Letter Sequence Other |
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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
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MONTHYEARML13024A0042013-01-0707 January 2013 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
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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 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
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Text
Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-15-095 May 14, 2015 10 CFR 50.4 10 CFR 50, Appendix H ATTN : Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Sequoyah Nuclear Plant, Unit 1 and 2 Facility Operating License Nos. DPR-77 and DPR-79 NRC Docket Nos. 50-327 and 50-328
Subject:
SEQUOYAH NUCLEAR PLANT- REVISION TO THE REACTOR PRESSURE VESSEL SURVEILLANCE CAPSULE WITHDRAWAL SCHEDULE FOR LICENSE RENEWAL
References:
- 1. NRC letter to TVA, Sequoyah Nuclear Plant, Units 1 and 2- Revise the Reactor Pressure Vessel Material Surveillance Capsule Withdrawal Schedule due to License Renewal Amendment (TAC NOS. MF0631 and MF0632}, dated September 27, 2013
- 2. TVA letter to NRC, Sequoyah Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedule Revision Due to License Renewal Amendment, dated January 10, 2013 By the Reference 1 letter, NRC provided acceptance of the Tennessee Valley Authority (TVA) revised reactor pressure vessel (RPV) material surveillance specimen withdrawal schedule for Sequoyah (SQN}, Units 1 and 2. The revised withdrawal schedule had been submitted by TVA's Reference 2 letter and supported license renewal of SQN , Units 1 and 2 operating licenses for an additional 20 years. The revised schedule was based on relocation of the "S" and "W" surveillance capsules for Units 1 and 2. The capsule relocation was completed during each unit's end of cycle (EOC) R19. The objective of this relocation was to place surveillance capsules in a leading fluence location so that the revised surveillance specimen withdrawal schedule would comply with the expectations of American Society for Testing and Materials (ASTM) E 185-82, NUREG-1801, Revision 2, "Generic Aging Lessons Learned (GALL) Report, " and the requirements of 10 CFR 50, Appendix H.
U.S. Nuclear Regulatory Commission CNL-15-095 Page2 May 14, 2015 As discussed with NRC staff on April 30, 2015, unanticipated damage to the "S" and "W' capsule specimens was discovered during Unit 1 EOC R20. TVA is requesting NRC review and approval of a proposed alternative withdrawal schedule that would support staff approval of SON's License Renewal Application. The proposed alternative withdrawal schedule continues to meet the provisions of the specific regulatory requirements for the License Renewal Rule, 10 CFR Part 54, [i.e., (ASTM) E 185-82, NUREG-1801, Revision 2, "Generic Aging Lessons Learned (GALL) Report," and the requirements of 10 CFR 50, Appendix H].
Relocation of Unit 1 reactor vessel surveillance Capsule V from the 176-degree azimuthal location to the 140-degree azimuthal location, a higher fluence location, is required to support the proposed alternative capsule withdrawal schedule. Because the relocation of the SQN Unit 1 surveillance capsule screens out under 10 CFR 50.59, NRC approval of the relocation is not required (see Enclosure 3).
No changes are requested in the NRC approved Unit 2 reactor vessel material surveillance capsule withdrawal schedule.
Based on the technical justification for the proposed change provided in WCAP-17539-NP, Revision 1 (Enclosure 2) and as discussed in Enclosure 1, TVA concludes that the proposed changes comply with ASTM Standard Practice E 185-82.
If you have any questions regarding this submittal, please contact Ms. Erin Henderson, Sequoyah Site Licensing Manager at (423) 843-7170.
I declare under penalty of perjury that the foregoing is true and correct. Executed on this 14th day of May 2015.
Enclosures 1. Request for Revision to Reactor Vessel Material Surveillance Capsule Withdrawal Schedule for Sequoyah Nuclear Plant Unit 1
- 2. WCAP-17539-NP Revision 1, May 2015
- 3. Westinghouse Electric Company -10 CFR 50.59 Applicability and Screening Review - Reactor Vessel Surveillance Capsule Relocation cc: NRC Regional Administrator - Region II NRC Senior Resident Inspector- Sequoyah Nuclear Plant NRR Project Manager- Sequoyah Nuclear Plant
ENCLOSURE1 Tennessee Valley Authority Sequoyah Nuclear Plant Unit 1 Request for Revision to Reactor Vessel Material Surveillance Capsule Withdrawal Schedule for Sequoyah Nuclear Plant Unit 1
- 1. Background In Reference 1, Tennessee Valley Authority (TVA) proposed a revision to the Unit 1 Reactor Vessel Surveillance Capsule withdrawal schedule to support renewal of the Sequoyah (SQN)
Unit 1 operating license for an additional 20 years. In Reference 2, TVA responded to an NRC Request for Additional Information (RAI) regarding the Reference 1 proposed schedule change. In Reference 3, the NRC approved the proposed revised reactor vessel material surveillance capsule withdrawal schedule. The NRC review concluded, given that the relocation of Capsules S and W occurs during the 191h or 20 refueling outages, the revised withdrawal schedule date of the end of cycle (EOC) 28 for Unit 1 for surveillance capsule S is acceptable.
SQN relocated Capsules S and W to higher fluence locations at EOC 19 on Unit 1 in accordance with the relocation plan established in Reference 1. Inspection of the Unit 1 Reactor Vessel at EOC 20 revealed that the S and W capsules had become dislodged from the capsule holders and were destroyed. As a result, the planned S capsule withdrawal at EOC 28 on Unit 1 cannot be performed and an alternative Unit 1 capsule withdrawal schedule must be proposed.
Relocation of Unit 1 reactor vessel surveillance Capsule V from the 176-degree azimuthal location to the 140-degree azimuthal location, a higher fluence location is required to support the proposed alternative capsule withdrawal schedule.
- 2. Proposed Revision To The Withdrawal Schedule for SQN Unit 1 TVA is planning to relocate Capsule V in Unit 1 EOC 21, 22 or 23. The proposed revised Unit 1 schedule is to withdraw the relocated Unit 1 Capsule V (140-degree location after relocation from location 176-degree) during the EOC 31 (see FSAR Figure 5.4.3-3 below for location azimuths).
The Unit 1 Reactor Vessel Surveillance Capsules S and W withdrawal schedule defined in Reference 1 and approved by the NRC in Reference 3 is withdrawn due to the loss of these two capsules. The removal schedule for Capsule Z in Unit 1 will remain unchanged at this time.
- 3. Technical Justification for SQN Unit 1 As stated in SQN FSAR Section 5.4.3.7, Reactor Vessel Material Surveillance Program Requirements, Unit 1 Capsules T, U, X andY have been previously withdrawn for specimen testing for the 40-year operational period. With the permanent loss of Capsules Sand W, Capsules V and Z are the remaining capsules in the SQN Unit 1 reactor vessel. SQN Unit 1 Capsules V and Z are located at the 176-degree and 356-degree locations, respectively.
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TVA has submitted an application for the renewal of the SQN Units 1 and 2 operating licenses that proposes to extend the plant operating licenses for an additional 20 years. To account for the license renewal, TVA proposes to withdraw one of the remaining two capsules (Capsule V) from Unit 1 after the capsule is relocated to the 140-degree location and receives neutron fluence greater than the 60-year vessel fluence or 52 EFPY, that is deemed end-of-license extension (EOLE). The remaining spare capsule, Capsule Z, will stay in the reactor vessel for future license renewal use. The removal schedule for Capsule Z remains unchanged from that contained in the FSAR.
The proposed surveillance capsule withdrawal schedule is based on the requirements specified in ASTM E 185-82, Section 7.6. In accordance with the requirements of ASTM E 185-82, Section 7.6, after the relocation of Capsule V, TVA proposes to withdraw Capsule V from Unit 1 after its vessel fluence exposure exceeds the new peak EOLE (52 EFPY) vessel fluence, but prior to exceeding twice that fluence exposure to support the application to extend the SQN Unit 1 operating license.
Reference 4 (WCAP 17539-NP), Revision 0, developed by Westinghouse to perform the Time-Limited Aging Analyses (TLAA) for the SQN Units 1 and 2 reactor pressure vessels in accordance with the requirements of the License Renewal Rule, 10 CFR Part 54, updated the reactor vessel fluence evaluation. The fluence evaluation included a plant and fuel specific analysis for fuel cycles 1 through 18 for Unit 1. Projections were then made for future operation through EOLE (60 years of plant life or 52 EFPY of operation). Reference 4 provided the technical basis for the revised capsule removal schedule proposed by TVA in Reference 1 and approved by the NRC in Reference 3.
WCAP 17539-NP has been revised (Reference 5) to recognize that Capsules S and W have been destroyed and to define a revised Capsule V removal plan. The changes in WCAP 17539-NP, Revision 1, were limited to the changes associated with the delay in repositioning a capsule from a lagging position to a leading position. No changes were made in the Unit 1 reactor vessel fluence evaluation and the projection of the reactor vessel fluence through EOLE.
Per Reference 5, Table 2-1, the maximum reactor vessel fluence at 52 EFPY for Unit 1 is projected to be 2.66 x 10 19 n/cm 2 (E>1.0 MeV). In accordance with the requirements of ASTM E 185-82, Section 7.6, the surveillance capsules should be removed when their neutron fluence exceeds the new peak EOLE vessel fluence (i.e., 2.66 X 1019 n/cm 2 for Unit 1 at 52 EFPY), but prior to exceeding twice that fluence exposure (i.e., 5.32 X 1019 n/cm 2 for Unit 1).
In Reference 5, Appendix B, Table 8.1-4, relocation of Unit 1 Capsule V from the 176-degree position to the 140-degree position results in Capsule V reaching EOLE vessel fluence exposure (2.66 x 1019 n/cm 2 ) at 35.4 EFPY, 36.4 EFPY, and 37.3 EFPY, for EOC 21, EOC 22, and EOC 23, respectively (Table 1).
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Table 1 SQN U1 Potential Capsule V Withdrawal Times Associate with Relocation from the 176-degree Azimuthal Location to the 140-degree Azimuthal Location Capsule Time (EFPY) Corresponding to Capsule Relocation Time Vessel Llfe1*)
. 60 Years of Operation (52 EFPY)
EOC21 35.4 EOC22 36.4 EOC23 37.3 Note:
a) These dates are based on the capsule fluence being equivalent to one times the peak vessel fluence at 60 years (2.66 x 1019 n/cm 2)
In Reference 5, Appendix B, Table 8.1-5, provides the earliest EOC outa~e after the Unit 1 Capsule V exceeds the EOLE vessel fluence exposure (2.66 x 1019 n/cm ) if repositioned to the 140-degree position at EOC 23 (Table 2). Because the 140-degree location has a lead factor of 3.23, relocation of Unit 1 Capsule V to the 140-degree location at EOC 21 or EOC 22 will also exceed the EOLE vessel fluence exposure.
Table 2 SQN U1 Future Capsule V Withdrawal Outage Number Associated with Capsule Relocation from 176-degree Azimuthal location to 140-degree Azimuthal Location at EOC 23 in Support of 60 Total Years of Operation Capsule Fluence Outage Number EFPY (x10 19 n/cm 2, E>1.0MeV)
EOC30 38.10 2.78 EOC31 39.43 2.97 EOC32 40.76 3.17 The projected Capsule V capsule time (39.43 EFPY) and fluence (2.97 x 1019 n/cm2 ) at the end of Unit 1 Cycle 31 is greater than the earliest withdrawal EFPY of 37.3 and fluence (2.66 x 1019 n/cm2 ) for the bounding Capsule V relocation time. The projected Capsule V fluence (2.97 x 1019 n/cm 2) at EOC 31 does not exceed twice the EOLE vessel fluence exposure (5.32 x 1019 n/cm2). Relocation of Capsule V at EOC 21 or EOC 22 will also result in a fluence less than twice the EOLE vessel fluence. Therefore, withdrawal of the Unit 1 Capsule V, relocated from the 176-degree azimuthal location at either EOC 21, 22 or 23 complies with the requirements of 10 CFR 50, Appendix H and ASTM E 185-82 for 60 years (52 EFPY) of operation.
Table 3 provides the proposed FSAR revised capsule removal schedule that complies with the requirements of ASTM E 185-82 for 60 years (52 EFPY) of operation. The SQN FSAR will be updated following relocation of Capsule V.
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Table 3 Proposed FSAR Reactor Vessel Capsule Removal Schedule for Unit 1 Neutron Fluence Capsule Vessel Lead Factor (c) Withdrawal Time!c) (EFPY) (x 1019 n/cm 2 ,
Number Location E>1.0 MeV)
T 40° 3.15 1.07 (removed) 0.241 u 140° 3.23 2.85 (removed) 0.693 X 220° 3.22 5.26 (removed) 1.16 y 320° 3.18 10.02 (removed) 1.97 s N/A N/A Destroyed(a) N/A v 140°(b) 3.23 EOC31 2.66(d) w N/A N/A Destroyed(al N/A z 356° 0.90 Standby N/A Notes:
a) Capsule S was relocated to the 40-degree azimuthal location and Capsule W was relocated to the 220-degree azimuthal location at EOC 19 and were found destroyed at EOC 20.
b) Capsule V was relocated from the 176-degree location to the 140-degree location.
c) Values taken from WCAP 17539-NP, Revision 1, Table 7-1 (Reference 5).
d) Neutron fluence values shown are the 60-year peak reactor vessel values. The Capsule V fluence values at EOC 31 will exceed the 60-year peak reactor vessel fluence values assuming Capsule Vis relocated at either EOC 21, 22 or 23, as shown in Table 2.
In summary, TVA is planning to relocate the Unit 1 Capsule V from the current 176-degree azimuthal location to the 140-degree azimuthal location at either EOC 21, 22 or 23. TVA is proposing a revised Unit 1 Capsule V withdrawal schedule to support the application for a SQN Unit 1 renewed license. The proposed revised schedule is to withdraw the relocated Unit 1 Capsule V during the EOC 31 outage. The remaining Capsule Z in Unit 1 will remain in standby.
- 4. References
- 1) TVA letter to NRC, Sequoyah Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedule Revision Due to License Renewal Amendment, dated January 10, 2013.
- 2) TVA letter to NRC, Response to NRC Request for Additional Information Regarding Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedule Revision (TAG Nos. MF0631 and MF0632), dated July 3, 2013.
- 3) NRC Letter to TVA, Sequoyah Nuclear Plant, Units 1 and 2- Revise the Reactor Pressure Vessel Material Surveillance Capsule Withdrawal Schedule Due To License Renewal Amendment (TAG NOs. MF0631 and MF0632), dated September 27, 2013.
- 4) Westinghouse Report WCAP-17539-NP, Revision 0, "SEQUOYAH NUCLEAR PLANT Units 1 and 2 Time-Limited Aging Analysis on Reactor Vessel Integrity," March 2012.
- 5) Westinghouse Report WCAP-17539-NP, Revision 1, "SEQUOYAH NUCLEAR PLANT Units 1 and 2 Time-Limited Aging Analysis on Reactor Vessel Integrity," May 2015.
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CNL-15-095 E1-5 of 6 ENCLOSURE 2 Tennessee Valley Authority Sequoyah Nuclear Plant Units 1 and 2 Westinghouse WCAP-17539-NP, Revision 1 Sequoyah Units 1 and 2 Time-Limited Aging Analysis on Reactor Vessel Integrity (Non-Proprietary)