| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
04/03/2015 - 04/06/2015 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 50806 | Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: KIRK DUEA
HQ OPS Officer: JEFF HERRERA | Notification Date: 02/10/2015
Notification Time: 20:39 [ET]
Event Date: 02/10/2015
Event Time: 12:40 [CST]
Last Update Date: 04/03/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
PATTY PELKE (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 95 | Power Operation | 95 | Power Operation | Event Text UNANALYZED CONDITION IN STATION BLACKOUT IMPLEMENTATION AT MONTICELLO
"On February 10, 2015, at 1240 EST, Northern States Power-Minnesota (NSPM) determined that the Station Blackout (SBO) implementation at Monticello Nuclear Generating Plant (MNGP) was not consistent with the NRC Safety Evaluation (SE). Specifically, the High Pressure Coolant Injection (HPCI) system was not being utilized in a manner consistent with the NRC SE for SBO. Current battery calculations do not reflect a full complement of HPCI system equipment running for the duration (coping requirements) of the SBO event. The calculation assumed a manual action to remove the HPCI auxiliary oil pump from operating during an SBO event in order to preserve the station battery.
"NSPM is reporting this as an Unanalyzed Condition pursuant to the requirements of 10 CFR 50.72(b)(3)(ii)(B). The health and safety of the public was not affected since no SBO event occurred. All station batteries and the HPCI system remain operable in accordance with the plant Technical Specifications.
"The NRC Resident Inspector was notified of the event."
* * * RETRACTION PROVIDED BY MICHAEL BURTON TO JEFF ROTTON AT 1254 EDT ON 04/03/2015 * * *
"An engineering analysis was performed updating the battery calculations for Station Blackout (SBO) implementation demonstrating the ability of the safety related station batteries to provide sufficient capacity and capability to ensure that the core is cooled and appropriate containment integrity is maintained in the event of the SBO for the specified four hours. Therefore, the battery calculation is analyzed and specifically the High Pressure Cooling Injection (HPCI) System is analyzed to run in automatic for the entire duration of the SBO event meeting the site licensing basis for SBO. The SBO procedure has been revised to incorporate HPCI running in automatic for the entire duration of the SBO event.
"The NRC Resident Inspector has been notified."
Notified R3DO (Duncan) |
| Agreement State | Event Number: 50929 | Rep Org: PA BUREAU OF RADIATION PROTECTION
Licensee: SYSTEM ONE HOLDINGS LLC
Region: 1
City: PITTSBURGH State: PA
County:
License #: PA-1148
Agreement: Y
Docket:
NRC Notified By: DAVID ALLARD
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 03/27/2015
Notification Time: 13:49 [ET]
Event Date: 02/24/2015
Event Time: [EDT]
Last Update Date: 03/27/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
TODD JACKSON (R1DO)
NMSS_EVENTS_NOTIFIC (EMAI)
| Event Text AGREEMENT STATE REPORT - RADIOGRAPHIC SOURCE FAILS TO RETRACT
The following report was received via e-mail:
"A radiographic source tube was damaged which temporarily restricted retraction of the source.
"The guide tube became crushed by a falling object thereby preventing the source from retracting. The assistant RSO performed a source recovery with help from an assistant radiographer. The damaged guide tube was removed from service. Licensee personnel were trained on proper stabilization techniques. No individual received a dose in excess of limits.
"Manufacturer: QSA
Model: 880D
Serial No.: 9212
Source: lr-192
Activity: 29 Ci"
PA Event #: PA150008. |
| Agreement State | Event Number: 50930 | Rep Org: ILLINOIS EMERGENCY MGMT. AGENCY
Licensee: AFFILIATED ONCOLOGISTS, LLC d/b/a SOUTHLAND ONCOLOTY
Region: 3
City: MOKENA State: IL
County:
License #: IL-02344-01
Agreement: Y
Docket:
NRC Notified By: DAREN TERRERO
HQ OPS Officer: JOHN SHOEMAKER | Notification Date: 03/27/2015
Notification Time: 14:17 [ET]
Event Date: 03/10/2014
Event Time: [CDT]
Last Update Date: 03/27/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
JAMNES CAMERON (R3DO)
NMSS_EVENTS_NOTIFIC (EMAI)
| Event Text AGREEMENT STATE REPORT - MEDICAL EVENT INVOLVING AN EXCESSIVE DOSE DELIVERED TO THE WRONG SITE
The following report was received from the State of Illinois via email:
"On March 25, 2015, Agency [Illinois Emergency Management Agency] representatives were advised via voicemail message by a medical physicist associated with the licensee's facility that a medical event had occurred at a point in the past. The medical physicist had been conducting a retrospective review of cases performed at the site which were similar to another case that had resulted in a medical event at another facility.
"The review included all 5 cases performed at the licensee's facility since August of 2013 when treatments were first started. The treatment protocols involved using a Strut Adjusted Volume Implant (SAVI) catheter, a Nucletron high dose rate afterloader and the Oncentra treatment planning system which was also used in the similar situation. They determined that at least one of the treatments conducted March 10-14, 2014, involved an error of greater than 20 percent which would meet the criteria of a medical event and dose to an unintended organ exceeding 50 rem.
"On March 26, 2015, a radiation oncologist from the licensee contacted the Agency with information to confirm the medical event. The patient had been treated twice a day for five days for a total intended V95 dose of 34 Gy in ten equal fractions. The target only received 43 percent of the intended dose with the majority instead being delivered to the catheter insertion site (approximately 30 Gy). It was determined that although the patient had later returned on June 24, 2014, with pain and redness at the incision site of the left breast, the cause of damage to the 21 cc tissue area was not attributed to radiation damage. The patient was referred to their surgeon who excised the affected area during an outpatient procedure.
"The licensee has suspended treatments using the protocol pending a full investigation and evaluation of appropriate corrective measures to prevent a recurrence by a physicist not associated with the treatments. The Agency is conducting its own investigation as well. This matter remains open at this time."
This event strongly parallels that of an event which the State of Illinois reported on February 13, 2015, see EN #50818.
Illinois State Item Number: IL15009
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: 50931 | Rep Org: VIRGINIA RAD MATERIALS PROGRAM
Licensee: MQC LABS
Region: 1
City: ABERDEEN State: MD
County:
License #: MD-19-28683-0
Agreement: Y
Docket:
NRC Notified By: ANTHONY SANDS
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 03/27/2015
Notification Time: 16:06 [ET]
Event Date: 03/25/2015
Event Time: [EDT]
Last Update Date: 03/27/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
TODD JACKSON (R1DO)
NMSS_EVENTS_NOTIFIC (EMAI)
| Event Text AGREEMENT STATE REPORT - RADIOGRAPHY SOURCE STUCK IN GUIDE TUBE
The following report was received via e-mail:
"Radiograph work was being performed on March 25, 2015, at Dominion Power in Dumfries, VA. After the second exposure was finished, the magnetic stand holding the source fell on the guide tube. The source became stuck inside the guide tube. [The radiographers] tried multiple times to retract the source, but did not succeed. At that time, the licensee secured the area and called the RSO [Radiation Safety Officer]. This occurred around 1830 EDT. The RSO and President [of MQC Labs] arrived at approximately 2200 EDT. The RSO called QSA Global, Inc. to retrieve the source. Subsequently, the RSO contacted the Virginia EOC to notify the VRMP [Virginia Radiation Materials Program] of the incident. QSA Global, Inc. arrived at 1330 EDT on March 26,2015, to retrieve the source at Dominion Power in Dumfries, VA. VRMP staff was present to observe the source retrieval. MQC LABS will submit its written report within 30 days. VRMP will review the report and discuss any corrective action with MQC Labs and Maryland RMP [Radiation Materials Program]".
MQC was performing work in Virginia under a reciprocity program with Maryland.
Virginia Report # VA-15-05 |
| Agreement State | Event Number: 50934 | Rep Org: KENTUCKY DEPT OF RADIATION CONTROL
Licensee: HARDIN MEMORIAL HOSPITAL
Region: 1
City: ELIZABETHTOWN State: KY
County:
License #: 202-148-26
Agreement: Y
Docket:
NRC Notified By: MARISSA VEGA VALEZ
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 03/27/2015
Notification Time: 17:28 [ET]
Event Date: 03/25/2015
Event Time: 12:00 [CDT]
Last Update Date: 03/27/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
TODD JACKSON (R1DO)
NMSS_EVENTS_NOTIFIC (EMAI)
| Event Text AGREEMENT STATE REPORT - MEDICAL EVENT DURING PROSTATE BRACHYTHERAPY
The following report was received via e-mail:
"RHB [Kentucky Radiation Health Branch] was notified by telephone on 3/26/15, by the licensee's RSO [Radiation Safety Officer] of a medical event involving an I-125 permanent prostate brachytherapy implant. A CT [computerized tomography] scan performed approximately 5 weeks post-implant revealed that 30% of the implanted activity was administered outside the treatment site (PTV). The delineation of PTV corresponds to a 3 mm margin around the contoured prostate gland, except in the direction of the rectum, prostate base and apex. The error was caused by the inherent difficulty in ultrasound imaging of the prostate, changes in the prostate volume before, during, and after an implant, subjectivity in the contouring of the prostate gland, and a common tendency to drop the seeds slightly inferior to the gland as the needle is retracted. The authorized user reviewed the post plan metrics with the patient and referring physician within 24 hours of the discovery of the medical event. The KY RHB [Kentucky Radiation Health Branch] has requested additional information."
Kentucky Report #: KY150002
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. |
| Non-Agreement State | Event Number: 50937 | Rep Org: CARMEUSE LIME & STONE
Licensee: CARMEUSE LIME & STONE
Region: 3
City: RIVER ROUGE State: MI
County: WAYNE
License #: 21-32513-01
Agreement: N
Docket:
NRC Notified By: JAMES MOSIER
HQ OPS Officer: JOHN SHOEMAKER | Notification Date: 03/28/2015
Notification Time: 12:19 [ET]
Event Date: 02/19/2015
Event Time: [EDT]
Last Update Date: 03/28/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
| Person (Organization):
JAMNES CAMERON (R3DO)
NMSS_EVENTS_NOTIFIC (EMAI)
| Event Text BROKEN SHUTTER SHIELDING BLOCK ON A FIXED PROCESS GAUGE
During a routine shutter check on 2/19/15, the licensee discovered the shutter shielding block had fallen off a fixed process gauge for the #2 lime conveyor.
The licensee had a representative from Vega America inspect the gauge on 3/25/15. Vega America determined that the shutter shield block cannot be repaired. The licensee is considering having Vega America replace the gauge with a new model and disposing of the old gauge. The shutter is normally open and the gauge remains in service. The gauge does not present a hazard to plant personnel due to it's normally inaccessible location.
The gauge is 1960s vintage, Ohmart SH-100, Model # A-2102, Serial #73799, with a 100 mCi Cs-137 source. |
| Power Reactor | Event Number: 50949 | Facility: QUAD CITIES
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: JOHN VESELY
HQ OPS Officer: DANIEL MILLS | Notification Date: 04/03/2015
Notification Time: 01:32 [ET]
Event Date: 04/02/2015
Event Time: 21:33 [CDT]
Last Update Date: 04/03/2015 | 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):
ROBERT DALEY (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | M/R | Y | 20 | Power Operation | 0 | Hot Shutdown | Event Text MANUAL REACTOR SCRAM DUE TO STEAM LEAK
"On April 2, 2015 at 2133 CDT, a manual scram was inserted on Unit 1 following discovery of a steam leak in the Turbine Building at the D-ring, near the Turbine Bypass valves. Following the reactor scram, reactor water level decreased to approximately -2 inches, which resulted in an automatic Group II and Group III isolation (expected response). The steam leak was isolated by manual closure of the Main Steam Isolation Valves. All systems responded properly to the event. Unit 1 remains in Mode 3, with cooldown in progress. Reactor water level is in the normal level band. The cause and details of the event are under investigation. Unit 2 was unaffected by the event and remains at 100 percent power."
Operators reduced reactor power to 20 percent before initiating a SCRAM. All rods fully inserted and the reactor is shutdown and stable. The electrical supply is in a normal shutdown lineup. The reactor is being supplied by normal feedwater, and decay heat is being controlled by use of the ADS valves. The licensee is currently cooling down and depressurizing the reactor in preparation for repair of the steam leak.
The licensee has notified the NRC Resident Inspector and the State of Illinois Resident Inspector. |
| Power Reactor | Event Number: 50950 | Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [ ] [2] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: JEFF HUMAN
HQ OPS Officer: DANIEL MILLS | Notification Date: 04/03/2015
Notification Time: 10:12 [ET]
Event Date: 04/03/2015
Event Time: 06:52 [CDT]
Last Update Date: 04/03/2015 | 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):
ERIC DUNCAN (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | M/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text MANUAL REACTOR SCRAM DUE TO LOSS OF MAIN FEEDWATER PUMP
"On April 3, 2015 at 0652 CDT, the Unit 2 reactor was manually tripped while operating at 100 percent power due to a lockout trip of 21 Main Feedwater Pump as required by the annunciator response procedure for the lockout alarm. This also resulted in a turbine trip. The crew entered the reactor trip emergency operating procedures and stabilized the unit in Mode 3 at normal operating pressure and temperature. All control rods fully inserted into the core following the trip. The manual trip is reportable per 10 CFR 50.72(b)(2)(iv)(B). The Auxiliary Feedwater System actuated to start the auxiliary feedwater pumps as designed on low narrow range steam generator level and provided makeup flow to the steam generators. The auxiliary feedwater actuation is reportable per 10 CFR 50.72(b)(3)(iv)(A). Steam generator levels have been returned to normal. The auxiliary feedwater pumps have subsequently been secured and returned to automatic. Steam generators are being supplied by 22 Main Feedwater Pump and decay heat is being removed by the condenser steam dump system.
"The cause of 21 Main Feedwater Pump trip has been determined to be a failed suction pressure switch.
"There was no effect on Unit 1 as a result of this trip. The health and safety of the public and site personnel were not at risk at any time during this event.
"The NRC Senior Resident Inspector has been notified."
The licensee plans to issue a press release. |
| Power Reactor | Event Number: 50951 | Facility: LIMERICK
Region: 1 State: PA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: JOHN HARKINS
HQ OPS Officer: STEVE SANDIN | Notification Date: 04/03/2015
Notification Time: 11:54 [ET]
Event Date: 04/03/2015
Event Time: 10:00 [EDT]
Last Update Date: 04/03/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
SILAS KENNEDY (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 | 82 | Power Operation | 82 | Power Operation | Event Text INOPERABLE SEISMIC INSTRUMENTATION IDENTIFIED DURING HISTORICAL REVIEW
"Limerick Generating Station (LGS) has completed a review of recent seismic monitor performance. The seismic monitor is currently capable of fulfilling its emergency assessment support function. The review of the system performance over the last three years identified two occasions when the system was degraded and incapable of performing its emergency assessment support function such that emergency classification at the UNUSUAL EVENT and ALERT levels could not be declared within fifteen minutes as required with site instrumentation. The seismic monitor was determined to be degraded and incapable of performing its emergency assessment support function on the following dates:
1) January 17, 2014 - Unit 1 100% power, Unit 2 97% power
2) March 22, 2014 - Unit 1 Refueling, Unit 2 100% power
"These unplanned inoperable conditions of the seismic monitor were entered into the LGS Corrective Action Program (CAP) when they occurred.
"While Exelon procedural direction allowed the use of offsite sources to obtain seismic data when the seismic monitor is incapable of assessing emergency plan Emergency Action Levels (EALs), this was not explicitly referenced in the approved EALs. The loss of assessment capability is reportable to the NRC within 8 hours of discovery in accordance with 10 CFR 50.72(b)(3)(xiii). This report is required per 10 CFR 50.72(a)(1)(ii) as an event that occurred within 3 years of the date of discovery."
For the two dates above, the 1/17/14 failure was related to function of the system CPU (central processing unit) and the 3/22/14 failure was due to a failed instrument backup battery. There was no seismic event on either of these two dates.
The licensee informed the NRC Resident Inspector. |
| Power Reactor | Event Number: 50952 | Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [1] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: JACK BREEN
HQ OPS Officer: JEFF ROTTON | Notification Date: 04/03/2015
Notification Time: 14:17 [ET]
Event Date: 04/03/2015
Event Time: 15:00 [EDT]
Last Update Date: 04/03/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
SHAKUR WALKER (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Defueled | 0 | Defueled | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text TECHNICAL SUPPORT CENTER VENTILATION NONFUNCTIONAL DURING PREPLANNED MAINTENANCE
"On April 3, 2015, at 1500 EDT, the Control Room Emergency Ventilation System on St. Lucie Unit 1 will be declared inoperable due to pre-planned maintenance during the current refueling outage. The Technical Support Center (TSC) ventilation system is part of the Unit 1 Control Room Emergency Ventilation System, therefore, the TSC ventilation system has been rendered non-functional during the course of the work activities. The TSC ventilation is expected to be returned to service in approximately 24 hours.
"If an emergency is declared requiring TSC activation during this period, the TSC will be staffed and activated using existing emergency planning procedures. Should the TSC become uninhabitable, the TSC staff will relocate to an alternate TSC location in accordance with applicable site procedures.
"This notification is being made in accordance with 10 CFR 50.72 (b)(3)(xiii) due to the potential loss of an emergency response facility. An update will be provided once the TSC ventilation system has been restored to normal operation.
"The NRC Resident Inspector has been notified."
* * * UPDATE PROVIDED BY DAVE FIELDS TO JEFF ROTTON AT 2240 EDT ON 4/03/2015 * * *
"The TSC ventilation system has been restored to normal operation as of 2230 EDT on April 3, 2015. The NRC Resident Inspector has been notified."
Notified R2DO (Walker). |
| Power Reactor | Event Number: 50953 | Facility: BRAIDWOOD
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MURTAZA ABBAS
HQ OPS Officer: STEVE SANDIN | Notification Date: 04/03/2015
Notification Time: 19:37 [ET]
Event Date: 04/03/2015
Event Time: 16:31 [CDT]
Last Update Date: 04/03/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
| Person (Organization):
ERIC DUNCAN (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | Event Text LIQUID PENETRATION EXAMINATION RESULTS IN INDICATION ON REACTOR VESSEL HEAD PENETRATION
"On April 3, 2015, during the Braidwood Station Unit 1 refueling outage (A1R18), an in-service Liquid Penetration examination was performed on the previously repaired control rod drive mechanism (CRDM) penetration 69. During the examination on the weld build up for CRDM penetration 69, a 3/8 inch rounded indication was discovered located at 0 degrees on the reactor head portion of the weld build up, and it is 4 inches from the transition of the head to penetration. 0 degrees is located at the outermost portion of the penetration on the flange side. The transition is the point where the vertical portion of the penetration meets the horizontal area of the reactor head.
"Rounded indications that exceed 3/16 inch are rejectable per ASME Code Case N-729-1.
"This is reportable pursuant to 10CFR50.72(b)(3)(ii)(A), 'Any event or condition that results in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded' since the as found indication did not meet the applicable acceptance criteria referenced in ASME Code Case N-729-1 to remain in-service without repair.
"The NRC Resident Inspector has been informed." |
| Power Reactor | Event Number: 50955 | Facility: COMANCHE PEAK
Region: 4 State: TX
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ROBERT DANIELS
HQ OPS Officer: STEVE SANDIN | Notification Date: 04/05/2015
Notification Time: 13:55 [ET]
Event Date: 04/05/2015
Event Time: 08:52 [CDT]
Last Update Date: 04/05/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
JACK WHITTEN (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 | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text LOSS OF BOTH PRIMARY AND BACKUP METEOROLOGICAL TOWERS DUE TO PARTIAL LOSS OF 25kV POWER DISTRIBUTION
"At 0852 CDT on 04/05/2015, a partial loss of the 25kV Plant Support Power Distribution System caused a loss of both the Primary and Backup Meteorological Towers at Comanche Peak Nuclear Power Plant. Loss of both Meteorological Towers constitutes a major loss of emergency assessment capabilities in regard to meteorological conditions.
"The 25kV Plant Support Power Distribution System feeds certain non-safety related equipment and does not affect plant operation.
"An investigation into the cause of the loss of power is in progress."
The licensee informed the NRC Resident Inspector. |
| Power Reactor | Event Number: 50956 | Facility: LIMERICK
Region: 1 State: PA
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: DAVE HOLCOMB
HQ OPS Officer: DONALD NORWOOD | Notification Date: 04/05/2015
Notification Time: 16:06 [ET]
Event Date: 04/05/2015
Event Time: 15:37 [EDT]
Last Update Date: 04/05/2015 | Emergency Class: ALERT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
| Person (Organization):
SILAS KENNEDY (R1DO)
WILLIAM GOTT (IRD)
DAVE LEW (R1RA)
JENNIFER UHLE (NRR)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 82 | Power Operation | 82 | Power Operation | Event Text ALERT DECLARED DUE TO FIRE IN MOTOR CONTROL CENTER
"An Alert was declared due to a fire in a Unit 2 Division 2 Safeguard [250 volt] DC Motor Control Center. This has made the High Pressure Core Injection system inoperable and unavailable. The fire is out. The emergency response organization has been activated and investigation / repair planning will commence. Unit 2 is stable with no other system affects."
The fire was extinguished by on-site personnel. No off-site responders were required. The Reactor Core Isolation Cooling system remains operable. A Fire Watch has been stationed to monitor for fire reflash. There were no injuries resulting from this event. There was no effect on Unit 1.
The licensee notified the NRC Resident Inspector and State and local government agencies.
Notified the following organizations: DHS SWO, DOE Ops Center, FEMA Ops Center, HHS Ops Center, NICC Watch Officer, USDA Ops Center, EPA EOC, FDA EOC, FEMA NWC, and Nuclear SSA.
* * * UPDATE FROM DAN BOYLAN TO DONALD NORWOOD AT 1812 EDT ON 04/05/15 * * *
The Alert was terminated at 1742 EDT.
The licensee notified the NRC Resident Inspector and State and local government agencies.
Notified R1DO (Kennedy), IRD (Gott), and NRR EO (Morris).
Notified the following organizations: DHS SWO, DOE Ops Center, FEMA Ops Center, HHS Ops Center, NICC Watch Officer, USDA Ops Center, EPA EOC, FDA EOC, FEMA NWC, and Nuclear SSA. | |