Event Notification Report for November 03, 2016

SERVICE WATER LEAK IDENTIFIED IN THE VAPOR CONTAINMENT BUILDING

"At 0300 EDT on November 3, 2016, it was identified that a Service Water leak existed in the Vapor Containment Building of Indian Point Unit 3. The leak was determined to be from 31 Fan Cooler Unit and was subsequently isolated at 0344 EDT by shutting the Service Water isolation valves to 31 Fan Cooler Unit. This isolation meets the Technical Specification 3.6.1 Condition A Required Action. The leaking defect could have resulted in post-LOCA air leakage out of containment in excess of that allowed by Technical Specification 3.6.1 (Containment) which requires leakage rates to comply with 10 CFR 50, Appendix J. This event had no effect on the health and safety of the public.

"This event is being reported under 10 CFR 50.72(b)(3) and the guidance of NUREG 1022, section 3.2.7 as a loss of safety function."

The licensee notified the NRC Resident Inspector.

AGREEMENT STATE REPORT - FAILURE OF SOURCE TO RETRACT TO SAFE POSITION

The following report was received from the Illinois Emergency Management Agency via email:

"On Thursday, November 3, [2016] the licensee's Corporate RSO [Radiation Safety Officer] called to advised that one of their crews experienced a source retraction problem while at a temporary jobsite. Radiography shots were being taken with a nominal 60 Ci Ir-192 source at the Wood River Refinery, Wood River, IL. During a shot around 1230 [EDT] that afternoon it became obvious that the source would not retract using normal means. The crew contacted the local facility radiation safety officer to advise him of the event. The local radiation safety officer responded to the site within 30 minutes to discover that a portion of the drive cable assembly had been laid across a bare spot on a pipe that was otherwise insulated. The heat from the uninsulated section of pipe had caused the return side, cable housing coating to melt, forming an obstruction that the return cable could not pass. The RSO, having retrieved a source from a similar predicament in the past was able to quickly and efficiently cut the return side cable guide tube creating an open path for the cable and bypass the obstruction. The source was then able to be returned to the safe position without undue effort. The matter was resolved within an hour. The drive cable equipment has been removed from service. The camera was inspected and tested and put back into service. The direct ion storage dosimeter for the facility RSO was immediately analyzed at the end of the event and a dose of 3 mR was noted. Doses for the crew members were similarly analyzed and both found to be less than 30 mR since the last read which was performed at the end of the previous month. As the area being radiographed was on an overhead scaffold, no other personnel were in the work area at any time during the event other than the radiographers who maintained vigilance over the scene. A preliminary report with supporting photos was received the next day. Based on that report, an immediate investigation was not conducted at that time."

Device: Radiography Exposure Device
Manufacture: QSA Global
Equipment Serial Number: D10972
Source Serial Number: 32867G
Model Number: 880-D
Radionuclide: IR-192
Activity: 2168.2 GBq

Illinois Item Number: IL16011

PART 21 - NOTIFICATION OF DEVIATION - SOR QUALIFICATION TEST REPORT 9058-102

The following information was excerpted from a facsimile received by SOR:

Pursuant to the requirements of 10CFR Part 21, this letter notifies the NRC of a Part 21 condition. Irradiation testing performed since 1984 did not take into account all of the uncertainties associated with reported doses of gamma radiation to nuclear test specimens for qualification testing.

SOR contracted services with lsomedix in 1992 for the radiation aging that was performed per SOR nuclear qualification report 9058-102 Revision 1. Although SOR imposed Part 21 reporting requirements, lsomedix did not include SOR as part of their Part 21 notification. The Part 21 was brought to SOR's attention through an inquiry by a nuclear power station.

SOR requested a conference with Steris lsomedix which occurred on November 3, 2016. The teleconference confirmed that the subject radiation aging test results report would be affected by the Steris lsomedix Part 21. As a result, corrections are underway per qualification test report 9058-102 regarding the uncertainty calculations.

SOR does not have the capability to perform further evaluations to determine if a safety hazard exists as the specific customer application is unknown. The end user must confirm for each application that the qualified life dose + accident dose + 10% of accident dose is less than or equal to the corrected values.

SOR is currently identifying all customers potentially affected by this deviation. At the conclusion of this activity, SOR will notify the customers and the U.S. Nuclear Regulatory Commission in accordance with the requirements of 10 CFR Part 21.

* * * UPDATE FROM MELANIE DIRKS TO JOHN SHOEMAKER AT 1455 EST ON 12/2/16 * * *

The following is an excerpt of an updated Part 21 received via email:

"Corrections are now complete to test report 9058-102 regarding the uncertainty calculations. The calculations changed from 8% uncertainty to 9.6% uncertainty for the minimum irradiation aging.

"SOR does not have the capability to perform further evaluations to determine if a safety hazard exists as the specific customer application is unknown. The end user must confirm for each application that the qualified life dose + accident dose + 10% of accident dose is less than or equal to the above noted values."

Should you have any additional questions regarding this matter, please contact:

Linda Coutts
Inside Sales Representative
Email: lcoutts@sorinc.com
Tel 91.3ú-956ú-3071

Charles Lautner
Customer Service Manager
Email: clautner@sorinc.com
Tel 913-956-3070

Notified R1DO (Bower), R2DO (McCoy), R3DO (Stoedter), R4DO (Haire), NMSS_Events_Notification, and Part 21/50.55 Reactors via email.

AGREEMENT STATE REPORT - LEAKING KR-85 SOURCE DURING TRANSFER TO APPROVED SHIPPING CONTAINER

The following report was received from the Louisiana Department of Environmental Quality via email:

"On the 3rd of November, 2016, QSA Global, Inc. had an incident during the transfer of Kr-85 sources to approved shipping containers for transportation to Qual-X, Inc. for recycling. The work was being preformed at approximately 1530 to 1600 hrs. [CST]. After the completion of the work, there was no indication at that time of any possible leakage.

"At approximately 1800 hrs., it was noticed that the scintillation counter background had a slightly higher than normal background reading. It was determined that the only possible cause was the Kr-85 sources, as that is all that QSA Global, Inc. had worked with that day. A visual inspection of the possible leaking Kr-85 sources was performed. There was no damage to any of the windows, but QSA Global, Inc. now knows that was the point of origin of the contamination due to the surveys of the lead container that they were stored in. The sources were sealed in a 10 gallon steel drum and then placed in a plastic bag to prevent any additional release of material.

"The sources involved are LFE Model S-70A s/n 9234 at 168 mCi, 9332 at 184 mCi and 9333 at 184 mCi. The original activity of these sources was 1200 mCi.

"The building was ventilated using fans to remove the Kr-85 that had accumulated in the building. The building was surveyed at 0230 hrs. [on November 4, 2016] with no contamination detected. Another survey of the building was performed again at 0530 again with no contamination found.

"After QSA Global discussed the situation with Qual-X, Inc. and using their expertise in these types of situations, it was determined from survey readings and building size, that an estimated amount of less than 1-2 mCi may have been released. They also indicated that the sources were of the type that are known to leak due to the way they are manufactured and their age being 29 years. At this point QSA Global, Inc. believes that all three may be leaking."

Event Report ID No.: LA160015