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| | number = ML16131A720 | | | number = ML16131A720 |
| | issue date = 05/05/2016 | | | issue date = 05/05/2016 |
| | title = Sequoyah, Units 1 and 2 - Registration of Spent Fuel Storage Cask Pursuant to 10 CFR 72.212(b)(2) | | | title = Registration of Spent Fuel Storage Cask Pursuant to 10 CFR 72.212(b)(2) |
| | author name = Schwarz C J | | | author name = Schwarz C J |
| | author affiliation = Tennessee Valley Authority | | | author affiliation = Tennessee Valley Authority |
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Category:Letter
MONTHYEARML24304A8492024-10-31031 October 2024 December 2024 Requalification Inspection Notification Letter IR 05000327/20250102024-10-29029 October 2024 Notification of Sequoyah, Units 1 and 2 - Comprehensive Engineering Team Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000327/2025010 and 05000328/2025010 ML24298A1172024-10-24024 October 2024 Cycle 26, 180-Day Steam Generator Tube Inspection Report CNL-24-074, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-10-23023 October 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 05000327/LER-2024-001, Reactor Trip Due to a Turbine Trip2024-10-17017 October 2024 Reactor Trip Due to a Turbine Trip PLA-8148, Registration for the Use of Spent Fuel Storage Casks 311, 308, and 3102024-10-15015 October 2024 Registration for the Use of Spent Fuel Storage Casks 311, 308, and 310 ML24282B0412024-10-15015 October 2024 Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 ML24260A1682024-10-0404 October 2024 Regulatory Audit Summary Related to Request to Add and Revise Notes Related to Technical Specification Table 3.3.2-1, Function 5 ML24284A1072024-09-26026 September 2024 Affidavit for Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2 05000328/LER-2024-001, Reactor Trip Due to an Electrical Trouble Turbine Trip2024-09-25025 September 2024 Reactor Trip Due to an Electrical Trouble Turbine Trip CNL-24-047, Decommitment of Flood Mode Mitigation Improvement Systems2024-09-24024 September 2024 Decommitment of Flood Mode Mitigation Improvement Systems CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024 Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description ML24262A0602024-09-23023 September 2024 Summary of August 19, 2024, Meeting with Tennessee Valley Authority Regarding a Proposed Supplement to the Tennessee Valley Authority Nuclear Quality Assurance Plan ML24267A0402024-09-19019 September 2024 Cycle 27 Core Operating Limits Report Revision 0 PLA-8142, Registration for the Use of Spent Fuel Storage Casks 306, 309, and 307 - PLA-81422024-09-18018 September 2024 Registration for the Use of Spent Fuel Storage Casks 306, 309, and 307 - PLA-8142 ML24185A1742024-09-18018 September 2024 Cover Letter - Issuance of Exemption Related to Non-Destructive Examination Compliance Regarding Sequoyah Nuclear Plant Independent Spent Fuel Storage Installation CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024 Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24253A0152024-09-0808 September 2024 Emergency Plan Implementing Procedure Revisions ML24247A2212024-08-29029 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 ML24211A0542024-07-29029 July 2024 Operator License Examination Report ML24211A0572024-07-29029 July 2024 Submittal of Emergency Plan Implementing Procedure Revision 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 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 ML24191A4652024-07-0909 July 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations 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 ML24176A0222024-06-24024 June 2024 Retraction of Interim Report of a Deviation or Failure to Comply – Transducer Model 8005N 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 2024-09-08
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Tennessee Valley Authority, Post Office Box 2000, Soddy Daisy, Tennessee 37384-2000 May 5, 2016 *ATTN: Document Control Desk 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 10 CFR 72.4 10 CFR 72.212 Renewed Facility Operating License Nos. DPR-77 and DPR-79 NRC Docket Nos. 50-327, 50-328, and 72-034 7 2.-I o 7-..
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: Licensee Address: Reactor License Numbers: Reactor Docket Numbers: Responsible Individual:
Cask Certificate Number: Cask Model Number: Tennessee Valley Authority Post Office Box 2000 Soddy-Daisy, Tennessee 37384-2000 DPR-77 and DPR-79 50-327 and 50-328 Michael McBrearty Manager, Sequoyah Nuclear Licensing 1032, Amendment No. 0, June 13, 2011 HI-STORM FW MPC Storage System U.S. Nuclear Regulatory Commission Page 2 May 5, 2016 For the initial use of the cask system on April 11, 2016: Cask Identification Numbers: Multi-Purpose Canister Type 37 Serial No. 0015 Overpack Serial No. 0027 This document contains no regulatory commitments.
If you have any questions, please contact Michael McBrearty at (423) 843-7170.
f . .fm-: Christop er J. Schwarz Site Vice President Sequoyah Nuclear Plant cc: NRC Regional Administrator
-Region II Tennessee Valley Authority, Post Office Box 2000, Soddy Daisy, Tennessee 37384-2000 May 5, 2016 *ATTN: Document Control Desk 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 10 CFR 72.4 10 CFR 72.212 Renewed Facility Operating License Nos. DPR-77 and DPR-79 NRC Docket Nos. 50-327, 50-328, and 72-034 7 2.-I o 7-..
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: Licensee Address: Reactor License Numbers: Reactor Docket Numbers: Responsible Individual:
Cask Certificate Number: Cask Model Number: Tennessee Valley Authority Post Office Box 2000 Soddy-Daisy, Tennessee 37384-2000 DPR-77 and DPR-79 50-327 and 50-328 Michael McBrearty Manager, Sequoyah Nuclear Licensing 1032, Amendment No. 0, June 13, 2011 HI-STORM FW MPC Storage System U.S. Nuclear Regulatory Commission Page 2 May 5, 2016 For the initial use of the cask system on April 11, 2016: Cask Identification Numbers: Multi-Purpose Canister Type 37 Serial No. 0015 Overpack Serial No. 0027 This document contains no regulatory commitments.
If you have any questions, please contact Michael McBrearty at (423) 843-7170.
f . .fm-: Christop er J. Schwarz Site Vice President Sequoyah Nuclear Plant cc: NRC Regional Administrator
-Region II