| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
10/26/2012 - 10/29/2012 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 48269 | Facility: CLINTON
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: DANIEL HUNT
HQ OPS Officer: DONG HWA PARK | Notification Date: 09/03/2012
Notification Time: 05:17 [ET]
Event Date: 09/02/2012
Event Time: 22:04 [CDT]
Last Update Date: 10/26/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
| Person (Organization):
JAMNES CAMERON (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 97 | Power Operation | 97 | Power Operation | Event Text TRANSFER OF EMERGENCY RESERVE AUXILIARY TRANSFORMER ISOLATING FUEL POOL COOLING AND CLEANUP SYSTEM, AND FUEL BUILDING VENTILATION SYSTEM
"At 22:04 CDT on 9/02/2012, the Emergency Reserve Auxiliary Transformer (ERAT) transferred unexpectedly to the Reserve Auxiliary Transformer (RAT). During this transfer, the Fuel Pool Cooling and Cleanup (FC) system pump 'A' tripped and the Fuel Building Ventilation (VF) system isolated. Upper containment pool level dropped below the minimum required level per Technical Specifications (TS) 3.6.2.4 and Secondary Containment differential pressure increased above 0.25 inches vacuum per TS 3.6.4.1. Upper Containment Pool level was restored above the minimum level at 01:27 CDT on 9/3/2012 within the 4 hour completion time. The Upper Containment Pool is a part of the suppression pool makeup system used to ensure the Primary Containment function. Secondary Containment differential pressure was restored at 22:19 on 9/2/2012 when the Standby Gas Treatment System was started. Maintaining secondary containment differential pressure helps to control the release of radioactive material.
"This event is being reported as a condition that could have prevented the fulfillment of a safety function per 10 CFR 50.72(b)(3)(v)(B) and 10 CFR 50.72(b)(3)(v)(C). The station is currently in a 72-hour action to restore the ERAT to an operable status per TS LCO 3.8.1 Required Action A.2. Plant conditions are stable and actions are underway to repair the ERAT.
"The NRC Resident [Inspector] has been notified."
* * * RETRACTION ON 10/26/12 AT 1322 EDT FROM KEN LEFFEL TO DONG PARK * * *
"Upper Containment Pool level dropped below the normal pool level of 827 feet-3 inches when the Fuel Pool Cooling and Cleanup system pump 'A' tripped, and was initially reported as dropping below the minimum level (825 feet-6 inches) required by Technical Specification (TS) 3.6.2.4. However, subsequent reports from the field confirmed that the lowest level reached was 827 feet 0 inches, which is greater than the minimum required TS level. Therefore, no loss of safety function occurred for the Upper Containment Pool level as a result of this event, and the event is not reportable under 50.72 (b)(3)(v)(B).
"The NRC Resident [Inspector] has been notified." Notified R3DO (Pelke). |
| !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 48353 | Facility: FITZPATRICK
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: JORGE O'FARRILL
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 09/27/2012
Notification Time: 22:17 [ET]
Event Date: 09/27/2012
Event Time: 12:12 [EDT]
Last Update Date: 10/26/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
| Person (Organization):
RONALD BELLAMY (R1DO)
PART 21 GROUP ()
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 92 | Power Operation | 100 | Power Operation | Event Text PART-21 REPORT - FAULTY MASTER TRIP UNITS, SLAVE UNITS, AND RESISTANCE TEMPERATURE DETECTORS
"On September 27, 2012, the Site Vice President was notified that a 10CFR21 evaluation of thirteen (13) reworked Master Trip Units, Resistance Temperature Detector Units, and Slave Units supplied by Rosemount Nuclear Instruments, Inc. (Rosemount) determined that a non-compliant condition involving a basic component existed.
"Rosemount informed James A. FitzPatrick Nuclear Power Plant (JAF) that 13 reworked Master Trip Units, Resistance Temperature Detector (RTD) Units and Slave Units were received at JAF which did not comply with their rebuild repair specification. Specifically, epoxy was not applied under certain resistors as required. In accordance with JA FitzPatrick plant procedures, this condition was determined as a 10CFRPart 21 condition involving a defect in a basic component.
"As noted by an engineering review, some of the applications for the trip units require them to energize to perform the associated safety functions. Therefore, a failure occurrence by an installed non-conforming unit could potentially have an adverse affect on the associated systems' safety/accident mitigation functions.
"JAF verified that none of the 13 deficient units were installed in any plant systems. Therefore, this condition had no actual safety consequences as the deficiency was identified by Rosemount prior to installation. The 13 units that were received at JAF without the epoxy have been returned to Rosemount for the addition of the epoxy and have subsequently been reworked and returned to JAF.
"This notification is made pursuant to 10CFR21.21(d)(3)(i)."
* * * RETRACTION ON 10/26/12 AT 1519 EDT FROM MARK HAWES TO DONG PARK * * *
"Subsequent to the original notification dated 9/27/2012, a study was performed by Rosemount (DS-RNII-2012-049). The study analyzed the reported condition of the Master Trip Units for a Static Coefficient Load Analysis and a calculation of the rigidity of the 2-Watt wire-wound resistor when installed without being secured by epoxy. The conclusion was that there is sufficient design margin to ensure that the resistor will remain rigid during qualified seismic conditions.
"Based on this assessment, there is not a significant safety concern related to the absence of epoxy and the previous 10 CFR 21.21(d)(3)(i) notification may be retracted."
The NRC Resident Inspector has been notified. Notified R1DO (Caruso) and Part 21 group. |
| Power Reactor | Event Number: 48368 | Facility: CALVERT CLIFFS
Region: 1 State: MD
Unit: [1] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: JOSEPH GIOFFRE
HQ OPS Officer: DONG HWA PARK | Notification Date: 10/03/2012
Notification Time: 07:25 [ET]
Event Date: 10/03/2012
Event Time: 08:00 [EDT]
Last Update Date: 10/26/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
WAYNE SCHMIDT (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 | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text TECHNICAL SUPPORT CENTER OUTAGE DUE TO PLANNED MAINTENANCE
"This report is being made in accordance with 10CFR50.72(b)(3)(xiii) due to the planned loss of an Emergency Response Facility (ERF). Calvert Cliffs will be implementing a scheduled modification to renovate the site's common Technical Support Center (TSC) which will temporarily remove it from service. The planned maintenance window is expected to be three weeks beginning on 10/3/12 and concluding on 10/26/12. Should an emergency be declared requiring TSC activation during this period, the procedurally identified alternate TSC will be staffed and activated (CCNPP Simulator). All TSC responders and other key ERO personnel have been briefed on this activity and the applicable contingency actions that will be required to be taken in their specific emergency response procedures. This condition has no adverse impact to the health and safety of the public. An update will be provided once the TSC has been restored to normal operation."
The licensee has notified the NRC Resident Inspector.
* * * UPDATE FROM TOM JONES TO DONG PARK AT 1302 EDT ON 10/26/12 * * *
The TSC has been restored to normal operation. The licensee will notify the NRC Resident Inspector. Notified R1DO (Caruso). |
| Agreement State | Event Number: 48420 | Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: METCO
Region: 4
City: HOUSTON State: TX
County:
License #: 03018
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: VINCE KLCO | Notification Date: 10/18/2012
Notification Time: 16:56 [ET]
Event Date: 10/17/2012
Event Time: [CDT]
Last Update Date: 10/18/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
GREG PICK (R4DO)
FSME EVENTS RESOURCE (EMAI)
| Event Text AGREEMENT STATE REPORT- UNABLE TO RETRACT RADIOGRAPHY CAMERA SOURCE
The following information was received by email:
"On October 18, 2012, the Agency [Texas Radiation Branch] was notified by the licensee that on October 17, 2012, a radiographer was unable to retract a [source] into the QSA 880F exposure device. The guide tube for the device was damaged during radiography operation in the fixed facility when a part fell on it, crimping the guide tube to a point where the source could not pass through it. The licensee stated that they were able to repair the guide tube enough to retract the source and lock it in the exposure device. The licensee stated that no over exposure occurred from the event and no member of the general public received any exposure from the event. Additional information will be provided as it is received in accordance with SA 300.
Texas Incident: I-8998 |
| Agreement State | Event Number: 48422 | Rep Org: TENNESSEE DIV OF RAD HEALTH
Licensee: DIVERSIFIED SCIENTIFIC SERVICES, INC.
Region: 1
City: KINGSTON State: TN
County:
License #: R-73014-H14
Agreement: Y
Docket:
NRC Notified By: DEBRA SHULTS
HQ OPS Officer: VINCE KLCO | Notification Date: 10/19/2012
Notification Time: 15:51 [ET]
Event Date: 10/19/2012
Event Time: [EDT]
Last Update Date: 10/19/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
BLAKE WELLING (R1DO)
FSME EVENT RESOURCE (EMAI)
| Event Text AGREEMENT STATE REPORT- CONTAMINATION EVENT
The following information was received by facsimile:
"DRH [Tennessee Division of Radiological Health] was notified on 10/19/12 by the licensee that preliminary analytical results of a 30-gallon waste container of tritium contaminated waste oil and absorbents indicate approximately 8,600 curies of tritium. The container was manifested by the generator (SRS) [Savannah River Site] as containing 14.9 curies. Post sampling of this container, DSSI [Diversified Scientific Services, Inc.] had a controlled but elevated level of tritium contamination in the process room; this room is under negative ventilation. The room has been decontaminated back to normal processing levels. Contents of the container have been overpacked and placed in a safe state, [and] not a source of tritium contamination to the air or surface."
Tennessee Event: TN-12-267 |
| Agreement State | Event Number: 48423 | Rep Org: IOWA DEPARTMENT OF PUBLIC HEALTH
Licensee: POLARIS
Region: 3
City: SPIRIT LAKE State: IA
County:
License #: 3093-1-30-SEM
Agreement: Y
Docket:
NRC Notified By: MELANIE RASMUSSON
HQ OPS Officer: VINCE KLCO | Notification Date: 10/19/2012
Notification Time: 16:25 [ET]
Event Date: 08/03/2012
Event Time: [CDT]
Last Update Date: 10/19/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
STEVE ORTH (R3DO)
FSME EVENTS RESOURCE (EMAI)
GARY LANGLIE-EMAIL (ILTA)
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text AGREEMENT STATE REPORT - LOST SOURCE
The licensee misplaced a static eliminator device containing 10 mCi of Po-210. The device model number is P-2021-8301; Serial number is A2HS590. The device was used to neutralize static charge on plastic parts prior to entering the paint process. The licensee considers the device as lost.
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 |
| Non-Agreement State | Event Number: 48424 | Rep Org: ACUREN INSPECTION
Licensee: ACUREN INSPECTION
Region: 4
City: PRUDHOE BAY State: AK
County:
License #: 42-32443-01
Agreement: N
Docket:
NRC Notified By: ROBERT JEFFERSON
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 10/19/2012
Notification Time: 17:08 [ET]
Event Date: 10/04/2012
Event Time: 23:30 [YDT]
Last Update Date: 10/19/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
| Person (Organization):
GREG PICK (R4DO)
FSME RESOURCES (FSME)
| Event Text RADIOGRAPHY SOURCE STUCK
"A drive cable designed for 25' controls was installed in a 35' control assembly. This resulted in 15' of usable drive cable to travel through the guide tube. The radiographers were using a guide tube and extension with a total length of 17' and were unaware that there was not enough drive cable to reach the source stop. The cable was run out past the stop, and could not be retracted.
"The exposure being taken at the time of the incident was a 6:00 shot on a 12" oil line. The line was 15' off the ground near an elevated platform. There was a 42" pipe running between the platform and the pipe being inspected. The exposure device was placed on the platform and an extension was added to the guide tube to route the source around the 42" pipe. The total length of the guide tube and extension was 16'11". The control cables were rerouted to take advantage of nearby shielding. The conduits were disconnected from the Pistol Grip Assembly exposing the drive cable. The source was then retracted into the fully shielded position by pulling the drive cable by hand.
"The entire inventory of control assemblies were inspected to ensure the proper drive cables are installed, as will new assemblies when they are initially received. Additionally, personnel qualified to repair control assemblies will be retrained with emphasis placed on ensuring proper length of drive cable is in place. Training will be documented and filed in personnel records.
"Qualifications of personnel involved in incident:
1. Radiographer, Texas Industrial Radiographer Certification holder, Dose Received, 3mR (dosimeter)
2. Radiographer, IRRSP card holder, Dose Received, 5mR (dosimeter)
3. Radiographer, Illinois Industrial Radiography Certification holder, Dose Received, 7mR (dosimeter)
4. Assistant Radiographer, Dose Received, 2mR (dosimeter)
Source retrieval personnel: Site Radiation Safety Officer, IRRSP card holder, Source Retrieval trained by LAMCO & Associate February 25, 2011, Dose Received, 2mR (Dosimeter)
"Equipment Involved:
7' flexible Guide Tube, serial # GT 1211 22
10' flexible Guide Tube Extension, serial # EXT 12 11
Crank Assembly serial # 11652
Exposure Device Model #: Sentinel Delta 880
Exposure Device serial #: D3534
Isotope: Iridium 192
Source serial #: 84462B |
| Agreement State | Event Number: 48425 | Rep Org: IOWA DEPARTMENT OF PUBLIC HEALTH
Licensee: UNIVERSITY OF IOWA HOSPITAL AND CLINIC
Region: 3
City: IOWA CITY State: IA
County:
License #: 0037-1-52-AAB
Agreement: Y
Docket:
NRC Notified By: MELANIE RASMUSSON
HQ OPS Officer: VINCE KLCO | Notification Date: 10/19/2012
Notification Time: 17:34 [ET]
Event Date: 10/18/2012
Event Time: [CDT]
Last Update Date: 10/19/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
STEVE ORTH (R3DO)
FSME EVENTS RESOURCE (EMAI)
| Event Text AGREEMENT STATE REPORT - MEDICAL DOSAGE NOT DELIVERED AS PLANNED
A patient was being treated for a liver tumor and the dosage was delivered to the wrong lobe. The physician prescribed 17 mCi of Y-90 to the left lobe of the liver. The prescribing physician was not present during the dose administration procedure. The intervention radiologist examined a fluoroscope of the patient's liver and noted a larger tumor on the right lobe. The prescribed dosage was then delivered to the right lobe of the liver, not in accordance with the prescribed dosage plan. Patient examination detected no observable impact, and the physician is developing another dosage plan for the patient. The Iowa Department of Public Health will perform an onsite investigation.
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. |
| Power Reactor | Event Number: 48442 | Facility: CALLAWAY
Region: 4 State: MO
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: ROB STOUGH
HQ OPS Officer: BILL HUFFMAN | Notification Date: 10/25/2012
Notification Time: 10:22 [ET]
Event Date: 10/25/2012
Event Time: 09:30 [CDT]
Last Update Date: 10/26/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
BOB HAGAR (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 PARTIAL LOSS OF EMERGENCY ASSESSMENT DURING PLANNED MODIFICATIONS
"On October 25, 2012, Callaway Plant will begin implementation of a modification to the plant computer system. The Emergency Response Data System (ERDS) and plant computer stations in the Technical Support Center (TSC) and Emergency Operations Facility (EOF) will be unavailable during the modification. Plant computer stations will remain available in the Control Room. The period of unavailability is anticipated to be approximately 12 hours on October 25, 2012, with an additional 8 hours for system testing on October 26, 2012.
"During the modification process, the TSC and EOF will remain functional and available for use. Plant procedures provide guidance for manual data collection and sending ERDS data to the NRC.
"This notification is being made in accordance with 10 CFR 50.72(b)(3)(xiii).
"The NRC Resident Inspector has been notified."
* * * UPDATE FROM SHANNON GAYDOS TO PETE SNYDER AT 2123 ON 10/25/12 * * *
"Based on the current work progress on the plant computer system, the Emergency Response Data System (ERDS) and the plant computer stations in the Technical Support Center (TSC) and Emergency Operations Facility (EOF) will not be available until early evening on October 26, 2012."
The NRC Resident Inspector will be notified. Notified R4DO (Hagar).
* * * UPDATE FROM DAVID LANTZ TO DONG PARK AT 2033 EDT ON 10/26/12 * * *
"Modification has been completed on the plant computer system. The Emergency Response Data System (ERDS) and the plant computer stations in the Technical Support Center (TSC) and Emergency Operations Facility (EOF) have been restored to normal operation."
The NRC Resident Inspector will be notified. Notified R4DO (Hagar). |
| Power Reactor | Event Number: 48448 | Facility: SOUTH TEXAS
Region: 4 State: TX
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ROBERT BRINKLEY
HQ OPS Officer: DONG HWA PARK | Notification Date: 10/27/2012
Notification Time: 17:43 [ET]
Event Date: 10/27/2012
Event Time: 14:15 [CDT]
Last Update Date: 10/28/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
BOB HAGAR (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text LOSS OF OFFSITE COMMUNICATIONS
"On 10/27/2012 at 1415 CDT, the control room was notified of a loss of telephone communications. Reason is unknown at this time.
"Offsite communications lost includes the state and county ring down lines, the NRC ring down line. The ability to transfer information from the Emergency Response Data System (ERDS) to offsite agencies is believed not to be available. Satellite phones remain available.
"At approximately 1500 CDT, the NRC Operations Center was notified via satellite communications of alternate phone numbers to contact the Unit 1 Control Room and that Unit 2 Control Room satellite phone is not available to receive calls. This is a follow up to make the notification of this event to the NRC pursuant 10 CFR 50.72(b)(3)(xiii).
"The NRC Senior Resident Inspector was notified of the issue." State and local agencies were notified via alternate means.
* * * UPDATE FROM CHRIS VANFLEET TO HOWIE CROUCH AT 0003 EDT ON 10/28/12 * * *
Emergency Notification System has been returned to service. The cause of the loss of communications was a cut fiber optic line.
Notified R4DO (Hagar). |
| Power Reactor | Event Number: 48449 | Facility: PERRY
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: JIM PRY
HQ OPS Officer: DONG HWA PARK | Notification Date: 10/28/2012
Notification Time: 16:27 [ET]
Event Date: 10/28/2012
Event Time: 10:08 [EDT]
Last Update Date: 10/28/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
PATTY PELKE (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 EQUIPMENT FAILURE AFFECTING SPDS AND ERDS
"At approximately 1008 EDT on October 28th, 2012, a failure between the Plant Computer and the MMI (Man Machine Interface) occurred. The cause is due to a failure of the data diode. The Plant Computer is still working however the MMI is not, therefore Safety Parameter Display System (SPDS) outside of the Control Room and the Emergency Response Data System (ERDS) is unavailable.
"In the event of an emergency, plant parameter data will be communicated to the facilities through the status board ring down circuit with back-up by the Private Branch Exchange (PBX), Off Premise Exchange (OPX), and various redundant intra-facility circuits throughout the emergency facilities. The dose assessment function is maintained during this out of service time period by manual input of data into the Meteorological Information and Dose Assessment System (MIDAS). The ability to open and maintain an 'open line' using the Emergency
Notification System is not affected and will be the primary means for transferring plant data to the NRC as a contingency until the ERDS can be returned to service.
"At 1548 EDT on October 28th, 2012, a re-start of the data diode was successful in restoring the connection between the Plant Computer and the MMI. SPDS and the ERDS are functioning as designed.
"This event is being reported in accordance with 10 CFR 50.72(b)(3)(xiii). The NRC Resident Inspector has been notified."
The licensee has notified the State and local agencies. | |