| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
07/11/2014 - 07/14/2014 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 50254 | Rep Org: OHIO BUREAU OF RADIATION PROTECTION
Licensee: HALLIBURTON ENERGY SERVICES
Region: 3
City: DUNCAN State: OH
County:
License #: 31210990018
Agreement: Y
Docket:
NRC Notified By: STEPHEN JAMES
HQ OPS Officer: CHARLES TEAL | Notification Date: 07/03/2014
Notification Time: 11:44 [ET]
Event Date: 06/28/2014
Event Time: [EDT]
Last Update Date: 07/03/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
AARON MCCRAW (R3DO)
FSME EVENT RESOURCE (EMAI)
| Event Text AGREEMENT STATE REPORT - FIXED INDUSTRIAL GAUGES DAMAGED DURING FIRE
The following was received from the State of Ohio via email:
"On 6/29/14 at 1330 EDT, ODH [Ohio Department of Health] received a call that there was a fire at an oil well location in Hannibal, Ohio, Monroe County. A hydraulic line on a piece of drilling equipment failed, spilling hydraulic fluid onto a hot engine, igniting the fluid. The fluid continued to rapidly leak, which caused the fire to spread. When the fire department arrived on scene, the well pad was reported to be fully engulfed in flames. The drilling company has reportedly lost 20 vehicles in the fire. There were three density gauges on site, two (2) of which were mounted on equipment and one was mounted on the well. There were no detections of radiation at that time.
"On 6/30/14 two ODH inspectors were dispatched to the site to verify that the gauges were secure and had not suffered damage from the fire. Upon arrival the ODH inspectors were not allowed to go onto the drilling pad area because it is still being cleared of potentially explosive hazardous chemicals and unexploded ordinance (used in fracking process). The inspectors attended a meeting regarding status of the site and were briefed by representatives from Halliburton (the licensee). The gauges involved were two (2) Model 100-SD, containing 120 mCi of Cs-137 each, and one (1) Model 55-SD containing 66 mCi of Cs-137.
"Halliburton was able to conduct an initial visual inspection and survey of the gauges. They stated that there did not appear to be any significant visible damage and the devices appeared to be intact. They recorded readings of 0.5 mR/hr on contact for the Model 100-SD gauges, and 0.3 mR/hr on contact on for the Model 55-SD gauge. Wipe tests were taken by the licensee to check for leakage and the field survey indicated no contamination. The wipes were sent to a laboratory for further analysis. Licensee personnel will put up warning signs and barriers around the gauges once the site is safe for other than emergency operations. It is expected to be several days before the site is determined to be safe enough for any movement or removal of the devices.
"On 7/2/14 the licensee was granted permission from the site manager to remove the gauges. All three gauges were removed without incident, and appeared to be intact (although scorched on the exterior from the fire). There were no incidents during the removal and no radiation readings recorded above those originally reported. The three gauges were placed in over packs, with proper labels and shipping papers, and were sent to the Halliburton headquarters in Texas for further evaluation."
Ohio Reference Number: ODH 2014-017. |
| Agreement State | Event Number: 50255 | Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: TERRACON CONSULTANTS INC
Region: 4
City: OLATHE State: KS
County:
License #: LA-5382-L01 A
Agreement: Y
Docket:
NRC Notified By: JOSEPH NOBLE
HQ OPS Officer: CHARLES TEAL | Notification Date: 07/03/2014
Notification Time: 16:46 [ET]
Event Date: 07/01/2014
Event Time: 14:30 [CDT]
Last Update Date: 07/03/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
BOB HAGAR (R4DO)
FSME EVENT RESOURCE (EMAI)
| Event Text AGREEMENT STATE REPORT - TROXLER MOISTURE/DENSITY GAUGE RUN OVER BY BULLDOZER
The following was received from the State of Louisiana via email:
"On July 2, 2014, the CRSO [Corporate Radiation Safety Officer], for Terracon Consultants (TCI) notified LDEQ [Louisiana Department of Environmental Quality] that a moisture density gauge being used at one of their projects was run over by a bulldozer.
"The source was left unattended when a bulldozer ran over the gauge and damaged the housing. They are conducting an investigation to determine the cause of the incident. It appears that it was human error.
"The sources were leak tested and TCI is waiting for the results of the test. The unit was surveyed and it appears the sources were not leaking. Results will be forwarded to NMED as an update when the information is obtained.
"All equipment involved is isolated and is not a threat to the public. There is no threat to TCI personnel and it appears to be safe.
"The damaged gauge was a Troxler, Model 3430, S/N 26346, loaded with 8 mCi of Cs-137 and 40 mCi of Am-241/Be. The gauge housing was damaged, but there was no indication the radioactive sources were compromised or leaking. The sources were isolated and leak tested." |
| Agreement State | Event Number: 50256 | Rep Org: FLORIDA BUREAU OF RADIATION CONTROL
Licensee: TALLAHASSEE MEMORIAL CANCER CENTER
Region: 1
City: TALLAHASSEE State: FL
County:
License #: 0416-2
Agreement: Y
Docket:
NRC Notified By: VICTOR GORETSKY
HQ OPS Officer: DANIEL MILLS | Notification Date: 07/03/2014
Notification Time: 17:21 [ET]
Event Date: 06/26/2014
Event Time: [EDT]
Last Update Date: 07/03/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
JONATHAN BARTLEY (R2DO)
FSME EVENTS RESOURCE (EMAI)
AARON MCCRAW (R3DO)
RAY MCKINLEY (R1DO)
|
| This material event contains a "Less than Cat 3 " level of radioactive material. | Event Text AGREEMENT STATE REPORT - MISPLACED IODINE 125 SOURCE FOUND IN SHIPPING CASE
The following was received from the State of Florida via email:
"A well chamber (HDR1000+, s/n A980392) was shipped to University of Wisconsin-Madison from Tallahassee Memorial Cancer Center Tallahassee FL. It arrived inside a case which also contained three source holders and an electrometer. An I-125 source was found on the bottom of the case on the foam inserts.
"Due to low exposure rate of the source (about two times background on contact) it was not detected by the monitoring system, but discovered visually. The UWADCL [University of Wisconsin Accredited Dosimetry Calibration Laboratory] received equipment on 6/26/2014. Calibration was completed on 7/2/2014. The shipper has been informed by phone and email."
Florida Incident #: FL14-062
THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL
Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf |
| Agreement State | Event Number: 50257 | Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: RAMMING PAVING COMPANY
Region: 4
City: AUSTIN State: TX
County:
License #: 04666
Agreement: Y
Docket:
NRC Notified By: KAREN BLANCHARD
HQ OPS Officer: DANIEL MILLS | Notification Date: 07/03/2014
Notification Time: 22:23 [ET]
Event Date: 07/03/2014
Event Time: 16:00 [CDT]
Last Update Date: 07/07/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
BOB HAGAR (R4DO)
MEXICO (FAX)
FSME EVENT RESOURCE (EMAI)
|
| This material event contains a "Less than Cat 3 " level of radioactive material. | Event Text AGREEMENT STATE REPORT - LOST MOISTURE/DENSITY GAUGE
The following was received from the State of Texas via email:
"On July 3, 2014, the licensee notified the Agency [Texas Department of Health] that one of its technicians left the licensee's facility in Austin, Texas, to transport a Troxler Model 4640 moisture/density gauge containing an 8 milliCurie cesium-137 source to the licensee's facility in Buda, Texas. The technician failed to properly secure the gauge for transport. When the technician arrived in Buda, he found the tailgate on pickup was down and the gauge was missing. The licensee retraced the technician's route of travel and found a water jug that had also been in the back of the truck near the licensee's Austin facility, but the gauge was not located. The licensee reported that the device (source rod handle) was not locked. The licensee reported that there were no locks on the transport case lid. More information will be provided as it is obtained in accordance with SA-300."
* * * UPDATE FROM KAREN BLANCHARD TO VINCE KLCO ON 7/7/2014 AT 1144 EDT * * *
The following update was received by the State of Texas by email:
"Reporting criteria changed, as the only source in device (8 milliCurie cesium-137) is less than 1,000 times greater than Appendix C values and therefore does not meet 20.2201(a)(1)(i) immediate reporting criteria. The incident does meet 20.2201(a)(1)(ii) and further information will be provided in accordance with SA-300."
Notified the R4DO (Kellar) and FSME Event Resource via email.
Texas Incident # I-9211 |
| !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 50261 | Facility: OYSTER CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-2
NRC Notified By: JOSHUA MCGUIRE
HQ OPS Officer: VINCE KLCO | Notification Date: 07/07/2014
Notification Time: 22:12 [ET]
Event Date: 07/07/2014
Event Time: 20:40 [EDT]
Last Update Date: 07/11/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
ANNE DeFRANCISCO (R1DO)
JOHN LUBINSKI (NRR)
JEFFERY GRANT (IRD)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 90 | Power Operation | 90 | Power Operation | Event Text TECHNICAL SPECIFICATION REQUIRED SHUTDOWN
"On July 7, 2014 at approximately [2040 EDT], an issue was discovered with currently removed Electromatic Relief Valves (EMRVs) that calls the operability of the currently installed EMRVs into question. Based on this new information, all 5 of the currently installed EMRVs were conservatively declared inoperable. With the potential of 5 EMRVs inoperable a Technical Specification shutdown is required under Technical Specification 3.4.b, whereby reactor pressure shall be reduced to 110 psig or less within 24 hours. This event is immediately reportable under:
"50.72(b)(2)(i), 'The initiation of any nuclear plant shutdown required by the plant's Technical Specifications.'
"50.72(b)(3)(v)(D), 'Any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to: (D) Mitigate the consequences of an accident.'"
The licensee notified the NRC Resident Inspector. The licensee will notify the State of New Jersey and issue a press release.
* * * RETRACTION AT 1745 EDT ON 7/11/2014 FROM CHARLES SPAGNUOLO TO MARK ABRAMOVITZ * * *
"The original concern and July 7, 2014 EN [report] was caused by abnormal wear found on removed Electromatic Relief Valve actuators. However, on July 8, 2014, upon completion of in situ testing as well as visual examination of the installed EMRV actuators, it was determined that the 5 currently installed EMRVs were fully operable and capable of performing their safety function. Therefore, Oyster Creek is retracting the notifications made under 50.72(b)(2)(i) and 50.72(b)(3)(v)(D)."
The licensee notified the NRC Resident Inspector and the State will be notified. The licensee will be issuing a press release.
Notified the R1DO (DeFrancisco). |
| Power Reactor | Event Number: 50270 | Facility: OYSTER CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-2
NRC Notified By: JOHN DEVENNEY
HQ OPS Officer: JOHN SHOEMAKER | Notification Date: 07/11/2014
Notification Time: 05:17 [ET]
Event Date: 07/11/2014
Event Time: 03:14 [EDT]
Last Update Date: 07/11/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
| Person (Organization):
ANNE DeFRANCISCO (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | M/R | Y | 55 | Power Operation | 0 | Hot Shutdown | Event Text MANUAL SCRAM DUE TO LOSS OF MAIN CONDENSER VACUUM
"Today at approximately 0312 [EDT on 7/11/14], during a planned reactor power ascension with reactor power at approximately 55 percent of rated thermal power, main condenser vacuum began to lower. In accordance with the abnormal operating procedure for degrading vacuum, Operators inserted a manual scram of the reactor at 0314 [EDT]. The cause of the degraded vacuum is currently under investigation.
"All rods inserted into the core and all systems functioned as expected during the scram. No electromatic (EMRVs) or safety relief valves lifted during the transient.
"This event is reportable within 4 hours per 10CFR50.72(b)(2)(iv)(B) - any event or condition that results in actuation of the reactor protection system (RPS) when the reactor is critical except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation."
The scram was uncomplicated, normal offsite power is available, and plant is being cooled down to cold shutdown. The cause of the degraded condenser vacuum is suspected condenser boot degradation.
The licensee has informed the NRC Resident Inspector. |
| Part 21 | Event Number: 50272 | Rep Org: NUCLEAR LOGISTICS INC
Licensee: NUCLEAR LOGISTICS INC
Region: 4
City: FT WORTH State: TX
County:
License #:
Agreement: Y
Docket:
NRC Notified By: TRACY BOLT
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 07/11/2014
Notification Time: 14:15 [ET]
Event Date: 03/27/2014
Event Time: [CDT]
Last Update Date: 07/11/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
| Person (Organization):
DAVID HILLS (R3DO)
PART-21 GROUP (EMAI)
| Event Text PART-21 NOTIFICATION - ASSEMBLY ERRORS DURING BREAKER REFURBISHMENT
The following is a summary of the information provided via facsimile:
"On March 27, 2014, at Exelon-Dresden Station, plant personnel identified that breaker UTC # 1185084 (3B CCSW Pump Breaker) was in the CLOSED condition, but did not indicate CHARGED. The breaker was last CLOSED successfully on March 19, 2014. The breaker charges the closing springs after a CLOSE operation.
"The breaker was OPENED and removed from service on 3/28/14, Dresden notified [Nuclear Logistic, Inc.] NLI on 3/28/14 of the issue and the breaker was returned to NLI on RMA 351022093.
"NLI performed a failure analysis on the breaker. The spring clamp cam 12mm nylon insert lock nut was not properly tightened on either side, resulting in insufficient clamping force of the cam on the jackshaft. In addition to the lock nuts not being sufficiently tightened, the closing springs were installed on the wrong side. There is a left and a right spring as identified by a red mark on the left spring. The left side spring is the shorter spring, and it was installed on the right side. Further evaluation by NLI determined that this may have been a contributing factor to the failure after the closing spring clamp started to move off the jackshaft.
"The presence of the under torque nuts resulted in insufficient clamping force, allowing the clamp to move off the jackshaft. The springs being on the wrong sides began to exert excessive force to the cam as it rotated, and after many operations, it had slipped enough to become partially dislodged from the jackshaft. This bent the spring guide arms, preventing the rotation of the jackshaft to the CHARGED position and did not allow the motor cutoff switch to activate. The result was the breaker did not CHARGE and the motor continued to run until it burned up."
Several AHMG breakers (1200 and 2000A) for Dresden and Quad Cities were refurbished by Nuclear Logistics, Inc from 2008 to March 2014. At least one breaker was found with insufficient cam nut spring torque and had the two closing springs installed improperly. |
| Power Reactor | Event Number: 50273 | Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: GRANT FLYNN
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 07/11/2014
Notification Time: 15:28 [ET]
Event Date: 07/11/2014
Event Time: 08:23 [EDT]
Last Update Date: 07/11/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
ANNE DeFRANCISCO (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 LOSS OF ASSESSMENT CAPABILITY - LOSS OF POWER TO THE PLANT PROCESS COMPUTER
"At 0823 EDT on Friday, July 11, 2014, the Pilgrim Nuclear Power Station (PNPS) determined that the plant process computer and, therefore, the in-plant Safety Parameter Display System (SPDS) was not functioning as designed due to a loss of power. The SPDS provides numerous plant parameters, some of which are credited for emergency assessment capability. The site has determined that this constitutes a major loss of assessment capability. Immediate actions were taken to restore the system to functional status and applicable plant procedures were entered to determine temporary mitigating actions. Power was subsequently restored at approximately 1030 EDT via an alternate supply, and SPDS has been restored to normal operation.
"This event had no impact on the health and/or safety of the public.
"This notification is conservatively being made in accordance with 10 CFR 50.72 (b)(3)(xiii).
"There is no impact to plant operations."
The licensee notified the NRC Resident Inspector and will notify the State. |
| Power Reactor | Event Number: 50275 | Facility: BEAVER VALLEY
Region: 1 State: PA
Unit: [1] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: JOHN KAMINSKAS
HQ OPS Officer: DONG HWA PARK | Notification Date: 07/11/2014
Notification Time: 18:00 [ET]
Event Date: 07/11/2014
Event Time: 15:00 [EDT]
Last Update Date: 07/11/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
ANNE DeFRANCISCO (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text OFFSITE NOTIFICATION MADE FOR HAZARDOUS CHEMICAL SPILL
"At 1415 [EDT] the Control Room received a report that a refrigeration unit had failed and was spilling coolant (Ethylene Glycol) on the floor of an office building inside the protected area. At 1440 [EDT] the leak was isolated. It is estimated that approximately 10 gallons of Ethylene Glycol was introduced to the floor drains which ultimately lead to the environment. This is not a Reportable Quantity for the Environmental Protection Agency but the Pennsylvania Department of Environmental Protection was notified in accordance with the Pennsylvania Clean Streams Law at 1500 hours. The spill was contained and cleanup is complete.
"This condition is being reported pursuant to 10 CFR 50.72 (b)(2)(xi).
"The NRC Resident Inspector has been notified." |
| Fuel Cycle Facility | Event Number: 50276 | Facility: GLOBAL NUCLEAR FUEL - AMERICAS
RX Type: URANIUM FUEL FABRICATION
Comments: LEU CONVERSION (UF6 TO UO2)
LEU FABRICATION
LWR COMMERICAL FUEL
Region: 2
City: WILMINGTON State: NC
County: NEW HANOVER
License #: SNM-1097
Agreement: Y
Docket: 07001113
NRC Notified By: PHILLIP OLLIS
HQ OPS Officer: DONG HWA PARK | Notification Date: 07/13/2014
Notification Time: 16:10 [ET]
Event Date: 07/12/2014
Event Time: 17:30 [EDT]
Last Update Date: 07/13/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
PART 70 APP A (b)(1) - UNANALYZED CONDITION
| Person (Organization):
ANTHONY MASTERS (R2DO)
DENNIS DAMON (NMSS)
| Event Text ITEMS RELIED ON FOR SAFETY ASSOCIATED WITH THE DRY SCRAP RECYCLE OPERATIONS NOT MEETING REQUIREMENTS
"It was determined at 1200 [EDT] on 7/13/14, that one of the Items Relied on for Safety (IROFS) associated with the Dry Scrap Recycle operation failed to meet performance requirements. At approximately 1730 [EDT] on July 12, 2014, a potable water line (1/2 inch poly) failed and resulted in a release of approximately 10 gallons of water into the area. The leak was contained and cleaned up. However, this water release is a failure of IROFS 900-03 for Moderation Restriction.
"Although the second IROFS (Process Equipment Barriers IROFS 301) prevented moderation intrusion into equipment and containers, it alone was not sufficient to meet performance requirements.
"The affected equipment has been shut down. At no time was an unsafe condition present. Special Nuclear Material (SNM) was not impacted by the leak. No water escaped the area or travelled to non-contaminated areas. While this did not result in an unsafe condition, the event is being reported pursuant with the reporting requirements of 10CFR70 Appendix A(b)(1) within 24 hours of discovery.
"Additional corrective actions, extent of condition, and the cause of the failure are being determined."
The licensee will notify NRC Region 2, State of North Carolina Radiation Protection, and New Hanover County Emergency Management. |
| Power Reactor | Event Number: 50277 | Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [1] [2] [3]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: NEEL SHUKLA
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 07/13/2014
Notification Time: 21:35 [ET]
Event Date: 07/13/2014
Event Time: 17:40 [CDT]
Last Update Date: 07/13/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
ANTHONY MASTERS (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 | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text OFFSITE NOTIFICATION OF A ONE GALLON DIESEL FUEL OIL SPILL
"On 07/13/2014 at approximately 1740 [CDT], it was reported that oil sheen was visible in the intake fore bay. Upon further investigation it was determined that a high cold water channel level had caused diesel fuel oil to wash free from an oil drain device from the channel diesel fire pump into the intake fore bay. This oil spill is reportable to the EPA (National Response Center under 40CFR112). Notification to the National Response Center was made at 1750 [CDT]. Notification number is 1088951.
"A total of <1 gallon was reported to enter US waters. The source of the leak into the intake fore bay and cold water channel has been stopped. All reportable oil spillage has been contained in the intake fore bay (considered US waters).
"Additional notifications have been made to Alabama Emergency Management.
"This event requires a 4 hour report pursuant to 10 CFR 50.72(b)(2)(xi), 'Any event or situation, related to the health and safety of the public or onsite personnel, or protection of the environment, for which a news release is planned or notification to other government agencies has been or will be made.'
"The NRC Resident Inspector has been notified."
Notified DOE, EPA, USDA, HHS, and FEMA. |
| Power Reactor | Event Number: 50278 | Facility: WATTS BAR
Region: 2 State: TN
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MATTHEW ROBERTSON
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 07/13/2014
Notification Time: 23:13 [ET]
Event Date: 07/13/2014
Event Time: 19:37 [EDT]
Last Update Date: 07/13/2014 | 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):
ANTHONY MASTERS (R2DO)
|
| 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 MANUAL REACTOR TRIP DUE TO AUTOMATIC FEEDWATER HEATER ISOLATION
"On July 13, 2014 at 1937 [EDT], Watts Bar Nuclear Plant Unit 1 reactor was manually tripped due to automatic isolation of all low pressure feedwater heaters. Concurrent with the reactor trip the Auxiliary Feedwater system actuated as designed.
"All Control and Shutdown rods fully inserted. All safety systems responded as designed. The unit is currently stable in Mode 3, with decay heat removal via Auxiliary Feedwater, steam dumps and the main condenser. The station is in a normal shutdown electrical alignment.
"The cause is currently under investigation.
"This is being reported under 10CFR 50.72(b)(3)(iv)(A) and 10CFR 50.72 (b)(2)(iv)(B).
"The NRC Senior Resident [Inspector] has been notified."
Initial indications are that a level switch failed on the #7 heater drain tank which caused the heater drain tank pumps to trip. When the high level tank setpoint was reached, the feedwater system isolated. | |