Event Notification Report for May 05, 2010

AUTOMATIC REACTOR SCRAM DUE TO REACTOR FEED PUMP TRIP

"On May 5, 2010, at 1144 hours Eastern Daylight Time (EDT), an automatic reactor scram occurred on Unit 1 following a trip of the 1B Reactor Feed Pump (RFP). Following the 1B RFP trip, the reactor recirculation pumps did not run back as expected. The resulting water level shrink caused level in the Reactor Pressure Vessel (RPV) to drop to Low Level 1, causing the activation of the Reactor Protection System (RPS) and the Primary Containment Isolation System (PCIS). All control rods properly inserted.

"PCIS Group 2 (i.e., Drywell Equipment and Floor Drain, Residual Heat Removal (RHR) Discharge to Radwaste, and RHR Process Sample), Group 6 (i.e., Containment Atmosphere Control/Dilution, Containment Atmosphere Monitoring, and Post Accident Sampling Systems), and Group 8 (i.e., RHR Shutdown Cooling) isolation signals were received on Low Level 1. Actuations of the Primary Containment Isolation Valves (PCIVs) were completed and the affected equipment responded as designed.

"Due to the expected RPV level reduction following a reactor scram, water level in the RPV momentarily reached Low Level 2. This initiated the High Pressure Coolant Injection (HPCI) System, the Reactor Core Isolation Cooling (RCIC) System, and a partial Group 3 PCIS (i.e., RWCU) isolation. The HPCI and RCIC systems did not inject. The 1-G31-F001 isolated (i.e., inboard isolation) but 1-G31-F004 (i.e., outboard isolation) did not automatically isolate. Based on a preliminary assessment, this response appears to be in accordance with plant design. Further
assessments of plant response are on-going to validate plant response.

"The licensee has notified the NRC Resident Inspector."

The scram was uncomplicated. No SRVs lifted. Decay heat removal is via the 'A' feed water pump via the turbine bypass valves to the condenser. The electrical line-up of Unit 1 is normal. Brunswick Unit 2 was not affected.

INJURED INDIVIDUAL HOSPITALIZED

"On May 5, 2010 at approximately 1510 PDT, a notification was made to the Washington State Department of Labor and Industries regarding an in-patient hospitalization of an Energy Northwest employee as required by Washington Administrative Code.

"On May 3, 2010 high wind conditions were occurring at the plant site. While this individual was outside, a high gust of wind occurred resulting in the individual falling and injuring himself. The individual received treatment from a local medical facility and was released that day. On May 5, the individual identified additional symptoms and was admitted to a local hospital which resulted in in-patient hospitalization and treatment."

The licensee notified the NRC Resident Inspector.

AGREEMENT STATE REPORT - FOUND GENERAL LICENSE DEVICE

The following information was received via facsimile:

"On the afternoon of May 5, 2010, the Alabama Office of Radiation Control received a phone call from a representative of ELG Metals in Mobile, Alabama advising the [Alabama Office of Radiation Control] Agency of the discovery of a device containing Am-241. The Agency was advised that the device was in two pieces. A member of the Department's Expanded Radiological Emergency Response Team was dispatched to verify if the sealed source was intact. On the afternoon of May 5, 2010, a field leak test was performed and its was determined that the sealed source was intact. The device was isolated at that time. On the morning of May 7, 2010, a representative of the Alabama Office of Radiation Control visited ELG Metals in Alabama to determine the condition of the device and assist in identifying the source of radiation. The source of radiation was identified as a NDC model 102, serial number 3572 containing 150 millicuries of Am-241. The investigation determined that the device was last owned by United Nonwoven in Mobile and was originally distributed as a General License device to Stems Technical Textiles in Cincinnati, OH. United Nonwoven in Mobile is no longer in business. The source of radiation was isolated and preliminary leak test results in the field indicate that the source is not ruptured.

"This is all the information that [Alabama Office of Radiation Control] Agency has at this time and is current as of 8:30 am central time, May 10, 2010."

THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL

Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf

This source is not amongst those sources or devices identified by the IAEA Code of Conduct for the Safety & Security of Radioactive Sources to be of concern from a radiological standpoint. Therefore is it being categorized as a less than Category 3 source

TECHNICAL SUPPORT CENTER OUT OF SERVICE FOR PREVENTIVE MAINTENANCE

"On May 5, 2010, at 0500 hours EDT, Fermi 2 removed the Technical Support Center (TSC) from operation to facilitate routine preventive maintenance on the facilities' heating ventilation and air-conditioning system. During this work, which is expected to last approximately 12 hours, the TSC will be unavailable. In the event TSC activation is necessary, the Emergency Operations Facility (EOF) will be used for the TSC function. Activation and use of the EOF as a backup for the TSC is included in Fermi 2's Radiological Emergency Response Preparedness Plan. The Emergency Call Out System (ECOS) is designed to facilitate contacting TSC personnel to respond directly to the EOF in the event of an emergency. Fermi 2 is making this notification in accordance with 10 CFR 50.72(b)(3)(xiii). Fermi 2 will notify the NRC upon completion of this work. Fermi 2 has notified the NRC Resident Inspector."

* * * UPDATE FROM JIM KONRAD TO PETE SNYDER ON 5/5/10 AT 1725 EDT * * *

"Maintenance to restore ventilation has been completed. The TSC has been restored as an Emergency Response Facility."

Notified R3DO (Passehl).

AGREEMENT STATE REPORT - PATIENT RECEIVED DOSE LESS THAN PRESCRIBED

The following information was received from the State of North Carolina via email:

"On 05/05/10, a physician at Iredell Memorial Hospital (NC License 049-0412-2) performed a prostate seed implant procedure. The prescribed dose was 1440 cGray (~1440 REM). After the seeds were implanted, they did a scan and discovered a seed in the urethra. They removed the seed and it was part of a strand of four seeds.

"On 05/19/10, the patient returned for a follow-up and had an additional strand of three seeds. The patient said the seeds had come out during urination about a week before.

"The patient went through the post-implant CT scan. On 07/02/10, the post-dose calculations were performed. The D-90 actual dose (dose to 90% of the mass) was calculated as 77% of the prescribed dose.

"The hospital has made the notification [to the North Carolina Division on Radiation Protection] and is attempting to make the physician and patient notification. A report will be prepared and delivered within 15 days."

State Event No.: NC 10-32

A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.