| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
06/13/2013 - 06/14/2013 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 48924 | Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: MICHAEL McDONNELL
HQ OPS Officer: DONALD NORWOOD | Notification Date: 04/15/2013
Notification Time: 06:04 [ET]
Event Date: 04/14/2013
Event Time: 22:16 [EDT]
Last Update Date: 06/13/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
| Person (Organization):
HAROLD GRAY (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Hot Shutdown | 0 | Hot Shutdown | Event Text PRIMARY CONTAINMENT AIR LOCK FAILED INTEGRATED LEAK RATE TEST
"On Sunday, April 14, 2013 at 2216 hours, with the Pilgrim Nuclear Power Station (PNPS) Reactor Mode Select Switch (RMSS) in Start-up, the turbine generator previously removed from service, and the reactor sub-critical on Intermediate Range Monitors Range 2 and lowering, the PNPS Containment Personnel Air Lock failed integrated air lock testing as required by TS 4.7.A.2.
"10CFR50 Appendix J requires that primary reactor containment meet certain leakage rate testing requirements. These test requirements ensure that 1) Leakage through the containment or systems and components penetrating the containment do not exceed allowable leakage rates specified in Technical Specifications and 2) The integrity of the containment structure is maintained during its service life. The test requirements include local leakage rate testing of containment air locks. The test criteria establishes a limit of less than or equal to 10.525 SLM, actual leakage was 16.7 SLM.
"PNPS was in the process of shutting down for a scheduled Refueling Outage during the scheduled testing.
"This event had no impact on the health and/or safety of the public.
"The USNRC Resident Inspector will be notified.
"This 8-hour notification is being made in accordance with 10CFR50.72(b)(3)(v)(c)."
* * * RETRACTION FROM BOB O'NEILL TO PETE SNYDER AT 1700 ON 6/13/13 * * *
"Subsequent investigation of the test failure determined that an o-ring in the Airlock Inner Pressure Equalizing Device (PED) was not properly seated resulting in exceeding the established leakage rate limit. Leakage was not observed on the Airlock Outer Boundary Surface. Thus, with the Airlock Outer Boundary Surface intact, the Airlock was capable of performing the safety function to control the release of radioactive material.
"In addition, even with the Airlock leakage of 16.7 standard liters per minute (SLM), the Technical Specification Primary Containment As-Found Minimum Pathway Leakage Limit of 0.6 La for all Type B and C leakage tests was not exceeded.
"Therefore, the initial 50.72(b)(3)(v)(C) report is being retracted."
The licensee will notify the NRC Resident Inspector. Notified R1DO (Dentel). |
| !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 48949 | Facility: SALEM
Region: 1 State: NJ
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: HARRY WIEDMAN
HQ OPS Officer: PETE SNYDER | Notification Date: 04/20/2013
Notification Time: 09:46 [ET]
Event Date: 04/20/2013
Event Time: 04:22 [EDT]
Last Update Date: 06/13/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
WILLIAM COOK (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 ACCIDENT MITIGATION - COMMON CONTROL ROOM EMERGENCY AIR CONDITIONING SYSTEM
"Salem Unit 2 was placed in a configuration that affected the ability to mitigate the consequences of an accident due to an inadvertent actuation of the common control room emergency air conditioning system (CREACS). CREACS was actuated as a result of an invalid Control Room air intake duct radiation monitor signal initiated on April 20, 2013 at 0422 hours [EDT].
"Salem Unit 1 is currently in Mode 6 with core offload in progress. Salem Unit 2 is in Mode 1 at 100% power. Unit 2 has two shutdown LCOs in effect. The first is for the CREACS, which is shared between Unit 1 & 2, being aligned for single train operation with the Unit 1 CREACS train out of service per LCO 3.7.6. The second shutdown LCO is for single source of offsite power due to scheduled maintenance.
"With Unit 1 having an invalid radiation monitor signal, the CREACS automatically aligned to accident pressurized mode. This mode of actuation starts the CREACS fans, isolates the Control Room Envelope from the normal control room ventilation system and aligns the two sets of CREACS outside air intake dampers. With a Unit 1 radiation monitor signal the Unit 1 CREACS intake dampers close and the Unit 2 CREACS intake dampers open. These damper positions are locked in until manually reset. With only one train of CREACS operable, the dose analysis indicates that the requirements of General Design Criteria (GDC) 19 can only be met during the worst case design basis accident if the Unit 2 CREACS intake dampers are closed and the Unit 1 CREACS intake dampers [are] open. Therefore, until the CREACS intake dampers were reset and realigned, Salem Unit 2 would not have been able to mitigate the consequences of an accident and is reportable in accordance with 10CFR50.72(b)(3)(v).
"The CREACS system actuation was reset after the failed radiation monitor (2R1B ch. II) was removed from service and the dampers were realigned to their pre-actuation alignment at 0457 hours, restoring Salem Unit 2 to within the assumptions of the dose analysis. Total duration in the condition was 35 minutes.
"The only pieces of major equipment out of service on Salem Unit 2 are the 4 Station Power Transformer and 23 Station Power Transformer which are out of service for scheduled maintenance."
The licensee will notifying Lower Alloways Creek township and the NRC Resident Inspector.
* * * RETRACTION FROM DAVID LAFLEUR TO PETE SNYDER AT 1304 EDT ON 6/13/13 * * *
"On April 20, 2013, Salem Unit 2 was placed in a configuration that was contrary to the current dose analysis of record due to an invalid actuation of the common Control Room Emergency Air Conditioning System (CREACS). The CREACS was initiated as a result of an invalid actuation of Control Room Air Intake Duct Radiation Monitoring Channel, 2R1B Channel 2. At the time of the actuation, the Unit 1 Train of CREACS was out of service due to scheduled maintenance leaving only the Unit 2 CREACS train operable. Unit 2 was at 100% power and Unit 1 was in Mode 6. With one train of CREACS out of service at the start of an accident the dose analysis of record requires that the CREACS Emergency Air Intake Dampers for the accident unit go closed and the opposite unit's emergency intake dampers go open. The actuation of the radiation monitoring channel 2R1B Channel 2 caused the Unit 2 Emergency Air Intake Dampers to open. If a design basis LOCA were to have occurred on Unit 2 during that period the alignment would have been contrary to the dose analysis-of-record.
"Subsequent to this event, an evaluation was performed utilizing the assumptions of the dose analysis of record with two exceptions. Actual measured Engineered Safety Feature system leakage outside containment and Containment Leakage at the time of the event were utilized in the evaluation. This evaluation determined that if a design basis LOCA had occurred on Unit 2 with the CREACS in accident pressurized mode with Unit 1 Emergency Intake Dampers closed and Unit 2 Emergency Intake Dampers opened, Control Room design dose limits would not have been exceeded. Based upon this evaluation, the CREACS system would have been able to maintain dose to Control Room operators below the limits of GDC-19 and the dose analysis of record. Since the CREACS was capable of performing its accident mitigation function, this event is being retracted."
The licensee will notify the NRC Resident Inspector. Notified R1DO (Dentel). |
| Agreement State | Event Number: 49090 | Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: IRISNDT MATRIX CORP.
Region: 4
City: DEER PARK State: TX
County:
License #: 06435
Agreement: Y
Docket:
NRC Notified By: CHRIS MOORE
HQ OPS Officer: HOWIE CROUCH | Notification Date: 06/05/2013
Notification Time: 11:19 [ET]
Event Date: 06/04/2013
Event Time: [CDT]
Last Update Date: 06/05/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
BLAIR SPITZBERG (R4DO)
FSME EVENTS RESOURCE (EMAI)
| Event Text AGREEMENT STATE REPORT - UNABLE TO RETRACT RADIOGRAPHY SOURCE
The following information was obtained from the State of Texas via email:
"On June 5, 2013, the licensee's Radiation Safety Officer (RSO) reported to the Agency [Texas Department of Health] that on June 4, 2013, one of its radiography crews had been unable to retract the Iridium-192 source back into the SPEC 150 camera they were using in a fixed bay. The disconnect occurred after the first shot. The RSO was notified and he and two other employees performed the source retrieval. Readings from the pocket dosimeters were: RSO - 21.3 mrem; other employees performing source retrieval received 53.9 and 26.9 mrem. No member of the public received any exposure from this event. Cause of the event unknown at this time. Further information will be provided as it is obtained, per SA-300.
"Radiography Camera: Spec 150, SN: 407
"Source: Iridium-192, SN: UE2912"
Texas Event Number: I-9089 |
| 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 |
| Power Reactor | Event Number: 49109 | Facility: VERMONT YANKEE
Region: 1 State: VT
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: MICHAEL PLETCHER
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 06/12/2013
Notification Time: 21:36 [ET]
Event Date: 06/12/2013
Event Time: 16:38 [EDT]
Last Update Date: 06/13/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
GLENN DENTEL (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 | Event Text TONE ALERT SYSTEM FAILURE
"Vermont Yankee Control Room was notified by E-Plan personnel at 1638 [EDT] that the tone test initiated by the National Weather Service from Albany, NY, failed to activate tone alert radios via the Ames Hill NOAA transmitter and would be out for greater than one hour. At 1712 [EDT] the tone alert radios were functionally tested from the backup transmitter link (WTSA Radio Studio) satisfactorily verifying the ability to activate tone alert radios is available."
The licensee suspects a phone service change was not sufficiently tested.
The licensee notified the NRC Resident Inspector.
* * * UPDATE FROM MIKE FRENCH TO NESTOR MAKRIS ON 6/13/13 AT 1207 EDT * * *
On 6/13/13 at 1045 EDT, the Ames Hill transmitter was returned to service after restoration of the transmission link between Ames Hill and the National Weather Service.
The licensee notified the NRC Resident Inspector.
Notified R1DO (Dentel). |
| Power Reactor | Event Number: 49110 | Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: JAMES PRIEST
HQ OPS Officer: HOWIE CROUCH | Notification Date: 06/13/2013
Notification Time: 09:41 [ET]
Event Date: 06/13/2013
Event Time: 02:52 [EDT]
Last Update Date: 06/13/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
| Person (Organization):
GLENN DENTEL (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Hot Shutdown | 0 | Hot Shutdown | Event Text DISCOVERY OF PRESSURE BOUNDARY LEAKAGE
"On 6/13/13 at approximately 0252 EDT, during the initial walk down of the drywell of the Hope Creek Unit 1 forced outage, water was observed leaking from a 40% circumferential crack in a weld in the RHR vent line adjacent to the outboard isolation valve (BCV-597). The estimated leakage rate through the crack is less than one gallon per minute. The RHR vent line is one-inch ASME Class 1 piping. Hope Creek Unit 1 is stable in Operational Condition 3, Hot Shutdown.
"This report is being made under 10CFR50.72(b)(3)(ii)(A) for a weld or material defect in the primary coolant system which cannot be found acceptable under applicable ASME standards.
"The NRC Resident Inspector has been notified. The only safety-related equipment out of service at the time event was the 'C' Service Water Pump, which was tagged for scheduled maintenance.
"No personnel injuries occurred. No radiation releases occurred."
The licensee entered a 24 hr. action statement under T.S. 3.4.3.2, Condition A to be in mode 4 by 0252 EDT on 6/14/13.
The licensee will be notifying the Lower Alloways Creek township. |
| Power Reactor | Event Number: 49112 | Facility: FORT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: (1) CE
NRC Notified By: MICHAEL PEAK
HQ OPS Officer: DONALD NORWOOD | Notification Date: 06/13/2013
Notification Time: 16:55 [ET]
Event Date: 06/13/2013
Event Time: 08:05 [CDT]
Last Update Date: 06/13/2013 | 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 UNANALYZED CONDITION
"The station is reporting an unanalyzed condition involving the steam driven auxiliary feedwater pump. A postulated high energy line break in the room containing the pump could result in steam communicating with equipment in the safety related switchgear and battery rooms which are immediately above the room. The plant is currently in cold shutdown with the fuel removed from the core."
The licensee stated that in the event of a postulated high energy line break, steam could possibly enter the switchgear and battery rooms via a stairwell and ventilation ductwork.
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 49113 | Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: KIRK DUEA
HQ OPS Officer: DONALD NORWOOD | Notification Date: 06/13/2013
Notification Time: 22:02 [ET]
Event Date: 06/13/2013
Event Time: 14:30 [CDT]
Last Update Date: 06/13/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
50.72(b)(3)(v)(B) - POT RHR INOP
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
ERIC DUNCAN (R3DO)
|
| 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 EMERGENCY DIESEL GENERATORS START
"While preparing for an equipment test Thursday afternoon, Monticello Nuclear Generating Plant lost off-site power on its normal off-site power feed. Power for safety related loads was automatically transferred to the alternate off-site power source. The Emergency Diesel Generators started as designed but did not load onto the safety related busses due to the availability of off-site power. Operators stabilized the plant, which is shutdown for a refueling and maintenance outage, in less than an hour and are investigating the cause of the event. The current plant focus is on restoring the normal off-site power feed. The event posed no danger to the public or plant workers, and no one was injured. There was no release of radiation. Plant safety systems continue to be powered by the backup off-site power feed, with the emergency diesel generators available if needed.
"Event Specifics:
"At approximately 1430 CDT, during a refueling outage with the plant in Mode 4, reactor level at approximately 200 inches, and a full Scram already inserted, a loss of normal off-site power occurred due to a fault in a non-safety related bus supply breaker. The fault was in the 13.8 KV supply breaker to the #11 bus. This caused the Station 2R transformer to lockout, resulting in a loss of the normal off-site power to Essential Busses 15 and 16. Shutdown Cooling (SDC) was lost for approximately 1 hour due to loss of supply power and isolation of the common suction valves.
"Both 11 and 12 Emergency Diesel Generators (EDGs) automatically started but did not load onto their respective busses (as designed) due to the 1AR emergency off-site transformer re-energizing both 15 and 16 bus. This essential bus transfer is being reported as a 'Valid actuation of emergency AC electrical power systems' under 10CFR50.72(b)(3)(iv).
"During the event the decision was made to shut down the EDGs which rendered them inoperable for a short period of time until the Fast Start capability was reset. The period of time that the EDGs were inoperable is being reported as a 'Condition that could have prevented the fulfillment of the safety functions to remove residual heat, control the release of radioactive material, and mitigate the consequences of an accident under 10CFR50.72(b)(3)(v)(B), (C), and (D). Both EDGs have been restored to Automatic Standby Status and are operable.
"The loss of power resulted in a Group II Containment Isolation signal causing secondary containment to isolate and Standby Gas Treatment and Control Room Emergency Filtration to initiate as well as associated Group II Containment Isolation Valves to close. This is being reported as a 'General containment isolation signal ESF actuation' under 10CFR50.72(b)(3)(iv). The containment isolation has been reset, and SDC and SFPC have been restored. Reactor temperature rose approximately 4 degrees F during the event from 161 degrees to 165 degrees which remained in the prescribed operating band. Reactor level did not change.
"The licensee has notified the NRC Resident Inspector." |
| Power Reactor | Event Number: 49114 | Facility: HARRIS
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP
NRC Notified By: KEVIN ABELL
HQ OPS Officer: PETE SNYDER | Notification Date: 06/13/2013
Notification Time: 22:03 [ET]
Event Date: 06/13/2013
Event Time: 18:30 [EDT]
Last Update Date: 06/13/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| 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 NOTIFICATION OF NORTH CAROLINA EMERGENCY MANAGEMENT DUE TO SPILL OF DIESEL OIL
"At 6:30 PM EDT on 6/13/13 an all spill was identified which resulted in approximately one quart of fuel oil spilled to the ground from a diesel powered portable light which overturned during a storm. The oil spill was outside of the dike containment in which the light unit was located and was approximately 10 feet from waters of the Harris Lake (waters of the US). No oil entered the lake. This event was reportable to the state of North Carolina because it occurred within 100 feet of the Harris Lake. At 7:03 PM EDT on 6/13/13 Harris Environmental Services Section personnel made the oil spill notification to North Carolina Emergency Management which was acting on behalf of the North Carolina Department of Environment and Natural Resources.
"The spill was cleaned up by removing the topsoil in the area.
"This event is reportable per 10 CFR 50.72(b)(2)(xi) as described in NUREG-1022, based on an event related to protection of the environment for which a notification to other government agencies has been made.
"There is no impact to public health and safety due to this condition.
"The NRC Resident Inspector has been notified." |
| 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." | |