Event Notification Report for April 23, 2012

CONTAMINATED INDIVIDUAL REQUIRED MEDICAL TREATMENT

"Westinghouse Environmental Health and Safety (EH&S) staff responded to an operator who was exposed to dilute nitric acid (30%) on the left forearm and left foot. Employee was cleaning scrubber piping in the conversion area of the plant when exposed to the nitric acid solution containing uranium. The employee was treated within the onsite medical facility where decontamination was performed. Medical, emergency response and health physics procedures were followed. Upon completion of the decontamination efforts, the smearable alpha reading was < 50 dpm/100 cm2 and alpha direct reading on forearm was 818 dpm/100 cm2, on foot direct alpha reading was 280 dpm/100 cm2. Medical staff recommended transfer to the hospital for further treatment. Westinghouse followed contaminated injury protocols and had the employee transported to the hospital emergency room via ambulance. A Westinghouse health physics (HP) technician accompanied the employee to the hospital. Surveys were conducted of the ambulance and all results were below established limits. Material Safety Data Sheets for the nitric acid and uranium were provided to the hospital in accordance with procedures. Hospital report describes injury as, 'irritation noted over the left forearm as well as over the left anterior part of the foot and dorsal part of the foot ...some mild orange discoloration noted to these areas.' Employee was monitored for a period of time, given treatment for pain, and then released from the hospital.

"Immediate Actions: Initial investigation into the event is ongoing. This event has been entered into the Facility Corrective Action Process Issue # 12-115-001. Local county authorities and state authorities are aware of this event."

ULTRASONIC EXAMINATION RESULTS IN AN INDICATION ON THE REACTOR PRESSURE VESSEL HEAD PENETRATION

"On April 23, 2012, during the Braidwood Station Unit 1 refueling outage, it was determined that the results of planned ultrasonic (UT) examinations performed on one penetration (Penetration No. 69) did not meet the applicable acceptance criteria, requiring repair prior to returning the reactor pressure vessel head to service. A portion of the indication was conservatively assumed to be within the J-groove weld. At the time of the examination, the Braidwood Station Unit 1 reactor pressure vessel head was classified as a low susceptibility head. The cause of the recordable indication is attributed to Primary Water Stress Corrosion Cracking. The examinations were being performed to meet the requirements of 10 CFR 50.55a(g)(6)(ii)(D) and ASME Code Case N-729-1, to ensure the structural integrity of the reactor pressure vessel head pressure boundary. All of the remaining penetrations have been examined during the current refueling outage. Repairs to Penetration No. 69 were completed prior to commencing startup. No other repairs were required.

"This is reportable pursuant to 10 CFR 50.72(b)(3)(ii)(A) since the as found indication did not meet the applicable acceptance criteria referenced in ASME Code Case N-729-1 to remain in-service without repair.

"The NRC Resident Inspector has been notified."

As a result of a follow-up review, at 0600 CDT on 05/18/12, the licensee determined this was an 8 hour reportable event while Unit 1 was in Mode 4. The licensee did not determine this was a reportable event immediately after the UT was conducted on April 23, 2012. The unit is currently in Mode 3.

Reactor Vessel Head Penetration No. 69 is a control rod penetration. Reactor Coolant Leakage test are satisfactory and there are no indications of boron buildup on the Reactor Vessel Head. Control rod testing has not yet been performed.