| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
01/17/2014 - 01/21/2014 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 49613 | Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: DARVIN DUTTRY
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 12/06/2013
Notification Time: 17:52 [ET]
Event Date: 12/06/2013
Event Time: 12:48 [EST]
Last Update Date: 01/17/2014 | 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 | 99 | Power Operation | Event Text HIGH PRESSURE COOLANT INJECTION SYSTEM INOPERABLE
"At 1248 EST, Unit 2 High Pressure Coolant Injection (HPCI) system was being tested for routine quarterly flow verification using surveillance test procedure SO-252-002. When HPCI turbine speed was lowered to approximately 2400 RPM, oscillations on turbine speed, flow and discharge pressure were observed. HPCI turbine speed was raised to approximately 2700 RPM and the oscillations stopped.
"Unit 2 HPCI system had been declared inoperable and LCO 3.5.1 entered at 1200 EST for the surveillance test. [This is a 14 day LCO.]
"Review by Engineering determined that cause of the oscillations warrant further evaluation and HPCI remains inoperable.
"HPCI is a single train Emergency Core Cooling Safety system. This event results in the loss of an entire safety function which requires an 8 hour ENS notification in accordance with 10CFR50.72(b)(3)(v).
"There are no other ECCS systems presently out of service."
The licensee notified the NRC Resident Inspector.
* * * RETRACTION FROM DARVIN DUTTRY TO JOHN SHOEMAKER AT 1201 EST ON 1/17/14 * * *
"NUREG-1022, Revision 3, states, 'if the retraction or cancellation of a report under this criterion is due to a revised operability determination, the retraction or cancellation should discuss the basis for why the operability determination was revised, and why it is believed that system operability was never lost (i.e., in lieu of the initial determination).'
"As indicated in the initial report, Engineering determined that the cause of the oscillations required further evaluation and HPCI remained inoperable. Additional evaluation by Engineering resulted in a conclusion that HPCI was OPERABLE with the observed oscillations at the low flow conditions. Details are as follows:
"HPCI speed/flow oscillations at low flow conditions can occur due to inherent instability at these conditions. This phenomenon is understood and documented in industry OE [Operating Experience], EPRI [Electric Power Research Institute] maintenance guidelines, and station procedures. HPCI system operation and control during the surveillance were as expected and demonstrated proper response and stable operation, with the only exception being the described oscillations at the low flow condition. This was confirmed by a review of the system response on the start-up traces. A system walkdown confirmed no abnormality with the control system equipment or governor setting. No tuning adjustments were considered to be necessary based on the low magnitude of the oscillations and their negligible impact on system operation. Unit 2 HPCI was declared OPERABLE and LCO 3.5.1 was cleared at 2308 [EST] on December 6, 2013.
"Based on the above additional information, PPL [Pennsylvania Power and Light] is retracting this report."
The licensee has notified the NRC Resident Inspector.
Notified the R1DO (Rogge). |
| Agreement State | Event Number: 49711 | Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: ASCEND PERFORMANCE MATERIALS OPERATIONS LLC
Region: 4
City: ALVIN State: TX
County:
License #: 06721
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: JIM DRAKE | Notification Date: 01/10/2014
Notification Time: 09:45 [ET]
Event Date: 01/09/2014
Event Time: [CST]
Last Update Date: 01/10/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
WAYNE WALKER (R4DO)
ANGELA MCINTOSH (FSME)
FSME EVENT RESOURCE (EMAI)
| Event Text AGREEMENT STATE REPORT INVOLVING STUCK SHUTTER ON LEVEL GAUGE
"On January 10, 2014, the Agency received a report from the licensee's Radiation Safety Officer (RSO) stating the shutter on a Ohmart Vega model SGLG gauge containing a 500 millicurie cesium - 137 source was found stuck in the open position. Open is the normal operation position of the gauge shutter. The RSO stated a contractor was performing a calibration of a level detector on January 9, 2014, when they could not get the gauge shutter to close. The contractor sprayed the shutter with a light oil and attempted to rotate the handle and operating arm. While trying to free the shutter, the operating arm separated from the gauge. The contractor was able to insert the operating rod into the gauge, but the shutter would not move. The manufacturer has been contacted to assist in the repair or replacement of the gauge. No exposure resulted from this event and the current position of the gauge shutter does not create any additional exposure risk to any personnel. A contact dose rate survey of the gauge was conducted and the highest reading observed was 1.2 millirem per hour. Additional information will be provided as it is received in accordance with SA-300."
Texas Incident Number: I-9145 |
| Power Reactor | Event Number: 49720 | Facility: HARRIS
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP
NRC Notified By: MIKE HERSHKOWITZ
HQ OPS Officer: HOWIE CROUCH | Notification Date: 01/13/2014
Notification Time: 13:09 [ET]
Event Date: 01/13/2014
Event Time: 10:22 [EST]
Last Update Date: 01/17/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
GEORGE HOPPER (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 EMERGENCY RESPONSE FACILITIES OUT OF SERVICE DUE TO PLANNED MAINTENANCE
"This is a non-emergency eight hour notification for a loss of Emergency Assessment Capability. This event is reportable in accordance with 10 CFR 50.72(b)(3)(xiii) because work activities affect the functionality of emergency response facilities. This condition does not affect the health and safety of the public or station employees.
"At approximately 1022 [EST] on January 13, 2014, planned maintenance activities began on the Emergency Operations Facility (EOF) heating ventilation and air conditioning (HVAC) system. The scope of the maintenance is to obtain samples of the charcoal filter. The planned work activity duration is expected to be approximately 20 hours ending on January 14, 2014. In addition, a multi-day (5 days) maintenance activity will begin on January 13, 2014 on the Technical Support Center (TSC) HVAC system, involving flow-balancing the system, which may involve intrusive maintenance during certain intervals. This intrusive maintenance will render the TSC HVAC system non-functional. This planned work activity is expected to be completed on January 17, 2014. The EOF and TSC HVAC systems will be restored periodically throughout this maintenance period.
"If an emergency is declared requiring emergency facility activation during this period, the emergency facilities will be staffed and activated using existing emergency planning procedures. If relocation of the emergency facilities becomes necessary, the Emergency Director will relocate the emergency response organization to an alternate location in accordance with applicable site procedures. The Emergency Response Organization team has been notified of the maintenance and the possible need to relocate during an emergency.
"An update will be provided once the EOF and TSC ventilation systems have been restored to normal operation and all planned maintenance is complete. The NRC Resident Inspector has been notified."
* * *UPDATE PROVIDED BY KEVIN ABELL TO JEFF ROTTON AT 1043 EST ON JANUARY 17, 2014 * * *
The planned maintenance is complete and the EOF and TSC have been restored to normal operation.
The licensee notified the NRC Resident Inspector.
Notified R2DO (King) |
| Power Reactor | Event Number: 49735 | Facility: FARLEY
Region: 2 State: AL
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: JOHN ANDREWS
HQ OPS Officer: CHARLES TEAL | Notification Date: 01/17/2014
Notification Time: 12:45 [ET]
Event Date: 01/17/2014
Event Time: 09:25 [CST]
Last Update Date: 01/17/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
MICHAEL F. KING (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 PYRO PANEL TAKEN OUT OF SERVICE FOR PLANNED MAINTENANCE
"At 0925 [CST] on January 17, 2014, the Unit 1 pyro panel (smoke detection panel) was removed from service for required maintenance. The pyro panel was declared non-functional when it was removed from service. Compensatory measures have been established for all affected areas except the Unit 1 Containment Building. Since a fire in Containment is an entry condition for the site's Emergency Plan, this is considered a loss of emergency assessment capability and is being reported per 10CFR50.72(b)(3)(xiii). Containment temperatures are being monitored while the pyro panel is out of service, however, this is not considered a satisfactory compensatory measure for maintaining effective assessment capability.
"The site NRC Resident Inspector has been notified."
* * * UPDATE FROM DARRIN GARD TO CHARLES TEAL AT 2202 EST ON 1/17/14 * * *
The pyro panel was restored to service as of 1650 CST. The licensee has notified the NRC Resident Inspector.
Notified R2DO (King). |
| Power Reactor | Event Number: 49736 | Facility: WATTS BAR
Region: 2 State: TN
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: HENRY TAYLOR
HQ OPS Officer: JOHN SHOEMAKER | Notification Date: 01/17/2014
Notification Time: 12:50 [ET]
Event Date: 01/17/2014
Event Time: 11:43 [EST]
Last Update Date: 01/17/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
MICHAEL F. KING (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 | N | 0 | Under Construction | 0 | Under Construction | Event Text OFFSITE NOTIFICATION DUE TO ONSITE DEATH OF AN EMPLOYEE
"On January 17, 2014, at approximately 0931 EST, with Watts Bar Nuclear Unit 1 at 100% power and Unit 2 under construction, an off duty security officer was found unresponsive in a personal vehicle in an owner controlled parking lot located outside of the Protected Area.
"An emergency medical team responded and the individual was transported off site to a nearby medical facility where he was pronounced dead at 1143 EST. The individual was not contaminated and there were no radiological or industrial safety issues associated with Watts Bar Nuclear Plant. Due to notification of local sheriff and OSHA, this report is submitted pursuant to 10 CFR 50.72(b)(2)(xi), as a notification to a government agency.
"NRC Senior Resident Inspector has been notified." |
| Power Reactor | Event Number: 49738 | Facility: SEQUOYAH
Region: 2 State: TN
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: RUSTY WHITEHEAD
HQ OPS Officer: CHARLES TEAL | Notification Date: 01/17/2014
Notification Time: 14:54 [ET]
Event Date: 01/17/2014
Event Time: 14:00 [EST]
Last Update Date: 01/17/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
MICHAEL F. KING (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 | 100 | Power Operation | 100 | Power Operation | Event Text FUEL OIL FOUND DURING CORE DRILLING
"On January 17, 2014, at 1400 EST Sequoyah (SQN) notified the Tennessee Department of Environment and Conservation (TDEC) of a condition that was identified on December 4, 2013, while conducting core samples. The core drilling contractor detected a petroleum odor, notified the SQN Environmental Group who observed the core drilling and confirmed a slight petroleum odor from a core boring in which water was detected at approximately 41 feet below the ground surface. At that time, as a result of the type of core drilling that was conducted, TVA could not verify if there were petroleum products in the groundwater.
"SQN obtained geoprobe boring samples to determine the extent and the depth of the petroleum. Petroleum product was detected in the soil between 30 and 35 feet in depth. This condition has been determined to be associated with a legacy diesel fuel oil leak at SQN in the 1990's and was previously reported. SQN previously completed a remediation project from 1992 - 2010, with oversight from TDEC. The petroleum product appears to be isolated at approximately 30 to 35 feet in depth, is in a perched water table not utilized for drinking water, and appears to be isolated to the diesel building area. To verify the petroleum product is isolated; TVA is conducting additional geoprobe boring to help define the limited area impacted by the legacy diesel fuel oil leak.
"The Sequoyah NRC Resident Inspectors have been notified." |
| Power Reactor | Event Number: 49739 | Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: ANGEL BRAY
HQ OPS Officer: CHARLES TEAL | Notification Date: 01/17/2014
Notification Time: 23:11 [ET]
Event Date: 01/17/2014
Event Time: 17:36 [CST]
Last Update Date: 01/17/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
| Person (Organization):
RICHARD SKOKOWSKI (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 91 | Power Operation | 0 | Cold Shutdown | Event Text TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO REACTOR PRESSURE BOUNDARY LEAKAGE
"Leakage into the Reactor Building Closed Cooling Water (RBCCW) system has been determined to be Reactor Pressure Boundary leakage as identified by the plant's Technical Specification [LCO 3.4.4]. Based on this, the LCO is not met and a plant shutdown is required. The shutdown commenced at 2029 CST.
"All of the leakage has been retained within the RBCCW system. There has been no radioactive release from the Monticello plant and all other systems remain operable and available. The unit continues to be operated in a safe and predictable fashion as it is being removed from service.
"The NRC Resident Inspector has been notified."
The leakage rate was 0.12 gallons per minute at power. |
| Power Reactor | Event Number: 49740 | Facility: SOUTH TEXAS
Region: 4 State: TX
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: PHIL STONE
HQ OPS Officer: DANIEL MILLS | Notification Date: 01/18/2014
Notification Time: 05:56 [ET]
Event Date: 01/18/2014
Event Time: 04:01 [CST]
Last Update Date: 01/18/2014 | Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
| Person (Organization):
RAY KELLAR (R4DO)
JENNIFER UHLE (NRR)
MARC DAPAS (R4RA)
SAMSON LEE (NRR)
JEFFERY GRANT (IRD)
|
| 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 UNUSUAL EVENT DUE TO FIRE IN THE PROTECTED AREA
"At 0346 CST [the Unit 1 control room] received a fire alarm in the plant computer room. Upon investigation [the licensee] discovered [the plant computer] room with heavy smoke present and the halon system actuated. [Plant operators] entered '0P0P04-ZO-0008, Fire and Explosion'. Entered Unusual Event at 0401 CST. Fire brigade present at Unit 1 electrical auxiliary building. At 0412 CST the fire was declared to be under control with no visible signs of flame noticed by the fire brigade. Unusual Event based on HU2 (fire or explosion) in the (Protected Area or Switchyard) which affects normal plant operations."
At 0446 CST the fire was declared to be extinguished. No plant equipment or indications were affected.
The licensee has notified the NRC Resident Inspector, the State of Texas, and other local authorities.
Notified DHS SWO, FEMA Operations Center, NICC Watch Officer, and NuclearSSA via e-mail.
* * * UPDATE FROM TRIPP FRAHM TO DANIEL MILLS AT 0957 EST ON 1/18/14 * * *
"At 0957 EST, [on 1/18/14, the] Unusual Event [was] terminated. Fire damage assessment not complete. Working with site engineering, fire protection, and maintenance personnel to restore all fire detection and protection systems. Continuous fire watch being maintained. Priority is to restore fire detection and protection systems to affected area, followed by repairs to damaged equipment."
The licensee has notified the NRC Resident Inspector, the State of Texas, and other local authorities.
Notified R4DO (Keller), NRR (Uhle), R4RA (Dapas), NRR EO (Lee), and IRD MOC (Grant).
Notified DHS SWO, FEMA Operations Center, NICC Watch Officer, and NuclearSSA via e-mail. |
| Power Reactor | Event Number: 49741 | Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: JACK EARSLEY
HQ OPS Officer: DANIEL MILLS | Notification Date: 01/18/2014
Notification Time: 07:45 [ET]
Event Date: 01/18/2014
Event Time: 03:38 [CST]
Last Update Date: 01/20/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
RICHARD SKOKOWSKI (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 25 | Power Operation | 0 | Hot Shutdown | Event Text OFFSITE NOTIFICATION DUE TO DISCHARGE CANAL TEMPERATURE DROP
"At 0338 CST, Xcel Energy Environmental Services made a report to the State of Minnesota due to cooling water return to the Mississippi River via the plant's discharge canal dropping by more than 5 deg F per hour. The cause of the temperature drop was due to a required time limited reactor shut down. The reactor is currently shut down with all systems responding as expected.
"This notification is being made under 10 CFR 50.72(b)(2)(xi) based on a notification to another government agency.
"The NRC Resident Inspector has been notified"
* * * UPDATE FROM JON LAUDENBACH TO VINCE KLCO ON 1/20/14 AT 1259 EST * * *
"At 1130 EST on 1/20/2014, XCEL Energy Environmental Services made a report to the State of Minnesota (Minnesota Pollution Control Agency and the Minnesota Department of Natural Resources) due to the recorded total fish loss (207) as a result of the Monticello Plant's discharge canal temperature change per above.
"This is an update notification only and has no safety significance and no impact on the health and safety of the general public."
The licensee notified the NRC Resident Inspector.
Notified the R3DO (Skokowski). |
| Power Reactor | Event Number: 49742 | Facility: HARRIS
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP
NRC Notified By: CARMINE MONTANA
HQ OPS Officer: DANIEL MILLS | Notification Date: 01/18/2014
Notification Time: 10:47 [ET]
Event Date: 01/18/2014
Event Time: 10:16 [EST]
Last Update Date: 01/18/2014 | Emergency Class: ALERT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
MICHAEL F. KING (R2DO)
ERIC LEEDS (NRR)
VICTOR McCREE (R2RA)
JEFFERY GRANT (IRD)
ELIOT BRENNER (OPA)
SAMSON LEE (NRR)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | M/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text ALERT DECLARED DUE TO FIRE IN 480V BUS
"[At 1016 EST, an] Alert [was declared] based on EAL # HA 2.1 Fire or explosion resulting in either: visible damage to any table H-1 structure or system/component required for safe shutdown of the plant, or control room indication of degraded performance of any safe shutdown structure, system, or component within any table H-1 area.
"Fire in 480V bus 1D2. Reactor was manually tripped"
480 VAC safety related transformer fire in switchgear room. Plant reduced power and tripped the reactor manually. Reactor trip was uncomplicated. Fire was extinguished when the 480 VAC bus was de-energized.
The licensee has notified the NRC Resident Inspector, the State of North Carolina, and other local authorities.
Notified DHS SWO, DOE Ops Center, FEMA Operations Center, HHS Ops Center, NICC Watch Officer, USDA Ops Center, EPA EOC, and NuclearSSA via e-mail.
* * * UPDATE FROM JOEL DUHON TO JOHN SHOEMAKER AT 1602 EST ON 1/18/14 * * *
Harris Nuclear Plant secured from the Alert at 1551 EST, on 1/18/14. The plant is stable, the fire is out, the TSC and EOF have been secured and plant recovery has been transferred to the outage control center.
There were no personnel injuries or radiological releases.
Radiation monitor RM-*1TS-3653C (Technical Support Center Radiation Monitor) is out of service.
The licensee has notified the NRC Resident Inspector.
Notified the R2DO (King), R2RA (McCree), NRR (Leeds), IRD MOC (Grant), OPA (Brenner), NRR EO (Lee)
Notified DHS SWO, DOE Ops Center, FEMA Operations Center, HHS Ops Center, NICC Watch Officer, USDA Ops Center, EPA EOC, and NuclearSSA via e-mail. |
| Power Reactor | Event Number: 49743 | Facility: COMANCHE PEAK
Region: 4 State: TX
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DANNY BRADFORD
HQ OPS Officer: CHARLES TEAL | Notification Date: 01/18/2014
Notification Time: 12:18 [ET]
Event Date: 01/18/2014
Event Time: 08:40 [CST]
Last Update Date: 01/18/2014 | 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):
RAY KELLAR (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | A/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text REACTOR TRIP DUE TO TURBINE TRIP
"At 0840 [CST], Comanche Peak NPP [CPNPP] Unit 1 turbine tripped causing a reactor trip. All rods inserted. No evolutions were in progress at time of trip. The cause of the trip is under investigation. A Generator Negative Sequence Current High Alarm was received immediately prior to turbine trip.
"Both Motor Driven Auxiliary Feed Water Pumps and the Turbine Driven Auxiliary Feed Water Pump started in response to Steam Generator Lo-Lo Levels.
"Currently, Unit 1 is being maintained in Hot Standby (Mode 3) in accordance with Integrated Plant Operating Procedure IPO-007A 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).
"Normal plant response was observed and all systems actuated as expected. No radiological release is in progress.
"There was no impact to CPNPP Unit 2, and off-site power remains available."
The licensee has notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 49744 | Facility: FARLEY
Region: 2 State: AL
Unit: [ ] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: RICK LULLING
HQ OPS Officer: CHARLES TEAL | Notification Date: 01/18/2014
Notification Time: 14:48 [ET]
Event Date: 01/18/2014
Event Time: 10:20 [CST]
Last Update Date: 01/20/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
MICHAEL F. KING (R2DO)
|
| 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 UNIT 2 PYRO PANEL NON-FUNCTIONAL DUE TO UNKNOWN EQUIPMENT PROBLEMS
"At 10:20 [CST] on January 18, 2014, the Unit 2 Pyro Panel (fire/smoke detection panel) was declared non-functional due to an unknown equipment problem. Compensatory measures (e.g. continuous roving fire watches) have been established for all affected areas with the exception of the Unit 2 Containment Building. Containment fire watches have been established per the FSAR, which includes monitoring various temperatures, pressures, and other parameters for Containment, and systems associated with containment. However, this is not considered a satisfactory compensatory measure for maintaining effective assessment capability. Since a fire in Containment is an entry condition for the site's Emergency Plan, this is considered a loss of emergency assessment capability, and is being reported per 10CFR50.72(b)(3)(xiii).
"The NRC Senior Resident Inspector has been informed."
* * * UPDATE FROM RICK LULLING TO DANIEL MILLS AT 0700 EST ON 1/20/14 * * *
"At 0404 CST on 1/20/14 the Unit 2 Pyro panel was declared functional following the replacement of the fire indicating unit (FIU) and the power supply, and successful post maintenance testing. The emergency assessment capability for the site's Emergency Plan has been fully restored concerning a Containment fire."
The licensee notified the NRC Resident Inspector.
Notified R2DO (King). |
| Power Reactor | Event Number: 49745 | Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [ ] [2] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: STEPHEN SEILHYMER
HQ OPS Officer: DANIEL MILLS | Notification Date: 01/20/2014
Notification Time: 05:28 [ET]
Event Date: 01/20/2014
Event Time: 02:16 [CST]
Last Update Date: 01/20/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
RICHARD SKOKOWSKI (R3DO)
|
| 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 LOSS OF SHIELD BUILDING GASEOUS RADIATION MONITOR
"2R-22, Unit 2 Shield Building Ventilation Gaseous Radiation Monitor was removed from service at 0216 CST on 01/20/2014 due to a broken belt. 2R-22 is important to the site's emergency plan for Notification of Unusual Event and Alert classifications in the event of an unplanned gaseous release from the Unit 2 Shield Building stack. It is also used for offsite dose projection calculations. There is no backup instrumentation or compensatory measure to perform these functions while 2R-22 is out of service. This results in a loss of emergency assessment capability, thus is reportable per 10CFR 50.72(b)(3)(xiii).
"2R-22 readings were normal prior to the equipment failure. Unit 2 Shield Building Ventilation Stack is also monitored by high range monitor, 2R-50, which is used for the same purpose in Site Area or General Emergency classifications. 2R-50 is being monitored and is indicating normal values. This event did not result in the unplanned release of radioactivity to the environment and did not adversely affect the safe operation of the plant or health and safety of the public.
"Immediate efforts are underway to repair 2R-22.
"The licensee has notified the NRC Resident Inspector." |
| Power Reactor | Event Number: 49746 | Facility: PERRY
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: DAVID DUESING
HQ OPS Officer: HOWIE CROUCH | Notification Date: 01/21/2014
Notification Time: 02:19 [ET]
Event Date: 01/21/2014
Event Time: 01:40 [EST]
Last Update Date: 01/21/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
RICHARD SKOKOWSKI (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 OFFSITE NOTIFICATION DUE TO TRITIUM DISCOVERED IN GROUNDWATER
"This notification is being made pursuant to [10 CFR] 50.72(b)(2)(xi), notification of other government agency. Notification to other government agency, State of Ohio, was made at 0140 [EST] on 1/21/14.
"At 1310 on 1/20/2014, a leak was identified on a feed water Venturi. In response to the water leak, samples were taken to check for the spread of tritium. A positive result for tritium was identified in the under drain system in the Auxiliary Building which requires communications as part of the NEI ground water protection initiative. The positive sample results were obtained at 2330 on 1/20/14. Actions are in progress stop the leak (perform leak injection)."
The EPA limit for groundwater is 20,000 pCi/l. The samples taken by the licensee indicated 46,000 pCi/l.
The licensee has notified the NRC Resident Inspector and will notify local counties. |
| Power Reactor | Event Number: 49747 | Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: STEPHEN SPEIRS
HQ OPS Officer: HOWIE CROUCH | Notification Date: 01/21/2014
Notification Time: 05:48 [ET]
Event Date: 01/20/2014
Event Time: 22:30 [CST]
Last Update Date: 01/21/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
RICHARD SKOKOWSKI (R3DO)
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| 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 TECHNICAL SUPPORT CENTER EMERGENCY DIESEL GENERATOR OUT OF SERVICE
"On 1/20/14 at 2230 CST, an interruption in the control power to the TSC diesel generator was discovered. Investigation revealed a blown fuse supplying the TSC diesel generator control panel. The blown fuse has resulted in the TSC diesel generator starting batteries depleting. The fuse has since been replaced, and the TSC diesel generator starting batteries are currently recharging. The TSC diesel generator remains non-functional until the starting batteries are charged. This notification is being made in accordance with 10 CFR 50.72(b)(3)(xiii) due to the unplanned loss of the backup power supply to the Emergency Response Facility (ERF). The NRC Resident Inspector has been informed. An update notification will be made when the TSC diesel generator has been restored to fully functional status." | |