| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
02/29/2012 - 03/01/2012 ** EVENT NUMBERS ** |
 | Independent Spent Fuel Storage Installation | Event Number: 47580 | Rep Org: DIABLO CANYON
Licensee: PACIFIC GAS & ELECTRIC CO.
Region: 4
City: AVILA BEACH State: CA
County: SAN LUIS OBISPO
License #: SNM-2511
Agreement: Y
Docket: 72-26
NRC Notified By: MICHAEL QUITTER
HQ OPS Officer: BILL HUFFMAN | Notification Date: 01/09/2012
Notification Time: 23:44 [ET]
Event Date: 01/09/2012
Event Time: 14:05 [PST]
Last Update Date: 02/29/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
INFORMATION ONLY
| Person (Organization):
RYAN LANTZ (R4DO)
WILLIAM RULAND (NRR)
CHRISTEPHER MCKENNEY (FSME)
| Event Text NUT ON HOLD-DOWN STUD WAS FOUND LOOSE
"On January 9, 2012, at 1405 [PST], plant personnel notified the Diablo Canyon shift manager that a nut on a hold-down stud on an Independent Spent Fuel Storage Installation(ISFSI) HISTORM spent fuel storage cask was loose to the touch. Plant personnel hand tightened the nut and verified that none of the other 16 casks in the facility had nuts that were loose to the touch.
"The Diablo Canyon ISFSI design requires that each spent fuel storage cask be installed with the cask compressed against the embedment plate using 16, two-inch diameter, anchor studs. Each stud is pre-loaded to approximately 157,000 lbf. This design ensures the cask will remain stable during a seismic event. A manufacturer's analysis of the stability of the cask with all of the 16 hold down stud nuts installed with no pre-load concluded that the cask would maintain its stability during a seismic event.
"PG&E has contracted the vendor to re-tension the stud and expect[s] completion [by] 1/13/2012. PG&E will assess the need to verify tension of the remaining studs based on the extent of condition evaluation.
"Cause of the loose nut has not yet been determined.
"The NRC Senior Resident Inspector has been informed."
* * * UPDATE AT 2007 EST ON 1/11/2012 FROM PHILIPPE SOENEN TO VINCE KLCO * * *
"On January 11, 2012, at 1325 PDT, plant personnel notified the Diablo Canyon shift manager that two additional nuts on hold-down studs for other ISFSI HISTORM spent fuel storage casks were discovered to be loose. The two additional nuts (one per cask) were discovered when the full effort of two hands was used on the nuts while performing an extent-of-condition evaluation. All 16 nuts on all 16 casks were tested for tightness using the full effort of two hands (i.e., no pre-load).
"NRC senior resident inspector has been informed."
Notified the R4DO (Powers), NRR EO (Cheok), and NMSS EO (Mohseni).
* * * UPDATE AT 1915 EST ON 2/29/2012 FROM DAN STERMER TO CHARLES TEAL * * *
"On February 29, 2012, at 1610 PST, plant personnel notified the Diablo Canyon shift manager that cause analysis of loose nuts on hold-down studs of ISFSI HISTORM spent fuel storage casks determined the cause is not a defect and this occurrence is not reportable. Accordingly, the reporting criteria for Event Notification 47580 is changed from '72.75(c)(1) Non-emergency condition' to 'Voluntary Report.' Pacific Gas and Electric (PG&E) plans to submit a voluntary, written report (licensee event report) to the NRC. PG&E personnel informed the NRC resident inspector."
Notified R4DO (Lantz), NRR EO (Lee), and NMSS EO (Rubenstone). |
| Agreement State | Event Number: 47698 | Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: UNIVERSITY OF TEXAS SOUTHWESTERN MEDICAL CENTER
Region: 4
City: DALLAS State: TX
County:
License #: L00384
Agreement: Y
Docket:
NRC Notified By: ROBERT FREE
HQ OPS Officer: VINCE KLCO | Notification Date: 02/24/2012
Notification Time: 16:54 [ET]
Event Date: 02/16/2012
Event Time: [CST]
Last Update Date: 02/24/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
RICK DEESE (R4DO)
KEVIN O'SULLIVAN (FSME)
| Event Text AGREEMENT STATE REPORT - MISADMINISTRATION OF A RADIOPHARMACEUTICAL
The following information was received from the State of Texas via email:
"On 2/22/12 the licensee notified the Agency [Texas Department of State Health Services] of a medical event that occurred on 2/16/12. The licensee reported that the wrong radiopharmaceutical had been administered to a patient. Tc-99m MAA was administered rather than the prescribed Tc-99m Pertechnitate. During the administration of the wrong drug, an estimated 1/3-1/2 of the dose infiltrated the skin causing an estimated 400 rad exposure subcutaneously. The referring physician and patient have been notified. No signs or symptoms have been observed in the patient as a result of the incident. The estimated exposure is being reevaluated by the licensee."
Texas Incident: I-8937
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: 47700 | Rep Org: NC DIV OF RADIATION PROTECTION
Licensee: CAROLINA CUSTOM FINISHING, LLC.
Region: 1
City: State: NC
County:
License #: 076-1820-0G
Agreement: Y
Docket:
NRC Notified By: WILLIAM JOHNSON
HQ OPS Officer: BILL HUFFMAN | Notification Date: 02/27/2012
Notification Time: 11:17 [ET]
Event Date: 02/27/2012
Event Time: 10:30 [EST]
Last Update Date: 02/27/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
MARC FERDAS (R1DO)
ANGELA MCINTOSH (FSME)
MATTHEW HAHN (ILTA)
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text AGREEMENT STATE REPORT - LOST PO-210 SOURCE
The following was received from the state of North Carolina Division of Radiation Control by facsimile:
"On February 16, 2012, the Section [North Carolina Division of Radiation Control] received a letter from the RSO for Carolina Custom Finishing LLC, License Number: 076-1820-0G, [stating] that on February 13, 2012, [the licensee] could not find a Po-210 source, 10 mCi, Model P-2021, S/N A2HL674. [This source is contained in] a static eliminator used for painting customer parts. [The RSO] performed an inspection and area survey of the facility on February 22, 2012 and could not locate the above source."
NC Incident Number: 12-25
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
This source is not amongst those sources or devices identified by the IAEA Code of Conduct for the Safety & Security of Radioactive Sources to be of concern from a radiological standpoint. Therefore is it being categorized as a less than Category 3 source |
| Agreement State | Event Number: 47701 | Rep Org: KENTUCKY DEPT OF RADIATION CONTROL
Licensee: EAST KENTUCKY POWER COOPERATIVE
Region: 1
City: WINCHESTER State: KY
County:
License #: 201-161-51
Agreement: Y
Docket:
NRC Notified By: CURT PENDERGRASS
HQ OPS Officer: CHARLES TEAL | Notification Date: 02/27/2012
Notification Time: 15:38 [ET]
Event Date: 02/24/2012
Event Time: 11:26 [CST]
Last Update Date: 02/27/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
MARC FERDAS (R1DO)
KEVIN O'SULLIVAN (FSME)
| Event Text AGREEMENT STATE REPORT - STUCK SHUTTER ON PROCESS GAUGE
The following was received from the State of Kentucky via facsimile:
" KY RHB [Kentucky Radiation Health Branch] was notified by telephone and email on 2/24/12 at 2:32 p.m. EST by the Radiation Safety Officer at East Kentucky Power Cooperative of a shutter on a Kay-Ray Model 7700D (S/N 17902) containing 10 mCi of Cs-137 being stuck in the closed position. The event occurred on 2/24/12 at 12:26 p.m. EST. The RSO is stationed in Winchester, KY and the incident occurred at the licensee's facility in Maysville, KY. The State has received an initial telephone notification and an initial written report from the licensee and will continue to keep NRC informed of the status of our investigation."
KY Event Report ID No: KY 120001 |
| Power Reactor | Event Number: 47708 | Facility: BYRON
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: CHRIS COTE
HQ OPS Officer: CHARLES TEAL | Notification Date: 02/28/2012
Notification Time: 19:03 [ET]
Event Date: 02/28/2012
Event Time: 17:31 [CST]
Last Update Date: 02/29/2012 | Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
ANN MARIE STONE (R3DO)
SAMSON LEE (NRR)
CYNTHIA PEDERSON (R3RA)
BRUCE BOGER (NRR)
SCOTT MORRIS (IRD)
KEVIN BISCOE (FEMA)
DAN GATES (DHS)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 99 | Power Operation | Event Text UNUSUAL EVENT DUE TO LOSS OF OFFSITE POWER
Byron Unit 1 declared an Unusual Event due to a loss of offsite power for greater than 15 minutes (EAL MU-1). The 1A and 1B emergency diesel generators auto-started and automatically restored power to ESF (Engineered Safety Feature) Busses 141 and 142. The 1A Auxiliary Feedwater pump auto-started due to an undervoltage signal to ESF bus 141. The 6.9 KV Busses (Non-ESF) and 4.16 KV Busses (Non-ESF) auto transferred to the Unit Auxiliary Transformers and Unit 1 remained online. The ESF reserve feed breakers are available and in the process of transferring ESF loads over to Unit 2 via the ESF cross-ties. This will allow shutdown of the 1A and 1B diesel-generators and allow alignment to standby status. Switchyard repairs are being initiated.
The licensee notified the State of Illinois, Ogle County, Oregon and Byron municipalities and the NRC Resident Inspector. The licensee plans on issuing a news release. Unit 2 remained online and was unaffected throughout the event.
Notified Nuclear SSA and NICC vie email.
* * * UPDATE FROM CHRISTOPHER COTE TO CHARLES TEAL ON 2/29/12 AT 2222 EST * * *
"Termination of Unusual Event. Repairs to switchyard components are complete. Offsite power has been restored to Unit One System Auxiliary Transformers. Unit One 4 KV ESF busses have been re-energized from Unit One System Auxiliary Transformers and are no longer cross tied to Unit Two System Auxiliary Transformers. This restores the normal electrical lineup to the ESF busses. The entry conditions for MU-1 are no longer met."
The licensee has notified the NRC Resident Inspector, the State of Illinois, Ogle County, Oregon and Byron municipalities.
Notified R3DO (Stone), NRR EO (Lee), IRD (Morris), and other FEDS (DHS SWO, DHS NICC, FEMA, and NuclearSSA via email). |
| Power Reactor | Event Number: 47709 | Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: DOUG PETERSON
HQ OPS Officer: STEVE SANDIN | Notification Date: 02/29/2012
Notification Time: 18:07 [ET]
Event Date: 02/29/2012
Event Time: 12:22 [CST]
Last Update Date: 02/29/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
| Person (Organization):
ANN MARIE STONE (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 SECONDARY CONTAINMENT ISOLATION DAMPERS FAIL TO CLOSE DURING QUARTERLY SURVEILLANCE
"On 2/29/2012 at 0905 [CST] during scheduled surveillance testing it was discovered that Secondary Containment isolation damper 1VAD017B3 would not fully isolate. 1VAD017B3 was declared inoperable per Technical Specification 3.6.4.2 Condition A and an 8 hour action statement to isolate the affected flowpath via a closed and deactivated damper was entered. While performing subsequent actions to isolate the companion isolation damper, 1VAD017A3, it was found on 2/29/2012 at 1222 [CST] that this damper also failed to fully isolate. This left both Secondary Containment isolation dampers in the same flowpath unable to isolate, and Technical Specification 3.6.4.2 Condition B was entered with a 4 hours action statement to isolate the affected flowpath. This condition is reported under 50.72(b)(3)(v)(C), any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of the structures or systems that are needed to control the release of radioactive material.
"Further actions to isolate the flowpath were successful and both 4 hour and 8 hour Technical Specification action statements were completed within the required time."
The licensee informed the NRC Resident Inspector. | |