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Event Notification Report for January 15, 2013

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
01/14/2013 - 01/15/2013

** EVENT NUMBERS **


48392 48655 48670 48672 48673

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Agreement State Event Number: 48392
Rep Org: ARKANSAS DEPARTMENT OF HEALTH
Licensee: APPLIED INSPECTION SYSTEMS, INC.
Region: 4
City: FAYETTEVILLE State: AR
County:
License #: ARK-0572-0332
Agreement: Y
Docket:
NRC Notified By: STEVE MACK
HQ OPS Officer: HOWIE CROUCH
Notification Date: 10/09/2012
Notification Time: 16:13 [ET]
Event Date: 10/08/2012
Event Time: [CDT]
Last Update Date: 01/14/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
DON ALLEN (R4DO)
FSME EVENTS RESOURCE (EMAI)

Event Text

AGREEMENT STATE REPORT - RADIOGRAPHY CAMERA SOURCE DISCONNECTED

The following information was obtained from the State of Arkansas via email:

"The Arkansas Department of Health [the Department] was notified on October 8, 2012 at 1345 [hrs. CDT], by the licensee, of a source disconnect. The radiography crew had completed a radiograph of a pipe weld and was unable to retract the source into the shielded position. The licensee's RSO was notified, the boundaries were verified and the radiography crew made several attempts to retract the source. The crank-out device was disassembled and the crew manually pulled the cable and discovered that the drive cable had separated.

"The licensee contacted Source Production & Equipment Company (SPEC) for source retrieval. Licensee representatives remained on-site and maintained direct surveillance awaiting the arrival of the source retrieval team. SPEC personnel arrived on site on October 9, 2012 and were able to retrieve the source into the radiography camera.

"The Department sent two Health Physicists to observe the source retrieval.

"Equipment involved: Radiography Camera is a SPEC 150, SN # 1357, radiography source is a SPEC G-60, SN # TH0302 containing [redacted] Iridium-192.

"The camera was inspected by SPEC personnel and the source leak tested. After the associated equipment (crank-out and guide tube) were replaced, the camera was returned to service.

"The Department is awaiting a report from SPEC and from the licensee.

"The Arkansas Department of Health, Radioactive Materials Program, Event Number is AR-2012-012"

* * * UPDATE AT 1555 EDT ON 10/16/12 FROM KRIESEL TO HUFFMAN * * *

The Arkansas Department of Health, Radioactive Materials Program, reported that the SPEC source retrieval crew received exposures of 12 mR for individual #1 and 10 mR for individual #2 during retrieval of the source back into the radiography camera.

R4DO(Pick) notified and a copy of this update was e-mailed to FSME Events Resource.

* * * UPDATE AT 1314 EST ON 01/14/13 FROM PEMBERTON TO ALEXANDER * * *

The Arkansas Department of Health reported that it received the final reports from SPEC and Applied Inspections Systems (the licensee). SPEC has found that their investigation of the failure of the drive cable to be inconclusive. The Arkansas Department of Health has concluded that the root cause of this incident cannot be determined from the data available.

Since the exposure device and source involved in the incident were certified for use and returned to service by SPEC personnel, the Arkansas Department of Health considers this event closed.

R4DO (Vasquez) notified and a copy of this update was e-mailed to FSME Events Resource.

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Agreement State Event Number: 48655
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: UNIVERSITY OF CALIFORNIA, SANTA CRUZ
Region: 4
City: SANTA CRUZ State: CA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: GENE FORRER
HQ OPS Officer: BILL HUFFMAN
Notification Date: 01/07/2013
Notification Time: 15:27 [ET]
Event Date: 11/13/2012
Event Time: 13:00 [PST]
Last Update Date: 01/07/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
VINCENT GADDY (R4DO)
FSME_EVENTS_RESOURCE (E-MA)

Event Text

AGREEMENT STATE REPORT - DAMAGE TO AM-241 SPECTROSCOPY SOURCE

The State of California Radiologic Health Branch forwarded the following report via e-mail:

"(1) A description of the event, including the probable cause and the manufacturer and model number (if applicable) of any equipment that failed or malfunctioned;

"A small alpha spectroscopy style source was damaged by a researcher who placed adhesive tape on the active source area. The source appears similar to an Isotope Products A-2 type.

"Removal of the tape lifted the active material and transferred it to the tape.

"Records of the source manufacturer were not available.

"(2) The exact location of the event;

"Room 369 GLAST Laboratory, Natural Sciences II Building, UC Santa Cruz campus.

"(3) The isotopes, quantities, and chemical and physical form of the licensed material involved;

"Am-241 solid, ~1 micro curie total, plated metal

"(4) Dale and time of the event;

"Occurrence on 11-13-2012 about 1:00 pm

"(5) Corrective actions taken or planned and the results of any evaluation or assessment;

"a. Suspend individual involved and laboratory supervisor until re-qualified by radiation safety on proper techniques for source handling. (Completed)
"b. Laboratory supervisor to retrain all users in specific laboratory on proper source handling. (Scheduled to be completed by 3-15-2013)
"c. Update online training materials to include information about fragility of certain types of sources. (Scheduled for 2-1-2013)
"d. Include information on the event in the next radiation safety newsletter. (Scheduled for 3-1-2013)
"e. Remove obviously damaged source from service. (Completed)
"f. Re-inspect similar sources and remove any damaged or suspect sources from service. (Scheduled for 2-15-2013)

"(6) The extent of exposure of individuals to radiation or to radioactive materials without identification of individuals by name.

"No exposure or contamination was identified in surveys conducted the day of the event."

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Power Reactor Event Number: 48670
Facility: HARRIS
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP
NRC Notified By: RICHARD HONEYCUTT
HQ OPS Officer: RYAN ALEXANDER
Notification Date: 01/14/2013
Notification Time: 08:44 [ET]
Event Date: 01/14/2013
Event Time: 08:40 [EST]
Last Update Date: 01/14/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
MARK FRANKE (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

Event Text

LOSS OF ASSESSMENT CAPABILITY - RADIATION MONITORS INOPERABLE FOR PRE-PLANNED MAINTENANCE

"This is a non-emergency notification. At approximately 08:40 EST on January 14, 2013, radiation monitor RM-01TV-3547-1, Waste Processing Building Vent Stack 5A Wide Range Gas Monitor (WRGM) will be declared inoperable for pre-planned maintenance. MST-I0377, WPB Stack 5A Accident Monitor Channel Calibration will be performed. The maintenance activity is expected to complete January 15, 2013.

"This radiation monitor is necessary for accident assessment and is credited for Emergency Action Level (EAL) classification in the Harris Nuclear Plant Emergency Plan. Inability to classify an EAL due to an out of service monitor is considered a loss of accident assessment capability and is reportable per 10 CFR 50.72(b)(3)(xiii) as described in NUREG-1022, Rev. 2. This condition does not affect the health of safety of the public or the operation of the facility.

"The NRC Resident Inspectors have been notified."

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Power Reactor Event Number: 48672
Facility: FARLEY
Region: 2 State: AL
Unit: [1] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: CHARLES BAREFIELD
HQ OPS Officer: STEVE SANDIN
Notification Date: 01/14/2013
Notification Time: 17:52 [ET]
Event Date: 01/14/2013
Event Time: 12:55 [CST]
Last Update Date: 01/14/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
MARK FRANKE (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

Event Text

TECHNICAL SUPPORT CENTER OUT-OF-SERVICE DUE TO FAILED AIR CONDITIONING BELT

"The facility Technical Support Center (TSC) was rendered non-functional due to a malfunctioning TSC ventilation system. The TSC HVAC Air Handling Unit fan belt broke rendering the air conditioning non functional. Repairs have been completed and the unit has been returned to service however, the out of service time was greater than 30 minutes which by the station's reporting procedures is an 8 hour non-emergency report. The out of service time was from 1225 to 1630 [CST].

"Compensatory measures per site procedure FNP-0-EIP-6.0 (TSC Setup and Activation) for maintaining emergency assessment, off-site response, and off-site communication capabilities were immediately put in place. These measures include the conditional relocation of the TSC staff in the event of a declared emergency if the Emergency Director deems the TSC to be uninhabitable."

The licensee informed the NRC Resident Inspector.

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Power Reactor Event Number: 48673
Facility: GRAND GULF
Region: 4 State: MS
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: HARDY FARRIS
HQ OPS Officer: VINCE KLCO
Notification Date: 01/14/2013
Notification Time: 22:04 [ET]
Event Date: 01/14/2013
Event Time: 18:05 [CST]
Last Update Date: 01/14/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
MICHAEL VASQUEZ (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 Shutdown

Event Text

AUTOMATIC REACTOR SCRAM FROM 100% POWER DUE TO A TURBINE/GENERATOR TRIP

"Actuation of RPS [Reactor Protection System] with reactor critical. The Reactor Scram occurred at 1805 [CST] 01/14/13 from 100% CTP [Core Thermal Power]. The cause of scram appears to be a Turbine Generator Trip.

"05-S-01-EP-2 RPV Control, Reactor Scram ONEP [Off Normal Event Procedure] 05-1-02-I-1, and Turbine and Generator Trips ONEP 05-1-02-1-2 were entered to mitigate the transient with all systems responding as designed. No loss of offsite or ESF power occurred. No ECCS initiation signals were reached and no ECCS or Diesel Generator initiation occurred.

"All control rods are fully inserted. MSIVs remained open and SRVs lifted and reseated as designed. Currently, reactor water level is being maintained by the Condensate and Feedwater system in the normal band and reactor pressure is being controlled via Main Turbine Bypass valves to the main condenser. There are no challenges to Primary or Secondary Containment at this time."

The licensee notified the NRC Resident Inspector.

Page Last Reviewed/Updated Tuesday, January 15, 2013
Tuesday, January 15, 2013