| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
03/17/2014 - 03/18/2014 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 49881 | Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: UMASS MEMORIAL HEALTH CARE
Region: 1
City: WORCESTER State: MA
County:
License #: 60-0096
Agreement: Y
Docket:
NRC Notified By: MICHAEL WHALEN
HQ OPS Officer: DONG HWA PARK | Notification Date: 03/07/2014
Notification Time: 08:27 [ET]
Event Date: 03/05/2014
Event Time: [EST]
Last Update Date: 03/07/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
FRED BOWER (R1DO)
FSME EVENTS RESOURCE (EMAI)
| Event Text AGREEMENT STATE REPORT - UNDER DOSE INVOLVING YTTRIUM 90 MICROSPHERES
The following information was received by email:
"On March 6, 2014, UMass Memorial Health Care (license number 60-0096) reported [to the Massachusetts Radiation Control Program] that on March 5, 2014 they had under dosed a patient by more than 20% using Y-90 microspheres. Further pertinent data is:
"Prescribed Activity: 26.4 mCi of Y-90 (in one fraction injection)
Delivered Activity: 20.4 mCi of Y-90 (more than 20% different from prescribed)
"Resulting in:
Prescribed Liver dose: = 32.6 Gy
Delivered Liver dose: = 25.2 Gy
Dose difference in organ: = 740 rads (i.e., greater than 50 rem and 20% difference)
"Note Also:
Effective dose (requested): 32.6 Gy * 0.04 = 1.3 Sv
Effective dose (delivered): 25.2 Gy * 0.04 = 1.0 Sv
Effective dose difference: 1.3-1.0=0.3 Sv = 30 rem (greater than 5 rem difference)"
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: 49883 | Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: ULRICH ENGINEERS INC
Region: 4
City: HOUSTON State: TX
County:
License #: 03950
Agreement: Y
Docket:
NRC Notified By: IRENE CASARES
HQ OPS Officer: PETE SNYDER | Notification Date: 03/07/2014
Notification Time: 16:52 [ET]
Event Date: 02/18/2014
Event Time: [CST]
Last Update Date: 03/07/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
TOM ANDREWS (R4DO)
FSME EVENT RESOURCE (EMAI)
ILTAB (EMAI)
MEXICO (FAX)
|
| This material event contains a "Less than Cat 3 " level of radioactive material. | Event Text AGREEMENT STATE REPORT - STOLEN MOISTURE DENSITY GAUGE
The following was received from the State of Texas via email:
"On March 7, 2014, the Agency [Texas Department of Health] was notified by the licensee that one of its vehicles had been stolen on February 18, 2014. The vehicle contained a moisture density gauge, Troxler model 3340, serial number 17909, containing 1.48 GBq of Americium-241/Beryllium serial number 4713350 and 0.30 GBq of Cesium-137 serial number 507394. A local police report was filed. No recovery of vehicle or gauge. One violation cited for not reporting incident within regulatory timeframe. Any further information will be reported within SA 300 guidelines."
Texas Incident #: I-9162
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: 49885 | Rep Org: COLORADO DEPT OF HEALTH
Licensee: DE-RAY ENGINEERING, INC.
Region: 4
City: LAKEWOOD State: CO
County:
License #: CO 1097-01
Agreement: Y
Docket:
NRC Notified By: JIM GRICE
HQ OPS Officer: JEFF ROTTON | Notification Date: 03/10/2014
Notification Time: 10:57 [ET]
Event Date: 03/10/2014
Event Time: 05:30 [MDT]
Last Update Date: 03/10/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
THOMAS FARNHOLTZ (R4DO)
FSME EVENTS RESOURCE (EMAI)
ILTAB (EMAI)
|
| This material event contains a "Less than Cat 3 " level of radioactive material. | Event Text AGREEMENT STATE - STOLEN MOISTURE DENSITY GAUGE
The following was received from the State of Colorado via email:
"At appx. 5:30 MST on 3/10/14 the licensee's employee noticed that the window in his vehicle had been broken and the contents stolen. This included a CPN Model MC-1-DR portable nuclear gauge (Serial Number : MD10800432) containing two licensed sources (10 mCi Cs-137 and 50 mCi Am:Be).
"The vehicle was parked at the employees residence. The gauge was contained within a locked transport container. Although, the vehicle was locked there was no secondary tangible barrier preventing unauthorized removal of the gauge.
"The event was reported to the Wheatridge police on the morning of 3/10/14 and to the Colorado Department of Public Health and Environment at appx. 8:15 a.m. MST 3/10/14.
"The Colorado Department of Public Health and Environment received a follow up call at appx. 11:00 a.m. MST 3/10/14, indicating that the gauge was located by a member of the public and recovered by the licensee.
"The gauge was still in the locked transport container when it was recovered and there was no signs of damage to the case or indications that an attempt was made to open the case.
"A site visit will be conducted by a Colorado Department of Public Health and Environment inspector to interview staff and complete the investigation of the incident in the near future."
Event Report ID Number: CO14-I14-03
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: 49886 | Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: AMERICAN XRAY AND INSPECTION SERVICES, INC.
Region: 4
City: MIDLAND State: TX
County:
License #: 05974
Agreement: Y
Docket:
NRC Notified By: GENTRY HEARN
HQ OPS Officer: JEFF ROTTON | Notification Date: 03/10/2014
Notification Time: 11:14 [ET]
Event Date: 03/06/2014
Event Time: 15:45 [CDT]
Last Update Date: 03/10/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
THOMAS FARNHOLTZ (R4DO)
FSME EVENTS RESOURCE (EMAI)
| Event Text AGREEMENT STATE - RADIOGRAPHY CAMERA SOURCE DISCONNECT
The following was received from the State of Texas via email:
"On March 10, 2014, the Agency [State of Texas] received notice of a radiography source disconnect that occurred on March 6, 2014. The source was a 92.2 curie iridium-192 radiography source. The event occurred at a temporary field site just south of the border with New Mexico near Carlsbad, NM on the Texas side. No exposures to the public resulted from this event. No overexposures resulted from this event. The cause of the event is unknown at this time. The source was retrieved by the licensee. The licensee's initial report to the Agency [State of Texas] was later than 24 hours after the event. Additional information will be supplied as it is received in accordance with SA-300."
Texas Incident #: I-9163 |
| Agreement State | Event Number: 49887 | Rep Org: NEW YORK CITY BUREAU OF RAD HEALTH
Licensee: MONTEFIORE MEDICAL CENTER
Region: 1
City: NEW YORK State: NY
County:
License #: 75-2885
Agreement: Y
Docket:
NRC Notified By: TOBIAS LICKERMAN
HQ OPS Officer: CHARLES TEAL | Notification Date: 03/10/2014
Notification Time: 12:21 [ET]
Event Date: 02/27/2014
Event Time: [EDT]
Last Update Date: 03/10/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
MARC FERDAS (R1DO)
FSME EVENT RESOURCE (EMAI)
| Event Text AGREEMENT STATE REPORT - UNDERDOSE OF Y-90 ADMINISTRATION TO LIVER
The following was received from New York City Bureau of Rad Health via email:
"[A] patient was receiving treatment of left lobe of liver with Y-90 Sir Spheres. Half way through the procedure the catheter became clogged. 30 mCi of Y-90 was prescribed, only 22.5 mCi was delivered. 7.5 mCi remained in the catheter. [The] initial report stated that treatment of right lobe of liver had been scheduled for April. [The] initial report stated that Physician decided to treat left lobe of liver with makeup dose of 7.5 mCi Y-90 at that time.
"[The] ORH [Office of Radiological Health] inspector stated that multiple attempts were made to flush the catheter without success. The catheter was removed and the remainder of the dose was administered at the date of the initial clog with a micro-catheter.
"[The] physician spoke to the vendor rep (company SureFire). [The] company stated that cause of the clog would be investigated when the Y-90 had decayed.
"[The] referring physician was notified.
"[This] incident is considered a reportable medical event because the administered dose differed from the prescribed dose by >20%.
"[The] hospital states that if any future incidents such as this equipment malfunction occurs, they will keep the patient in treatment position to determine by measurement if proper dosage was delivered. If measurements indicate that inadequate dosage was delivered, they will draw another dose to supplement the original administration until the appropriate dose is administered to the patient."
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. |
| Fuel Cycle Facility | Event Number: 49913 | Facility: HONEYWELL INTERNATIONAL, INC.
RX Type: URANIUM HEXAFLUORIDE PRODUCTION
Comments: UF6 CONVERSION (DRY PROCESS)
Region: 2
City: METROPOLIS State: IL
County: MASSAC
License #: SUB-526
Agreement: Y
Docket: 04003392
NRC Notified By: ROSS LINDBERG
HQ OPS Officer: DONG HWA PARK | Notification Date: 03/13/2014
Notification Time: 15:46 [ET]
Event Date: 03/13/2014
Event Time: 13:00 [CDT]
Last Update Date: 03/13/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
40.60(b)(3) - MED TREAT INVOLVING CONTAM
| Person (Organization):
KATHLEEN O'DONOHUE (R2DO)
JAMES ANDERSEN (NMSS)
| Event Text CONTAMINATED PLANT EMPLOYEE RECEIVED MEDICAL TREATMENT INSIDE THE RESTRICTED AREA
"An employee with a wooden splinter in his right hand reported to the on-site dispensary this afternoon. The plant nurse administered first aid. A whole body survey of the employee in his plant clothing was performed; the maximum amount of contamination present was on the employee's right pant leg, 12,550 dpm/100cm2. The plant nurse allowed the employee to return to work. The employee remained inside the Restricted Area over the course of the event."
The licensee will inform R2 (Hartland). |
| Power Reactor | Event Number: 49920 | Facility: GRAND GULF
Region: 4 State: MS
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: FRANK WEAVER
HQ OPS Officer: PETE SNYDER | Notification Date: 03/17/2014
Notification Time: 09:25 [ET]
Event Date: 03/17/2014
Event Time: 05:14 [CDT]
Last Update Date: 03/17/2014 | 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):
GREG PICK (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | M/R | Y | 41 | Power Operation | 0 | Hot Shutdown | Event Text MANUAL REACTOR SCRAM DUE TO STEAM LEAK IN LOW PRESSURE TURBINE LINE
"On 3/17/2014 at 0514 [CDT] the reactor was manually scrammed from approximately 41% core thermal power due to a steam leak in the turbine building. All control rods fully inserted and all systems actuated and operated as designed. All Main Steam Isolation Valves were manually shut. The Reactor Core Isolation Cooling System was manually initiated to assist in level control and pressure control. No safety relief valves actuated automatically. Manual cycling of safety relief valves and Reactor Core Isolation Cooling are being used to maintain reactor water level and pressure within normal bands. Group 2 and 3 RHR isolation signals were received; however no valve movement occurred since the affected valves are normally closed.
"This event is reportable under 10CFR50.72(b)(2)(iv)(B) for the reactor trip and 50.72(b)(3)(iv)(A) for the manual start of the reactor core isolation cooling system."
The licensee informed the NRC Resident Inspector. |
| Power Reactor | Event Number: 49921 | Facility: BRUNSWICK
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: MARK R. DeWIRE
HQ OPS Officer: STEVE SANDIN | Notification Date: 03/17/2014
Notification Time: 11:26 [ET]
Event Date: 03/17/2014
Event Time: 07:50 [EDT]
Last Update Date: 03/17/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
| Person (Organization):
KATHLEEN O'DONOHUE (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | Event Text SECONDARY CONTAINMENT AIRLOCK DOOR INTERLOCK MALFUNCTION
"At 0750 EDT on March 17, 2014, Operations determined that both the inner and outer secondary containment airlock doors, on the 20 foot elevation of the Unit 1 reactor building, had been simultaneously opened for approximately 10 seconds. This event occurred while an employee was exiting secondary containment immediately after another employee had previously entered. Upon recognition of the condition, the employees took action to secure both doors. The cause of this event was malfunction of the secondary containment airlock door interlock.
"This condition is being reported in accordance with 10CFR50.72(b)(3)(v)(C), event or condition that could have prevented fulfillment of a safety function needed to control the release of radioactive material. With both doors open, Surveillance Requirement 3.6.4.1.3 of Technical Specification 3.6.4.1, Secondary Containment, was not met, rendering secondary containment inoperable. At the time at the time of the condition, Unit 1 was engaged in Operations with the Potential to Drain the Reactor Vessel (OPDRV) and was crediting Secondary Containment as Operable.
"This event did not result in any adverse impact to the health and safety of the public.
"The safety significance of this is minimal. Secondary containment was only inoperable for approximately 10 seconds. This event did not result in any adverse impact to the health and safety of the public.
"The door interlock investigation [is] in progress. Doorwatches with communications have been stationed on either side of the Unit 1 and Unit 2 20 foot reactor building air lock doors. All other secondary containment access doors on both Reactor Building have been controlled as emergency exit only. Installation of temporary video surveillance system [is] being pursued until long term corrective action can be established per the corrective action program.
"The NRC Senior Resident has been notified." |
| Power Reactor | Event Number: 49922 | Facility: MILLSTONE
Region: 1 State: CT
Unit: [ ] [ ] [3]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: RICHARD VIGNEAU
HQ OPS Officer: DONG HWA PARK | Notification Date: 03/17/2014
Notification Time: 11:40 [ET]
Event Date: 03/17/2014
Event Time: 10:25 [EDT]
Last Update Date: 03/17/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
BLAKE WELLING (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text MILLSTONE STATION MAIN STEAM RADIATION MONITORS OUT OF SERVICE FOR MAINTENANCE
At 1025 EDT on 3/17/14, the Millstone Station main steam radiation monitors were removed from service for pre-planned maintenance. This resulted in a degradation in the ability to detect steam generator tube leakage. The main steam radiation monitors will be returned to service within 79 hours.
The licensee informed State/local agencies and the NRC Resident Inspector. |
| Part 21 | Event Number: 49923 | Rep Org: DRESSER-RAND COMPANY
Licensee: DRESSER-RAND COMPANY
Region: 1
City: WELLSVILLE State: NY
County:
License #:
Agreement: Y
Docket:
NRC Notified By: ED GRANDUSKY
HQ OPS Officer: DANIEL MILLS | Notification Date: 03/17/2014
Notification Time: 13:53 [ET]
Event Date: 02/17/2014
Event Time: [EDT]
Last Update Date: 03/17/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
| Person (Organization):
BLAKE WELLING (R1DO)
KATHLEEN O'DONOHUE (R2DO)
JULIO LARA (R3DO)
PART 21 GROUP (EMAI)
| Event Text PART 21 - BEARING DEFECT
The following was received via email:
"On Dresser-Rand Drawing 75439A part number 07 is identified as a Heim LSS-8 bearing that has an Aluminum Bronze insert to accommodate a non-lubricated application. Dresser-Rand shipped 10 bearings part number 75439A07 to Dominion Nuclear in 2006 that were Seal Master Com 8 bearings that do not have an Aluminum Bronze insert.
"This bearing is used on turbines that have a PG type mechanical governor with the cam plate linkage. Extended operation without lubrication will result in the Seal Master Com 8 bearing seizing. The customer should visually inspect this bearing for the bronze insert. If no insert is visible then the bearing should be replaced at the first opportunity."
Licensees potentially affected (turbine serial numbers): Calvert Cliffs (T36674A, T36674B, T36674C, T36674D), DC Cook (T36700A, T36700B), Salem (T36988A, T36988B), Crystal River (T37009A), Davis Besse (T37686A, T37686B), Millstone (F37273A, T38587A), Summer (T38765A).
International sites potentially affected: Bugey (T38498A, T38498B, T38880A, T38880B). |
| Power Reactor | Event Number: 49924 | Facility: PALISADES
Region: 3 State: MI
Unit: [1] [ ] [ ]
RX Type: [1] CE
NRC Notified By: TERRY DAVIS
HQ OPS Officer: DONG HWA PARK | Notification Date: 03/17/2014
Notification Time: 15:12 [ET]
Event Date: 03/17/2014
Event Time: 14:18 [EDT]
Last Update Date: 03/17/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
JULIO LARA (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 64 | Power Operation | 64 | Power Operation | Event Text DISPLAYED METEOROLOGICAL DATA POTENTIALLY INACCURATE
"At 1418 EDT on 03/17/2014, it was determined the atmospheric stability classification data display on the plant process computer (PPC) could have been potentially inaccurate.
"In September 2012, implementation of a hardware and software modification to separate the meteorological tower computer from the PPC introduced a calculation error to the PPC software design that resulted in the PPC potentially displaying inaccurate stability class data. The ability to accurately perform dose assessment calculations could potentially be affected when using the stability class indication obtained from the PPC.
"The availability and accuracy of backup stability class data via the meteorological tower computer or from Weather Services International were not affected.
"Within 24 hours of discovery, the procedurally described alternatives for obtaining stability class data were implemented.
"Subsequently, the PPC stability class software calculation was corrected and the PPC stability class display restored for use.
"There was no impact to any emergency declaration because there were no actual emergencies from the time the modification was implemented until the error was corrected.
"The licensee has notified the NRC Resident Inspector." |
| Power Reactor | Event Number: 49925 | Facility: WATERFORD
Region: 4 State: LA
Unit: [3] [ ] [ ]
RX Type: [3] CE
NRC Notified By: KEVIN HALE
HQ OPS Officer: DANIEL MILLS | Notification Date: 03/17/2014
Notification Time: 15:53 [ET]
Event Date: 03/17/2014
Event Time: 07:37 [CDT]
Last Update Date: 03/17/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
GREG PICK (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text LOSS OF EMERGENCY SIRENS
"At approximately 0737 (CDT) on March 17, 2014, Waterford 3 was informed that four emergency sirens were inoperable. One other siren had previously been determined to be inoperable on March 12, 2014. Subsequent review during preparation of this notification has identified an additional eight inoperable sirens, which brings the total number of inoperable sirens to thirteen. There are a total of seventy-three sirens distributed among two parishes (counties). The loss of these thirteen sirens for more than one hour is considered a major loss of offsite response capability and is reported pursuant to 10 CFR 50.72(b)(3)(xiii).
"The two affected parish Emergency Operations Centers were notified of the condition and it was confirmed that they will use the preplanned alternative method of Route Alerting for the affected areas until notified that repairs to the sirens have been completed.
"Waterford 3 is working to repair the sirens. There is no effect on the plant. This issue has been entered into the Waterford 3 Corrective Action Program and appropriate corrective actions will be developed.
"The NRC Resident Inspectors, local agencies, and the State of Louisiana were notified." |
| Power Reactor | Event Number: 49926 | Facility: FORT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: (1) CE
NRC Notified By: SCOTT MOECK
HQ OPS Officer: DONG HWA PARK | Notification Date: 03/17/2014
Notification Time: 15:55 [ET]
Event Date: 03/17/2014
Event Time: 12:02 [CDT]
Last Update Date: 03/17/2014 | 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):
GREG PICK (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 AUTOMATIC REACTOR TRIP DUE TO TURBINE TRIP INITIATED BY LOSS OF STATOR COOLING WATER
"Ft. Calhoun station automatically tripped due to a loss of turbine load. The turbine tripped due to loss of stator cooling water. Maintenance was in progress on the stator cooling system when inventory was lost and low pump discharge pressure caused an automatic turbine trip and reactor trip. All systems operated as expected. Ft. Calhoun station is shutdown and stable in mode 3 at this time."
All control rods fully inserted into the core and decay heat is being removed using the normal condenser steam dump system.
The licensee has notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 49927 | Facility: TURKEY POINT
Region: 2 State: FL
Unit: [3] [4] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: TIMOTHY JONES
HQ OPS Officer: DANIEL MILLS | Notification Date: 03/17/2014
Notification Time: 17:09 [ET]
Event Date: 03/17/2014
Event Time: 10:18 [EDT]
Last Update Date: 03/18/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
KATHLEEN O'DONOHUE (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | N | 0 | Hot Shutdown | 0 | Cold Shutdown | | 4 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text TECHNICAL SUPPORT CENTER HABITABILTY IMPACTED DUE TO LOSS OF AIR CONDITIONING
"At approximately 1018 EDT on March 17, 2014, during a check of facility equipment, the Technical Support Center (TSC) was found to be degraded due to the loss of the air conditioning (AC) system. Due to the loss of AC, TSC habitability is impacted.
"The emergency assessment function can be performed in the control room as addressed in emergency response procedures. This event is reported in accordance with 10 CFR 50.72(b)(3)(xiii).
"This condition is common to both units.
"Unrelated to this condition, Unit 3 is currently in the process of shutting down in preparation for a refueling outage.
"Unit 4 will remain Mode 1, 100% Power.
"The TSC AC system repairs are in progress."
The licensee has notified the NRC Resident Inspector.
* * * UPDATE AT 0359 ON 3/18/14 FROM PELL TO SNYDER * * *
The TSC AC system has been repaired and restored to service. The licensee will notify the NRC Resident Inspector.
Notified R2DO (O'Donohue). | |