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Category:Letter
MONTHYEARML24032A4762024-02-0101 February 2024 Final Report of a Part 21 Evaluation Associated with Starter Contactors for the BFN Unit 1 High Pressure Coolant Injection Suppression Pool Inboard Suction Valve ML24016A1902024-01-30030 January 2024 International, Inc. - Notice of Violation; the U.S. Nuclear Regulatory Commission Inspection Report 07201014/2022201 ML24023A2802024-01-23023 January 2024 Final Report of a Deviation or Failure to Comply Associated with a Relay in the Reactor Core Isolation Cooling Condensate Pump ML24018A1992024-01-18018 January 2024 International, Administrative Change to HI-2200343-A CNL-24-017, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2024-01-17017 January 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions ML24016A3042024-01-16016 January 2024 Final Report of a Part 21 Evaluation Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump CNL-23-071, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-472024-01-11011 January 2024 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47 ML23363A0312024-01-0404 January 2024 Application for HI-STORM 100 Cask System, Amendment No. 19 - Acknowledgement of Withdrawal and Notification of the U.S. Nuclear Regulatory Commission Staff Efforts Closure ML24022A1732024-01-0303 January 2024 Receipt and Availability of the Subsequent License Renewal Application ML23319A1992024-01-0303 January 2024 Issuance of Amendment Nos. 333, 356, and 316 Regarding the Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves ML23355A0842023-12-21021 December 2023 International, Withdrawal of HI-STORM I00 Multipurpose Canister Storage System Amendment ML23355A2062023-12-21021 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23348A3942023-12-14014 December 2023 Interim Part 21 Report of a Potential Deviation or Failure to Comply Associated with Starter Contactors for the High Pressure Coolant Injection Suppression Pool Inboard Suction Valve IR 05000259/20230102023-12-11011 December 2023 Commercial Grade Dedication Inspection Report 05000259/2023010 and 05000260/2023010 and 05000296/2023010 ML23324A0952023-12-0606 December 2023 Amendment No. 19 to Certificate of Compliance No. 1014 for the HI-STORM 100 Multi-purpose Canister Storage System - Request for Additional Information ML23328A0052023-12-0505 December 2023 Issuance of Renewed Certificate of Compliance No. 1014, Amendment No. 17 for the Hi-Storm 100 Cask System (Cac/Epid 001028/L-2021-LLA-0140) ML23338A3052023-12-0404 December 2023 International, Submittal of Supplement to RAI Responses on HI-STORM 100 Amendment 18 ML23335A0722023-12-0101 December 2023 Interim Report of a Deviation or Failure to Comply Associated with a Relay in the Unit 2 Reactor Core Isolation Cooling Condensate Pump ML23334A2492023-11-30030 November 2023 Site Emergency Plan Implementing Procedure Revision ML23334A1912023-11-30030 November 2023 International, Submittal of Topical Report HI-2210161-A Version CNL-23-070, Submittal of Fifth 10-Year Interval Inservice Testing Program Plan2023-11-29029 November 2023 Submittal of Fifth 10-Year Interval Inservice Testing Program Plan CNL-23-067, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-11-27027 November 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML23331A2532023-11-27027 November 2023 Summary Report for 10 CFR 50.9 Evaluations, Technical Specifications Bases Changes, Technical Requirement Manual Changes, and NRC Commitment Revisions ML23325A1102023-11-21021 November 2023 Anchor Darling Double Disc Gate Valve Commitment Revision ML23321A2172023-11-17017 November 2023 International, Responses to NRC Questions Form EA-23-044 Pre-Decisional Enforcement Conference ML23320A2542023-11-16016 November 2023 Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump JAFP-23-0063, Registration of Spent Fuel Cask Use2023-11-13013 November 2023 Registration of Spent Fuel Cask Use IR 05000259/20230032023-11-13013 November 2023 Integrated Inspection Report 05000259/2023003, 05000260/2023003 and 05000296/2023003 ML23310A0362023-11-0909 November 2023 International, Inc. - U.S. Nuclear Regulatory Commission Inspection Report 07201014/2023201 IR 05000259/20230402023-11-0202 November 2023 Supplemental Inspection Supplemental Report 05000259 2023040 and Follow-Up Assessment Letter ML23283A1262023-11-0202 November 2023 Letter - Second Request for Additional Information - HI-STORM 100 Amd 18 ML23292A2532023-10-18018 October 2023 BFN 2024-301, Corporate Notification Letter (210-day Ltr) ML23289A1582023-10-16016 October 2023 Decommissioning International - Registration of Spent Fuel Casks and Notification of Permanent Removal of All Indian Point Unit 3 Spent Fuel Assemblies from the Spent Fuel Pit ML23282A0022023-10-0606 October 2023 Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump ML23278A0122023-10-0505 October 2023 Updated Final Safety Analysis Report, Amendment 30 ML23271A1702023-09-28028 September 2023 Site Emergency Plan Implementing Procedure Revision ML23270A0082023-09-27027 September 2023 Registration of Spent Fuel Casks ML23270A0702023-09-26026 September 2023 SLRA Pre-Application Meeting Summary 09-13-2023 ML23257A1232023-09-22022 September 2023 Administrative Changes to Technical Specification Pages Issued for License Amendment Nos. 332, 355, and 315 ML23263B1042023-09-20020 September 2023 Special Report 260/2023-001 for Inoperable Post Accident Monitoring (PAM) Instrumentation ML23263B1232023-09-20020 September 2023 HI-STORM 100 Amendment 16 Responses to Second Round Requests for Additional Information CNL-23-061, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-09-20020 September 2023 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision ML23234A1572023-09-14014 September 2023 Letter to Holtec International Final Safety Evaluation for Hi-2210161, Revision No. 4, Topical Report on the Radiological Fuel Qualification Methodology for Dry Storage Systems 2024-02-01
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Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 March 2, 2012 10 CFR 72.4 10 CFR 72.212 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 Browns Ferry Nuclear Plant, Units 1, 2, and 3 Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 NRC Docket Nos. 50-259, 50-260, 50-296, and 72-052
Subject:
Registration of Use of Cask to Store Spent Fuel In accordance with 10 CFR 72.212, "Conditions of General License Issued Under §72.210,"
paragraph (b)(1)(ii), the Tennessee Valley Authority (TVA) is submitting the registration, for the use of three spent fuel storage casks under the general license to store spent fuel at the Browns Ferry Nuclear Plant (BFN) Independent Spent Fuel Storage Installation. The initial use of the first cask listed below to store spent fuel occurred on February 1, 2012. This registration is required to be submitted within 30 days of initial use. Accordingly, this submittal is due by March 2, 2012.
Pursuant to 10 CFR 72.212, paragraph (b)(1)(ii), TVA is providing the following cask loading information:
Licensee Name: Tennessee Valley Authority Licensee Address: Post Office Box 2000 Decatur, Alabama 35609-2000 Reactor License Numbers: DPR-33, DPR-52, and DPR-68 Reactor Docket Numbers: 50-259, 50-260, and 50-296
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U.S. Nuclear Regulatory Commission Page 2 March 2, 2012 Responsible Individual: Thomas A. Hess Program Manager, Corporate Nuclear Licensing, BFN Cask Certificate Number: 1014, Amendment 5 Cask Model Number: Holtec International, HI-STORM 100S For the cask system placed in service on February 1, 2012:
Cask Identification Multi-Purpose Canister Numbers: Type 68, Serial No. 0234 Overpack Serial No. 0360 For the cask system placed in service on February 11, 2012:
Cask Identification Multi-Purpose Canister Numbers: Type 68, Serial No. 0237 Overpack Serial No. 0359 For the cask system placed in service on February 16, 2012:
Cask Identification Multi-Purpose Canister Numbers: Type 68, Serial No. 0236 Overpack Serial No. 0364 There are no new regulatory commitments contained in this letter. If you have any questions, please contact T. A. Hess at (423) 751-3487.
Respe~f~lly, LI_eý iger, Corporate Nuclear Licensing cc: NRC Regional Administrator - Region II