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Event Notification Report for April 07, 2016

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
04/06/2016 - 04/07/2016

EVENT NUMBERS
51857519065185651854

Agreement State
Event Number: 51857
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: GEO-ADVANTEC, INC.
Region: 4
City: SAN DIMAS   State: CA
County:
License #: 7949-19
Agreement: Y
Docket:
NRC Notified By: DONALD OESTERLE
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 04/08/2016
Notification Time: 13:10 [ET]
Event Date: 04/07/2016
Event Time: 00:00 [PDT]
Last Update Date: 04/08/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
Person (Organization):
RAY KELLAR (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)
Event Text
AGREEMENT STATE REPORT - DAMAGED MOISTURE DENSITY GAUGE

The following report was received from the State of California via email:

"On April 7, 2016, [the licensee gauge operator] for Geo-Advantec, Inc., contacted the California Office of Emergency Services to report a moisture density gauge, a CPN Model MC3 Elite (10 mCi Cs-137, 50 mCi Am:Be-241, S/N30625), was run over by an unknown type of vehicle. The incident occurred at 2003 Speyer Lane, Redondo Beach, CA. After taking the report, the report was forwarded to the Los Angeles County Radiation Management which was then forwarded to Brea office of Radiologic Health Branch (RHB).

"[The licensee gauge operator] was contacted by a RHB inspector and stated that the gauge had been run over and that the source rod had been broken. He was also asked if the Cs-137 source had been exposed, and he stated that he was taking a standard count and that the source was in the shielded position at the time of the incident. [The licensee gauge operator] was then asked to take pictures of the gauge so that it could be evaluated to determine if the sources were still intact and to determine the extent of the damage to the gauge. The pictures indicated that the source rod was broken approximately 1-2 inches below the bottom of the guide tube, which had broken off the source shield, and that the rest of the source rod appeared to be inside the opening on the top part of the source shield. The Am:Be-241 source appeared to be intact and still attached to the body of gauge. [The licensee gauge operator] was instructed to place the body of the gauge into the transport case in its normal position and then place the rest of the pieces of the gauge into the case. He was also instructed to lock the case and secure it into the transport vehicle as normal. He was then instructed to check ground below the gauge to verify that the source was not exposed during the incident. After [the licensee gauge operator] verified that there were no signs of the source having been extended during the incident, he was instructed to mark the area where the gauge was damaged to ensure that area could be found if a survey was needed and then he was allowed to transport the gauge to Maurer Technical Services (MTS) to be inspected and surveyed to ensure the sources were still in the gauge and to verify they were intact.

"When the gauge arrived at Maurer Technical Services, a survey was performed by the MTS RSO [Radiation Safety Officer] (meter type not reported). The gauge had contact reading of 8.5 mR/hr, which was consistent with a CPN MC3 moisture/density gauge with both sources in their shielded positon. The RSO also took swipes of the device, the hands of the operator and the trunk of the operator's car. An RHB inspector arrived at MTS to perform a count of the swipes with a Ludlum general purpose meter and a 44-9 Geiger-Mueller probe and found all of the swipes were at background, indicating that there was not leakage and the sources were intact. The gauge will be stored at MTS until disposal of the gauge can be arranged.

"The investigation is on-going and any citations will be determined at a later date."

CA 5010 # 040716.


Agreement State
Event Number: 51906
Rep Org: FLORIDA BUREAU OF RADIATION CONTROL
Licensee: JAMES HARDIE BUILDING PRODUCTS
Region: 1
City: PLANT CITY   State: FL
County:
License #: G0663-1
Agreement: Y
Docket:
NRC Notified By: RENO FABII
HQ OPS Officer: HOWIE CROUCH
Notification Date: 05/04/2016
Notification Time: 09:27 [ET]
Event Date: 04/07/2016
Event Time: 00:00 [EDT]
Last Update Date: 05/04/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
Person (Organization):
FRED BOWER (R1DO)
NMSS_EVENTS_NOTIFIC (EMAI)
Event Text
FLORIDA AGREEMENT STATE REPORT - LOST RADIOACTIVE THICKNESS GAUGE

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

"An audit conducted on James Hardie Building Products on April 4th, 2016 discovered a thickness gauge (NDC Model 102) was unaccounted for. The company was in the process of transferring equipment and under going an expansion. The auditor gave the company time to search for the device. As of 5/4/2016 all nine (9) of their facilities have been searched and the gauge has not been found. The last positive 'eyes on' sighting of device occurred in 2013 at the Plant City facility. The device was locked down to a wooden pallet. New policies and procedures are being implemented by James Hardie Building Products."

Although the audit was completed on April 4, 2016, the licensee did not conclude their search of all their facilities until April 7, 2016. The gauge was an NDC Systems Model 102, serial number 11838, containing 25 mCi of Am-241.

Florida Incident Number: FL16-059

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: 51856
Facility: NINE MILE POINT
Region: 1     State: NY
Unit: [] [2] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: CARL JONES
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 04/07/2016
Notification Time: 22:32 [ET]
Event Date: 04/07/2016
Event Time: 17:30 [EDT]
Last Update Date: 04/07/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
DON JACKSON (R1DO)
Power Reactor Unit Info
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
BOTH DOORS OF SECONDARY CONTAINMENT OPEN SIMULTANEOUSLY

"Nine Mile Point Unit 2 (NMP2) experienced a momentary loss of Secondary Containment due to both Reactor Building (RB) airlock doors being opened at the same time.

"At 1730 [EDT] on 04/07/16, both RB airlock doors were opened simultaneously for less than 5 seconds. This resulted in Secondary Containment being declared Inoperable (TS 3.6.4.1). Secondary Containment was restored to Operable when the doors were closed.

"The event is reportable in accordance with 10 CFR 50.72(b)(3)(v)(C), 'Any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to control the release of radioactive material.'

"The condition has been entered into the station's corrective action program and the NRC Resident Inspector has been notified."

There is no interlock on these doors, just lights to verify the opposite door is open or shut. An Operator was entering secondary containment as another Operator was leaving.


Power Reactor
Event Number: 51854
Facility: SEQUOYAH
Region: 2     State: TN
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: XAVIER DECAMBRA
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 04/07/2016
Notification Time: 18:01 [ET]
Event Date: 04/07/2016
Event Time: 15:07 [EDT]
Last Update Date: 04/07/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
REBECCA NEASE (R2DO)
Power Reactor Unit Info
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
UNANALYZED CONDITION - HIGH PRESSURE FIRE SUPPRESSION ISOLATED FROM CONTAINMENT

"This notification is being made as the result of the review of an occurrence on March 30, 2016 at 2220 [EDT] that resulted when a major portion of the site high pressure fire protection (HPFP) system, including fire suppression capabilities for the Main Turbine Building, Auxiliary Building, Control Building, Diesel Generator Buildings, and both Unit 1 and Unit 2 Containments were isolated without having the required compensatory suppression systems established. Upon discovery of the non-functional HPFP system, compensatory fire watches were established and an alternate means to provide water to the HPFP system was aligned.

"A review of the Sequoyah Nuclear Plant (SQN) Safe Shutdown Analysis identified this loss of fire suppression may not have ensured the required equipment remained available under certain postulated fire scenarios. The analysis determined that the effects of a postulated fire in specific fire areas could have prevented critical systems or components from performing their intended functions, potentially resulting in the inability to achieve and maintain safe shutdown.

"Analysis identified areas which credit the availability of fire suppression to assure that the safe shutdown capability could have been achieved, the site did not have fire suppression for approximately 45 hours.

"No actual fire occurred or existed during the time the fire suppression system was not functional. Installed fire detection equipment and communication to the Main Control Room remained available.

"The condition has been corrected and the HPFP system is functional.

"At the time of the non-functional HPFP system, it was not recognized that an unanalyzed condition that could have significantly degraded plant safety existed. The condition placed both Unit 1 and Unit 2 in an unanalyzed condition that significantly degraded plant safety and is reportable under 10 CFR 50.72(b)(3)(ii)(B). This 8-hour non emergency notification is being made in accordance with 10 CFR 50.72(b)(3)(ii)(B). The condition has been entered into the licensee's corrective action program (CR 1155763) and a License Event Report will be submitted.

"The NRC Resident Inspector has been notified of this condition."

The original clearance that created this event was satisfactory as written, however, one of the valves was leaking and the clearance boundaries were expanded. The clearance was issued at 1411 EDT on 3/29/2016.