Letter Sequence Request |
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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-15-098 Revision 1 July 10 , 2015 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 10 CFR 50.4 10 CFR Part 54
Subject:
Sequoyah Nuclear Plant -Revision to Commitment No. 28 and Review of Impacts to the SQN Reactor Vessel Internals Aging Management Program Due to Dislodged Reactor Vessel Surveillance Capsules in Unit 1 Reactor
References:
- 1. TVA Letter to NRC , "Sequoyah Nuclear Plant, Units 1 and 2 License Renewal" , dated January 7, 2013 2. TVA letter to NRC , "Sequoyah Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedule Revision Due to License Renewal Amendment," dated January 10 , 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 (TAC NOS. MF0631 and MF0632)," dated September 27 , 2013 4. TVA letter to NRC, " Sequoyah Nuclear Plant -Revision to Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedule for License Renewal," dated May 14, 2015 5. NRC letter to TVA, "Safety Evaluation Report Related to the Sequoyah Nuclear Plant , Units 1 and 2, License Renewal Application (TAC NOS. MF0481 and MF0482), dated January 29 , 2015 6. Westinghouse Report, "Sequoyah Unit 1U1R2010-YR Reactor Vessel IWI & Loose Part Inspections Field Service Report , dated May 2015 7. Westinghouse Procedure WDl-STD-088, Rev. 12 for Sequoyah Unit 1 U.S. Nuclear Regulatory Commission CNL-15-098 Revision 1 Page2 July 10, 2015 During the Sequoyah Nuclear Plant (SQN) Unit 1 end of cycle (EOC) R20 outage, inspections of the Unit 1 reactor vessel internals revealed that the reactor pressure vessel (RPV) material surveillance capsules S and W had become dislodged from their intact designated baskets and were no longer available to provide fluence data. These capsules had been relocated in Unit 1 EOC R19. ASME Section XI inservice inspections of the Sequoyah (SQN) Unit 1 reactor vessel internals identified that specimen pieces of the capsules had come in contact with some of the reactor vessel internals components.
On April 30, 2015, TVA conducted a phone call with Nuclear Regulatory Commission (NRC) staff to inform the staff of the damage to the Unit 1 Capsules S and W. The NRC requested that SQN evaluate the impacts to the SQN License Renewal Application (LRA) (Reference 1). TVA has evaluated the following potential impacts: (1) the reactor vessel surveillance capsule withdrawal schedule, (2) LRA commitment changes, (3) potential impacts to MRP-227-A assumptions that support the SQN Reactor Vessel Internals Aging Management Program defined in the LRA, and (4) Potential Aging Management mechanisms involved in the damaged S and W Capsules.
Results of the impact reviews are provided herein. Planned corrective actions to prevent recurrence are described in this letter. TVA's evaluation of the impact to the SQN LRA are addressed below. 1. Reactor Vessel Surveillance Capsule Withdrawal Schedule In Reference 2, TVA provided the NRC with a revised Reactor Vessel Surveillance Capsule Withdrawal Schedule for review and approval.
As discussed in Reference 2, relocation of SQN Unit 1 Capsule S to a location of higher fluence was required to ensure that a Unit 1 capsule withdrawal schedule consistent with the expectations of American Society for Testing and Materials (ASTM) E-185-82 and compliance with 10 CFR 50, Appendix H could be attained.
The Unit 1 withdrawal schedule required Capsule S to be removed during U1 EOC R28 outage. The capsule withdrawal schedule revision was approved by the NRC in Reference
- 3. SQN relocated the Unit 1 Capsule S to the 40-degree higher fluence location during the EOC R19 outage. Capsule W was also relocated during EOC R19 outage to a location of higher fluence (220-degree) for future removal to support a potential plant life extension beyond 60 years. The Capsule W withdrawal schedule (Standby) is unchanged from the current Final Safety Analysis Report. Because the Capsule S is no longer available, the revised capsule withdrawal schedule provided to the NRC in Reference 2 and approved by the NRC in Reference 3 cannot be completed.
In Reference 4, TVA submitted a second revised Reactor Vessel Surveillance Capsule Withdrawal Schedule for SQN Unit 1 to the NRC for review. The second revised schedule complies with the expectations of 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-15-098 Revision 1 Page 3 July 10, 2015 2. LRA Commitment Changes In letter dated January 7, 2013 (Reference 1), TVA submitted an application to the NRC to renew the operating licenses for SQN Units 1 and 2. The request would extend the licenses for an additional 20 years beyond the current expiration dates. NRC developed its final Safety Evaluation Report (SER) (ML 15021A356) to document findings associated with the safety review of TVA's LRA and supporting documentation for SQN. In Reference 5, NRC determined that TVA's LRA was complete and closed all open items. Appendix A of the NRC SER provides a list of TVA commitments related to SQN's aging management programs.
The list included Commitment No. 28 that addresses SQN's Reactor Vessel Surveillance Program. Commitment No. 28 (Item B) provides a schedule for withdrawal of SQN's capsules to meet the ASTM E-185-82 requirements, including the possibility of operation beyond 60 years. Commitment No. 28 (Item B) 8. Revise Reactor Vessel Surveillance Program procedures to incorporate an NRG-approved schedule for capsule withdrawals to meet ASTM E 185-82 requirements, including the possibility of operation beyond 60 years (refer to TVA Letter to NRG, "Sequoyah Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedule Revision Due to License Renewal Amendment," dated 01110113, ML 13032A251; NRG final safety evaluation report approved on 09127113, ML 13240A320)
As noted above, SQN Unit 1 cannot comply with the specimen withdrawal schedule for Capsule S as defined by the TV A letter to the NRC referenced in this commitment.
As noted previously, TVA has submitted a revised capsule withdrawal schedule (Reference
- 5) that complies with (ASTM) E 185-82, NUREG-1801, Revision 2, "Generic Aging Lessons Learned (GALL) Report," and the requirements of 10 CFR 50, Appendix H. Accordingly, TVA is proposing a revision to Commitment No. 28 to divide Item B into two parts (B.1 and B.2) as follows: (Note that deletions are struck-through and additions are underlined.
Revised Commitment No. 28 (Item 8) 8. 1 Revise Unit 2 Reactor Vessel Surveillance Program procedures to incorporate an NRG-approved schedule for capsule withdrawals to meet ASTM-E185-82 requirements, including the possibility of operation beyond 60 years (refer to the TVA Letter to NRG, "Sequoyah Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedule Revision Due to License Renewal Amendment," dated 01110113, ML 13032A251; NRG final safety evaluation report approved on 09127113, ML 13240A320).
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!\IRC FSER afJfJFOv.ed OR 09127/13, ML 13240A320 Sequoyah Nuclear Plant -Revision to Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedule for License Renewal), dated May 14. 2015. Enclosure 1 provides the revised Commitment No. 28. 3. Potential Impact to MRP-227-A Assumptions The Westinghouse Reactor Vessel Internals group reviewed the results of the SQN Unit 1 Reactor Vessel Internals Foreign Object Search and Retrieval (FOSAR) effort and ASME Section XI VT-3 lnservice Inspections to determine the possibility of internals damage associated with the dislodged RPV surveillance capsule loose parts. Completed structural evaluation and disposition reports as well as the chemistry evaluation and disposition reports were also reviewed.
The results are reported in Enclosure
- 2. References 6 and 7 support the Westinghouse conclusion that the observed Reactor Vessel Internals components were within existing design considerations and qualification of the components.
This conclusion was based on: (1) there was no measurable impact to original design data, (2) there was no risk to structural integrity for any loading condition, (3) there was no impact on corrosion potential as a result of dissolution of materials in the primary water, and (4) there was no risk for increased crack initiation as a result of localized stress, noting specifically the lower support casting and instrumentation guide extension evaluation.
References 6 and 7 are available at the site (TVA offices) for review. To determine if the inspection findings necessitated a change to the MRP-227-A requirements and inspection protocols for the SQN Reactor Vessel Internals (RVI) aging management program (AMP}, the following were considered:
- a. Did aging related degradation contribute to the failure of the specimen capsule? b. Did the surveillance capsule loose parts cause damage to the reactor vessel internals components that would impact their design function or expected life? c. Do the indications cause a change to the SQN Unit 1 RVI AMP MRP-227-A requirements and protocols (e.g., expansion to primary)?
Factored into this review is the following SQN Unit 1 Operating Experience (OE) relative to this event. a. No evidence of increases in fluence on components other than what would be expected as a result of operation.
- b. No evidence of increases in temperature.
- c. No material changes due to chemicals in the primary water. d. No evidence of cracking.
- e. No indication of structural frequency shifts. f. Multiple indications of superficial wear that are not isolated to being caused by this event.
U.S. Nuclear Regulatory Commission CNL-15-098 Revision 1 Page 5 July 10 , 2015 The Westinghouse OE evaluation for the dislodged SQN Unit 1 capsule specimens concluded that without a driver for degradation initiation or propagation, there is no basis to identify or technically justify a cause for concern that this event would cause a noncompliance or need for change in the existing MRP-227-A.
As a result, Westinghouse concluded that the assessment for MRP-227-A applicability , including consideration of the specific requirements of NRC SER Applicant Licensee Action Items (A/LAI) 1 and 2, remain valid as is. There is no impact to the existing SON Reactor Vessel Internals aging management programs that was previously reviewed and approved by the NRC in Reference 5. 4. Potential Aging Management mechanisms involved in the damaged capsules.
The TVA and Westinghouse root cause analyses (RCAs) for the damaged specimens in the SON Unit 1 Reactor Vessel are complete. The direct cause of this event is installation errors and installation procedural inadequacies. Specimen and specimen basket failure due to unanticipated potential aging effects was not identified as a direct or contributing cause. Enclosure 1 provides the proposed revision to TVA's Commitment No.28 (Item B). Enclosure 2 provides an Evaluation of Failed Specimen Capsules on the Reactor Internals Aging Management Program Plan at Sequoyah Unit 1. Please address any questions regarding this submittal to Erin Henderson , SQN Site Licensing Manager , at (423) 843-7170.
I declare under penalty of perjury that the foregoing is true and correct. Executed on this 10th day of July 2015. ice President Nuclear Licensing Enclosures
- cc: 1. Proposed Revisions to Commitment No. 28 and LRA Sections A.1.35 and B.1.35 2 Westinghouse Letter L TR-RIAM-15-40-NP , RO , Evaluation of Failed Specimen Capsules on the Reactor Internals Aging Management Program Plan at Sequoyah Unit 1, (Non-Proprietary)
Regional Administrator, Rll NRC Project Manager, Sequoyah License Renewal Project NRC Senior Resident Inspector , Sequoyah Nuclear Plant ENCLOSURE 1 Tennessee Valley Authority Sequoyah Nuclear Plant Units 1 and 2, Proposed Revisions to Commitment No. 28 and LRA Sections A.1.35 and 8.1.35 Current Commitment No.28 28 A. Revise Reactor Vessel Surveillance Program procedures to consider B.1.35 SQN1: Prior to Letter the area outside the beltline such as nozzles, penetrations and 03/17/2020 ML 13190A276 discontinuities to determine if more restrictive P-T limits are required than SQN2: Prior to (7/1/13) would be determined by just considering the reactor vessel beltline 03/15/2021 materials.
B. Revise Reactor Vessel Surveillance Program procedures to incorporate an NRG-approved schedule for capsule withdrawals to meet ASTM-E185-82 requirements, including the possibility of operation beyond 60 years (refer tot he TVA Letter to NRC, "Sequoyah Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedule Revision Due to License Renewal Amendment," dated 01/10/13, ML13032A251; NRC final safety evaluation report approved on 09/27/13, ML 13240A320).
C. Revise Reactor Vessel Surveillance Program procedures to withdraw and test a standby capsule to cover the peak fluence expected at the end of the period of extended operation.
Revised Commitment No. 28 28 A. Revise Reactor Vessel Surveillance Program procedures to consider B.1.35 SQN1: Prior to Letter the area outside the beltline such as nozzles, penetrations and 03/17/2020 ML13190A276 discontinuities to determine if more restrictive P-T limits are required SQN2: Prior to (7/1/13) than would be determined by just considering the reactor vessel beltline 03/15/2021 materials.
fil Revise Unit 2 Reactor Vessel Surveillance Program procedures to incorporate an NRG-approved schedule for capsule withdrawals to meet ASTM-E185-82 requirements, including the possibility of operation beyond 60 years (refer to the TVA Letter to NRC, "Sequoyah Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedule Revision Due to License Renewal Amendment," dated 01/10/13, ML 13032A251; NRC final safety evaluation report approved on 09/27/13, ML 13240A320).
8.2 Revise
Unit 1 Reactor Vessel Surveillance Program 12rocedures to incor12orate an NRC-a1212roved schedule for ca12sule withdrawals to meet ASTM-E185-82 reguirements, including the 12ossibility of 012eration beyond 60 years (refer to the TVA Letter to NRC, Seguoyah Nuclear Plant, Revision to Reactor Pressure Vessel Surveillance Ca12sule Withdrawal Schedule for License Renewal dated May 14, 2015). c. Revise Reactor Vessel Surveillance Program procedures to withdraw and test a standby capsule to cover the peak fluence expected at the end of the period of extended operation.
Changes to LRA Section A.1.35, Reactor Vessel Surveillance Program, follow with additions underlined and deletions line through. The Reactor Vessel Surveillance Program will be enhanced as follows. Revise Reactor Vessel Surveillance Program procedures to consider the area outside the beltline such as nozzles, penetrations and discontinuities to determine if more restrictive temperature limits are required than would be determined by just considering the reactor vessel beltline materials.
Revise Unit 2 Reactor Vessel Surveillance Program procedures to incorporate an NRG-approved schedule for capsule withdrawals to meet ASTM E 185-82 requirements, including the possibility of operation beyond 60 years (refer to the TVA Letter to NRC, Sequoyah Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedule Revision Due to License Renewal Amendment," dated January 10, 2013 (ML13032A251)).
Revise Unit 1 Reactor Vessel Surveillance Program procedures to incorporate an NRG-approved schedule for capsule withdrawals to meet ASTM E 185-82 requirements.
including the possibility of operation beyond 60 years (refer to the TV A Letter to NRC. Sequoyah Nuclear Plant. Revision to Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedule for License Renewal dated May 14. 2015). Changes to LRA Section 8.1.35, Reactor Vessel Surveillance Program, follow with additions underlined and deletions line through. The following enhancements will be implemented prior to the period of extended operation.
Element Affected Enhancement
- 4. Detection of Aging Effects Revise Unit 2 Reactor Vessel Surveillance Program procedures to incorporate an NRG-approved schedule for capsule withdrawals to meet ASTM-E185-82 requirements, including the possibility of operation beyond 60 years (refer to the TV A Letter to NRC, Sequoyah Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedule Revision Due to License Renewal Amendment, dated January 10, 2013(ML13032A251)).
Revise Unit 1 Reactor Vessel Surveillance Program procedures to incorporate an NRG-approved schedule for capsule withdrawals to meet ASTM E 185-82 requirements, including the possibility of operation beyond 60 years {refer to the TVA Letter to NRC, Sequoyah Nuclear Plant, Revision to Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedule for License Renewal dated May 14, 2015}.
ENCLOSURE 2 Tennessee Valley Authority Sequoyah Nuclear Plant, Unit 1 Westinghouse Letter L TR-RIAM-15-40-NP, RO, Evaluation of Failed Specimen Capsules on the Reactor Internals Aging Management Program Plan at Sequoyah Unit 1 (Non-Proprietary)
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