ML100620233
| ML100620233 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 03/01/2010 |
| From: | Krich R Tennessee Valley Authority |
| To: | Document Control Desk, NRC/NMSS/SFPO, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML100620233 (2) | |
Text
Tennessee Valley Authority 1101 Market Street, LP 3R Chattanooga, Tennessee 37402-2801 R. M. Krich Vice President Nuclear Licensing March 1, 2010 10 CFR 72.4 10 CFR 72.44(d)(3)
ATTN: Document Control Desk Director, Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards U. S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Sequoyah Nuclear Plant, Units 1 and 2 Facility Operating License Nos. DPR-77 and DPR-79 NRC Docket Nos. 50-327, 50-328, and 72-034
Subject:
Sequoyah Nuclear Plant - Annual 2010 Independent Spent Fuel Storage Installation Effluent Release Report
Reference:
Certificate Number 1014, Certificate of Compliance for Spent Fuel Storage Casks, Appendix B, Section 5.4, "Radioactivity Effluent Control Program" Amendments Nos. 1 and 2 Sequoyah Nuclear Plant's (SQN's) Certificate of Compliance (CoC) for spent fuel storage casks requires the submittal of an annual radioactive effluent release report in accordance with 10 CFR 72.44(d)(3), which specifies reporting within 60 days after the end of the 12-month monitoring period. The purpose of this letter is to fulfill this reporting requirement for the 2009 calendar year. As specified in the CoC, "The HI-STORM 100 Cask System does not create any radioactive materials or have any radioactive waste treatment systems." There is no gaseous or liquid radioactive effluent pathway attributed to the spent fuel stored in the Independent Spent Fuel Storage Installation. Therefore, there were no radionuclides released to the environment in liquid or gaseous effluents during the previous 12 months of operation.
SQN provides the following confirmatory information that supports the CoC. The gamma isotopic analyses performed on SQN's radiological environmental monitoring plan monthly air filter composite samples and weekly charcoal cartridge samples for the 2009 monitoring year did not detect any fission or activation product radionuclides.
The levels of naturally occurring radionuclides identified by these analyses were consistent with the normal background levels measured in previous monitoring years.
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U.S. Nuclear Regulatory Commission Page 2 March 1, 2010 The lower limit of detection (LLD) values achieved for these analyses met the LLD requirements in the SQN Offsite Dose Calculation Manual Table 2.3-3. This data will be reported in the SQN Annual Radiological Environmental Qperating Report to be submitted to the NRC on or before May 1, 2010.
This letter contains no regulatory commitments. If you have any questions, please contact James W. Proffitt at (423) 843-6651.