| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
11/01/2013 - 11/04/2013 ** EVENT NUMBERS ** |
 | Power Reactor | Event Number: 49383 | Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: MIKE STROPE
HQ OPS Officer: DANIEL MILLS | Notification Date: 09/25/2013
Notification Time: 11:08 [ET]
Event Date: 09/25/2013
Event Time: 03:04 [CDT]
Last Update Date: 11/02/2013 | 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 | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text LOSS OF NORMAL TSC POWER DUE TO TRANSFORMER ISOLATION
"At 0304 (CDT), on Sept 25, 2013, the Duane Arnold Energy Center (DAEC) Technical Support Center (TSC) normal power supply was lost when the T4 '36KV-12.5KV DAEC SITE TRANSFORMER' was lost. Automatic power transfer occurred to maintain power to the TSC from the TSC Emergency Diesel Generator (EDG) which automatically started. Prior to the loss of normal power, the TSC Emergency Diesel Generator maintenance functional testing had been completed and was in standby readiness, awaiting post maintenance testing to be completed on the auto start circuit. The TSC Emergency Diesel Generator responded normally to the loss of power and energized TSC loads. The TSC remained functional throughout the incident.
"This notification is being made pursuant to 10 CFR 50.72(b)(3)(xiii) due to the loss of an emergency assessment capability. An update will be provided once the normal power supply has been restored."
The NRC Resident Inspector has been notified.
* * * UPDATE FROM STEVE SPEIRS TO HOWIE CROUCH AT 1844 EDT ON 11/2/13 * * *
The TSC normal power supply was returned to service at 1830 EDT on 11/2/13. The licensee will be notifying the NRC Resident Inspector.
Notified R3DO (Daley). |
| Agreement State | Event Number: 49447 | Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: NMG GEOTECHNICAL INC
Region: 4
City: IRVINE State: CA
County:
License #: 6052-30
Agreement: Y
Docket:
NRC Notified By: DONALD OESTERLE
HQ OPS Officer: CHARLES TEAL | Notification Date: 10/18/2013
Notification Time: 00:19 [ET]
Event Date: 10/09/2013
Event Time: [PDT]
Last Update Date: 10/18/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
RAY AZUA (R4DO)
BARRY WRAY (ILTA)
FSME EVENT RESOURCE (EMAI)
MEXICO (FAX)
|
| This material event contains a "Less than Cat 3 " level of radioactive material. | Event Text AGREEMENT STATE REPORT - STOLEN MOISTURE DENSITY GAUGE
"On October 17, 2013 ICE-RAM [Inspections Compliance and Enforcement - Radioactive Materials Branch] received a letter dated October 14, 2013, from the RSO at NMG Geotechnical, Inc. (NMG), reporting that, on October 9, 2013, one of their moisture density gauge (CPN MC-1DRP, S/N M60408283, 10 mCi Cs-137, 50 mCi Am:Be-241) was discovered to be lost or stolen at an apartment complex at 1601 W. MacArthur Blvd., Santa Ana, CA, after the gauge operator was on a lunch break. The gauge was placed in the vehicle after using the gauge at the apartment complex just prior to starting lunch. The gauge operator discovered that the gauge and transport box were missing from the rear of the Jeep Cherokee SUV. There were no indications that the vehicle was broke into, making it most likely that the gauge and case were left in the vehicle while it was unlocked and the gauge case was not secured to the frame of the vehicle. The operator contacted the RSO and then filed a report with the Santa Ana Police and notified the Irvine Police afterwards.
"On October 17, 2013, an ICE RAM-South inspector contacted the RSO to confirm the information in the letter. The inspector inquired if the operator had searched the complex for the gauge prior to reporting the gauge stolen and the RSO confirmed that they had. The RSO also noted that the operator returned to the complex later to give the apartment management fliers to distribute to residents. The gauge has not been recovered to date. This RSO was informed that they will be cited for loss of control of the gauge and failure to immediately report the loss of the gauge as required. The investigation will continue to determine if any other items of non-compliance are identified."
California 5010 Number: 101713
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 |
| Agreement State | Event Number: 49472 | Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: LTI GROUP/SMART GLASS DIVISION
Region: 1
City: PITTSFIELD State: MA
County:
License #: G0350
Agreement: Y
Docket:
NRC Notified By: DOUG CULLEN
HQ OPS Officer: JOHN SHOEMAKER | Notification Date: 10/25/2013
Notification Time: 14:04 [ET]
Event Date: 10/14/2013
Event Time: [EDT]
Last Update Date: 10/25/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
JOHN ROGGE (R1DO)
FSME EVENTS RESOURCE (EMAI)
MATTHEW HAHN (ILTA)
|
| This material event contains a "Less than Cat 3 " level of radioactive material. | Event Text AGREEMENT STATE REPORT - MISSING STATIC ELIMINATORS
The following Agreement State Report was received via facsimile:
"Two static eliminators each initially containing 10 mCi, Po-210, were misplaced during the departmental move from one [licensee] facility to another. Each alpha emitting device is identified as a static eliminator manufactured by NRD, LLC of Grand Island, NY, Model No. P.2021.8203, with corresponding Serial No.'s of A2GF745 and A2HD506. The devices were reported missing subsequent to an inventory check.
"Calculated device activity with Po-210 half-life = 138 days.
"Device Serial No. A2GF745 was shipped by NRD to LTI on June 6, 2008 thus the original activity of 10 mCi is currently calculated to be 0.5 uCi.
"Device Serial No. A2HD506 was shipped by NRD to LTI on April 7, 2010 thus the original activity of 10 mCi is currently calculated to be 15 uCi.
"The aggregate activity exceeds the threshold of 1.0 uCi (i.e.10 X 0.1 uCi), per CMR 120.297 Appendix C.
"The Agency [Commonwealth of Massachusetts] will continue to investigate this matter.
"Cause: It is believed that during departmental moves from the Lenox, MA facility to a new location in Pittsfield, MA, that two static eliminators were misplaced."
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 |
| Agreement State | Event Number: 49474 | Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: FAZEL BARMAKI
Region: 4
City: ORANGE State: CA
County:
License #:
Agreement: Y
Docket: 7923-37
NRC Notified By: ANDREW TAYLOR
HQ OPS Officer: JOHN SHOEMAKER | Notification Date: 10/25/2013
Notification Time: 21:21 [ET]
Event Date: 10/25/2013
Event Time: 14:30 [PDT]
Last Update Date: 10/25/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
WAYNE WALKER (R4DO)
FSME EVENTS RESOURCE (EMAI)
| Event Text AGREEMENT STATE REPORT - MOISTURE DENSITY GAUGE DAMAGED BY EXCAVATOR
The following Agreement State Report was received via email:
"On October 25, 2013, at approximately 1430 [PDT], Fazel Barmaki, RSO [Radiation Safety Officer] of Fazel Barmaki, RML 7923-37, contacted [California Radiologic Health Branch] RHB Brea concerning their moisture/density gauge, CPN model MC-3, S/N M321106780 (with 10 mCi Cs-137 and 50 mCi Am-241/Be sources) that had been run over by an excavator and damaged while performing measurements at a construction site at 1186 N Ridgeline Rd., Orange, CA. A [California State] ICE RAM-South inspector arrived at the scene to assess the situation and to verify the integrity of the sources. The inspector observed the scene and was able to determine that the Cs-137 source was in the shielded position and the Am-241/Be source was still in the shielded housing. Wipe tests taken at the scene were surveyed and were found to be at background, indicating that the sources were not leaking. The rest of the gauge was inspected and it was observed that the hand and guide tube had broken off from the housing and the electronics were smashed and broken off of the gauge. Despite the damage to the non-radioactive parts, the shielding appeared to be undamaged, and the housing was placed in the transport case. A survey was performed on the transport case while using a Victoreen CHP-450. The highest dose rate on contact with the transport case was 1.8 mR/hr and 0.3 mR/hr at one foot, with a background of 0.01 mR/hr. These dose rates are consistent with a CPN MC-3 moisture density gauge.
"The RSO was interviewed by the [California State] inspector who stated that, between taking readings, he was observing the excavator as it was moving while standing near the gauge, making sure to maintain position between the excavator and gauge. While observing the excavator, the excavator made a sudden move toward him and he had to jump out of the way to prevent being run-over and the gauge was run over, causing the damage to the gauge. After checking on the damage, the RSO then immediately contacted RHB to report the incident.
"Since the radiation surveys indicated the dose rates were consistent with an intact and operational CPN MC-3 gauge and no leakage was indicated by an inspection of the integrity of the shielding and wipe tests at the scene of the incident, the RSO was allowed to return the gauge to their storage location at [in Escondido, CA.], for storage until the gauge can be sent to a service provider or CPN for repair or replacement. The [State's] investigation will be ongoing to determine if licensee will be cited. This is being reported to the NRC Operations Center as a 24 hour report under 10 CFR 30.5(b)(2) since the gauge cannot be locked in the shielded position (due to the source rod being sheared off from the gauge) despite the fact that the Cs-137 source is in the shielded position since it was in the shielded position at the time of the incident."
California Report Number: 102513 |
| Power Reactor | Event Number: 49492 | Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: DOUGLAS LAMARCA
HQ OPS Officer: PETE SNYDER | Notification Date: 11/01/2013
Notification Time: 09:51 [ET]
Event Date: 11/01/2013
Event Time: 03:09 [EDT]
Last Update Date: 11/01/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
| Person (Organization):
PAUL KROHN (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 SECONDARY CONTAINMENT DIFFERENTIAL PRESSURE NOT WITHIN LIMITS FOLLOWING TRIP OF EXHAUST FAN
"On November 1, 2013 at 0309 EDT, Secondary Containment Zone I (Unit 1 Reactor Building) differential pressure was lost following a routine transfer of Reactor Protection System Power supplies. Upon restoration from the power supply transfer, one of the Reactor Building Exhaust Fans tripped. There were no obvious malfunctions associated with the equipment and fan was able to be restarted. Zone II (Unit 2 Reactor Building) and III (Common Refuel Floor Area) ventilation remained in service and stable.
"Zone I differential pressure recovered within a few minutes and was verified to be stable. LCO 3.6.4.1 was entered for both units at 0309 EDT and exited at 0315 EDT. Tech Spec Secondary Containment Operability requires a negative pressure of at least 0.25 inches water gauge.
"There have been no further perturbations in differential pressure and secondary containment remains operable.
"This event is being reported under 10 CFR 50.72(b)(3)(v) and per the guidance of NUREG 1022 Rev 3 section 3.2.7 as a loss of a Safety Function. There is no redundant Susquehanna Secondary Containment System."
The licensee notified the NRC Resident Inspector. See similar event number #49489. |
| Power Reactor | Event Number: 49495 | Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: STEPHEN SEILHYMER
HQ OPS Officer: HOWIE CROUCH | Notification Date: 11/01/2013
Notification Time: 17:31 [ET]
Event Date: 11/01/2013
Event Time: 12:06 [CDT]
Last Update Date: 11/01/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
| Person (Organization):
ROBERT DALEY (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 BOTH TRAINS OF AUXILIARY BUILDING SPECIAL VENTILATION SYSTEM DECLARED INOPERABLE
"During Unit 2 refueling outage [currently defueled] preventative maintenance on CV-31117, Loop B Main Steam Isolation Valve (MSIV), an opening in the valve was discovered without direct administrative controls to ensure the opening could be closed within 6 minutes following a Loss of Coolant Accident on Unit 1. Addition of this opening to other openings created a total of greater than 10 square feet of non-closable openings and required declaring the Auxiliary Building Special Ventilation System (ABSVS) boundary inoperable. The inoperable ABSVS boundary caused both trains of ABSVS to be declared inoperable and required entry into Technical Specification (TS) 3.7.12, Condition B. This could have prevented the ability to control the release of radioactive material and is considered a potential loss of safety function per 10CFR50.72(b)(3)(v)(C).
"Administrative controls in the ABSVS Boundary were re-established by installing a closure device in the opening on CV-31117 at 1246 CDT. The ABSVS boundary and both trains of ABSVS were declared operable at that time."
During the time that the ventilation system was out of service, no evolutions were in progress that could have resulted in an unmonitored release.
The licensee has notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 49497 | Facility: COMANCHE PEAK
Region: 4 State: TX
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DANNY BRADFORD
HQ OPS Officer: BILL HUFFMAN | Notification Date: 11/02/2013
Notification Time: 01:44 [ET]
Event Date: 11/01/2013
Event Time: 21:47 [CDT]
Last Update Date: 11/02/2013 | 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):
JAMES DRAKE (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | A/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text AUTOMATIC REACTOR TRIP DURING SOLID STATE PROTECTION SYSTEM TESTING
"At 2147 CDT on 11/1/2013, Unit 2 Reactor tripped during Solid State Protection System Slave Relay Testing. This test utilizes a blocking circuit to verify the operability of the slave relay which trips the Main Turbine and both Main Feedwater pump turbines, on a Hi-Hi Steam Generator level or Safety Injection. No valve actuation is expected to occur. While positioning the Slave Relay switch in a testing lineup, the relay actutated. The Unit 2 Turbine tripped as well as both Main Feedwater Pumps. The Turbine Trip actuated the Reactor Trip since power was above 50%. The trip of both Main Feedwater Pumps started both Motor Driven Auxiliary Feedwater Pumps. The Steam Generator Lo Lo Levels started the Turbine Driven Auxiliary Feed Water Pump. All systems responded as expected.
"Currently, Unit 2 is being maintained in Hot Standby (Mode 3) in accordance with Integrated Plant Operating Procedure IPO-007B and the Emergency Response Guideline Procedure Network has been exited. Decay Heat is being rejected to the Main Condenser via Steam Dump Valves (Turbine Bypass Valves)."
The licensee has notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 49498 | Facility: MILLSTONE
Region: 1 State: CT
Unit: [ ] [2] [ ]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: STEPHAN LAMBERT
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 11/03/2013
Notification Time: 09:15 [ET]
Event Date: 11/03/2013
Event Time: 06:00 [EST]
Last Update Date: 11/03/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
PAUL KROHN (R1DO)
|
| 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 MAIN STEAM LINE RADIATION MONITOR OUT OF SERVICE
"At 0600 [EST] on 11/3/2013 main steamline radiation monitor RM4299A failed to zero and is not available. It is undetermined at this time how long the radiation monitor will be out of service. This action is reportable as a loss of assessment capability in accordance with 10CFR50.72(b)(3)(xiii)."
The licensee notified the NRC Resident Inspector, and state, and local governments. | |