, [the Oklahoma Department of Environmental Quality] will provide more information as it becomes available."
Troxler Model 3420 Density gauges typically contain Cs-137 8 mCi and Am-241/Be 40 mCi sources.
* * * UPDATE FROM MIKE BRODERICK TO JOHN SHOEMAKER AT 1100 EDT ON 6/9/2013 * * *
The State of Oklahoma reports that the gauge has been recovered and is now in the possession of the licensee. A private citizen found the missing gauge on the side of a road near the location where the gauge was stolen in Ponca City, OK. The source rod was still locked and it is believed that no exposures have occurred. The licensee will return the gauge to a secure storage location.
Notified R4DO (Spitzberg) and FSME Events Resource and ILTAB via email.
THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL
Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf |
| Power Reactor | Event Number: 49115 | Facility: HARRIS
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP
NRC Notified By: KEVIN ABELL
HQ OPS Officer: CHARLES TEAL | Notification Date: 06/14/2013
Notification Time: 03:25 [ET]
Event Date: 06/13/2013
Event Time: 21:27 [EDT]
Last Update Date: 06/14/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
| Person (Organization):
FRANK EHRHARDT (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 LOSS OF ONE OF TWO NATIONAL WEATHER SERVICE TONE ALERT RADIO TRANSMITTERS
"At 9:27 p.m. EDT June 13, 2013, the National Weather Service reported a loss of the National Weather Service (NOAA) Tone Alert Radio Transmitter, WXL-58 located in Chapel Hill, NC serving the northeast Piedmont on 162.550 MHz, due to damage or power failure sustained during the passage of severe thunderstorms. The National Weather Service expects the transmitter to be out of service through at least Friday morning June 14, 2013.
"The purpose of the National Weather Service (NOAA) Tone Alert Radio transmitters is a redundant means to the 83 Harris Nuclear Plant Emergency Sirens to warn the public within the 5 mile radius of the plant of an actual event. The 83 Harris Nuclear Plant Emergency Sirens were verified at 12:05 a.m. EDT June 14, 2013 to be in service and fully functional to alert the public within the 5 mile radius of the plant of an actual event should an event occur.
"There is no impact to public health and safety due to this condition.
"The NRC Resident Inspector has been notified." |
| Power Reactor | Event Number: 49116 | Facility: BEAVER VALLEY
Region: 1 State: PA
Unit: [ ] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: DAN SCHWER
HQ OPS Officer: CHARLES TEAL | Notification Date: 06/14/2013
Notification Time: 09:20 [ET]
Event Date: 06/14/2013
Event Time: 08:35 [EDT]
Last Update Date: 06/14/2013 | Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
GLENN DENTEL (R1DO)
BILL DEAN (R1RA)
JENNIFER UHLE (NRR)
HAROLD CHERNOFF (NRR)
JEFFERY GRANT (IRD)
|
| 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 UNUSUAL EVENT DECLARED DUE TO HIGH CO2 LEVELS IN THE TURBINE BUILDING
"Beaver Valley Unit 2 declared an Unusual Event (EAL HU.5, Toxic Gas Release) at 0835 EDT hours due to a CO2 (Toxic Gas) discharge in the turbine building. No report of fire and no injuries resulted from discharge. At 0851 EDT, the turbine building was clear of any detectible CO2. There was no operational impact from the CO2 discharge. The cause of the CO2 discharge is under investigation. The required states and counties were notified. The Resident NRC inspector was notified."
The inadvertent CO2 discharge was from the turbine fire protection system which now isolated while troubleshooting is in progress.
Notified DHS SWO, FEMA, DHS NICC, and Nuclear SSA via email.
* * * UPDATE FROM JAMES SCHWER TO CHARLES TEAL ON 6/14/13 AT 1006 EDT * * *
"Beaver Valley Unit 2 has terminated the Unusual Event at 0955 EDT * * *
Notified R1DO (Dentel), NRR EO (Chernoff), IRD (Grant), DHS SWO, FEMA, DHS NICC, and Nuclear SSA via email. |
| Research Reactor | Event Number: 49117 | Facility: KANSAS STATE UNIVERSITY
RX Type: 250 KW TRIGA MARK II
Comments:
Region: 4
City: MANHATTAN State: KS
County: RILEY
License #: R-88
Agreement: Y
Docket: 05000188
NRC Notified By: JEFFREY GEUTHER
HQ OPS Officer: CHARLES TEAL | Notification Date: 06/14/2013
Notification Time: 11:20 [ET]
Event Date: 06/13/2013
Event Time: 15:39 [CDT]
Last Update Date: 06/14/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
NON-POWER REACTOR EVENT
| Person (Organization):
HEATHER GEPFORD (R4DO)
ALEXANDER ADAMS (NRR)
SPIROS TRAIFOROS (NRR)
| Event Text FAILURE OF IN-CORE THERMOCOUPLE
"Description of Event:
"During operations at full power (500 kWth), the Senior Reactor Operator (SRO) on duty noticed that the fuel temperature thermocouple reader indicated a temperature of 202 [degrees] C, approximately 60 - 70 [degrees] C below the expected value. The SRO recognized that the problem was likely caused by a fuel thermocouple wire grounding to its conduit. A trainee was instructed to move the wires to avoid grounding. Following this action, the thermocouple reader indicated the proper value.
"Upon review of the log book, the SRO noticed that the faulty fuel temperature reading had been logged for several days without corrective action. The facility Technical Specifications (TS) require at least one fuel temperature indication to be operable during operation, and define a system as 'operable' when it is capable of performing its intended function in a normal manner.
"Therefore the fuel temperature indication was not operable as defined in the TS. Since the reactor was not immediately secured nor was the indication immediately fixed, the event constitutes a Reportable Occurrence per facility TS 6.9.2.
"Background:
"For the four days of reactor operations during which the problem with the thermocouple existed, the reactor was operated for short amounts of time (approximately 10 -15 minutes) at various power levels in order to characterize a new beam port configuration and test an experimental apparatus. The total time above 100 kWth was 2 hours and 51 minutes. The reactor was typically staffed by a trainee at the panel, supervised by a licensed reactor operator (RO).
"The indicated temperature is the average reading of three thermocouples. One thermocouple is at the fuel midplane, one is 2 [inches] above the midplane, and one is 2 [inches] below the midplane. The fuel temperature indication, when partially grounded, is approximately correct below the point of adding heat (approximately 10 kWth). It differs from the expected value by approximately 15 [degrees] C at 100 kWth, and by approximately 65 [degrees] C at 500 kWth. The fuel temperature readout at the control panel is used to provide an automatic scram at 400 [degrees] C. This setpoint is set well below the Safety Limit of 750 [degrees] C fuel temperature during steady state reactor operations. The fuel temperature scram is NOT required by TS. Normal operations at the reactor do not approach this scram setpoint or the Safety Limit.
"The logbooks are reviewed daily as part of the pre-operation reactor checkout procedure. The staff is trained to review logs back to the most recent time they were on duty, to check for changes to the reactor, problems with instruments, etc. The staff is not trained to audit the previous days' logs for anomalous readings.
"Timeline:
"The following timeline of operations is taken from the reactor logbook. Only operations at or above 100 kWth are listed, because the difference between measured and expected temperature is small at lower power levels. All times are local (Central Daylight Time).
Date Time Power T (Measured, [degrees] C) T (Expected, [degrees] C)
6/7/2013 0946-1001 500kW 200 265
6/7/2013 1037 - 1050 500kW 202 265
6/7/2013 1441 - 1446 500kW 202 265
6/10/2013 0937 - 0950 100kW 83 100
6/10/2013 1005 - 1015 100kW 87 100
6/10/2013 1029-1041 100kW 84 100
6/12/2013 0906 - 0919 100kW 84 100
6/12/2013 0934 - 0959 530kW 217 270
6/12/2013 1611 - 1633 100kW 74* 100
6/13/2013 1103 - 1143 500kW 201 265
6/13/2013 1352 - 1406 530kW 209 270
*Temperature was logged while it was still rising toward an equilibrium value.
"6/13/2013 - 1559 - Problem observed and corrected by repositioning thermocouple wires.
"6/14/2013 - 1020 - Reportable occurrence reported to NRC Headquarters Operations Center.
"Causes:
"The facility has identified the following as contributing causes to the event.
"1. Licensed operators were not sufficiently attentive when supervising trainees at the control panel. The licensed operators were focused on reactor power indications and did not pay sufficient attention to other TS related indications.
"2. The log book review required prior to daily operations was not conducted with sufficient rigor to detect the improper thermocouple readings logged the previous day. The review was instead focused on noting changes to the reactor facility and problems with instrumentation since the operators' previous duty at the panel.
"3. Only one functioning instrumented fuel element was used to provide the required fuel temperature indication channel. Therefore no redundant readout was available to check against the indicated fuel temperature.
"4. The sharp edge on the instrumented fuel element conduit can cut through the insulation on the thermocouple wires, causing grounding.
"Corrective Actions:
"The facility will perform the following corrective actions. All changes to the reactor systems, such as thermocouple wire insulation, are subject to review per the requirements of 10CFR50.59.
"Time: Prior to operation;
"Action: Attempt to improve insulation on thermocouple wires, using electrical tape, shrink tubing, or spray-on insulation.
"Time: Prior to operation;
"Action: Attempt to repair thermocouple wires for a currently installed but non-functional instrumented fuel element to provide an independent fuel temperature indication channel.
"Time: Prior to operation;
"Action: Install a new instrumented fuel element. This will bring the total number of independent channels of fuel temperature indication to 2 - 3.
"Time: Prior to operation and as part of requalification training program;
"Action: Train reactor staff on the importance of vigilance when supervising trainees and the importance of attentiveness to all channels of information at the control console, as opposed to focusing on a few specific indicators, such as reactor power channels.
"Time: Prior to operation and as part of requalification training program;
"Action: Train reactor staff to check for anomalous values in the prior days' log entries during the daily reactor checkout.
"Time: Upon approval by Reactor Safeguards Committee, but not necessarily prior to operation;
"Action: Append Procedure 15 - Reactor Startup with a list of observed instrument values for different reactor power levels to be used as a reference by trainees and licensed staff.
"A copy of this report will be provided to the Kansas State University Reactor Safeguards Committee for review." |
| Power Reactor | Event Number: 49119 | Facility: FORT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: (1) CE
NRC Notified By: MICHAEL PEAK
HQ OPS Officer: PETE SNYDER | Notification Date: 06/14/2013
Notification Time: 18:28 [ET]
Event Date: 06/14/2013
Event Time: 11:00 [CDT]
Last Update Date: 06/14/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
HEATHER GEPFORD (R4DO)
|
| 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 CONDITIONS DISCOVERED DUE TO EXCLUSION OF SMALL BORE PIPING FROM ANALYSIS
"While revising calculations for the station analyses for potential high-energy line breaks outside of containment, the station determined that the conditions required to validate the exclusion from analyzing for a break in some small-bore (1- to 4-inch diameter) piping could not be validated. The piping is contained within the station's auxiliary building. In the unlikely event of a break of one of these lines during power operations, the plant may not have been able to respond as expected. The plant is currently in cold shutdown, with the fuel removed from the core."
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 49120 | Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: BRUCE HUGO
HQ OPS Officer: PETE SNYDER | Notification Date: 06/15/2013
Notification Time: 18:38 [ET]
Event Date: 06/15/2013
Event Time: 12:22 [PDT]
Last Update Date: 06/15/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
HEATHER GEPFORD (R4DO)
|
| 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 DIVISION 1 AND 2 EMERGENCY DIESEL GENERATORS POWER BUSES AFTER MOMENTARY OFFSITE POWER LOSS
"Columbia Generating Station is shutdown for a refueling outage and is currently in Mode 4. At 1222 PDT June 15, 2013, the 115 kV offsite power to the backup transformer relayed off and then came back on. Both Division 1 and Division 2 4.16 kV critical switchgear buses were powered from the backup transformer at the time of the loss of backup power.
"Upon detection of under voltage conditions, Emergency Diesel Generators 1 and 2 started and powered the Division 1 and Division 2 4.16 kV critical switchgear buses after approximately 5 seconds. The temporary loss of power to the Division 1 and Division 2 4.16 kV critical switchgear buses also resulted in the closure of containment isolation valves in the Reactor Water Cleanup System, Equipment Drain System and the Floor Drain System. Shutdown cooling had previously been secured in preparation of performing the reactor pressure vessel hydro test. Investigation into the cause of the temporary loss of the 115 kV offsite power is on-going.
"The Division 1 and Division 2 4.16 kV critical switchgear buses are currently being powered from the 230 kV offsite power through the startup transformer.
"There were no radiological releases as a result of this event."
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 49121 | Facility: PERRY
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: ROBERT KIDDER
HQ OPS Officer: BILL HUFFMAN | Notification Date: 06/16/2013
Notification Time: 02:42 [ET]
Event Date: 06/16/2013
Event Time: [EDT]
Last Update Date: 06/16/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
| Person (Organization):
ERIC DUNCAN (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 8 | Power Operation | 8 | Power Operation | Event Text TECHNICAL SPECIFICATION SHUTDOWN DUE TO SMALL REACTOR COOLANT LEAK ON A RECIRCULATION FLOW CONTROL VALVE VENT LINE
"This event is being reported in accordance with 10 CFR 50.72(b)(2)(i) and 50.72(b)(3)(ii)(A).
"On June 16, 2013 at 0200 EDT, the Perry Nuclear Power Plant commenced a controlled plant shutdown. The shutdown was due to a small leak through the base of a vent line on the 'B' Reactor Recirculation Flow Control Valve.
"On June 15, 2013 at 2250 EDT, the leak was identified and was subsequently determined to require a plant shutdown in accordance with Technical Specification 3.4.5, Action (C) which requires the plant to be in Mode 3 within 12 hours.
"The NRC Resident Inspector has been notified." The licensee will also be notifying state and local authorities.
The licensee had come down in power to make a drywell entry and investigate drywell leakage indications. Steam was observed to be coming from a vent line that comes off the top of the recirc flow control valve. The licensee was unable to characterize the leak rate other than a small leak. The licensee stated that the steam appeared be coming from a weld location where the vent line comes out of the flow control valve which would classify it as pressure boundary leakage. |
| Power Reactor | Event Number: 49122 | Facility: RIVER BEND
Region: 4 State: LA
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: DANIEL PIPKIN
HQ OPS Officer: PETE SNYDER | Notification Date: 06/16/2013
Notification Time: 13:32 [ET]
Event Date: 06/16/2013
Event Time: 04:56 [CDT]
Last Update Date: 06/16/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
HEATHER GEPFORD (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 BROKEN DAMPER BLADE LINKAGE FOUND ON TECHNICAL SUPPORT CENTER VENTILATION LINE
"At 0456 CDT, while performing scheduled maintenance on HVL-AOD408, HVL-AHU1 Suction AOD [Air Operated Damper], the linkage inside the damper connecting the two damper blades was found to be broken. HVL-AHU1, Service Bldg. TSC A/C Unit, provides ventilation to the Technical Support Center. With the linkage on HVL-AOD408 broken, there is the potential that a filtered air supply cannot be provided to the TSC. As a result the TSC ventilation was placed in Emergency Mode and positive pressure could not be maintained. Investigation revealed, in addition to [the broken linkage on] HVL-AOD 408, a broken seal on bottom of door SB-123-19.
"A contingency plan is in place to relocate personnel if needed per EIP-2-018, 'Technical Support Center' and EIP-2-016, 'Operations Support Center.'"
The licensee notified the NRC Resident Inspector. | |