Event Notification Report for March 24, 2014

TECHNICAL SUPPORT CENTER VENTILATION OUT OF SERVICE DUE TO PLANNED MAINTENANCE

"This is a non-emergency eight hour notification for a loss of Emergency Assessment Capability. This event is reportable in accordance with 10 CFR 50.72(b)(3)(xiii) because the work activity affects the functionality of an emergency response facility. Planned maintenance activities are being performed on 03/24/14 starting at approximately 2300 [EDT] to the Technical Support Center (TSC) ventilation system.

"The work includes performance of planned carbon bed filter sample. The planned work activity duration is approximately 5 hours.

"If an emergency is declared requiring TSC activation during this period, the TSC will be staffed and activated using existing emergency planning procedures unless the TSC becomes uninhabitable due to ambient temperature, radiological, or other conditions. If relocation of the TSC becomes necessary, the Emergency Director will relocate the TSC staff to an alternate location in accordance with applicable site procedures.

"The NRC Resident Inspector has been notified.

"This event poses no threat to the public or station employees."

* * * UPDATE FROM THOMAS GARRISON TO HOWIE CROUCH AT 0325 EDT ON 3/25/14 * * *

The TSC was returned to service at 0325 EDT on 3/25/14. The licensee will be notifying the NRC Resident Inspector.

Notified R2DO (Shaeffer).

UNANALYZED CONDITION DUE TO POSTULATED FIRE-INDUCED SHORT

"On March 24, 2014, during an extent of condition review for a separate problem evaluation report (PER) for the Browns Ferry Nuclear Plant (BFN), it was discovered that a postulated fire-induced wire-to-wire short of 250V DC control cables associated with 480V AC Shutdown Boards 2B, 3A, and 3B could cause the 480V AC Shutdown Board control power to spuriously transfer and could result in loss of control power to the 480V AC Shutdown Board. In the event of a 10 CFR 50 Appendix R fire, these conditions could result in loss of power to credited safe shutdown equipment that would challenge the ability to provide adequate core cooling during performance of BFN Safe Shutdown Instructions.

"Roving fire watches have been established as compensatory measures in accordance with the BFN Fire Protection Report.

"These conditions are being reported pursuant to 10 CFR 50.72(b)(3)(ii)(B). These conditions are also reportable as a 60-day written report in accordance with 10 CFR 50.73(a)(2)(ii)(B). These conditions have been entered into the Corrective Action Program.

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

SECONDARY CONTAINMENT INOPERABLE AND UNPLANNED ISOLATION OF THE REACTOR BUILDING VENT RADIATION MONITOR

"At 0031 [EDT] on March 24, 2014, Nine Mile Point Unit 2 was lowering power for the planned refueling outage. The loss of reactor building heating resulted in the isolation of the reactor building to maintain building temperature. Isolation of the reactor building resulted in the isolation of the reactor building vent radiation monitor (Vent WRGMS) which is a loss of emergency assessment capability. The isolation of the reactor building also resulted in declaring secondary containment inoperable due to secondary containment differential pressure being positive. Secondary containment was declared operable at 0034 [EDT] when differential pressure was restored to greater than negative 0.25 inches water gauge.

"Secondary containment being inoperable is a 8-hour report for 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 mitigate the consequences of an accident. The unplanned isolation of Vent WRGMS is a 8-hour report for 10 CFR 50.72(b)(3)(xiii), any event that results in a major loss of emergency assessment capability.

"The NRC Resident Inspector has been notified."

The licensee will notify the New York Public Service Commission.

FITNESS FOR DUTY REPORT INVOLVING A NON-LICENSED SUPERVISORY EMPLOYEE

A non-licensed supervisory employee had a confirmed positive for alcohol during a for-cause fitness-for-duty test. The employee's access to the plant has been terminated.

The licensee notified the NRC Resident Inspector and the New York Public Service Commission.

OFFSITE NOTIFICATION DUE TO DEATH OF EMPLOYEE

"On March 24, 2014, at approximately 0200 EDT, with Watts Bar Nuclear Unit 1 at 0% power while commencing a planned refueling outage and Unit 2 under construction, a radiation protection technician was found unresponsive in the protected area.

"An emergency medical team responded and the individual was transported off site to a medical facility where he was pronounced dead at 0530 EDT. The individual was not contaminated and there were no radiological or industrial safety issues associated with Watts Bar Nuclear Plant. Due to notification of OSHA at 1255 EDT, this report is submitted pursuant to 10 CFR 50.72(b)(2)(xi), as a notification to a government agency.

"The NRC Senior Resident Inspector has been notified."

RADIATION MONITOR OUT OF SERVICE FOR PRE-PLANNED MAINTENANCE

"System affected: SLCRS [Supplementary Leakage Collection and Release System] radiation monitor.

"Actuations and their initiation signals: N/A.

"Causes: Pre-planned maintenance.

"Effect of event on plant: Ventilation process radiation for SLCRS.

"Actions taken or planned: Return to service within 24 hrs.

"Additional information: None."

The licensee notified the NRC Resident Inspector and applicable State and local agencies.

STACK RADIATION MONITOR REMOVED FROM SERVICE FOR PRE-PLANNED MAINTENANCE

"The Millstone Station Stack Radiation Monitor, RM-8169 was removed from service for pre-planned maintenance. This is reportable as a loss of assessment capability in accordance with 10 CFR 50.72 (b)(3)(xiii).

"RM-8169 was restored at 1539 EDT."

The licensee notified the NRC Resident Inspector and applicable State and local agencies.