Event Notification Report for August 24, 2016

AGREEMENT STATE REPORT - DAMAGED SOURCE ROD

The following information was received from the Commonwealth of Pennsylvania via facsimile:

"Notifications: On August 25, 2016, the Department [Pennsylvania Bureau of Radiation Protection] was notified that a licensee had a cobalt-60 (Co-60) source rod that became bent and unusable during installation into a gauge at a work location. This is reportable per 10 CFR 30.50(b)(2).

"Event Description: During the process of installing a Co-60 source rod and moving it from a transfer shield to a gauge and industrial process mold, the licensee observed difficulty in getting the source rod to insert into the mold. Using a remote handling device, the Co-60 source was partially removed from the transfer shield and briefly (about 30 seconds) inspected. It was noted that the rod was partially bent. The rod was immediately retracted into the fully shielded position in the transfer shield. The transfer shield containing the Co-60 rod was then taken to a designated storage area where it is secured from unauthorized access. The calculated dose to the workers was estimated to be 0.44 millirem. No exposures over regulatory limits occurred.

"Radionuclide: Co-60; Manufacturer: Berthold Technologies; Source Model: P 2608-100; Gauge Model: LB 300 ML; Source Serial Number: 1766-10-13; Activity: 3.8 milliCuries

"ACTIONS: The rod has been securely stored and placed out of service until repairs or return can be accomplished by a licensed service provider. The Department has scheduled a reactive inspection. More information will be provided when available."

Pennsylvania Event: PA160024

REACTOR TRIP DUE AUTOMATIC TURBINE TRIP FROM 100 PERCENT POWER

"At 1338 [EDT] on 08/24/2016, a turbine trip, and a subsequent reactor trip occurred. The cause is under investigation. Following the reactor trip, the Auxiliary Feedwater System actuated as expected on low steam generator level. At the time of the trip, the plant was in Mode 1. As of 1643 [EDT], the Plant is in Mode 3. The current RCS [Reactor Coolant System] Temperature is 548 degrees F (Average), and the Steam Generator Levels are in the range of 40 to 45% (normal range) with levels controlled by the Main Feedwater System. All systems and equipment operated as expected.

"Due to the automatic actuation of the Reactor Protection System, this event is being reported as a 4 hour Non-Emergency per 10 CFR 50.72(b)(2)(iv)(B). Due to the valid actuation of Auxiliary Feedwater System, this event is also being reported as an 8 hour Non-Emergency per 10 CFR 50.72(b)(3)(iv)(A)(B)(6). At no time during this occurrence was the public or plant staff at risk as a result of this event.

"The NRC Resident Inspector has been notified."

AGREEMENT STATE REPORT - POTENTIAL RADIOGRAPHER OVEREXPOSURE

The following report was received from the Texas Department of State Health Services via email:

"On August 24, 2016, the licensee reported a potential overexposure of an employee to the Agency [Texas Department of State Health Services]. The licensee reported one of its radiographers had received 5.5 rem on the July monthly monitoring report resulting in a total dose of 6.4 rem for the year. The radiation safety officer [RSO] is investigating the cause of the overexposure although believes the radiographer has not been following procedures. The RSO stated the radiographer is working in an enclosed area and not distancing himself from the source as required when the source is exposed. The RSO will provide a detailed report within the next few days. An update will be sent in accordance of SA300 guidelines."

Texas Incident #: I 9426

UNANALYZED CONDITION ASSOCIATED WITH DAMAGING EFFECTS OF TORNADOS

"During performance of an extent of condition evaluation of protection for Technical Specification (TS) equipment from the damaging effects of tornados, Arkansas Nuclear One, Unit 1, identified non-conforming conditions in the plant design such that specific TS equipment on Unit 1 is considered to not be adequately protected from tornado missiles. The reportable condition is postulated by tornado missiles entering the Unit 1 Cable Spreading Room through penetrating the hollow metal door or potentially from spalling of the block wall separating Room 96 and 97. A tornado could generate multiple missiles capable of striking the Unit 1 Cable Spreading Room and rendering both safety related electrical trains inoperable.

"This condition is reportable per 10 CFR 50.72(b)(3)(ii)(B) for any event or condition that results in the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety, and per 10 CFR 50.72(b)(3)(v) for 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 (A) Shut down the reactor and maintain it in a safe shutdown condition, (B) Remove residual heat, or (D) Mitigate the consequences of an accident.

"This condition was identified as part of an on-going extent of condition review of potential tornado missile related site impacts. Licensee Event Report (LER) 50-313/2016-002-00 was recently submitted addressing previously identified tornado missile vulnerabilities at the Unit 1 plant.

"Enforcement discretion per Enforcement Guidance Memorandum EGM 15-002 has been implemented and required actions taken. Corrective actions will be documented in a follow-on licensee event report.

"The licensee has notified the NRC Resident Inspector."