ML102510517
| ML102510517 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 09/08/2010 |
| From: | John Hughey Division of Operating Reactor Licensing |
| To: | Exelon Corp |
| Hughey J, NRR/DORL, 301-415-3204 | |
| References | |
| Download: ML102510517 (2) | |
Text
Enclosure DRAFT REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST TO ALLOW RECIEPT AND STORAGE OF LOW-LEVEL RADIOACTIVE WASTE GENERATED OFF-SITE LASALLE COUNTY STATION, UNITS 1 AND 2 DOCKET NOS. 50-373 AND 50-374 By letter to the Nuclear Regulatory Commission (NRC) dated January 6, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML ML100070297), as supplemented by letter dated August 20, 2010 (ADAMS Accession No. ML102320599), Exelon Generation Company, LLC (EGC) submitted a request to revise license paragraph 2.B(5) of LaSalle County Station (LSCS) Units 1 and 2. The proposed change would enable LSCS to possess byproduct material from Braidwood Station Units 1 and 2, Byron Station Units 1 and 2, and Clinton Power Station Unit 1. The NRC staff has reviewed Exelons submittal and determined that additional information, as described below, is needed to complete the review.
RAI-05
Will waste classified as Greater Than Class C (GTCC) be transferred and stored in the LLRW Storage Facility?
RAI-06
Describe the reprocessing and repackaging capabilities in the Radwaste Building where waste from the LLRW Storage Facility would be transferred for reprocessing and repackaging if necessary due to loss of container integrity in order to meet storage, transportation and / or disposal requirements.
RAI-07
For onsite radiation protection purposes, describe the boundaries of the Title 10 of the Code of Federal Regulations Part 20 (10 CFR 20) controlled area (e.g., provide map and distances to the LLRW Storage Facility); describe whether members of the public are allowed in the controlled area, and describe how the dose limits of 10 CFR 20.1301(a) and (b) will be met.
RAI-08
For offsite radiation protection considerations under 10 CFR 20.1301(e),
explain the methods used in the Offsite Dose Calculation Manual methods to measure and/or calculate the net dose at the nearest residence attributable to the LLW Storage Facility and those doses attributable to the nuclear site from other sources of the direct radiation. For the environmental monitoring dosimeters, describe how the background (baseline) radiation dose will be (or has been) determined, how the standard deviation at each environmental dosimeter location has been determined, and the estimated Lower Limit of Detection for dosimeters that can be achieved at the 95% confidence level.
RAI-9.a: How many plant-to-plant shipments of LLRW are projected in a year?
RAI-9.b: How does the number of trips stated in the response to RAI-12.a compare to the past average annual number of trips to the Barnwell facility?
RAI-10.a: Will there be any new construction (i.e., staging pads, shelters, support, or storage buildings) in any undisturbed land portions of the Braidwood, Byron, Clinton, or LaSalle plant sites?
RAI-10.b: If the response to RAI-13.a is yes, please provide a discussion of the potential impact to the terrestrial and aquatic environment and your procedures for the protection of cultural and archeological artifacts.