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Event Notification Report for June 03, 2015

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
06/02/2015 - 06/03/2015

EVENT NUMBERS
51121511255111651243

Agreement State
Event Number: 51121
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: LEIGHTON & ASSOCIATES
Region: 4
City: IRVINE   State: CA
County:
License #: 3109-30
Agreement: Y
Docket:
NRC Notified By: ROBERT GREGER
HQ OPS Officer: DONALD NORWOOD
Notification Date: 06/04/2015
Notification Time: 14:32 [ET]
Event Date: 06/03/2015
Event Time: 00:00 [PDT]
Last Update Date: 06/04/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
Person (Organization):
JACK WHITTEN (R4DO)
NMSS_EVENTS_NOTIFICA (EMAI)
DAVEY TOTTERER (ILTA)
CNSNS (MEXICO) (FAX)
Event Text
AGREEMENT STATE REPORT - STOLEN MOISTURE/DENSITY GAUGE

The following information was received via E-mail.

"On June 3, 2015, Leighton & Associates notified RHB [California Department of Public Health, Radiologic Health Branch] that a moisture/density gauge was stolen from a pick-up truck's bed at a temporary job site in Riverside that morning. The gauge is a 2014 InstroTek model MC-3 Elite, s/n 30481, containing a 10 mCi Cs-137 source, s/n CZ4587 and a 50 mCi Am-241/Be source, s/n 038/14.

"The authorized gauge technician reported the security cables were cut and the density gauge was missing while he was parked at the job site but away from his vehicle. He immediately notified his RSO and the Riverside Police, who took report number P15-082748. RHB's inspector spoke with the RSO and recommended that a lost and found ad be placed in the local newspaper offering a cash reward for the return of the stolen gauge and requested additional information from the responsible technician. The Inspection/Compliance/Enforcement section will review the security measures that were in place to determine if a violation of their license condition took place."

California 5010 Report Number: 060315

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: 51125
Rep Org: TEXAS DEPT OF STATE HEALTH SERVICES
Licensee: BASF CORPORATION
Region: 4
City: FREEPORT   State: TX
County:
License #: 01021
Agreement: Y
Docket:
NRC Notified By: KAREN BLANCHARD
HQ OPS Officer: DONALD NORWOOD
Notification Date: 06/04/2015
Notification Time: 18:10 [ET]
Event Date: 06/03/2015
Event Time: 00:00 [CDT]
Last Update Date: 06/04/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
Person (Organization):
JACK WHITTEN (R4DO)
NMSS_EVENTS_NOTIFICA (EMAI)
Event Text
AGREEMENT STATE REPORT - FAILURE OF SHUTTERS ON FOUR FIXED NUCLEAR GAUGES TO CLOSE

The following information was received via E-mail:

"On June 4, 2015, the licensee notified the Agency [Texas Department of State Health Services] that on June 3, 2015, it was performing routine shutter checks on fixed nuclear gauges at its facility and found the shutters on four of the gauges would not close. All four gauges were Ronan Model SA-1 containing cesium-137 sources (20, 40, 50, and 200 millicuries). The licensee lubricated the shutter mechanisms on all four gauges and let them sit overnight. Two of the gauges closed the next morning (June 4th) with no problem. The other two shutters still would not close. The licensee contacted an outside service group and it recommended using a different lubricant. The licensee followed the suggestion and both became operable that afternoon. These gauges normally operate with the shutter in the open position. There were no radiation exposures or increased risk of exposure as a result of this event. An investigation into this event is ongoing. More information will be provided as it is obtained in accordance with SA-300."

Texas Incident Number: I-9318


Power Reactor
Event Number: 51116
Facility: WATERFORD
Region: 4     State: LA
Unit: [3] [] []
RX Type: [3] CE
NRC Notified By: SCOTT MEIKLEJOHN
HQ OPS Officer: DONG HWA PARK
Notification Date: 06/03/2015
Notification Time: 21:36 [ET]
Event Date: 06/03/2015
Event Time: 17:05 [CDT]
Last Update Date: 06/03/2015
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):
JACK WHITTEN (R4DO)
SCOTT MORRIS (NRR)
WILLIAM GOTT (IRD)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
3 M/R Y 100 Power Operation 0 Hot Standby
Event Text
MANUAL REACTOR TRIP DUE TO LOSS OF MAIN FEEDWATER PUMP

"This is a non-emergency notification from Waterford 3.

"At 1705 [CDT] the reactor was manually tripped in anticipation of an automatic trip due to loss of main feedwater pump 'A'.

"The plant is currently in mode 3 and stable with emergency feedwater feeding and maintaining both steam generators due to an automatic emergency feed actuation signal.

"During the trip, the 'B' electrical safety and non safety busses did not automatically transfer from the unit auxiliary transformer to the startup transformer causing a loss of off-site power to the 'B' electrical busses. This resulted in a loss of main feedwater pump 'B'.

"The 'B' emergency diesel generator started as designed and reenergized the 'B' safety related buses.

"The plant entered the emergency operating procedure for loss of main feedwater.

"Off-site power has been restored to the 'B' safety and non safety busses, and the emergency diesel generator 'B' is secured.

All control rods fully inserted into the core following the trip. Decay heat is being removed by the main condenser using the turbine bypass valves. The electric plant is in a normal shutdown lineup.

The licensee has notified the NRC Resident Inspector.


Part 21
Event Number: 51243
Rep Org: UNITED CONTROLS INTERNATIONAL
Licensee: UNITED CONTROLS INTERNATIONAL
Region: 1
City: NORCROSS   State: GA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: WILLIAM MALLIA
HQ OPS Officer: JEFF HERRERA
Notification Date: 07/20/2015
Notification Time: 16:48 [ET]
Event Date: 06/03/2015
Event Time: 00:00 [EDT]
Last Update Date: 07/20/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(a)(2) - INTERIM EVAL OF DEVIATION
Person (Organization):
MICHAEL F. KING (R2DO)
HEATHER GEPFORD (R4DO)
PART 21/50.55 REACT (EMAI)
Event Text
POTENTIAL PART 21 - ALLEN BRADLEY FAILURE TO DOCUMENT DESIGN CHANGE

The following information is excerpted from an email received from United Controls International:

"[In] August 2014, United Controls supplied four (4) time delay relays to Omaha Public Power-Fort Calhoun Station. The subject relay was qualified in accordance with IEEE 323-74/83, IEEE 344-1975/1987 and IEEE C37.98-1987, for use in mild environment safety related applications.

"Per NRC Part 21 notifications, UCI was informed that the Allen Bradley relays base model 700RTC contain a Complex Programmable Logic Device (CPLD) which was unpublished. This design change could not be noticed since the external appearance of the relay and the relay part number remained the same. Hence, UCI has qualified the subject relay as solid state relay whereas the presence of the CPLD device elects the item as a digital device which can be affected by EMI/RFI noises.

"At this time, UCI has no sufficient information to determine whether this design change would create a Substantial Safety Hazard as it relates to the plant applications for the subject relay.

"Per the Nutherm Part 21 ML 1516IA230, Allen Bradley has indicated that a rolling change occurred from mid-2009 with no specific manufacturing date to distinguish between the old and the new configuration. Hence, all units manufactured during 2009 and later are suspect.

"If you have any questions or wish to discuss this matter or this report, please contact:

"Jim Garrison
"Engineering Manager
"jgarrison@unitedcontrols.com
"770-496-1406 x 103"

Affected facility: Omaha Public Power-Fort Calhoun Station
Part Number: 700-RTC-11200U1
Quantity: 4