| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
07/02/2013 - 07/03/2013 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 49145 | Rep Org: NEW YORK STATE DEPT. OF HEALTH
Licensee: MATERIALS TESTING LABORATORY
Region: 1
City: FAR ROCKAWAY State: NY
County:
License #: NYS C2274
Agreement: Y
Docket:
NRC Notified By: ROBERT SNYDER
HQ OPS Officer: CHARLES TEAL | Notification Date: 06/24/2013
Notification Time: 11:06 [ET]
Event Date: 06/20/2013
Event Time: [EDT]
Last Update Date: 06/24/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
MARC FERDAS (R1DO)
FSME EVENT RESOURCE (EMAI)
| Event Text AGREEMENT STATE REPORT - DAMAGED MOISTURE DENSITY GAUGE
The following was received from the State of New York via fax:
"The RSO of NYS (New York State) Licensee C2274 called to report a moisture/density (Troxler Model 4640-B 'thin layer') gauge was damaged at a worksite in Far Rockaway, NY. The source (8 mCi of 137 Cs) was in the safe position when it got damaged and the source is within the unit as determined by survey meter readings. The operator was about 5 ft. away from the gauge when it was run over by a roller. The RSO visited the site took measurements to confirm the source was still in the gauge. He called the QC Resources and took a leak test measurement. He is awaiting the results before shipping the gauge to QC Resources. A written report is forthcoming."
New York State Event Report: NY-13-03 |
| Agreement State | Event Number: 49146 | Rep Org: OR DEPT OF HEALTH RAD PROTECTION
Licensee: UNKNOWN
Region: 4
City: PORTLAND State: OR
County:
License #: UNKNOWN
Agreement: Y
Docket:
NRC Notified By: RICHARD WENDT
HQ OPS Officer: JOHN SHOEMAKER | Notification Date: 06/24/2013
Notification Time: 15:23 [ET]
Event Date: 06/24/2013
Event Time: 11:30 [PDT]
Last Update Date: 06/24/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
GREG PICK (R4DO)
FSME EVENT RESOURCES (EMAI)
| Event Text AGREEMENT STATE REPORT - SCRAP METAL SHIPMENT FOUND TO CONTAIN UNIDENTIFIED RADIOACTIVE MATERIAL
The Oregon Department of Radiation Protection Services received notification, from a scrap metal recycler in Portland, Oregon, that a shipment of scrap metal, for recycling, contains unidentified radioactive material causing low levels of radiation outside the transport vehicle. The shipment originated from a company located in Missoula, Montana. The shipment is under special permit DOT-SP-10656 without a determination of materials meeting or not meeting the regulatory definition of radioactive material. The shipment is a minor radiological concern [approximately 6,000 cpm] based on considerations of the U.S. Department of Transportation and the state official aligning this shipment approval document.
The radioactive material was detected in a truck at a scrap metal recycler's portal monitor in Portland, Oregon. The unidentified item is suspected to be located on the left side, near the landing gear, and on the floor of the trailer. The driver was directed to not rearrange the contents of the truck and the shipment will be returned to the originating company in Missoula, Mt. There is no suspected release of radioactive material, radiation exposures, or personnel injury or contamination.
The state is continuing it's investigation and has notified the Montana Department of Public Health.
Oregon State Incident Docket # 13-0457 and RPS # 13-0024. |
| Power Reactor | Event Number: 49157 | Facility: MCGUIRE
Region: 2 State: NC
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: LARRY KUNKA
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 06/29/2013
Notification Time: 03:12 [ET]
Event Date: 06/29/2013
Event Time: 00:00 [EDT]
Last Update Date: 07/02/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
MARK FRANKE (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 | | 2 | N | Y | 37 | Power Operation | 37 | Power Operation | Event Text OFFSITE NOTIFICATION TO NORTH CAROLINA - RAIN CAUSED OVERFLOW OF HOLDUP POND TO CATAWBA RIVER
"Notification is to be made to an offsite agency: North Carolina Department of Environment and Natural Resources [NCDENR]. Due to heavy rains on site, a holdup pond overflowed to the Catawba River. Holdup pond overflow included chemicals (Rotenone) used to treat macro fouling in the Standby Nuclear Service Water Pond. Notification to NCDENR will be made by telephone Saturday morning 6/29/13."
The licensee notified the NRC Resident Inspector.
* * * UPDATE ON 7/2/13 AT 1139 EDT FROM BRENT BARE TO DONG PARK * * *
"Due to continued rains on site, the holdup pond continues to overflow to the Catawba River. The overflow includes a new chemical, Potassium Permanganate, used to neutralize the Rotenone treatment of the Standby Nuclear Service Water Pond. This new chemical has the potential to initially turn water purple, which is normal when applied. The North Carolina Department of Environment and Natural Resources (NCDENR) has been updated."
The licensee notified the NRC Resident Inspector.
Notified R2DO (Freeman). |
| Power Reactor | Event Number: 49168 | Facility: BRUNSWICK
Region: 2 State: NC
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: MARK TURKAL
HQ OPS Officer: DONG HWA PARK | Notification Date: 07/02/2013
Notification Time: 10:10 [ET]
Event Date: 05/07/2013
Event Time: 21:14 [EDT]
Last Update Date: 07/02/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
| Person (Organization):
SCOTT FREEMAN (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 | | 2 | N | Y | 24 | Power Operation | 24 | Power Operation | Event Text INVALID ACTUATION OF EMERGENCY DIESEL GENERATORS
"This 60-day telephone notification is provided in accordance with 10 CFR 50.73(a)(1) to report an invalid actuation of the Emergency Diesel Generators (EDGs) reportable under 10 CFR 50.73(a)(2)(iv)(A). Due to the shared configuration of the onsite AC Electrical Distribution System, this event is applicable to both Units 1 and 2.
"On May 7, 2013, at approximately 2114 hours Eastern Daylight Time (EDT), while Operations personnel were making preparations for Unit 2 main turbine generator synchronization to the grid, a Main Generator Reverse Power Trip occurred. Main Generator Reverse Power Trip was actuated after adjusting the Manual Voltage Regulator on the Main Generator. The reverse power relay operates the Generator Primary Lockout which initiates a turbine trip and start of all four EDGs. These features functioned as designed. The main generator breaker was open at the time of the event; as such, electrical power was not lost to the emergency busses.
"All four EDGs started and operated as expected. Because electrical power was never lost to the emergency busses and none of the EDGs loaded to their respective emergency busses, the actuations were considered to be partial.
"The EDGs were returned to their standby line-up by 2229 hours on May 7, 2013. Since no actual bus under voltage condition existed which required the EDGs to start and the start was not in response to actual plant conditions satisfying the requirements for initiation, this event has been classified as an invalid actuation.
"This event did not result in any adverse impact to the health and safety of the public."
The licensee has notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 49169 | Facility: PALO VERDE
Region: 4 State: AZ
Unit: [1] [ ] [ ]
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: JAMES BLAZEK
HQ OPS Officer: PETE SNYDER | Notification Date: 07/03/2013
Notification Time: 00:24 [ET]
Event Date: 07/03/2013
Event Time: [MST]
Last Update Date: 07/03/2013 | Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
| Person (Organization):
ART HOWELL (R4)
ERIC LEEDS (NRR)
WILLIAM GOTT (IRD)
VINCENT GADDY (R4DO)
HO NIEH (NRR)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 61 | Power Operation | Event Text NOTICE OF UNUSUAL EVENT DUE TO EXPLOSION IN A NON-SAFETY RELATED LOAD CENTER
"The following event description is based on information currently available. If through subsequent reviews of this event additional information is identified that is pertinent to this event or alters the information being provided at this time a follow-up notification will be made via the ENS or under the reporting requirements of 10CFR50.73.
"On 7/2/2013, at approximately 2027 MST, Palo Verde Unit 1 experienced a reactor power cutback from 100% rated thermal power due to explosion [in a non-safety related load center (1ENGNL02)]. The unit was at normal temperature and pressure prior to the cutback.
"At 2035 [MST] PVNGS Unit 1 declared an Unusual Event due to the explosion EAL HU 2.2.
"Unit 1 is stable at 61% rated thermal power. No ESF actuations occurred and none were required. The event did not result in any challenges to the fission product barrier or result in any releases of radioactive materials. There were no adverse safety consequences or implications as a result of this event. The event did not adversely affect the safe operation of the plant or health and safety of the public."
The licensee will notify the NRC Resident Inspector.
Notified DHS SWO, FEMA, DHS NICC, and Nuclear SSA via email.
* * * UPDATE ON 7/3/13 AT 0229 EDT FROM JEONG LIM TO PETE SNYDER * * *
"Palo Verde Unit 1 is stable at 58% rated thermal power and is implementing abnormal operating procedures for reactor power cutback due to loss of one Main Feedwater Pump and degraded electrical power due to loss of non-class 13.8kV load center 1ENGNL02. Load center 1ENGNL02 was damaged from an apparent electrical malfunction that originated within the load center. The 13.8kV supply breaker to load center 1ENGNL02 tripped to deenergize the load center. Palo Verde Fire Department personnel responded but determined that the load center was deenergized and no fire existed and no extinguishing agents were applied. No damage to other equipment in proximity to load center 1ENGNL02 was identified during a preliminary inspection of the area around the damaged load center. The NRC Resident Inspector has been notified.
"At 2315 [MST] on 07/02/2013, the Unusual Event was terminated."
Notified R4DO (Gaddy), NRR EO (Nieh), IRD MOC (Gott), DHS SWO, FEMA, DHS NICC, and Nuclear SSA via email. |
| Power Reactor | Event Number: 49170 | Facility: COOK
Region: 3 State: MI
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BUD HINCKLEY
HQ OPS Officer: DONALD NORWOOD | Notification Date: 07/03/2013
Notification Time: 01:15 [ET]
Event Date: 07/03/2013
Event Time: 01:15 [EDT]
Last Update Date: 07/03/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
MICHAEL KUNOWSKI (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 | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text UNAVAILABILITY OF TECHNICAL SUPPORT CENTER VENTILATION SYSTEM DUE TO SCHEDULED MAINTENANCE
"At 0115 EDT on Wednesday, July 3, 2013, the Cook Nuclear Plant (CNP) Technical Support Center (TSC) air conditioning and charcoal filtration systems will be removed from service for scheduled maintenance.
"Under certain accident conditions the TSC may become unavailable due to the inability of the air conditioning and charcoal filtration systems to maintain a habitable atmosphere. Compensatory measures exist to relocate TSC personnel to the unaffected unit's control room if necessary.
"TSC ventilation system maintenance and post maintenance testing is scheduled to be completed by 2100 EDT on July 3, 2013.
"The licensee has notified the NRC Resident Inspector.
"This notification is being made in accordance with 10CFR50.72(b)(3)(xiii) due to the loss of an emergency response facility." | |