| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
12/05/2013 - 12/06/2013 ** EVENT NUMBERS ** |
 | Non-Agreement State | Event Number: 49583 | Rep Org: AMERICAN ELECTRIC POWER
Licensee: AMERICAN ELECTRIC POWER
Region: 1
City: MOUNDSVILLE State: WV
County:
License #: GL 700076-18
Agreement: N
Docket:
NRC Notified By: DENISE POWELL
HQ OPS Officer: CHARLES TEAL | Notification Date: 11/26/2013
Notification Time: 14:27 [ET]
Event Date: 11/26/2013
Event Time: 12:00 [EST]
Last Update Date: 11/26/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
| Person (Organization):
DAN SCHROEDER (R1DO)
FSME EVENT RESOURCE (EMAI)
| Event Text PROCESS GAUGE SHUTTER CABLE FAILURE
The cable used to remotely operate the shutter for a fixed process gauge broke. The gauge is installed in a location that is not readily accessible by personnel. The normal position for the gauge is open. The gauge is currently open and in use. The licensee can manually close the shutter if needed. There were no personnel exposures.
The licensee has contacted the manufacturer to repair the cable.
The gauge is a Termo MeasureTech Model 5202, Serial Number B2813, containing 200 mCi of Cs-137. |
| Non-Agreement State | Event Number: 49584 | Rep Org: HARRISON STEEL CASTINGS
Licensee: HARRISON STEEL CASTINGS
Region: 3
City: ATTICA State: IN
County:
License #: 13-02141-01
Agreement: N
Docket:
NRC Notified By: DAVE HOLLANDER
HQ OPS Officer: CHARLES TEAL | Notification Date: 11/26/2013
Notification Time: 16:00 [ET]
Event Date: 11/25/2013
Event Time: 19:00 [EST]
Last Update Date: 11/27/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
| Person (Organization):
DAVID HILLS (R3DO)
FSME EVENT RESOURCE (EMAI)
| Event Text RADIOGRAPHY CAMERA LOCKING MECHANISM FAILURE
After the licensee completed an exposure and was retracting the source, the radiographer noticed that he did not hear the click of the posi-lock. The radiographer finished retracting the source using the hand crank.
The radiographer then entered the room using a radiac to ensure the source was in the safe position. He found that the spring for the posi-lock had broken. He manually locked the source in the camera and took it out of service.
The licensee will send the camera to the manufacturer for repair.
There were no overexposures to personnel as a result of this event.
* * * UPDATE AT 1043 ON 11/27/2013 FROM DAVE HOLLANDER TO MARK ABRAMOVITZ * * *
The projector (camera) is an Amersham 680BE, S/N BE132.
Notified the R3DO (Peterson) and FSME Event Resources via e-mail. |
| Agreement State | Event Number: 49587 | Rep Org: NEW YORK STATE DEPT. OF HEALTH
Licensee: UNSPECIFIED
Region: 1
City: State: NY
County:
License #:
Agreement: Y
Docket:
NRC Notified By: ROBERT SNYDER
HQ OPS Officer: DONG HWA PARK | Notification Date: 11/27/2013
Notification Time: 10:58 [ET]
Event Date: 10/30/2013
Event Time: [EST]
Last Update Date: 11/27/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
DAN SCHROEDER (R1DO)
FSME EVENTS RESOURCE (EMAI)
| Event Text AGREEMENT STATE REPORT - RADIOACTIVE SEED INCORRECTLY PLACED ON PATIENT
The following information was received by facsimile:
"Reported to NYS DOH [New York State Department of Health] on 11/12/2013. A patient received two seeds for right breast radioactive seed localization when only one was intended. The patient had two marker clips, a cylinder clip marking a benign biopsy site and a coil clip marking a papilloma. It was intended for her to only receive one seed placed at the papilloma site, but the benign site was marked with a 0.252 mCi iodine-125 seed. A second seed (0.251 mCi) was then placed to mark the correct site. The unintended dose from the 0.252 mCi seed in place for 2 days was 0.61 Gy @ 0.5 cm. Root cause analysis is ongoing."
Event Report Identification Number: NY-13-06
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. |
| Power Reactor | Event Number: 49606 | Facility: COMANCHE PEAK
Region: 4 State: TX
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MATT KARL
HQ OPS Officer: DANIEL MILLS | Notification Date: 12/04/2013
Notification Time: 15:14 [ET]
Event Date: 12/04/2013
Event Time: 13:50 [CST]
Last Update Date: 12/05/2013 | Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
MICHAEL VASQUEZ (R4DO)
WILLIAM GOTT (IRD)
JENNIFER UHLE (NRR)
MARK DAPAS (R4RA)
MARK KING (NRR)
|
| 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 UNUSUAL EVENT - LOSS OF STARTUP POWER DUE TO A CUT CABLE
"At 1343 CST on 12/04/2013, Comanche Peak Nuclear Power Plant experienced a loss of safeguards electrical power when 345KV transformer XST2 lost power from offsite while 138KV transformer XST1 was out of service for maintenance. Non-Safeguards electrical power remained energized. Both Units remain at power in Mode 1. Both units Emergency Diesel Generators automatically started and all safeguards busses were re-energized from the Emergency Diesel Generators. All ESF systems functioned as expected and the Turbine Driven Auxiliary Feedwater Pump automatically started as designed. Operators reduced reactor power to maintain reactor power less than 100 percent rated thermal power."
At 1350 CST, the licensee declared an Unusual Event due to losing both startup transformers. The cause of the loss of the second start up transformer was a cut cable. No one was injured during this event.
The licensee informed State and Local Government Agencies and the NRC Resident Inspector.
Notified other Federal Agencies (DHS SWO, FEMA Ops, DHS NICC, and Nuclear SSA via email).
* * * UPDATE AT 1718 EST ON 12/4/2013 FROM MATT KARL TO STEPHEN SANDIN * * *
Correction to initial event report description; actual loss of electrical power time was 1341 CST.
Include 8-HR Non-Emergency report for Specified System Actuation for automatic start of Auxiliary Feedwater and Emergency Diesel Generators.
Notified the R4DO (Vasquez).
* * * UPDATE FROM DAVE BUTLER TO JOHN SHOEMAKER AT 1840 EST ON 12/05/13 * * *
Comanche Peak terminated from the Unusual Event at 1717 CST on 12/05/13. Offsite power has been restored to both safeguard busses on both units via the transformer XST2. Work continues on transformer XST1. Comanche Peak Units 1 and 2 continue to operate at 100% power.
The licensee has notified the NRC Resident Inspector.
Notified R4DO (Vasquez), NRR EO (Bahadur), IRD MOC (Gott), and DHS SWO, FEMA Ops, DHS NICC, and Nuclear SSA via email. |
| Power Reactor | Event Number: 49608 | Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: THOMAS AGSTER
HQ OPS Officer: DONG HWA PARK | Notification Date: 12/05/2013
Notification Time: 05:40 [ET]
Event Date: 12/05/2013
Event Time: 03:25 [EST]
Last Update Date: 12/05/2013 | 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):
WILLIAM COOK (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | A/R | Y | 76 | Power Operation | 0 | Hot Shutdown | Event Text AUTOMATIC REACTOR SCRAM FOLLOWING TURBINE TRIP ON HIGH MOISTURE SEPARATOR LEVEL
"While operating at 76% power on 12/5/13 at 0325 EST, the main turbine tripped on moisture separator hi level. The reactor scrammed along with the main turbine trip. All safety systems responded as designed and expected. There was no radiological release. There were no injuries.
"During the scram, all rods inserted into the core. Plant is stable in Mode 3 in its normal S/D [shutdown] electrical line up. Decay heat is being removed via the turbine bypass valves dumping steam to the main condenser.
"At 0505 EST while securing from cooldown in an attempt to start a recirc pump, BPVs [Bypass Valve] opened causing reactor level swell and subsequent shrink. During this time, RPV [Reactor Pressure Vessel] level lowered to below RPV level 3 and caused a RPS [Reactor Protection System] actuation. RPV level was recovered and is now stable in normal band."
The licensee has notified the NRC Resident Inspector.
* * * UPDATE ON 12/5/13 AT 1000 EST FROM LINDSAY KOBERLEIN TO DONG PARK * * *
"This update to ENS #49608 adds reporting criterion 10CFR50.72(b)(3)(iv)(A) for the RPS actuation at 0505 EST during post-scram recovery."
The licensee notified the NRC Resident Inspector and the Lower Alloways Creek township. The licensee will be making a press release.
Notified R1DO (Cook). |
| Power Reactor | Event Number: 49609 | Facility: WATTS BAR
Region: 2 State: TN
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DAVID ALLEN
HQ OPS Officer: JEFF ROTTON | Notification Date: 12/05/2013
Notification Time: 11:07 [ET]
Event Date: 12/04/2013
Event Time: 13:35 [EST]
Last Update Date: 12/05/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
| 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 | N | 0 | Under Construction | 0 | Under Construction | Event Text FITNESS FOR DUTY - ALCOHOL FOUND IN PROTECTED AREA
"On December 4, 2013, at approximately 1335 EST with Watts Bar Nuclear Unit 1 at 100% power and Unit 2 under construction, a small whiskey bottle was found by a Unit 2 construction employee within the protected area. Site Security took possession of the bottle and it was removed from the protected area. The seal on the container did not appear to have been broken. An investigation has been initiated by Site Security. This condition has been documented in TVA's corrective action program as Service Request 818776. This report is submitted pursuant to 10 CFR 26.719 (b)(1) based on the presence of alcohol within the protected area.
"The licensee notified the NRC Resident Inspector."
Unit 2 does share the same protected area boundary as Unit 1. |
| Part 21 | Event Number: 49610 | Rep Org: GE HITACHI NUCLEAR ENERGY
Licensee: GE HITACHI NUCLEAR ENERGY
Region: 1
City: WILMINGTON State: NC
County:
License #:
Agreement: Y
Docket:
NRC Notified By: JIM HARRISON
HQ OPS Officer: JOHN SHOEMAKER | Notification Date: 12/05/2013
Notification Time: 16:35 [ET]
Event Date: 10/09/2013
Event Time: [EST]
Last Update Date: 12/05/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
| Person (Organization):
WILLIAM COOK (R1DO)
ANTHONY MASTERS (R2DO)
ERIC DUNCAN (R3DO)
MICHAEL VASQUEZ (R4DO)
PART 21 GROUP (EMAI)
| Event Text PART 21 - FAILURE OF RELAY LOGIC CARD MODULES IN 2 OUT OF 4 VOTERS FOR POWER RANGE MONITORS
The observed aging characteristics of the Solid State Relays on two particular Voter Relay Logic Cards Modules present a future challenge to the Power Range Neutron Monitoring System's ability to reliably insert the Average Power Range Monitor High-High/INOP scram and/or the Oscillating Power Range Monitor Scram to the Reactor Protection System in plant conditions warrant such action.
For Relay Logic Cards that have been in operation for over 10 years, Relay Logic Card Module replacement should be scheduled and accomplished at the first reasonable opportunity.
For Relay Logic Cards in operation for less than 10 years, a program should be implemented to replace Relay Logic Card Modules before the 10 years is reached.
Plant affected; Nine Mile Point 2, Fermi 2, Grand Gulf, Limerick 1 & 2, Peach Bottom 2 & 3, Susquehanna 1&2, Brunswick 1 & 2, Hatch 1 & 2, Browns Ferry 1, 2, & 3, Monticello, and Columbia. | |