CNL-15-178, License Renewal Application - Clarifications (TAC Nos. MF0481 and MF0482)
Letter Sequence Other | |
---|---|
Initiation
Administration Questions
Answers
Results Other: CNL-15-095, Revision to the Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedule for License Renewal, CNL-15-164, Second Annual Update, License Renewal Application, CNL-15-178, License Renewal Application - Clarifications (TAC Nos. MF0481 and MF0482), ML13032A251, ML13057A873, ML13067A201, ML13141A320, ML15236A067 | |
MONTHYEARML13024A0042013-01-0707 January 2013
[Table View]Transmittal of License Renewal Application Project stage: Request ML13032A2512013-01-10010 January 2013 Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedule Revision Due to License Renewal Amendment Project stage: Other ML13057A8732013-03-0808 March 2013 Plan for the Scoping and Screening Regulatory Audit Regarding the Sequoyah Nuclear Plant, Unit 1 and 2, LRA Review Project stage: Other ML13067A2012013-03-11011 March 2013 Plan for the Aging Management Program Regulatory Audit Regarding the Sequoyah Nuclear Plant, Units 1 and 2 License Renewal Application Review (TAC Nos. MF0481 and MF0482) Project stage: Other ML13109A5152013-04-26026 April 2013 Requests for Additional Information for the Review of the Sequoyah Nuclear Plant, Units 1 and 2, License Renewal Application (TAC Nos. MF0481 and MF0482) Project stage: RAI ML13122A3402013-05-0808 May 2013 RAI for the Review of the Sequoyah Nuclear Plant, Units 1 and 2, License Renewal Application (TAC Nos. MF0481 and MF0482) Project stage: RAI ML13119A0972013-05-21021 May 2013 Summary of Telephone Conference Call Held on April 22, 2013 Between the U.S. Nuclear Regulatory Commission and Tva,Concerning Requests for Additional Information Pertaining to the Sequoyah Nuclear Plant, License Renewal Application Project stage: RAI ML13142A3322013-05-21021 May 2013 Requests for Additional Information for the Review of the Sequoyah Nuclear Plant, Units 1 and 2, License Renewal Application (TAC Nos. MF0481 and MF0482) Project stage: RAI ML13128A5192013-05-31031 May 2013 Request for Additional Information for the Review of the Sequoyah Nuclear Plant, Units 1 and 2, License Renewal Application Project stage: RAI ML13134A2012013-06-0505 June 2013 RAI for the Review of the Sequoyah Nuclear Plant, Units 1 and 2, LRA Project stage: RAI ML13163A4422013-06-0707 June 2013 Response to NRC Request for Additional Information Regarding the Scoping and Screening Methodology Review of the License Renewal Application, Set 3 Project stage: Response to RAI ML13144A7122013-06-11011 June 2013 Requests for Additional Information for the Review of the Sequoyah Nuclear Plant, Units 1 and 2, License Renewal Application (Tac Nos. MF0481 and MF0482)- Set 6 Project stage: RAI ML13134A3712013-06-13013 June 2013 5/9/2013 Summary of Telephone Conference Call Between the U.S. Nuclear Regulatory Commission and Tennessee Valley Authority, Concerning Requests for Additional Information Pertaining to the Sequoyah Nuclear Plant, Units 1 and 2, License Ren Project stage: RAI ML13141A3202013-06-13013 June 2013 Letter Aging Management Programs Audit Report Regarding the Sequoyah Nuclear Plant, Units 1 and 2 Project stage: Other ML13150A4122013-06-24024 June 2013 Requests for Additional Information for the Review of the Sequoyah Nuclear Plant, Units 1 and 2, License Renewal Application (TAC Nos. MF0481 and MF0482) - Set 8 Project stage: RAI ML13178A2832013-06-25025 June 2013 Response to NRC Request for Additional Information Regarding the Reactor Vessel Internals Review of the License Renewal Application, Set 1 Project stage: Response to RAI ML13158A0162013-06-25025 June 2013 Requests for Additional Information for the Review of the Sequoyah Nuclear Plant, Units 1 and 2, License Renewal Application (TAC Nos. MF0481 and MF0482) Set 9 Project stage: RAI ML13190A2762013-07-0101 July 2013 Response to NRC Request for Additional Information Regarding the Review of the License Renewal Application, Set 4 Project stage: Response to RAI ML13192A3302013-07-0303 July 2013 Response to NRC Request for Additional Information Regarding the Review of License Renewal Application, Set 5 (TAC Nos. MF0481 and MF0482) Project stage: Response to RAI ML13204A3992013-07-11011 July 2013 Response to NRC Request for Additional Information Re Reactor Vessel Internals Review of the License Renewal Application, Set 6 Project stage: Response to RAI ML13213A0262013-07-25025 July 2013 Response to NRC Request for Additional Information Regarding the Review of License Renewal Application, Set 4/Buried Piping, Set 8, and Set 9 (TAC MF0481 and MF0482) Project stage: Response to RAI ML13213A0272013-07-29029 July 2013 Response to NRC Request for Additional Information Regarding the Review of License Renewal Application, Set 7 (TAC Nos. MF0481 and MF0482) Project stage: Response to RAI ML13213A0142013-07-30030 July 2013 Revised Response to NRC Request for Additional Information Regarding the Review of the License Renewal Application, Sets 1 and 3 (TAC MF0481 and MF0482) Project stage: Response to RAI ML13171A0362013-08-0101 August 2013 Summary of Telephone Conference Call Held on June 13, 2013, Between the NRC and Tennessee Valley Authority, Concerning RAI Pertaining to the Sequoyah Nuclear Plant, Units 1 and 2, LRA Project stage: RAI ML13204A2572013-08-0202 August 2013 Requests for Additional Information for the Review of the Sequoyah Nuclear Plant, Units 1 and 2, License Renewal Application (TAC Nos. MF0481 and MF0482) - Set 10 Project stage: RAI ML13225A3872013-08-0909 August 2013 Response to NRC Request for Additional Information Regarding the Review of the Sequoyah Nuclear Plant, Units I and 2, License Renewal Application, Sets 1, 6, 7, and Revised Responses for 1.4-2, 1.4-3 and 1.4-4 (TAC Nos. MF0481 and MF0482) Project stage: Response to RAI ML13224A1262013-08-22022 August 2013 RAI for Review of Sequoyah, Units 1 & 2 License Renewal Application - Set 11 Project stage: RAI ML13238A2442013-08-30030 August 2013 RAI Set 12 Project stage: RAI ML13252A0362013-09-0303 September 2013 Response to NRC Request for Additional Information Regarding the Review of the License Renewal Application, Set 10 (30-day), B.1.9-1, B.1.4-4 Revised RAI Responses and Revision to LRA Page 2.4-44 (TAC Nos. MF0481 and MF0482) Project stage: Response to RAI ML13226A3712013-09-10010 September 2013 Summary of Telephone Conference Call Held on August 1, 2013, Between the U.S. Nuclear Regulatory Commission and Tennessee Valley Authority, Concerning Requests for Additional Information Pertaining to the Sequoyah Nuclear Plant, Units 1 Project stage: RAI ML13267A1592013-09-20020 September 2013 Response to NRC Request for Additional Information Regarding the Review of the Sequoyah Nuclear Plant, Units 1 and 2, License Renewal Application, Set 11 (30-day), and Revised RAI Responses for B.1.14-1a, 2.5. Project stage: Response to RAI ML13247A4272013-09-23023 September 2013 Summary of Telephone Conference Call Held on August 19, 2013, Between the NRC and Tennessee Valley Authority, Concerning RAI Pertaining to the Sequoyah Nuclear Plant, Units 1 and 2, LRA Project stage: RAI ML13263A3382013-09-26026 September 2013 RAI Set 14 Project stage: RAI ML13268A4922013-09-27027 September 2013 RAI Set 15 Project stage: RAI ML13276A0182013-09-30030 September 2013 Response to NRC Request for Additional Information Regarding the Review of the License Renewal Application, Sets 10 (B.1.23-2a), 11 (4.1-8a), and 12 (30-day) Project stage: Response to RAI CNL-13-103, Response to NRC Request for Additional Information Regarding the Review of the Sequoyah Nuclear Plant, Units 1 and 2, License Renewal Application, Sets 8 (B.1.33-1), 10 (3.0.3-1 Request 1), 12 (B.1.23-2b), 13 (30-day), 14 (B.0.4-1a)2013-10-17017 October 2013 Response to NRC Request for Additional Information Regarding the Review of the Sequoyah Nuclear Plant, Units 1 and 2, License Renewal Application, Sets 8 (B.1.33-1), 10 (3.0.3-1 Request 1), 12 (B.1.23-2b), 13 (30-day), 14 (B.0.4-1a) Project stage: Response to RAI ML13282A3302013-10-18018 October 2013 RAI Set 16 Project stage: RAI CNL-13-104, Response to NRC Request for Additional Information Regarding the Review of License Renewal Application, Sets 11 (B.1.40-4a, B.1.25.1a), 13 (B.1.41-4a),14 (3.5.1-57, 3.5.1-87)2013-10-21021 October 2013 Response to NRC Request for Additional Information Regarding the Review of License Renewal Application, Sets 11 (B.1.40-4a, B.1.25.1a), 13 (B.1.41-4a),14 (3.5.1-57, 3.5.1-87) Project stage: Response to RAI CNL-13-105, Response to NRC Request for Additional Information Regarding Review of the License Renewal Application, Sets 10 (3.0.3-1, Requests 3, 4, 6), 12 (B.1.6-1b, B.1.6-2b), 16 (4.3.1-8a)2013-11-0404 November 2013 Response to NRC Request for Additional Information Regarding Review of the License Renewal Application, Sets 10 (3.0.3-1, Requests 3, 4, 6), 12 (B.1.6-1b, B.1.6-2b), 16 (4.3.1-8a) Project stage: Response to RAI CNL-13-106, Response to NRC Request for Additional Information Regarding the Review of the Sequoyah Nuclear Plant, Units I and 2, License Renewal Application, Sets 13 (B.1.34-5a), 15 (4.2-1a), 16 (B.1.23-2c), 17 (B.1.23-2d), LRA Sections A.1.34 and B2013-11-15015 November 2013 Response to NRC Request for Additional Information Regarding the Review of the Sequoyah Nuclear Plant, Units I and 2, License Renewal Application, Sets 13 (B.1.34-5a), 15 (4.2-1a), 16 (B.1.23-2c), 17 (B.1.23-2d), LRA Sections A.1.34 and B.1 Project stage: Response to RAI ML13323A0972013-12-0606 December 2013 RAI Set 18 Project stage: RAI CNL-13-130, Response to NRC Request for Additional Information Regarding the Review of the License Renewal Application, B.1.41-4b, 3.0.3-1 (Requests La, 3a, 4a, 6a), B.1.23-2e, 3.4.2.1.1-2a, Tables (3.4.1, 3.4.2-3-5, 3.3.1..2013-12-16016 December 2013 Response to NRC Request for Additional Information Regarding the Review of the License Renewal Application, B.1.41-4b, 3.0.3-1 (Requests La, 3a, 4a, 6a), B.1.23-2e, 3.4.2.1.1-2a, Tables (3.4.1, 3.4.2-3-5, 3.3.1.. Project stage: Response to RAI ML13353A5382013-12-23023 December 2013 RAI Set 19 Project stage: RAI ML13338A3332014-01-0808 January 2014 Summary of Telephone Conference Call Held on August 22, 2013, Between the U.S. Nuclear Regulatory Commission and Tennessee Valley Authority, Concerning Requests for Additional Information Pertaining to the Sequoyah Nuclear Plant, Units 1 an Project stage: RAI CNL-14-021, Response to Request for Clarification to NRC Request for Additional Information Re Review of License Renewal Application, LRA B.1.31, B.1.25.1b, B.1.34-8a, B.1.34-9A, LRA Annual Update (TAC MF0481 & MF0482)2014-03-0303 March 2014 Response to Request for Clarification to NRC Request for Additional Information Re Review of License Renewal Application, LRA B.1.31, B.1.25.1b, B.1.34-8a, B.1.34-9A, LRA Annual Update (TAC MF0481 & MF0482) Project stage: Supplement ML14059A3472014-03-0404 March 2014 Schedule Revision for the Review of the Sequoyah Nuclear Plant License Renewal Application (TAC Nos. MF0481 and MF0482) Project stage: Approval ML14063A5422014-03-0404 March 2014 TVA Response to Request for Clarification to NRC Request for Additional Information Regarding the Review of the Sequoyah Nuclear Plant, Units 1 and 2, License Renewal Application, LRA B.1.31, B.1.25.1 B, B.1.34-Sa, B.1.34-9a, LRA Annual ... Project stage: Supplement ML14064A4732014-03-12012 March 2014 Request for Additional Information for the Review of the Sequoyah Nuclear Plant, Units 1 and 2, LRA - Set 20 Project stage: RAI ML14094A2942014-04-11011 April 2014 Project Manager Change for the Safety Review of the Sequoyah Nuclear Plant, Units 1 & 2, License Renewal Application (TAC Nos. MF0481 & MF0482) Project stage: Approval CNL-14-052, TVA Response to NRC Request for Additional Information Regarding the Review of the Sequoyah Nuclear Plant, Units 1 and 2, License Renewal Application: RAIs B.1.13-4 and 3.0.3-1-3c, Commitment 9.G, and 2013 LRA Annual Update (TAC Nos. MF042014-04-22022 April 2014 TVA Response to NRC Request for Additional Information Regarding the Review of the Sequoyah Nuclear Plant, Units 1 and 2, License Renewal Application: RAIs B.1.13-4 and 3.0.3-1-3c, Commitment 9.G, and 2013 LRA Annual Update (TAC Nos. MF0481 Project stage: Response to RAI 2013-07-01 |
ML15240A145 | |
Person / Time | |
---|---|
Site: | Sequoyah |
Issue date: | 08/28/2015 |
From: | James Shea Tennessee Valley Authority |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
CNL-15-178, TAC MF0481, TAC MF0482 | |
Download: ML15240A145 (3) | |
Similar Documents at Sequoyah | |
---|---|
Category:Letter type:CNL
MONTHYEARCNL-24-017, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2024-01-17017 January 2024
[Table view]Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions CNL-23-068, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-21021 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation CNL-23-036, Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08)2023-12-18018 December 2023 Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08) 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 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 CNL-23-059, Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-2023-09-20020 September 2023 Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 CNL-23-057, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 642023-09-0505 September 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 64 CNL-23-028, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06)2023-08-0202 August 2023 Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06) CNL-23-055, Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills2023-07-25025 July 2023 Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills CNL-23-053, Tennessee Valley Authority - Radiological Emergency Plan Revisions2023-07-18018 July 2023 Tennessee Valley Authority - Radiological Emergency Plan Revisions CNL-23-049, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan .2023-06-26026 June 2023 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan . CNL-23-042, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-05-16016 May 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-23-032, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 412023-04-27027 April 2023 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 41 CNL-23-030, Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update2023-04-27027 April 2023 Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-23-033, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-04-24024 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision CNL-23-029, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-04-11011 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-23-012, Revision to the Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis, (TS-19-02)2023-04-11011 April 2023 Revision to the Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis, (TS-19-02) CNL-23-023, Annual Insurance Status Report2023-03-30030 March 2023 Annual Insurance Status Report CNL-23-024, TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report2023-03-29029 March 2023 TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report CNL-23-022, Decommissioning Funding Status Report2023-03-29029 March 2023 Decommissioning Funding Status Report CNL-23-021, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-03-0808 March 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-22-037, Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533)2023-01-31031 January 2023 Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533) CNL-23-003, Browns Nuclear Plant, Units 1, 2 & 3; Sequoyah Nuclear Plant, Units 1 & 2; and Watts Bar Nuclear Plant, Units 1 & 2 - Organizational Topic Report TVA-NPOD89-A2023-01-30030 January 2023 Browns Nuclear Plant, Units 1, 2 & 3; Sequoyah Nuclear Plant, Units 1 & 2; and Watts Bar Nuclear Plant, Units 1 & 2 - Organizational Topic Report TVA-NPOD89-A CNL-23-011, Steam Generator Tube Inspection Report to Reflect TSTF-577 Reporting Requirements2023-01-18018 January 2023 Steam Generator Tube Inspection Report to Reflect TSTF-577 Reporting Requirements CNL-23-009, Response to Request for Additional Information Request to Revise Technical Specification 3.4.122023-01-0404 January 2023 Response to Request for Additional Information Request to Revise Technical Specification 3.4.12 CNL-23-008, Tennessee Valley Authority Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2022-12-22022 December 2022 Tennessee Valley Authority Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-22-106, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-14, Revision 38, Nuclear Emergency Public Information Organization and Operat2022-11-28028 November 2022 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-14, Revision 38, Nuclear Emergency Public Information Organization and Operatio CNL-22-099, Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update2022-10-31031 October 2022 Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-22-104, Correction to Response to Request for Additional Information Regarding Sequoyah Nuclear Plant, Units 1 and 2, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RV-022022-10-31031 October 2022 Correction to Response to Request for Additional Information Regarding Sequoyah Nuclear Plant, Units 1 and 2, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RV-02 CNL-22-098, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC EPIP-7, Rev. 45 & CECC EPIP-8, Rev. 552022-10-17017 October 2022 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC EPIP-7, Rev. 45 & CECC EPIP-8, Rev. 55 CNL-22-084, Response to Request for Additional Information Regarding License Amendment Request to License Amendment Request to Modify Approved 10 CFR 50.69 Categorization Process (SQN-TS-21-07)2022-09-16016 September 2022 Response to Request for Additional Information Regarding License Amendment Request to License Amendment Request to Modify Approved 10 CFR 50.69 Categorization Process (SQN-TS-21-07) CNL-22-085, Response to Request for Additional Information Regarding Sequoyah Nuclear Plant (Sqn), Units 1 and 2 and Watts Bar Nuclear Plant (Wbn), Units 1 and 2, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Al2022-09-0202 September 2022 Response to Request for Additional Information Regarding Sequoyah Nuclear Plant (Sqn), Units 1 and 2 and Watts Bar Nuclear Plant (Wbn), Units 1 and 2, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alte CNL-22-053, Response to Request for Additional Information Regarding Application to Revise Sequoyah Nuclear Plant Units 1 and 2 Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis - Second Partial Response to Additional Requ2022-08-22022 August 2022 Response to Request for Additional Information Regarding Application to Revise Sequoyah Nuclear Plant Units 1 and 2 Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis - Second Partial Response to Additional Reques CNL-22-077, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2022-08-11011 August 2022 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-22-030, Application to Revise Technical Specification 3.4.12, Low Temperature Overpressure Protection System for Sequoyah Nuclear Plant (SQN-TSC-22-01) and TS 3.4.12 Cold Overpressure Mitigation System for Watts Bar Nuclear Plant (WBN-TS-22-03)2022-07-27027 July 2022 Application to Revise Technical Specification 3.4.12, Low Temperature Overpressure Protection System for Sequoyah Nuclear Plant (SQN-TSC-22-01) and TS 3.4.12 Cold Overpressure Mitigation System for Watts Bar Nuclear Plant (WBN-TS-22-03) CNL-22-080, Request for Enforcement Discretion from the Requirements of Technical Specification 3.5.2, ECCS - Operating2022-07-22022 July 2022 Request for Enforcement Discretion from the Requirements of Technical Specification 3.5.2, ECCS - Operating CNL-22-081, Supplement to Sequoyah Nuclear Plant, Unit 1, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RP-122022-07-21021 July 2022 Supplement to Sequoyah Nuclear Plant, Unit 1, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RP-12 CNL-22-079, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RP-122022-07-20020 July 2022 American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RP-12 CNL-22-071, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections (SQN-TS-21-03 and WBN-TS-21-08)2022-07-13013 July 2022 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections (SQN-TS-21-03 and WBN-TS-21-08) CNL-22-039, Application to Revise Technical Specifications to Adopt TSTF-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements (BFN TS-537) (SQN-21-05) (WBN-TS-21-04)2022-07-13013 July 2022 Application to Revise Technical Specifications to Adopt TSTF-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements (BFN TS-537) (SQN-21-05) (WBN-TS-21-04) CNL-22-069, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf.2022-07-0101 July 2022 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf. CNL-22-070, Status Regarding the Improved Flood Mitigation System Project2022-06-30030 June 2022 Status Regarding the Improved Flood Mitigation System Project CNL-22-062, Response to Request for Additional Information Regarding American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RV-022022-06-28028 June 2022 Response to Request for Additional Information Regarding American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RV-02 CNL-22-008, and Watts Bar Nuclear Plant - Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules (BFN-TS-541, SQN-TS-21-09, and WBN-TS-22-002)2022-06-13013 June 2022 and Watts Bar Nuclear Plant - Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules (BFN-TS-541, SQN-TS-21-09, and WBN-TS-22-002) CNL-22-064, Response to Request for Additional Information Regarding Tennessee Valley Authority License Amendment Request to Revise Emergency Plan Implementing Procedure Regarding Seismic Event Emergency Action Level Change2022-06-0909 June 2022 Response to Request for Additional Information Regarding Tennessee Valley Authority License Amendment Request to Revise Emergency Plan Implementing Procedure Regarding Seismic Event Emergency Action Level Change CNL-22-068, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2022-06-0808 June 2022 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-22-047, Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2022-05-23023 May 2022 Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions CNL-22-034, Second Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b (SQN-TS-20-03)2022-05-13013 May 2022 Second Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b (SQN-TS-20-03) CNL-22-027, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 40 - Annual Update and Proposed Changes to Revision 402022-04-28028 April 2022 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 40 - Annual Update and Proposed Changes to Revision 40 CNL-22-023, Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf2022-04-28028 April 2022 Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf 2024-01-17 Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50 MONTHYEARCNL-23-036, Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08)2023-12-18018 December 2023
[Table view]Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08) CNL-23-059, Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-2023-09-20020 September 2023 Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 CNL-23-028, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06)2023-08-0202 August 2023 Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06) CNL-22-037, Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533)2023-01-31031 January 2023 Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533) CNL-22-030, Application to Revise Technical Specification 3.4.12, Low Temperature Overpressure Protection System for Sequoyah Nuclear Plant (SQN-TSC-22-01) and TS 3.4.12 Cold Overpressure Mitigation System for Watts Bar Nuclear Plant (WBN-TS-22-03)2022-07-27027 July 2022 Application to Revise Technical Specification 3.4.12, Low Temperature Overpressure Protection System for Sequoyah Nuclear Plant (SQN-TSC-22-01) and TS 3.4.12 Cold Overpressure Mitigation System for Watts Bar Nuclear Plant (WBN-TS-22-03) CNL-22-039, Application to Revise Technical Specifications to Adopt TSTF-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements (BFN TS-537) (SQN-21-05) (WBN-TS-21-04)2022-07-13013 July 2022 Application to Revise Technical Specifications to Adopt TSTF-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements (BFN TS-537) (SQN-21-05) (WBN-TS-21-04) CNL-22-071, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections (SQN-TS-21-03 and WBN-TS-21-08)2022-07-13013 July 2022 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections (SQN-TS-21-03 and WBN-TS-21-08) ML22165A1052022-07-12012 July 2022 Issuance of Amendment Nos. 357 and 351 Regarding Revision to Technical Specification Table 3.3.1-1, Reactor Trip System Instrumentation CNL-22-008, and Watts Bar Nuclear Plant - Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules (BFN-TS-541, SQN-TS-21-09, and WBN-TS-22-002)2022-06-13013 June 2022 and Watts Bar Nuclear Plant - Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules (BFN-TS-541, SQN-TS-21-09, and WBN-TS-22-002) ML22115A0022022-05-17017 May 2022 Correction to Amendment No. 350 Regarding One-Time Change to Technical Specification3.4.12, Low Temperature Overpressure Protection System, CNL-22-034, Second Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b (SQN-TS-20-03)2022-05-13013 May 2022 Second Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b (SQN-TS-20-03) ML22125A1272022-05-0404 May 2022 Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Specification Bases CNL-22-023, Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf2022-04-28028 April 2022 Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf CNL-22-001, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections (SQN-TS-21-03 and WBN-TS-21-08)2022-04-0404 April 2022 Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections (SQN-TS-21-03 and WBN-TS-21-08) CNL-21-085, License Amendment Request to Modify Approved 10 CFR 50.69 Categorization Process (SQN-TS-21-07)2022-02-24024 February 2022 License Amendment Request to Modify Approved 10 CFR 50.69 Categorization Process (SQN-TS-21-07) CNL-21-001, Application to Modify the Technical Specification Table 3.3.1-1, Reactor Trip System Instrumentation (SQN-TS-21-01)2021-11-29029 November 2021 Application to Modify the Technical Specification Table 3.3.1-1, Reactor Trip System Instrumentation (SQN-TS-21-01) CNL-21-091, Exigent License Amendment Request to Revise Technical Specification 3.4.12, Low Temperature Overpressure Protection System (SQN-TS-21-06)2021-10-22022 October 2021 Exigent License Amendment Request to Revise Technical Specification 3.4.12, Low Temperature Overpressure Protection System (SQN-TS-21-06) CNL-21-026, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b (SQN-TS-20-03)2021-08-0505 August 2021 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b (SQN-TS-20-03) CNL-21-045, Bellefonte Nuclear Plant, Units 1 and 2; Browns Ferry Nuclear Plant, Units 1, 2, and 3; Clinch River Nuclear Site; Sequoyah Nuclear Plant, Units 1 and 2; Watts Bar Nuclear Plant, Unit 1 and 2 - Nuclear Quality Assurance Plan, TVA-NQA-PLN82021-04-29029 April 2021 Bellefonte Nuclear Plant, Units 1 and 2; Browns Ferry Nuclear Plant, Units 1, 2, and 3; Clinch River Nuclear Site; Sequoyah Nuclear Plant, Units 1 and 2; Watts Bar Nuclear Plant, Unit 1 and 2 - Nuclear Quality Assurance Plan, TVA-NQA-PLN89- CNL-20-014, Application to Modify the Technical Specification to Allow for Transition to Westinghouse RFA-2 Fuel (SQN-TS-20-09)2020-09-23023 September 2020 Application to Modify the Technical Specification to Allow for Transition to Westinghouse RFA-2 Fuel (SQN-TS-20-09) CNL-20-041, License Amendment Request to Remove Licensee Control (BFN TS-527, SQN-TS-20-08, and WBN-TS-20-016)2020-08-14014 August 2020 License Amendment Request to Remove Licensee Control (BFN TS-527, SQN-TS-20-08, and WBN-TS-20-016) CNL-20-047, Brown Ferry Nuclear Plant, Sequoyah Nuclear Plant & Watts Bar Nuclear Plant - Tennessee Valley Authority License Amendment Request to Revise Radiological Emergency Plan Regarding On-shift Emergency Medical Technician and Onsite Ambulance2020-07-31031 July 2020 Brown Ferry Nuclear Plant, Sequoyah Nuclear Plant & Watts Bar Nuclear Plant - Tennessee Valley Authority License Amendment Request to Revise Radiological Emergency Plan Regarding On-shift Emergency Medical Technician and Onsite Ambulance Re CNL-20-042, Exigent License Amendment Request to Revise Technical Specification 4.2.2, Control Rod Assemblies (SQN-TS-20-05)2020-04-17017 April 2020 Exigent License Amendment Request to Revise Technical Specification 4.2.2, Control Rod Assemblies (SQN-TS-20-05) CNL-20-010, Application to Revise Sequoyah Nuclear Plant (SQN) Unit 1 Technical Specifications for Steam Generator Tube Inspection Frequency (SQN-TS-20-01)2020-02-24024 February 2020 Application to Revise Sequoyah Nuclear Plant (SQN) Unit 1 Technical Specifications for Steam Generator Tube Inspection Frequency (SQN-TS-20-01) CNL-19-066, Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis, (TS-19-02)2020-01-14014 January 2020 Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis, (TS-19-02) CNL-19-116, Exigent License Amendment Request to Revise Technical Specification 4.2.2, Control Rod Assemblies (SQN-TS-19-05)2019-11-16016 November 2019 Exigent License Amendment Request to Revise Technical Specification 4.2.2, Control Rod Assemblies (SQN-TS-19-05) CNL-19-005, Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program (SQN-TS-19-01)2019-02-0101 February 2019 Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program (SQN-TS-19-01) CNL-18-130, Revised Application to Modify the Technical Specifications for Unbalanced Voltage Relays2018-11-19019 November 2018 Revised Application to Modify the Technical Specifications for Unbalanced Voltage Relays CNL-18-085, License Amendment Request to Change the Implementation Date for License Amendments to Upgrade Emergency Action Level Scheme2018-06-15015 June 2018 License Amendment Request to Change the Implementation Date for License Amendments to Upgrade Emergency Action Level Scheme CNL-17-010, Submittal of Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (SQN-TS-17-06)2018-03-16016 March 2018 Submittal of Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (SQN-TS-17-06) CNL-17-150, Request to Modify Essential Raw Cooling Water Motor Control Center Breakers and to Revise the Updated Final Safety Analysis Report (SQN-TS-17-04)2018-03-0909 March 2018 Request to Modify Essential Raw Cooling Water Motor Control Center Breakers and to Revise the Updated Final Safety Analysis Report (SQN-TS-17-04) NL-18-021, Supplement to Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plants, Units 1 and 2 License Amendment Request to Modify Technical Specification (TS) Surveillance Requirement 2.4, Qptr, and TS 3.3.1, 'Reactor Trip System (RTS) .2018-02-0808 February 2018 Supplement to Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plants, Units 1 and 2 License Amendment Request to Modify Technical Specification (TS) Surveillance Requirement 2.4, Qptr, and TS 3.3.1, 'Reactor Trip System (RTS) .. CNL-18-021, Supplement to Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plants, Units 1 and 2 License Amendment Request to Modify Technical Specification (TS) Surveillance Requirement 2.4, QPTR, and TS 3.3.1, 'Reactor Trip System (RTS)2018-02-0808 February 2018 Supplement to Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plants, Units 1 and 2 License Amendment Request to Modify Technical Specification (TS) Surveillance Requirement 2.4, QPTR, and TS 3.3.1, 'Reactor Trip System (RTS) .. NL-17-034, Application to Modify the Technical Specifications for Browns Ferry (TS-512), Sequoyah (TS-17-03), and Watts Bar (TS-17-20) to Resolve the Open Phase Issue Identified in NRC Bulletin 2012-01, Design Vulnerability in Electrical Power System2017-11-17017 November 2017 Application to Modify the Technical Specifications for Browns Ferry (TS-512), Sequoyah (TS-17-03), and Watts Bar (TS-17-20) to Resolve the Open Phase Issue Identified in NRC Bulletin 2012-01, Design Vulnerability in Electrical Power System. CNL-17-034, Application to Modify the Technical Specifications for Browns Ferry (TS-512), Sequoyah (TS-17-03), and Watts Bar (TS-17-20) to Resolve the Open Phase Issue Identified in NRC Bulletin 2012-01, Design Vulnerability in Electrical Power Syste2017-11-17017 November 2017 Application to Modify the Technical Specifications for Browns Ferry (TS-512), Sequoyah (TS-17-03), and Watts Bar (TS-17-20) to Resolve the Open Phase Issue Identified in NRC Bulletin 2012-01, Design Vulnerability in Electrical Power System. CNL-17-008, License Amendment Request to Modify Technical Specification (TS) Surveillance Requirement 3.2.4, QPTR, and TS 3.3.1, Reactor Trip System (RTS) Instrumentation, Condition D (SQN-TS-17-02 and WBN-TS-17-014)2017-08-0707 August 2017 License Amendment Request to Modify Technical Specification (TS) Surveillance Requirement 3.2.4, QPTR, and TS 3.3.1, Reactor Trip System (RTS) Instrumentation, Condition D (SQN-TS-17-02 and WBN-TS-17-014) NL-17-008, Sequoyah and Watts Bar - License Amendment Request to Modify Technical Specification (TS) Surveillance Requirement 3.2.4, Qptr, and TS 3.3.1, Reactor Trip System (RTS) Instrumentation, Condition D (SQN-TS-17-02 and WBN-TS-17-014)2017-08-0707 August 2017 Sequoyah and Watts Bar - License Amendment Request to Modify Technical Specification (TS) Surveillance Requirement 3.2.4, Qptr, and TS 3.3.1, Reactor Trip System (RTS) Instrumentation, Condition D (SQN-TS-17-02 and WBN-TS-17-014) CNL-16-051, Proposed Technical Specification Change to Revise the Note Modifying SR 3.8.1.17 of TS 3.8.1 AC Sources - Operating (TS-SQN-16-04)2017-03-13013 March 2017 Proposed Technical Specification Change to Revise the Note Modifying SR 3.8.1.17 of TS 3.8.1 AC Sources - Operating (TS-SQN-16-04) CNL-16-121, Supplemental Information Regarding Proposed Technical Specification Change to Extend the Allowed Completion Time to Restore Essential Raw Cooling Water System Train to Operable Status from 72 Hours to 7 Days2016-07-22022 July 2016 Supplemental Information Regarding Proposed Technical Specification Change to Extend the Allowed Completion Time to Restore Essential Raw Cooling Water System Train to Operable Status from 72 Hours to 7 Days CNL-16-001, Application to Modify Sequoyah Nuclear Plant, Units 1 and 2 Technical Specifications Regarding Diesel Generator Steady State Frequency (SQN-TS-14-02)2016-05-26026 May 2016 Application to Modify Sequoyah Nuclear Plant, Units 1 and 2 Technical Specifications Regarding Diesel Generator Steady State Frequency (SQN-TS-14-02) CNL-16-018, License Amendment Request (SQN-TS-16-03) to Change the Completion Date of Cyber Security Plan Implementation Milestone 82016-05-16016 May 2016 License Amendment Request (SQN-TS-16-03) to Change the Completion Date of Cyber Security Plan Implementation Milestone 8 CNL-15-178, License Renewal Application - Clarifications (TAC Nos. MF0481 and MF0482)2015-08-28028 August 2015 License Renewal Application - Clarifications (TAC Nos. MF0481 and MF0482) CNL-15-164, Second Annual Update, License Renewal Application2015-08-14014 August 2015 Second Annual Update, License Renewal Application CNL-14-075, Redacted Version of License Amendment Request (SQN-TS-14-01) to Change the Completion Date of Cyber Security Plan Implementation Milestone 82014-05-27027 May 2014 Redacted Version of License Amendment Request (SQN-TS-14-01) to Change the Completion Date of Cyber Security Plan Implementation Milestone 8 ML13329A7172013-11-22022 November 2013 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) ML13281A8062013-08-0606 August 2013 Operating License Renewal, Site 40HA22 and Revision to Phase I Cultural Resources Survey Final Report, Hamilton County, Tn ML13199A2812013-07-0303 July 2013 Application to Modify Ice Condenser Technical Specifications to Address Revisions in Westinghouse Mass and Energy Release Calculation (SQN-TS-12-04) ML13024A0072013-01-0707 January 2013 License Renewal Application, Part 5 of 8 ML13024A0112013-01-0707 January 2013 Sequoyah Nuclear Plant, Units 1 and 2 - License Renewal Application, Part 1 of 8 ML13024A0062013-01-0707 January 2013 License Renewal Application, Part 4 of 8 2023-09-20 |
Text
Tennessee Valley Authority, 1101 Market Street, Chattanooga , Tennessee 37402 CNL-15-178 August 28, 2015 10 CFR Part 54 ATTN: Document Control Desk 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 and 50-328
Subject:
Sequoyah Nuclear Plant, Units 1 and 2, License Renewal Application -
Clarifications (TAC Nos. MF0481 and MF0482)
References:
- 1. TVA Letter to NRC, "Second Annual Update to the Sequoyah Nuclear Plant, Units 1 and 2, License Renewal Application ," dated August 14, 2015 By letter dated August 14, 2015 (Reference 1), Tennessee Valley Authority (TVA) submitted to the Nuclear Regulatory Commission (NRC) the second annual update to the Sequoyah Nuclear Plant (SQN) License Renewal Application (LRA). Subsequent discussions with the NRC SQN License Renewal Project Manager identified the need to provide additional clarification with regard to the Current Licensing Basis change discussed in the Reference 1 letter. The requested clarification is provided in the enclosure.
There are no new regulatory commitments contained in this letter. Please address any questions regarding this submittal to Erin Henderson at (423) 843-7170.
I declare under penalty of perjury that the foregoing is true and correct. Executed on this 28th day of August 2015 .
ly, JC ice President, Nuclear Licensing Enclosure cc: See Page 2
Nuclear Regulatory Commission CNL-15-178 Page 2 August 28, 2015
Enclosure:
Sequoyah Nuclear Plant, Units 1 and 2 License Renewal Application Second Annual Update - Clarifications cc (Enclosure):
NRC Regional Administrator - Region II NRC Senior Resident Inspector - Sequoyah Nuclear Plant NRC Project Manager - Sequoyah Nuclear Plant NRR License Renewal Project Manager - Sequoyah Nuclear Plant EDMS
ENCLOSURE Sequoyah Nuclear Plant, Units 1 and 2 License Renewal Application Second Annual Update - Clarifications Section 2.5 of the Sequoyah Nuclear Plant (SQN), Units 1 and 2 License Renewal Application (LRA) is modified as provided below with the additional text underlined and deleted text lined through. These changes supplement those previously provided in the enclosure to Reference 1 of the cover letter.
Section 2.5 SCOPING AND SCREENING RESULTS: ELECTRICAL AND INSTRUMENTATION AND CONTROL SYSTEMS Commodity Groups Not Subject to AMR Electrical and I&C Penetration Assemblies All Primary Containment SQN Environmentally qualified electrical and I&C penetration assemblies, with the exception of penetrations SQN-1-PENE-302-0026-S and SQN-1-PENE-302-0040-S , are in the EQ program (10 CFR 50.49). SQN electrical and I&C penetration assemblies in the EQ program are subject to replacement based on their qualified life, so they are not subject to aging management review (AMR). Cables and connections in non-EQ electrical and I&C penetration assemblies (such as SQN-1-PENE-302-0026-S and SQN-1-302-0040-S) are within the scope of license renewal and are subject to AMR as identified in Table 2.5-1, with AMR results as shown in Table 3.6.2. Non-EQ cables and connections to electrical and I&C penetrations are evaluated in the insulated cable and connection commodity group.
The pressure boundary function of electrical penetration assemblies SQN-1-PENE-302-0026-S and SQN-1-PENE-302-00 are included in the evaluation for the Reactor Building in Section 2.4.1.
E 1 of 1 CNL-15-178