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Category:Letter
MONTHYEARML24247A2212024-08-29029 August 2024 Notification of Deviation from Pressurized Water Reactor Owners Group (PWROG) Letter OG-21-160, NEI 03-08 Needed Guidance: PWR Lower Radial Support Clevis Insert X-750 Bolt Inspection Requirements, September 1, 2021 ML24247A1802024-08-28028 August 2024 Application to Revise the Fuel Handling Accident Analysis, to Delete Technical Specification 3.9.4, Containment Penetrations, and to Modify Technical Specification 3.3.6, Containment Ventilation Isolation Instrumentation for Sequoyah Nuclea ML24240A1112024-08-27027 August 2024 Registration of Use of Casks to Store Spent Fuel L-24-190, Spent Fuel Storage Cask Registration2024-08-26026 August 2024 Spent Fuel Storage Cask Registration IR 05000327/20240052024-08-26026 August 2024 Updated Inspection Plan for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327/2024005 and 05000328/2024005 ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 CNL-24-061, Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08),”2024-08-19019 August 2024 Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08),” ML24199A2372024-08-13013 August 2024 Letter - Issuance of CoC No. 1032, Amendment 7 for HI-STORM Flood/Wind Multi-Purpose Canister Storage System ML24221A2782024-08-0808 August 2024 Schedule for Responses to HI-STORM FW Amd. 10 Requests for Supplemental Information IR 05000327/20240022024-07-31031 July 2024 Integrated Inspection Report 05000327/2024002 and 05000328/2024002 ML24211A0572024-07-29029 July 2024 Submittal of Emergency Plan Implementing Procedure Revision ML24211A0542024-07-29029 July 2024 Operator License Examination Report ML24211A0412024-07-26026 July 2024 Unit 1 Cycle 26 Refueling Outage - 90-Day Inservice Inspection Summary Report ML24199A0012024-07-22022 July 2024 Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2) ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter ML24172A2122024-07-12012 July 2024 Letter - Acceptance Review of Request for Amendment 10 to Certificate of Compliance 1032 for the HI-STORM Flood/Wind Cask System - Request for Supplemental Information ML24191A4652024-07-0909 July 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations ML24138A1242024-07-0909 July 2024 Amendment to List of Approved Spent Fuel Storage Casks: Holtec International, HI-STORM Flood/Wind System Certificate of Compliance No. 1032, Amendment No. 7 ML24191A0612024-07-0606 July 2024 Independent Spent Fuel Storage Installation (ISFSI) - Annual Radioactive Effluent Release Report ML24177A0282024-06-25025 June 2024 Emergency Plan Implementing Procedure Revisions ML24089A1152024-06-21021 June 2024 Transmittal Letter, Environmental Assessments and Findings of No Significant Impact Related to Exemption Requests from 10 CFR 37.11(c)(2) ML24158A5312024-06-0606 June 2024 Registration of Use of Cask to Store Spent Fuel (MPC-361, -362, -363) ML24145A0852024-05-30030 May 2024 1B-B Diesel Generator Failure - Final Significance Determination Letter ML24145A1052024-05-29029 May 2024 301 Exam Approval Letter ML24134A1762024-05-13013 May 2024 Submittal of 2023 Annual Radiological Environmental Operating Report CNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24128A0352024-05-0707 May 2024 Providing Supplemental Information to Apparent Violation ML24120A0582024-04-26026 April 2024 10 CFR 50.46 Annual Report for Sequoyah Nuclear Plant Units 1 and 2 ML24116A2612024-04-25025 April 2024 Interim Report of a Deviation or Failure to Comply - Transducer Model 8005N ML24114A0482024-04-23023 April 2024 Annual Radioactive Effluent Release Report for 2023 Monitoring Period CNL-24-037, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 422024-04-22022 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 42 ML24144A2362024-04-20020 April 2024 Discharge Monitoring Report (Dmr), March 2024 ML24144A2322024-04-20020 April 2024 Tennessee Multi-Sector Permit (Tmsp), 2024 Annual Discharge Monitoring Report for Outfalls SW-3, SW-3, and SW-9 ML24102A1212024-04-18018 April 2024 Summary of Conference Call with Tennessee Valley Authority Regarding Sequoyah Nuclear Plant, Unit 1 Spring 2024 Steam Generator Tube Inspections ML24089A0882024-04-18018 April 2024 – Exemption from Select Requirements of 10 CFR Part 73; Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting CNL-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-24-024, Hydrologic Engineering Center River Analysis System Project Milestone Status Update2024-04-17017 April 2024 Hydrologic Engineering Center River Analysis System Project Milestone Status Update IR 05000327/20240012024-04-17017 April 2024 Integrated Inspection Report 05000327/2024001 and 05000328/2024001 ML24109A0272024-04-16016 April 2024 Cycle 27 Core Operating Limits Report Revision 0 CNL-23-006, Application to Modify Technical Specifications 3.8.1, AC Sources – Operating, and 3.8.2, AC Sources – Shutdown, for Sequoyah Nuclear Plant (SQN-TSC-22-03)2024-04-15015 April 2024 Application to Modify Technical Specifications 3.8.1, AC Sources – Operating, and 3.8.2, AC Sources – Shutdown, for Sequoyah Nuclear Plant (SQN-TSC-22-03) ML24106A0502024-04-12012 April 2024 Discharge Monitoring Report (Dmr), February 2024 ML24100A0162024-04-11011 April 2024 Request for Regulatory Conference (Tennessee Valley Authority - Sequoyah Nuclear Plant) ML24100A0282024-04-0808 April 2024 HI-STORM FW Amendment 7 RAI Response Clarifications (Part 5) CNL-24-020, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements2024-04-0101 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements ML24088A0332024-03-28028 March 2024 Request for Regulatory Conference (Tennessee Valley Authority) CNL-24-007, Annual Insurance Status Report2024-03-27027 March 2024 Annual Insurance Status Report CNL-24-008, Guarantee of Payment of Deferred Premiums - 2023 Annual Report2024-03-27027 March 2024 Guarantee of Payment of Deferred Premiums - 2023 Annual Report ML24040A2062024-03-26026 March 2024 Issuance of Amendment Nos. 367 and 361 Regarding Changes to the Hydrologic Analyses (EPID L-2020-LLA-0004) - Public ML24082A0082024-03-22022 March 2024 Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 2024-08-08
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lill Tennessee Valley Authority, Post Office Box 2000, Soddy Daisy, Tennessee 37384-2000 April 14, 2016 10 CFR 72.4 10 CFR 72.212 ATTN: Document Control Oesk Director, Division of Spent Fuel Management Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Sequoyah Nuclear Plant, Units 1 and 2 Renewed Facility Operating License Nos. DPR-77 and DPR-79 NRC Docket Nos. 50-327, 50-328, and 72-034 1 2- - I D.3 2-
Subject:
Sequoyah Nuclear Plant - Registration of Spent Fuel Storage '
Cask Pursuant to 10 CFR 72.212(b)(2)
In accordance with 10 CFR 72.212, "Conditions of General License Issued Under
§72.21 O," paragraph (b)(2), Sequoyah Nuclear Plant (SQN) is registering with NRC the use of spent fuel storage casks at SQN's Independent Spent Fuel Storage Installation. Accordingly, SQN provides the following information: '
Licensee Name: Tennessee Valley Authority Licensee Address: Post Office Box 2000 Soddy-Daisy, Tennessee 37384-2000 Reactor License Numbers: DPR-77 and DPR-79 Reactor Docket Numbers: 50-327 and 50-328 Responsible Individual: Michael McBrearty Manager, Sequoyah Nuclear Licensing Cask Certificate Number: 1032, Amendment No. 0, June 13, 2011 Cask Model Number> HI-STORM FW MPC Storage System
U.S. Nuclear Regulatory Commission Page2 April 14, 2016 For the initial use. of the cask system on March 15, 2016:
Cask Identification Multi-Purpose Canister Numbers: Type 37 Serial No. 0011 Overpack Serial No. 0023 For the initial use of the cask system on March 22, 2016:
Cask Identification Multi-Purpose Canister Numbers: Type 37 Serial No. 0012 Overpack Serial No. 0024 For the initial use of the cask system on March 28, 2016:
Cask Identification Multi-Purpose Canister Numbers: Type 37 Serial No. 0013 Overpack Serial No. 0025 For the initial use of the cask system on April 4, 2016:
Cask Identification Multi-Purpose Canister Numbers: Type 37 Serial No. 0014 Overpack Serial No. 0026 This document contains no regulatory commitments.
If you have any questions, please contact Michael McBrearty at (423) 843-7170.
ristopher J. Schwarz Site Vice President Sequoyah Nuclear Plant cc:
NRC Regional Administrator - Region II
lill Tennessee Valley Authority, Post Office Box 2000, Soddy Daisy, Tennessee 37384-2000 April 14, 2016 10 CFR 72.4 10 CFR 72.212 ATTN: Document Control Oesk Director, Division of Spent Fuel Management Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Sequoyah Nuclear Plant, Units 1 and 2 Renewed Facility Operating License Nos. DPR-77 and DPR-79 NRC Docket Nos. 50-327, 50-328, and 72-034 1 2- - I D.3 2-
Subject:
Sequoyah Nuclear Plant - Registration of Spent Fuel Storage '
Cask Pursuant to 10 CFR 72.212(b)(2)
In accordance with 10 CFR 72.212, "Conditions of General License Issued Under
§72.21 O," paragraph (b)(2), Sequoyah Nuclear Plant (SQN) is registering with NRC the use of spent fuel storage casks at SQN's Independent Spent Fuel Storage Installation. Accordingly, SQN provides the following information: '
Licensee Name: Tennessee Valley Authority Licensee Address: Post Office Box 2000 Soddy-Daisy, Tennessee 37384-2000 Reactor License Numbers: DPR-77 and DPR-79 Reactor Docket Numbers: 50-327 and 50-328 Responsible Individual: Michael McBrearty Manager, Sequoyah Nuclear Licensing Cask Certificate Number: 1032, Amendment No. 0, June 13, 2011 Cask Model Number> HI-STORM FW MPC Storage System
U.S. Nuclear Regulatory Commission Page2 April 14, 2016 For the initial use. of the cask system on March 15, 2016:
Cask Identification Multi-Purpose Canister Numbers: Type 37 Serial No. 0011 Overpack Serial No. 0023 For the initial use of the cask system on March 22, 2016:
Cask Identification Multi-Purpose Canister Numbers: Type 37 Serial No. 0012 Overpack Serial No. 0024 For the initial use of the cask system on March 28, 2016:
Cask Identification Multi-Purpose Canister Numbers: Type 37 Serial No. 0013 Overpack Serial No. 0025 For the initial use of the cask system on April 4, 2016:
Cask Identification Multi-Purpose Canister Numbers: Type 37 Serial No. 0014 Overpack Serial No. 0026 This document contains no regulatory commitments.
If you have any questions, please contact Michael McBrearty at (423) 843-7170.
ristopher J. Schwarz Site Vice President Sequoyah Nuclear Plant cc:
NRC Regional Administrator - Region II