Event Notification Report for July 06, 2016

MANUAL REACTOR TRIP AND UNUSUAL EVENT DECLARATION DUE TO STEAM LEAK IN TURBINE BUILDING

"On July 6, 2016, at 0038 [EDT], DC Cook Unit 2 Reactor was manually tripped and at 0050 [EDT] an Unusual Event (N-7 'Unanticipated Explosion') Emergency Declaration was made due to steam leak and associated damage to the turbine building.

"In accordance with Emergency Plan procedures, notifications of Berrien County and State of Michigan were completed. The licensee has notified the NRC Senior Resident Inspector. The Unusual Event was terminated at 0207 [EDT].

"This notification is being made in accordance with 10 CFR 50.72 (a)(1)(i) due to declaration of an emergency class. Original notification to NRC made at 0100 EDT via ENS. This event is reportable under 10 CFR 50.72(b)(2)(iv)(B), Reactor Protection System (RPS) actuation and 10 CFR 50.72(b)(2)(xi) Offsite Notification, as a four (4) hour report, and under 10 CFR 50.72(b)(3)(iv)(A), specified system actuation of the Auxiliary Feedwater System, as an eight (8) hour report. The DC Cook NRC Resident Inspector has been notified. A press release is planned.

"Unit 2 is being supplied by offsite power. All control rods fully inserted. Decay heat is being removed via Steam Generator PORVs [Power Operated Relief Valve]. Preliminary evaluation indicates all plant systems functioned normally following the reactor trip. DC Cook Unit 2 remains stable in Mode 3 while conducting the Post Trip Review. No radioactive release is in progress as a result of this event."

Notified DHS SWO, FEMA Ops Center, DHS NICC. Notified FEMA National Watch and Nuclear SSA via email.

AGREEMENT STATE REPORT - DAMAGED MOISTURE DENSITY GAUGE

The following information was received from the State of Texas via email:

"On July 6, 2016, the licensee reported to the Agency [Texas Department of State Health Services] that one of its moisture density gauges had been run over and damaged, a Troxler Model 3411 containing 10 millicurie cesium-137 source and a 40 millicurie americium-241/beryllium source, serial number 10471 [at a highway construction site near Robstown, TX]. The technician had started the test and the source rod was extended into the ground. While the test was in progress the step-up grader hit the gauge, causing the source rod to bend. The technician stopped all work at the jobsite and setup a boundary of fifteen feet because the source rod could not be retracted. The technician called the RSO [Radiation Safety Officer] and RSO contacted a service company, Qual-Tek, to respond to the site to retrieve the gauge. The site foreman moved the road crew down the highway to avoid the gauge. The technician will stay at the site near the gauge until it is collected by Qual-Tek. [The RSO is investigating.] No member of the public or worker received any exposure as a result of this event. An update will be provided as obtained in accordance with SA300."

Texas Incident: I-9417

AUTOMATIC REACTOR TRIP WHILE PERFORMING TESTING

"On July 6, 2016 at 0938 EDT Indian Point Unit 2 experienced a trip from 100% steady state power during the performance of reactor protection testing. The cause of the trip is under investigation.

"All control rods fully inserted and all systems responded as expected. The auxiliary feedwater system actuated as expected on a low level in the steam generators which occurs as a result of a trip from full power. Auxiliary feedwater is maintaining steam generator levels and decay heat removal is via the steam generators to the main condenser.

"Offsite power and plant electrical line ups are normal with the exception of 13.8kV feeder 33332 which remains out of service during the replacement of breaker BT4-5.

"No primary or secondary code safety relief valves lifted. The reactor is in Mode 3 and stable.

"Indian Point Unit 3 was unaffected and remains at 100% steady state power.

"The NRC Resident Inspector has been notified."

The licensee notified the New York Public Service Commission and the New York Independent System Operator. Indian Point indicated they have issued a press release regarding the event.

AGREEMENT STATE REPORT - MISSING GENERALLY LICENSED DEVICE

The following information was received from the State of Tennessee via email:

"A licensee reported a generally licensed device as missing. Further details will be reported as the information becomes available. The specifics on the device are as follows: Manufacturer- Industrial Dynamics, Model-FT-50B, Serial-113439, Isotope-Am-241, Activity-100 mCi."

State Event Report ID No.: TN-16-098

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

OFFSITE NOTIFICATION TO THE UNITED STATES DEPARTMENT OF TRANSPORTATION

"In accordance with 10 CFR 50.72(b)(2)(xi), Duke Energy is notifying the NRC of a report made to the Department of Transportation concerning the identification of removable contamination in excess of 49 CFR 173.443(a) limits. This report was made at 1807 Eastern Daylight Time (EDT).

"On July 6, 2016, an EnergySolutions 3-60B Transportation Package was received onsite. As a result of receipt surveys, Brunswick Health Physics personnel confirmed removable surface contamination on the transportation package in excess of 49 CFR 173.443(a) limits. The package was shipped as UN2910, Radioactive material, excepted package-limited quantity of material, 7, and was consigned as a non-exclusive use shipment.

"Surveys identified mixed beta/gamma contamination ranging from approximately 2500 to 4500 dpm/100 sq cm on the surface of the transportation package. All other smears taken on the cask raincover, trailer bed and tires were less than minimum detectable activity for removable contamination.

"The transportation package is located in a radiological controlled area and access is controlled by Radiation Protection. Surveys have confirmed that the contamination is limited to the surface of the cask. In addition, no personnel contamination events have been attributed to the contamination found on the transportation package.

"This event did not result in any adverse impact to the health and safety of the public.

"The NRC Resident [Inspector] has been notified.

"The safety significance of this condition is minimal. There is no indication of onsite or personnel contamination as a result of this event.

"The transportation package is controlled in a radiological controlled area and access is controlled by Radiation Protection."

The originator of the empty cask arriving at the site (Westinghouse-Pittsburgh) was notified of the contamination. The cask is used for control rod blades and local power range neutron monitoring string shipping.