Event Notification Report for October 23, 2013

OFFSITE NOTIFICATION OF A FATALITY ONSITE

"This is a non-emergency event notification.

"On 10/23/2013, a supplemental worker (i.e., a contract individual) suffered an apparent heart attack while servicing portable lighting equipment in a site perimeter parking lot. This parking lot is used by plant workers and is located outside of the Owner Controlled Area. Medical personnel who responded to this location found the worker unresponsive and transported the individual by ambulance to a local hospital for treatment. Following the evaluation by emergency room personnel, the individual was pronounced deceased at 1016 EDT. OSHA was being notified pursuant to the requirements of 29 CFR 1904.39 based on a fatality that could be work related. As such, this ENS report was made to the NRC in accordance with 10 CFR 50.72(b)(2)(xi). There was no radioactive contamination involved in this event. The health and safety of the public was not affected.

"The NRC Resident Inspector has been notified."

AGREEMENT STATE REPORT - DAMAGED SOIL MOISTURE DENSITY GAUGE

The following report was received from the Florida Department of Health, Bureau of Radiation Control, via e-mail:

"A soil moisture density gauge was damaged by heavy construction equipment. The source was reported to be retracted and not exposed. The electronics panel and housing was reported to be damaged. A Bureau of Radiation Control Inspector is en route.

"The incident occurred at a temporary work site in Walnut Hill, Florida. The gauge contained a 10 mCi Cesium 137 source and a 50 mCi Americium241/Beryllium source."

The State of Florida Bureau of Radiation Control will update the report as more information is known.

Verbal information from the State indicated that the licensee could not verify the integrity of the source because the company does not have access to a radiation detector.

Florida Incident Number: FL13-074

REACTOR BUILDING DIFFERENTIAL PRESSURE LESS THAN REQUIRED BY TECHNICAL SPECIFICATIONS

"On October 23, 2013 at 0620, Susquehanna Steam Electric Station operators observed secondary containment differential pressure was at negative 0.17 inches water gauge for Zone II (Unit 2 Reactor Building). Tech Spec Secondary Containment Operability requires a negative pressure of at least 0.25 inches water gauge. Zone I (Unit 1 Reactor Building) and III (Common Refuel Floor Area) ventilation remained in service and stable.

"Zone II differential pressure was restored to within the required band by manual damper adjustment in about 15 minutes and was verified to be stable. LCO 3.6.4.1 was entered for both units at 0620 and exited at 0635.

"This event is being reported under 10 CFR 50.72(b)(3)(v) and per the guidance of NUREG 1022 Rev 3 section 3.2.7 as a loss of a Safety Function. There is no redundant Susquehanna Secondary Containment System."

The licensee has notified the NRC Resident Inspector.

AGREEMENT STATE REPORT - FAILURE OF RADIOGRAPHY CAMERA SOURCE TO FULLY RETRACT

The following report was received from the Texas Department of State Health Services, Radiation Branch, via e-mail:

"On October 23, 2013, the licensee notified the Agency [Texas Department of Health] that one of its radiography crews had been unable to retract an iridium-192 source back into a QSA 880D exposure device at a temporary work site in Baytown, Texas. Following an exposure, the source pigtail would not retract fully into the device. An authorized person, the Radiation Safety Officer (RSO), performed the source retrieval. He received an estimated 600 millirem dose. No member of the public received any exposure as a result of this event. The RSO reported that he had to disconnect the crank handle from the drive cables to pull the source back into the camera. The cause was an equipment failure of the drive cable which was binding. A new set of drive cables was attached to the camera and the source moved in and out freely about 10 times. The drive cables were only 3 weeks old. They will be returned to the manufacturer for inspection. An investigation into this event is ongoing. Information will be provided as it is obtained in accordance with SA-300.

"Camera and source information: QSA 880D camera, serial number D4621, source model number 424-9, source serial number 98960B."

Texas Incident Number: I-9130

STACK RADIATION MONITORS OUT OF SERVICE FOR PRE-PLANNED MAINTENANCE

Millstone Unit-2 is performing pre-planned maintenance on the power station stack and Unit-2 high range stack radiation monitors. The monitors are expected to be out of service for six hours.

Notified the R1DO (Holody).

AGREEMENT STATE REPORT - GAUGE DAMAGED IN A FIRE

The following report was received from the Illinois Emergency Management Agency, Bureau of Radiation Safety via e-mail:

"PDV Midwest Refining (CITGO) in Lemont, IL called on 10/26/13 to report a fixed gauge that was involved in a fire on 10/23/13. The gauge is an Ohmart/Vega gauge containing 37 GBq (1 Ci) of Cs-137. Their consultant had been on site and done a characterization of the area. The housing looked to be intact and radiation surveys at 35 feet from below the housing were 40 microR/hr. A contamination survey of material under the vessel indicated no contamination at this time. No one is able to get into the immediate area because of debris and a perimeter has been established. IEMA/BRS [Illinois Emergency Management Agency, Bureau of Radiation Safety] inspectors have been dispatched to the scene for further evaluation."

Item Number: IL13030

PART 21 - DAMAGED SURVEILLANCE CAPSULES

"In April 2015, during Sequoyah Nuclear Plant Unit 1 end of cycle 20 refueling outage, the Tennessee Valley Authority (TVA) identified that there was unanticipated damage to the 'S' and 'W' surveillance capsules that were located within the reactor pressure vessel. Inspections determined that the surveillance capsules were not contained within the intact designated baskets. TVA conducted an extensive foreign object search and recovery initiative to recover the specimen capsule contents prior to concluding the refueling outage.

"During the October 2013 Sequoyah Unit 1 refueling outage, the Westinghouse Electric Company (WEC) relocated the above referenced surveillance capsules in accordance with Westinghouse procedure MRS-SPP-2970. The procedure specified the requirements for performing specimen capsule relocations. WEC created a deviation when an inadequate procedure referenced in the applicable purchase order, which did not ensure proper seating of the sample capsule, was used at Sequoyah Nuclear Plant Unit 1.

"TVA considers the above condition to be reportable pursuant to 10 CFR 21.21 as a defect associated with a condition that, if uncorrected, could have created a substantial safety hazard."

"The NRC Resident Inspector and the vendor were notified."