ML16286A059
| ML16286A059 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 10/17/2016 |
| From: | Vaaler M Reactor Decommissioning Branch |
| To: | Bruce Watson Reactor Decommissioning Branch |
| Shared Package | |
| ML16286A049 | List: |
| References | |
| Download: ML16286A059 (20) | |
Text
NRC Public Meeting September 20, 2016 LACBWR Decommissioning Update and LTP Overview
AEC demonstration reactor Owned by Dairyland Power Cooperative (DPC)
Operated from 1967 to 1987 Licensed site shared with operational fossil plant
LACBWR Site
LACBWR Site
Decommissioning to Date LACBWR staff performed limited dismantlement work between 1996 and 2004 In 2005, efforts shifted to RPV and Class B/C waste removal that was successfully completed in 2007 EnergySolutions (ES) performed the removal and disposal of the RPV and B/C waste at the Barnwell disposal facility Fuel transfer to dry storage commenced in 2008 and was completed September 19, 2012 Additional dismantlement work completed in 2012 - 2014 including removal of fuel racks and completion of main turbine generator component removal
Decommissioning to Date All spent fuel is in dry storage at the Independent Spent Fuel Storage Facility (ISFSI)
Metal removal project performed from 2012 to 2014 Plant buildings still standing LACBWR placed in Passive SAFSTOR in 2014 Initial Site Characterization completed by ES License Transferred on June 1, 2016
Overview of the Agreements ES created a special purpose subsidiary, LaCrosseSolutions, to be licensee for LACBWR LaCrosseSolutions Became the lead licensee for LACBWR decommissioning operations Took possession of the used nuclear fuel (but not ownership)
Assumed full responsibility for licensed activities Assumed all liabilities and obligations for radiological decommissioning and site restoration directly related to LACBWR decommissioning Dairyland remains the licensed owner and retains title to Used nuclear fuel The Nuclear Decommissioning Trust Real estate and site improvements Dairyland operates and maintains the ISFSI
LACBWR Current Status License Termination Plan submitted June 27, 2016 Partial Site Release Request submitted June 27, 2016 Decommissioning transitioned from SAFSTOR to DECON in August 2016.
Active decommissioning in progress Stack will be the first structure to be removed this Fall.
Decommissioning Approach
& Schedule Source term removal within radiologically controlled areas Minimize survey and surgical removal Utilize large capacity intermodals and rail cars to move LLW to Clive Remove structures to a minimum of 3 feet below grade Affected systems/buildings - ship to Clive Non-rad materials and areas Remove hazardous materials such as asbestos, light ballasts, PCBs, Hg switches and oil before removal of components or demolition as necessary Clean components with scrap value will be evaluated for salvage
Decommissioning Approach &
Schedule Demolish buildings Radioactive building debris sent to Clive Final Status Survey per MARSSIM Program NRC/ORISE Confirmatory Surveys Backfill
Decommissioning Approach
& Schedule Completion of Major Structure Demolition Stack February 23, 2017 Waste Treatment Building May 15, 2017 Turbine Building November 30, 2017 Misc. (Storage, Offices)
December 20, 2017 Reactor Building January 2, 2018 Site Restoration January 2, 2018 Submit Final Survey Report July 1, 2018 Project Completion April 2, 2019 Transfer NRC License April 2, 2019
State of Wisconsin Maintain radiological effluent monitors Inspectors have open site access Radiation Protection Section invited to all NRC LTP meetings and inspections Copied on all submittals to the NRC
LTP Overview Chapter 1: General Information Chapter 2: Site Characterization Chapter 3: Remaining Site Dismantlement Activities Chapter 4: Remediation Plan Chapter 5: Final Radiation Survey Plan Chapter 6: Compliance With the Radiological Criteria for License Termination Chapter 7: Update of the Site-Specific Decommissioning Costs Chapter 8: Supplement to the Environmental Report
Chapter 2: Site Characterization Extent and distribution of residual radioactivity at Site well known LTP provides results of extensive characterization:
Soil samples Surface and subsurface land area measurements Structure measurements including concrete core samples Essentially no soil contamination identified No groundwater contamination identified
Chapter 3: Remaining Site Dismantlement Activities Completion of Major Structure Demolition Stack February 23, 2017 Waste Treatment Building May 15, 2017 Turbine Building November 30, 2017 Misc. (Storage, Offices)
December 20, 2017 Reactor Building January 2, 2018 Site Restoration January 2, 2018 Submit Final Survey Report July 1, 2018 Project Completion April 2, 2019 Transfer NRC License April 2, 2019
Chapter 4: Remediation Plan Methods that may be used to remediate contaminated systems, components and structures:
Scabbling and Shaving Needle Guns Chipping Sponge and Abrasive Blasting Pressure Washing High-Pressure Water Blasting Grit Blasting Removal of Activated/Contaminated Concrete Planned remediation meets NRC As Low As Reasonably Achievable (ALARA) criterion
Chapter 5: Final Radiation Survey Plan Comprehensive Sampling and Measurements will be performed to demonstrate that Site meets NRC unrestricted release criteria Soil: Scan/static measurements, volumetric sampling Concrete: Insitu Gamma Spectroscopy Buried Pipe and Penetrations: pipe crawlers, sediment sampling and/or other methods
Chapter 6: Compliance With the Radiological Criteria for License Termination Radiological criteria for unrestricted release specified in NRC Regulations Dose Criterion: The residual radioactivity that is above natural background levels results in dose to a member of the critical group that does not exceed 25 mrem/year*, and ALARA Criterion: The residual radioactivity has been reduced to levels that are ALARA.
To determine compliance with 25 mrem/year criterion, the critical group is conservatively assumed to be an Industrial Worker
- Avg. natural background radiation in the US is 310 mrem/year
Chapter 7: Update of the Site-Specific Decommissioning Costs Provides an estimate of remaining decommissioning costs at the time of LTP submittal and compares the estimated costs with the present funds set aside The DCE includes an evaluation of the following elements:
Cost assumptions used, including contingency factor Major decommissioning activities and tasks Unit cost factors Costs of decontamination and removal of equipment/structures Final Radiation Survey costs Estimated total costs Current trust fund provides sufficient funding and financial assurance for completion of LACBWR Decommissioning
Chapter 8: Supplement to the Environmental Report Describes any new information or significant environmental change associated with the site-specific decommissioning and site closure activities
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Conclusion:==
Potential environmental impacts associated with decommissioning will be bounded by the previously issued environmental impacts statements (Post Shutdown Activities report, NUREG-0586, and LACBWR Environmental Statement).
There are no new or significant environmental changes associated with decommissioning