Event Notification Report for November 18, 2016

PART 21 NOTIFICATION - CONTROL ROD GUIDE CARD EXCESSIVE WEAR

The following report is excerpted from Westinghouse fax LTR-NRC-16-74:

"Westinghouse nuclear steam supply system (NSSS) plants that are using iron nitride rod cluster control assemblies (RCCAs) in conjunction with Westinghouse 17x17 A or 17x17 AS style guide tubes (GTs), the GT guide card wear inspection guidance provided in Westinghouse report WCAP-17451-P, Revision 1, is not conservative.

"Based on the data, a determination was made as to whether an affected plant could exceed its permissible number of worn guide cards before completing its first guide card wear measurement (GCWM) inspection, the timing of which is based on recommendations documented in the WCAP. The concern associated with exceeding the permissible number of worn guide cards is that a rodlet might slip out of alignment with the GT guide card fingers and become stuck. For example, if an unsupported rodlet were to deflect as a result of applied lateral fluid forces during normal operation, it could get caught on the corner of a worn guide card finger and jam or buckle during rod motion (i.e., scram). Additionally,. if a GT with an excessive number of worn guide cards experiences a seismic event or loss-of-coolant accident (LOCA), an unsupported rodlet might become plastically deformed, which could prevent a RCCA from scramming properly. Should this affect multiple GT locations, it could prevent a plant from achieving reactor shutdown using only the RCCAs.

"Left uncorrected, the wear inspection guidelines in WCAP-17451-P, Revision 1, underestimate the 17x17 A and 17x17 AS style GT guide card wear attributed to the use of iron nitride RCCAs to the extent that, for the four plants listed, the WCAP recommended number of effective full-power years (EFPYs) until the first GCWM is performed may no longer have margin to safety. The guidelines presented in this WCAP do not result in a defect for the other plants to which the WCAP applies."

Affected reactors are: Catawba Units 1 and 2, McGuire Unit 2 , and Millstone Unit 3.

AGREEMENT STATE REPORT - AUTOMATIC LOCKING DEVICE FAILURE

The following is a synopsis of information received via E-mail from the Louisiana Department of Environmental Quality (LDEQ):

TUV Rheinland (TUVR) was working at the Sasol Mega Project in Westlake, Louisiana under reciprocity (RC-662). TUVR was utilizing four industrial radiography exposure devices but only had a problem with one device.

TUVR made an exposure and then retracted the source into the shielded position. The source returned to the shielded position, but the automatic locking device did not lock/engage. The exposure device was manually locked with the plunger-lock and then key locked. It appears that the spring in the locking mechanism was either broken or blocked from working. The device is a Sentinel model 880D with S/N D13509. The device contains an INC model 7 source with 36.9 Curies of Ir-192 with S/N T0274. Safety surveys were made and there appears to be no radiation exposure hazard. The device was taken out of service, 'locked and tagged' out of service, and is being transported back to Woodstock, Alabama for a complete evaluation.

LDEQ was notified of the event by a phone call and a follow-up written report. From the report, it appears there is not a Radiation Safety Officer named on the Texas license at this time. A copy of the complete evaluation report will be provided when available.

Louisiana Event Report ID No.: LA-160014