For PWR plants: Do you move fuel in containment with the equipment hatch open?
What is your accident release dose assessment methodology for a dropped a fuel bundle with the hatch open? At Diablo Canyon, we have a DB worst case calculation submitted with the LAR for allowing us to refuel with the equipment hatch open with worst case (conservative) iodine partitioning and X/Q, and we have an "an expected case" calculation that assumes one row of ruptured pins, an average X/Q, and immediate release of all the activity from containment. Diablo Canyon has a "manual method" in our dose assessment software with the capability to calculate SB and offsite dose by estimating the total activity released into containment at the time ot the dropped bundle based on containment area radiation monitor reading, and then making assumptions about release of the activity as either DB containment leak rate if the hatch is closed during fuel movement, or we assume that all the activity is released all at once if the hatch is open. In both cases we use real time meteorology data for calculating/determining X/Q. Thanks is advance Curtis Hansen Sr. EP Coordinator - Radiation Dose Assessment Diablo Canyon Power Plant Pacific Gas and Electric Company 805-545-6278 work 805-801-8185 cell ----------------------------------- Powernet - a service of the Health Physics Society Power Reactor Section Powernet archives at http://www.mail- archive.com/[email protected]/<mailto:archive.com/[email protected]/> Reply to: [email protected]<mailto:[email protected]> If Questions, contact Mike Russell, CHP at [email protected]<mailto:[email protected]> PG&E is committed to protecting our customers' privacy. To learn more, please visit http://www.pge.com/about/company/privacy/customer/
