| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
07/25/2014 - 07/28/2014 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 50283 | Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: BYER GEOTECHNICAL, INC.
Region: 4
City: GLENDALE State: CA
County:
License #: 6094-19
Agreement: Y
Docket:
NRC Notified By: DONALD OESTERLE
HQ OPS Officer: DONALD NORWOOD | Notification Date: 07/17/2014
Notification Time: 16:48 [ET]
Event Date: 07/17/2014
Event Time: 07:30 [PDT]
Last Update Date: 07/23/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
THOMAS FARNHOLTZ (R4DO)
FSME EVENTS RESOURCE (EMAI)
|
| This material event contains a "Less than Cat 3 " level of radioactive material. | Event Text AGREEMENT STATE REPORT - STOLEN MOISTURE/DENSITY GAUGE
The following information was received via E-mail:
"The RSO for Byer Geotechnical contacted RHB [Radiologic Health Branch] to report that an employee working at a construction site at Colorado Blvd. and Glacier St. in Eagle Rock (a suburb of Los Angeles) had a CPN model MC 1DRP gauge (s/n MD50902828) stolen from the back of his pick-up truck around 0730 PDT. This moisture density gauge contains 370 mBq (10 mCi) of Cs-137 and 1.85 Gbq ( 50 mCi) of Am-241:Be. The security chains attaching the gauge transportation case to the vehicle were cut. The employee notified his RSO asap, who contacted RHB. RHB instructed the RSO to contact the local police dept. to make a report and also place an ad in a local newspaper for return of the gauge with a monetary reward. More information will be obtained from the employee via a written report of the incident."
Notified Mexico via E-mail.
* * * UPDATE AT 1431 EDT ON 07/23/14 FROM KATHLEEN HARKNESS TO S. SANDIN VIA EMAIL * * *
"This CPN gauge was recovered by the licensee on 7/22/2014 at 1500 PDT from the driveway at the same location that it was stolen from.
"The RSO notified the RHB inspector on 7/23/2014 at 1000 PDT by phone.
"The transportation box's latch was damaged and the padlock missing, but the gauge itself appeared intact. The RSO will be bringing it to a CPN service provider for repair of the case and inspection of the gauge prior to placing it back into service. California will continue to investigate."
Notified R4DO (Miller), FSME Events Resource and ILTAB (email) and Mexico (fax).
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 |
| Power Reactor | Event Number: 50287 | Facility: TURKEY POINT
Region: 2 State: FL
Unit: [3] [4] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: ROBERT PELL
HQ OPS Officer: DONALD NORWOOD | Notification Date: 07/20/2014
Notification Time: 20:02 [ET]
Event Date: 07/20/2014
Event Time: 14:54 [EDT]
Last Update Date: 07/27/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
| Person (Organization):
GERALD MCCOY (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | | 4 | N | Y | 100 | Power Operation | 95 | Power Operation | Event Text ULTIMATE HEAT SINK TEMPERATURE EXCEEDED TECHNICAL SPECIFICATION LIMIT
"At 1454 EDT on 20 July 2014, Turkey Point Units 3 and 4 entered the Action for Technical Specification (TS) 3.7.4, Ultimate Heat Sink (UHS). The action was entered because UHS temperature exceeded the limit of 100 degrees F due to a natural event. This report is in accordance with 10CFR50.72(b)(3)(v)(B) because UHS capability to remove residual heat is impacted. At 1800 EDT the NRC verbally approved a natural event Notice of Enforcement Discretion (NOED) which allows the ultimate heat sink temperature to exceed 100 degrees F up to 103 degrees F. Unit power levels have been maintained at Unit 3 100% and Unit 4 95%.
"The NRC Resident Inspector has been notified."
* * * UPDATE FROM CHRIS TRENT TO DANIEL MILLS AT 2058 EDT ON 7/26/2014 * * *
"At 2046 on 7/20/14, Turkey Point Units 3 and 4 exited the Action for Technical Specification (TS) 3.7.4, Ultimate Heat Sink, when the ultimate heat sink (UHS) temperature decreased below the TS limit of 100 degrees F.
"At 1604 on 7/26/14, Turkey Point Units 3 and 4 entered the Action for TS 3.7.4, Ultimate Heat Sink. The action was entered because UHS temperature exceeded the limit of 100 degrees F. This report is in accordance with 10 CFR 50.72(b)(3)(v)(B) because UHS capability to remove residual heat is impacted. Turkey Point is currently complying with NOED No. 14-2-001, which allows a temporary maximum UHS temperature of 103 degrees F.
"The NRC Resident Inspector was notified."
At 2058 on 7/26/14 the UHS average temperature was 100.3 degrees F and the peak temperature was 100.5 degrees F. Unit 4 is currently operating at 75% power in anticipation of elevated intake temperature in the next several days.
Notified R2DO (Musser)
* * * UPDATE FROM JOSE VASQUEZ TO DANIEL MILLS AT 1913 EDT ON 7/27/2014 * * *
"At 2102 on 7/26/14, Turkey Point Units 3 and 4 exited the Action for Technical Specification (TS) 3.7.4, Ultimate Heat Sink, when the ultimate heat sink (UHS) temperature decreased below the TS limit of 100 degrees F.
"At 1602 on 7/27/14, Turkey Point Units 3 and 4 entered the Action for TS 3.7.4, Ultimate Heat Sink. The action was entered because UHS temperature exceeded the limit of 100 degrees F. This report is in accordance with 10 CFR 50.72(b)(3)(v)(B) because UHS capability to remove residual heat is impacted. Turkey Point is currently complying with NOED No. 14-2-001, which allows a temporary maximum UHS temperature of 103 degrees F.
"The NRC Resident Inspector was notified."
At 1913 on 7/27/14 the UHS average temperature was 101.1 degrees F and the peak temperature was 101.3 degrees F. Units 3 and 4 are currently operating at 75% power in anticipation of elevated intake temperature in the next several days.
Notified R2DO (Musser) |
| Power Reactor | Event Number: 50307 | Facility: CALVERT CLIFFS
Region: 1 State: MD
Unit: [1] [ ] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: JAY GAINES
HQ OPS Officer: DONALD NORWOOD | Notification Date: 07/24/2014
Notification Time: 23:41 [ET]
Event Date: 07/24/2014
Event Time: 23:15 [EDT]
Last Update Date: 07/25/2014 | 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):
MEL GRAY (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 TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO REACTOR COOLANT SYSTEM PRESSURE BOUNDARY LEAKAGE
"At 2315 EDT on July 24th, 2014, CCNPP [Calvert Cliffs Nuclear Power Plant] U1 identified RCS [Reactor Coolant System] pressure boundary leakage from the instrument line to 1-PDT-123A, 11A reactor coolant pump differential pressure transmitter. Technical Specification 3.4.13, Action B was entered and requires that the unit be placed in Mode 3 within 6 hours and Mode 5 within 36 hours. [CCNPP has] initiated plant shutdown in accordance with this Technical Specification. Therefore, this is reportable under 10 CFR 50.72(b)(2)(i) Plant Shutdown Required by Technical Specifications. This is also reportable under 50.72(B)(3)(ii)(A) as a material defect in the primary coolant system that cannot be found acceptable under ASME Section XI, IWB-3600 or ASME Section XI, Table IWB-3410-1."
The licensee notified the NRC Resident Inspector.
* * * UPDATE FROM JAY GAINES TO VINCE KLCO AT 0320 EDT ON 7/25/14 * * *
The licensee reduced reactor power to 10 percent and entered containment. The pressure boundary leak was isolated and the licensee exited the Technical Specification 3.4.13, Action B. The Technical Specification required shutdown was terminated. The licensee is making preparation to increase power to full load.
The licensee will notify the NRC Resident Inspector.
Notified the R1DO (Gray). |
| Research Reactor | Event Number: 50309 | Facility: TEXAS A&M UNIVERSITY
RX Type: 1000 KW TRIGA (CONVERSION)
Comments:
Region: 4
City: COLLEGE STATION State: TX
County: BRAZOS
License #: R-83
Agreement: Y
Docket: 05000128
NRC Notified By: SEAN MCDEAVITT
HQ OPS Officer: JEFF ROTTON | Notification Date: 07/25/2014
Notification Time: 13:24 [ET]
Event Date: 07/25/2014
Event Time: 09:50 [CDT]
Last Update Date: 07/25/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
NON-POWER REACTOR EVENT
| Person (Organization):
DUANE HARDESTY (NPR)
PATRICK ISAAC (NPR)
ALEXANDER ADAMS (PRLB)
| Event Text TECHNICAL SPECIFICATION VIOLATION DUE TO CONTROL ROOM STAFFING
"This morning around 9:45 a.m. (CDT), a reportable occurrence under Section 1.28.f of the NSC [Nuclear Science Center] Technical Specifications was documented at the Texas A&M University Nuclear Science Center (NRC License No. R-83). The incident involved leaving the control room unstaffed by a licensed operator (Section 6.1.3.a.2 of the NSC Technical Specifications) for approximately 2.5 minutes while the 1 MW TRlGA reactor was operating at full power.
"The text below presents a brief description of the event:
"On the morning of July 25, 2014, during steady state operation at 1 MW [full power], Reactor Operator (RO) trainee [Deleted] was in the control room, along with a Senior Reactor Operator on Duty (SRO) [Deleted] and electronic technician [Deleted]. Senior Reactor Operator [Deleted] and Reactor Operator (RO) [Deleted] were signed in as the operators on duty during the duration of the incident.
"Duty SRO and RO were elsewhere in the facility performing Operations tasks, and RO (Licensed) [Deleted] had remained in the Control Room to fulfill the requirement set forth in TS (Staffing) 6.1.3.a.2. At approximately 0948, NSC Radiation Safety Officer (RSO) [Deleted] entered the control room and requested the use of RO [Deleted] key to access a building on site. RO offered to open the building and left [control room] leaving RO trainee and electronic technician alone in the control room. At 0950, RO trainee noted that there was no licensed reactor operator in the control room. RO Trainee paged RO over the intercom and shutdown the reactor via manual SCRAM.
"Manager of Reactor Operations [also SRO] heard the reactor SCRAM from his office above the control room and went to the control room to investigate. [Duty] SRO was notified and immediately returned to the control room. It was determined by SROs that during the 2.5 minutes that RO was absent from the control room, the requirements outlined in Technical Specification 6.1.3.a.2 were not fulfilled. NSC Director was informed of the incident and NSC Form 590 (Unscheduled Scram Recovery Form) was filled out after the unscheduled shutdown. Manager of Reactor Operations authorized the restart of the reactor. NSC Director began implementation of Reportable Occurrence reporting procedures according to Technical Specification 1.28.f."
Licensee is initiating an internal review to identify and correct any practices and/or procedures that may have systematically contributed to the environment that created this situation. Other corrective actions include the internal suspension of one reactor operator's license privileges pending satisfactory retraining.
The unit response during and after the scram was normal. |
| Power Reactor | Event Number: 50310 | Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [ ] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: TIM KUDO
HQ OPS Officer: DANIEL MILLS | Notification Date: 07/25/2014
Notification Time: 14:02 [ET]
Event Date: 07/25/2014
Event Time: 11:29 [EDT]
Last Update Date: 07/26/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
50.72(b)(2)(i) - PLANT S/D REQD BY TS
| Person (Organization):
RANDY MUSSER (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 TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO A SAFETY INJECTION VALVE DEFECT
"On July 25th, 2014 at 1129 EDT, during investigation of a small leak inside Saint Lucie Unit 2 containment, a defect was identified on a valve (V3811, Safety Injection Tank 281 Outlet Vent Valve). This valve is within the Q-Group A (ASME Class 1 equivalent) boundary of the safety injection line. The leak is currently isolated from the reactor coolant system by a Technical Specification credited isolation check valve. The affected Safety Injection Tank has been declared inoperable and the unit has entered 24 hour shutdown [Technical Specification] action statement 3.5.1.b. Unit shutdown is currently being planned for repair of the flaw.
"This condition is being reported pursuant to 10 CFR 50.72(b)(3)(ii)(A)."
The licensee has notified the NRC Resident Inspector.
* * * UPDATE FROM JOHN REXRODE TO VINCE KLCO AT 0053 EDT ON 7/26/14 * * *
"On July 26, 2014 at 0002 EDT, Saint Lucie Unit 2 commenced shutdown to repair the identified leak.
"This condition is being reported pursuant to 10 CFR 50.72(b)(3)(ii)(A) and 10 CFR 50.72(b)(2)(i).
"The NRC Resident Inspector has been notified."
Unit 2 current power is 88% at 0105 EDT and expect to trip the unit at approximately 0400 EDT.
Notified the R2DO (Musser). |
| Fuel Cycle Facility | Event Number: 50312 | 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: VINCE KLCO | Notification Date: 07/26/2014
Notification Time: 10:44 [ET]
Event Date: 07/26/2014
Event Time: 04:00 [CDT]
Last Update Date: 07/26/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
40.60(b)(3) - MED TREAT INVOLVING CONTAM
| Person (Organization):
RANDY MUSSER (R2DO)
MERAJ RAHIMI (NMSS)
| Event Text UNPLANNED MEDICAL TREATMENT OF A CONTAMINATED INDIVIDUAL
"[A Honeywell] employee with dust in his right eye reported to the on-site dispensary this morning. 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 work boots, 331,597 dpm/100 sq.cm. The plant nurse allowed the employee to return to work following treatment. The employee remained inside the Restricted Area over the entire course of the event."
The licensee will notify the NRC Resident Inspector and Region 2 (David Hartland via email). |
| Power Reactor | Event Number: 50313 | Facility: MILLSTONE
Region: 1 State: CT
Unit: [ ] [2] [ ]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: MICHAEL FRECHETTE
HQ OPS Officer: JEFF ROTTON | Notification Date: 07/26/2014
Notification Time: 15:14 [ET]
Event Date: 07/26/2014
Event Time: 14:11 [EDT]
Last Update Date: 07/26/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
| Person (Organization):
MEL GRAY (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 100 | Power Operation | 80 | Power Operation | Event Text TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO TURBINE DRIVEN AFW PUMP FAILURE
"At 1458 [EDT] on 7/26/14, the [Technical Specification] 72 hour action statement for TDAFWP [Turbine Driven Auxiliary Feedwater Pump] inoperable expires (LCO 3.7.1.1 Action C). Per Technical Specification Action Statement, plant is required to be in HOT STANDBY by 2058 on 7/26/14 (6 hours) and in HOT SHUTDOWN by 0858 on 7/27/14 (additional 12 hours). MPS [Millstone Power Station] Unit 2 shutdown (using normal procedures) has commenced at 1411 when troubleshooting and repairs were unable to determine and correct cause of low pump recirculation flow. Additional activities will continue to correct issue."
Unit 3 is not affected by this event. All safety-related systems and equipment required for safe plant shutdown are available.
The licensee notified the NRC Resident Inspector, Waterford Dispatch, and State of Connecticut Department of Energy and Environmental Protection. |
| Power Reactor | Event Number: 50314 | Facility: VOGTLE
Region: 2 State: GA
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DAN MONAHON
HQ OPS Officer: JEFF ROTTON | Notification Date: 07/27/2014
Notification Time: 15:22 [ET]
Event Date: 07/27/2014
Event Time: 14:09 [EDT]
Last Update Date: 07/27/2014 | 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):
RANDY MUSSER (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 LOSS OF MAIN FEED PUMP DURING TESTING
"VEGP [Vogtle Electric Generation Plant] Unit One was at 100 percent power, with a Main Feed Pump (MFP) Turbine A trip mechanism test in-progress, when MFP A Trip alarm was received in the Main Control Room. Control Room crew identified MFP A speed and steam generator levels lowering and initiated a manual reactor trip. All control rods fully inserted and nothing unusual was noted. Auxiliary feed water and feedwater isolation actuated as expected. The unit is currently stable in MODE 3 at normal operating temperature and pressure. A forced outage response team has been formed to determine the cause of the MFP A trip and determine restart criteria and time of restart."
The unit is in a normal shutdown electric plant lineup. No effect on Unit 2.
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 50315 | Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: MICHAEL MOORE
HQ OPS Officer: HOWIE CROUCH | Notification Date: 07/28/2014
Notification Time: 05:06 [ET]
Event Date: 07/28/2014
Event Time: 01:18 [EDT]
Last Update Date: 07/28/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
MEL GRAY (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 METEOROLOGICAL DATA TO THE SITE
"At 0118 [EDT] on 7/28/2014, meteorological data was lost to both Salem and Hope Creek. At the time, there were storms in the vicinity which [were] the apparent cause of the temporary loss of data. Both Salem and Hope Creek lost wind direction information. This event is being reported under 10CFR50.72(b)(3)(xiii), major loss of emergency assessment capabilities.
"At 0130, meteorological data was restored to the control rooms. Plant operations at Hope Creek and both Salem Units 1 and 2 were not affected. All three units remain at full power.
"The licensees notified the NRC Resident Inspectors." | |