| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
03/11/2015 - 03/12/2015 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 50714 | Facility: TURKEY POINT
Region: 2 State: FL
Unit: [ ] [4] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: DIRK DRINKARD
HQ OPS Officer: VINCE KLCO | Notification Date: 01/02/2015
Notification Time: 16:45 [ET]
Event Date: 01/02/2015
Event Time: 09:25 [EST]
Last Update Date: 03/11/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
GEORGE HOPPER (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 4 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text HIGH HEAD SAFETY INJECTION INOPERABLE DUE TO VOIDS IDENTIFIED IN PIPING
"At 0925 [EST] on 1/2/2015, Engineering personnel identified a gas void in each of two Unit 4 cold leg High Head Safety Injection (HHSI) discharge lines which exceeded procedural gas accumulation acceptance criteria. This condition rendered the cold leg HHSI flow path inoperable and required entry into Technical Specification 3.0.3. The voids were vented and Technical Specification (TS) 3.0.3 was exited at 1032.
"The testing for gas voids conducted on 1/2/2015 was a follow-up to a gas void found in one Unit 4 HHSI line on 12/26/2014. On 12/26/14, TS 3.0.3 was entered at 1020 and exited at 1048 after the gas void was vented. After further review, the 12/26/2014 event was also reportable in accordance with 10 CFR 50.72(b)(3)(v)(D).
"Engineering evaluation will be performed for both events to determine the specific impact of the gas voids on HHSI system function. Cause evaluation is being conducted to determine the source of the gas and any needed corrective actions."
Unit 3 was verified to not have this voiding issue.
The licensee notified the NRC Resident Inspector.
* * * RETRACTION FROM SEAN BLOOM TO VINCE KLCO AT 1120 EDT ON 3/11/15 * * *
"On 1/2/2015 at 1645 [EST], Event Notification 50714 reported to the NRCOC [Nuclear Regulatory Commission Operations Center] gas voids detected on 12/26/2014 and 1/2/2015 in Unit 4 cold leg High Head Safety Injection (HHSI) piping which exceeded procedural gas accumulation acceptance criteria.
"Subsequent analysis has determined that if a HHSI pump started with the measured gas voids present, the resulting system conditions would not have impacted the integrity of the Unit 4 HHSI discharge flow path to the reactor coolant system (RCS) and therefore its safety related function would not be impaired.
"The Unit 4 HHSI system discharge flow path to the RCS had been operable with the voids present, Technical Specification (TS) requirements were met, and entry into TS 3.0.3 was not required. The HHSI system remained capable of fulfilling the safety function to mitigate the consequences of an accident on Unit 4. Therefore, the immediate notification to the NRCOC on 1/2/2015 at 1645 in accordance with 10 CFR 50.72(b)(3)(v)(D) is hereby retracted."
The NRC Resident Inspector has been informed.
Notified R2DO (Shaeffer). |
| Power Reactor | Event Number: 50773 | Facility: COMANCHE PEAK
Region: 4 State: TX
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ROBERT DANIELS
HQ OPS Officer: VINCE KLCO | Notification Date: 01/28/2015
Notification Time: 11:38 [ET]
Event Date: 01/28/2015
Event Time: 10:18 [CST]
Last Update Date: 03/11/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
MICHAEL VASQUEZ (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text EMERGENCY OPERATIONS FACILITY UNAVAILABLE DUE TO PLANNED VENTILATION MAINTENANCE
"The Comanche Peak Primary Emergency Operations Facility (EOF) will be unavailable during planned maintenance on the EOF ventilation system.
"On January 28, 2015, CPNPP [Comanche Peak Nuclear Power Plant] began planned work to improve the reliability of the EOF ventilation system. The EOF will be unavailable for approximately three weeks. During the time the primary EOF is unavailable, the affected ERO members will respond to the Backup EOF in Granbury, Texas for any declared emergency event. Therefore, it is expected that appropriate assessment of plant conditions, notifications, and communications could still be made, if required, during the time the primary EOF is unavailable.
"The extended unavailability of the primary EOF is being reported in accordance with 10CFR50.72(b)(3)(xiii), which is any event that results in a major loss of emergency assessment capability, offsite response capability, or offsite communications capability. The NRC Resident [Inspector] has been notified. A follow-up ENS communication will be made when the primary EOF availability is restored."
* * * UPDATE ON 03/11/2015 AT 1811 EDT FROM BRIAN MITCHELL TO JEFF HERRERA * * *
"The availability of the Comanche Peak Primary Emergency Operations Facility (EOF) has been restored following planned maintenance on the EOF ventilation system.
"On January 28, 2015, CPNPP (Comanche Peak Nuclear Power Plant) began planned work to improve the reliability of the EOF ventilation system. The unavailability of the primary EOF was reported in accordance with 10 CFR 50.72(b)(3)(xiii). This report serves as a follow-up to Event Number 50773."
The licensee notified the NRC Resident Inspector.
The R4DO (Okeefe) was notified. |
| !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 50855 | Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: DANIEL BOWERS
HQ OPS Officer: JEFF ROTTON | Notification Date: 02/28/2015
Notification Time: 05:24 [ET]
Event Date: 02/28/2015
Event Time: 00:00 [CST]
Last Update Date: 03/11/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
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 | 25 | Power Operation | 0 | Hot Standby | Event Text AUTOMATIC AUXILIARY FEEDWATER ACTUATION DUE TO PLANNED REACTOR TRIP
"Wolf Creek Generating Station performed a planned shutdown for the start of a refueling outage. As part of the procedure GEN 00-005, Minimum Load to Hot Standby, a planned manual reactor trip was initiated from 25 percent power level with the plant in Mode 1. As part of this planned shut down sequence, an anticipated automatic Auxiliary Feedwater [AFW] actuation signal was generated. This is a non-emergency event notification in accordance with 10 CFR 50.72(b)(3)(iv)(A) due to preplanned manual actuation of the reactor protection system and auto-initiation of auxiliary feed water system.
"All systems and components operated as designed with the exception of the main generator output breakers. They did not open as designed. They were manually opened using the main control room hand switches as directed by EMG ES-02, Reactor Trip Response.
"The plant is stable in Mode 3 with AFW secured, with plans to cool down and enter Mode 5 for the planned refueling outage.
"The NRC Resident Inspector has been notified."
* * * EVENT RETRACTED ON 03/11/15 AT 13:05 EDT FROM BRET DAVIS TO JEFF HERRERA * * *
"WCNOC [Wolf Creek Nuclear Operating Corporation] is retracting the 10 CFR 50.72(b)(3)(iv)(A) notification based on further review of the event. A valid AFAS [Auxiliary Feedwater Actuation signal] actuation occurred during the planned shutdown as a result of SG [Steam Generator] water level reaching the lo lo level setpoint. The AFAS actuation was an expected actuation that occurred due to preplanned activities covered by GEN 00-005. On-shift control room personnel were aware that an AFAS actuation would occur as a result of tripping the plant between 30% and 25% power. The AFAS actuated consistent with the planned shutdown with no anomalies. This is consistent with NUREG-1022, Rev. 3, Section 3.2.6 that states, in part: 'With regard to preplanned actuations, operation of a system as part of a planned test or operational evolution need not be reported. Preplanned actuations are those that are expected to actually occur due to preplanned activities covered by procedures. Such actuations are those for which a procedural step or other appropriate documentation indicates that the specific actuation is actually expected to occur. Control room personnel are aware of the specific signal generation before its occurrence or indication in the control room.'"
The NRC Resident Inspector was notified.
Notified R4DO(Okeefe). |
| Non-Agreement State | Event Number: 50861 | Rep Org: UNIVERSITY OF MISSOURI
Licensee: UNIVERSITY OF MISSOURI
Region: 3
City: COLUMBIA State: MO
County:
License #: 24-00513-32
Agreement: N
Docket:
NRC Notified By: JACK CRAWFORD
HQ OPS Officer: STEVE SANDIN | Notification Date: 03/04/2015
Notification Time: 10:50 [ET]
Event Date: 03/04/2015
Event Time: [CST]
Last Update Date: 03/04/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
| Person (Organization):
KENNETH RIEMER (R3DO)
NMSS_EVENTS_NOTIFIC (EMAI)
ILTAB (EMAI)
|
| This material event contains a "Less than Cat 3 " level of radioactive material. | Event Text MISSING TRITIUM EXIT SIGN
A tritium exit sign was discovered missing during a December 2014 inventory. The missing tritium exit sign is an Isolite Model 2000 containing two (2) 10 Ci sources, S/N 11-38620 and 11-38621. It was originally scheduled for installation in December 2012 at the University of Missouri Power Station but not installed due to other extensive renovations. The licensee conducted an investigation contacting both the contractor who was to perform the install and the manufacturer before concluding that the sign was missing.
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: 50862 | Rep Org: TEXAS DEPT OF STATE HEALTH SERVICES
Licensee: THE UNIVERSITY OF TEXAS MD ANDERSON CANCER CENTER
Region: 4
City: HOUSTON State: TX
County:
License #: 00466
Agreement: Y
Docket:
NRC Notified By: IRENE CASARES
HQ OPS Officer: JEFF HERRERA | Notification Date: 03/04/2015
Notification Time: 11:52 [ET]
Event Date: 03/03/2015
Event Time: 16:01 [CST]
Last Update Date: 03/04/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
RAY KELLAR (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)
| Event Text AGREEMENT STATE REPORT - IRRADIATOR SOURCE WOULD NOT FULLY LOWER TO SHIELDED POSITION
The following report was received from the Texas Department of State Health Services via email:
"On March 4, 2015, the licensee reported that a malfunction had occurred involving its J.L. Shepherd Mark I, Model 30, self-contained irradiator. [The] irradiator contains a J. L. Shepard Type 6810, 10,000 curie, Cs-137 source with serial number 85CS26. The source would not fully raise nor would it lower into the fully shielded position. The interlock system functioned as designed and the irradiator door remained locked. No one received any exposures and there is no risk for exposure as a result of this event. The licensee has contacted the manufacturer and scheduled repair. An investigation into this event is ongoing. An update will be forwarded in accordance with SA-300."
Texas Incident #: I-9282 |
| Agreement State | Event Number: 50865 | Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: EXXON MOBIL OIL CORPORTATION
Region: 4
City: TORRANCE State: CA
County:
License #: CA-0113-19
Agreement: Y
Docket:
NRC Notified By: TANYA RIDGLE
HQ OPS Officer: JEFF HERRERA | Notification Date: 03/04/2015
Notification Time: 19:31 [ET]
Event Date: 03/04/2015
Event Time: 09:00 [PST]
Last Update Date: 03/04/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
RAY KELLAR (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)
| Event Text AGREEMENT STATE REPORT - SHUTTER NOT OPERATING PROPERLY ON NUCLEAR PROCESS GAUGE
The following information was received from the Los Angeles Radiation Management Department via facsimile:
"On March 4, 2015, the Radiation Safety Officer (RSO), Exxon Mobil Oil Corporation (License #0113-19) reported to LA County Radiation Management that the shutter on one of their Thermo Nuclear gauges was not operating such that it could be completely closed per the manufacturer's design/specifications. This issue was discovered while Exxon Mobil was testing the integrity of all sources and source holders located in the area affected by the explosion that took place on February 18, 2015 (5010 #021815).
"At approximately 0900 [PST], [the RSO], along with a licensed Thermo Nuclear technician discovered that the Thermo Nuclear source holder, would not close completely, despite multiple attempts by the Thermo Nuclear technician. A radiation survey was performed around the source holder and the surrounding area was taped off with caution tape. The radiation level surrounding the source holder was found to be approximately 4 mR/hr. Exxon Mobil identified the source holder as Thermo Nuclear Model 5197, S/N CN-2435, with a 100 mCi Cs-137 source (S/N B8849).
"Upon discovery, [the RSO] immediately contacted LA County Radiation Management to report the findings. In addition to taping off the area, [the RSO] stated that the source is still in its normal position, approximately 10 feet from the ground and away from any routine traffic. Exxon Mobil has 24 gauges in the area that [were] impacted by the explosion on February 18, 2014. [The RSO] stated that only 11 gauges have been inspected thus far for leakage and damage. The remaining gauges will be inspected by the end of the week. Should Exxon Mobil discover another damaged source or source holder, they have been instructed to report the findings to LA County Radiation Management immediately."
California 5010 Number: 030415 |
| Power Reactor | Event Number: 50878 | Facility: SEQUOYAH
Region: 2 State: TN
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MATT JUNGELS
HQ OPS Officer: VINCE KLCO | Notification Date: 03/11/2015
Notification Time: 09:30 [ET]
Event Date: 03/11/2015
Event Time: 06:21 [EDT]
Last Update Date: 03/11/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
SCOTT SHAEFFER (R2DO)
|
| 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 A NUCLEAR INSTRUMENTATION SIGNAL
"At [0621 EDT] on 3/11/2015, Sequoyah Unit 1 reactor/turbine automatically tripped.
"Following the reactor trip, all safety-related equipment operated as designed. Auxiliary Feedwater automatically initiated as expected from the Feedwater Isolation Signal.
"Unit 1 is currently being maintained in Mode 3 at NOT/NOP, approximately 547 F and 2235 psig, with auxiliary feedwater supplying decay heat removal via the steam generators and condenser steam dumps.
"The immediate cause of the trip was a Power Range Nuclear Instrumentation negative rate signal, caused by a malfunction in the rod control system. There was no associated work in progress related to this and all systems were normally aligned.
"Current Temperature and Pressure - temperature is 547 degrees F and stable, pressure is 2235 psig and stable. There is no indication of any primary/secondary leakage. All rods are inserted. Electrical alignment is normal, supplied from Off-Site power. There is no operational impact to Unit 2. Unit 2 continues to operate in Mode 1 at 100%.
"There was no impact on public health and safety. Post-trip investigation is in progress and planned restart timeline has not yet been determined.
"The licensee notified the NRC Resident Inspector." |
| Power Reactor | Event Number: 50879 | Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [3] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: STEVE RADOMSKI
HQ OPS Officer: JEFF HERRERA | Notification Date: 03/11/2015
Notification Time: 11:54 [ET]
Event Date: 03/10/2015
Event Time: 18:14 [EDT]
Last Update Date: 03/11/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
| 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 | 100 | Power Operation | | 3 | N | N | 0 | Defueled | 0 | Defueled | Event Text NON-LICENSED SUPERVISORY EMPLOYEE TESTED POSITIVE FOR ALCOHOL
A non-licensed employee supervisor had a confirmed positive for alcohol during a random fitness-for-duty test. The employee's access to the plant has been terminated.
The NRC Resident Inspector was notified and the NY Public Service Commission will be notified. | |