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| {{#Wiki_filter:Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 | | {{#Wiki_filter:Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-18-109 August 24, 2018 10 CFR 50.4 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Sequoyah Nuclear Plant, Units 1 and 2 Renewed Facility Operating License Nos. DPR-77 and DPR-79 NRC Docket Nos. 50-327 and 50-328 |
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| CNL-18-109 August 24, 2018 | |
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| 10 CFR 50.4 | |
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| ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 | |
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| Sequoyah Nuclear Plant, Units 1 and 2 Renewed Facility Operating License Nos. DPR-77 and DPR-79 NRC Docket Nos. 50-327 and 50-328 | |
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| ==Subject:== | | ==Subject:== |
| Sequoyah Nuclear Plant, Units 1 and 2 - Fourth Periodic Schedule Update for Revision of Loss-of-Coolant Accident Mass and Energy Release Calculations Related to Containment Integrity Response Analyses | | Sequoyah Nuclear Plant, Units 1 and 2 - Fourth Periodic Schedule Update for Revision of Loss-of-Coolant Accident Mass and Energy Release Calculations Related to Containment Integrity Response Analyses |
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| ==References:== | | ==References:== |
| : 1. TVA letter to NRC, "Sequoyah Nuclear Plant, Units 1 and 2 - Application to Modify Ice Condenser Technical Specifications to Address Revisions in Westinghouse Mass and Energy Release Calculation (SQN-TS-12-04)," | | : 1. TVA letter to NRC, Sequoyah Nuclear Plant, Units 1 and 2 - Application to Modify Ice Condenser Technical Specifications to Address Revisions in Westinghouse Mass and Energy Release Calculation (SQN-TS-12-04), |
| dated July 3, 2013 (ML13199A281) | | dated July 3, 2013 (ML13199A281) |
| : 2. TVA letter to NRC, CNL-16-049, "Sequoyah Nuclear Plant, Units 1 and 2 - Withdrawal of Application to Modify Ice Condenser Technical Specifications to Address Revisions in Westinghouse Mass and Energy Release Calculation (SQN-TS-12-04)," dated September 19, 2016 (ML16264A456) | | : 2. TVA letter to NRC, CNL-16-049, Sequoyah Nuclear Plant, Units 1 and 2 - |
| | Withdrawal of Application to Modify Ice Condenser Technical Specifications to Address Revisions in Westinghouse Mass and Energy Release Calculation (SQN-TS-12-04), dated September 19, 2016 (ML16264A456) 3 TVA letter to NRC, CNL-17-041, Sequoyah Nuclear Plant, Units 1 and 2 - |
| | Periodic Schedule Update for Revision of Loss-of-Coolant Accident Mass and Energy Release Calculations Related to Containment Integrity Response Analyses, dated March 10, 2017 (ML17069A391) |
| | : 4. TVA letter to NRC, CNL-17-103, Sequoyah Nuclear Plant, Units 1 and 2 - |
| | Second Periodic Schedule Update for Revision of Loss-of-Coolant Accident Mass and Energy Release Calculations Related to Containment Integrity Response Analyses, dated August 24, 2017 (ML17257A330) |
| | : 5. TVA letter to NRC, CNL-18-031, Sequoyah Nuclear Plant, Units 1 and 2 - |
| | Third Periodic Schedule Update for Revision of Loss-of-Coolant Accident Mass and Energy Release Calculations Related to Containment Integrity Response Analyses, dated February 28, 2018 (ML1860A334) |
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| | U.S. Nuclear Regulatory Commission CNL-18-109 Page 2 August 24, 2018 In Reference 1, Tennessee Valley Authority (TVA) submitted license amendment request (LAR) SQN-TS-12-04 for Sequoyah Nuclear Plant (SQN), Units 1 and 2. The proposed changes were to revise SQN Units 1 and 2 Technical Specifications (TSs) 3/4.6.5, "Ice Condenser" (currently TS 3.6.12, "Ice Bed"), to increase the total ice weight from 2,225,880 pounds to 2,540,808 pounds to address a non-conservatism with respect to the required total ice weight. |
| | In Reference 2, TVA withdrew LAR SQN-TS-12-04 and stated that a new LAR would be submitted, if necessary, using the revised SQN containment integrity response analyses. |
| | Reference 2 also committed to provide periodic schedule updates to the Nuclear Regulatory Commission (NRC) for revising the LOCA mass and energy release calculations and the associated SQN containment integrity response analyses every six months until the non-conservative TS condition is resolved. |
| | In References 3, 4, and 5, TVA provided the first, second, and third six-month updates, respectively. The enclosure to this letter provides the fourth and final six-month update. |
| | Based on the results of the updated containment analysis, TVA has determined that the current SQN TS 3.6.12 Surveillance Requirements are conservative and adequate to ensure the operability of the SON ice bed . As such, the TS changes proposed in Reference 1 are not required . The updated containment analysis will be adopted as the SON analysis of record as a result of revising the Updated Final Safety Analysis Report (UFSAR) and associated TS Bases in accordance with TVA procedures for control of the UFSAR and TS Bases. |
| | This letter serves as notification of the completion of the commitment in Reference 2. There are no new regulatory commitments contained in this submittal. Please address any questions regarding this submittal to Edward Schrull at (423) 751-3850. |
| | Respectfully, |
| | ~810-- |
| | E. K. Henderson Director, Nuclear Regulatory Affairs |
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| 3 TVA letter to NRC, CNL-17-041, "Sequoyah Nuclear Plant, Units 1 and 2 -
| | ==Enclosure:== |
| Periodic Schedule Update for Revision of Loss-of-Coolant Accident Mass and Energy Release Calculations Related to Containment Integrity Response Analyses," dated March 10, 2017 (ML17069A391) | | Periodic Schedule Update for Revision of Loss-of-Coolant Accident Mass and Energy Release Calculations Related to Containment Integrity Response Analyses cc: (w/Enclosure) |
| : 4. TVA letter to NRC, CNL-17-103, "Sequoyah Nuclear Plant, Units 1 and 2 - Second Periodic Schedule Update for Revision of Loss-of-Coolant Accident Mass and Energy Release Calculations Related to Containment Integrity Response Analyses," dated August 24, 2017 (ML17257A330)
| | NRC Regional Administrator - Region II NRC Senior Resident Inspector - Sequoyah Nuclear Plant NRC Project Manager - Sequoyah Nuclear Plant |
| : 5. TVA letter to NRC, CNL-18-031, "Sequoyah Nuclear Plant, Units 1 and 2 - Third Periodic Schedule Update for Revision of Loss-of-Coolant Accident Mass and Energy Release Calculations Related to Containment Integrity Response Analyses," dated February 28, 2018 (ML1860A334)
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| CNL-18-109 Page E1 of 1 Enclosure Periodic Schedule Update for Revision of Loss-of-Coolant Accident Mass and Energy Release Calculations Related to Containment Integrity Response Analyses The table below includes the milestones for the revised loss-of-coolant accident (LOCA) mass and energy release calculations and associated containment integrity response analyses utilizing the new Westinghouse WCOBRA/TRAC model. All milestones have been completed.
| | Enclosure Periodic Schedule Update for Revision of Loss-of-Coolant Accident Mass and Energy Release Calculations Related to Containment Integrity Response Analyses The table below includes the milestones for the revised loss-of-coolant accident (LOCA) mass and energy release calculations and associated containment integrity response analyses utilizing the new Westinghouse WCOBRA/TRAC model. All milestones have been completed. |
| Phase 1 Target Milestones Schedule Date 1 Project Customer Kickoff June 2016 (Complete) 2 Input Request Letter to TVA August 2016 (Complete) 3 TVA issuance of analytical input summary (AIS) September 2016 (Complete) 4 Completion of WCOBRA/TRAC Model July 2017 (Complete) 5 Issuance of preliminary containment response results November 2017 (Complete) 6 TVA issuance of Phase 2 guidance on margin allocation February 2018 (Complete) | | Phase 1 Target Milestones Schedule Date 1 Project Customer Kickoff June 2016 (Complete) 2 Input Request Letter to TVA August 2016 (Complete) 3 TVA issuance of analytical input summary (AIS) September 2016 (Complete) 4 Completion of WCOBRA/TRAC Model July 2017 (Complete) 5 Issuance of preliminary containment response results November 2017 (Complete) 6 TVA issuance of Phase 2 guidance on margin allocation February 2018 (Complete) |
| Phase 2 Target Milestones Schedule Date 7 Issuance of draft LOCA M&E and Containment Integrity analysis report March 2018 (Complete) 8 TVA reviews the draft Containment Integrity analysis report and provides owners review comments April 2018 (Complete) 9 Issuance of final Containment analysis report plus FSAR, Accident Analysis Parameter Checklist, Technical Specification markups (if necessary) 1 June 2018 (Complete) 2 1. As noted in the cover letter, TVA determined that no changes to the SQN Technical Specifications are required. 2. The original completion date for this milestone was May 2018. Due to resolution of TVA comments, the final report was not issued until June 15, 2018.}} | | Phase 2 Target Milestones Schedule Date 7 Issuance of draft LOCA M&E and Containment Integrity March 2018 (Complete) analysis report 8 TVA reviews the draft Containment Integrity analysis April 2018 (Complete) report and provides owners review comments 9 Issuance of final Containment analysis report plus FSAR, June 2018 (Complete)2 Accident Analysis Parameter Checklist, Technical Specification markups (if necessary)1 |
| | : 1. As noted in the cover letter, TVA determined that no changes to the SQN Technical Specifications are required. |
| | : 2. The original completion date for this milestone was May 2018. Due to resolution of TVA comments, the final report was not issued until June 15, 2018. |
| | CNL-18-109 Page E1 of 1}} |
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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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Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-18-109 August 24, 2018 10 CFR 50.4 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Sequoyah Nuclear Plant, Units 1 and 2 Renewed Facility Operating License Nos. DPR-77 and DPR-79 NRC Docket Nos. 50-327 and 50-328
Subject:
Sequoyah Nuclear Plant, Units 1 and 2 - Fourth Periodic Schedule Update for Revision of Loss-of-Coolant Accident Mass and Energy Release Calculations Related to Containment Integrity Response Analyses
References:
- 1. TVA letter to NRC, Sequoyah Nuclear Plant, Units 1 and 2 - Application to Modify Ice Condenser Technical Specifications to Address Revisions in Westinghouse Mass and Energy Release Calculation (SQN-TS-12-04),
dated July 3, 2013 (ML13199A281)
- 2. TVA letter to NRC, CNL-16-049, Sequoyah Nuclear Plant, Units 1 and 2 -
Withdrawal of Application to Modify Ice Condenser Technical Specifications to Address Revisions in Westinghouse Mass and Energy Release Calculation (SQN-TS-12-04), dated September 19, 2016 (ML16264A456) 3 TVA letter to NRC, CNL-17-041, Sequoyah Nuclear Plant, Units 1 and 2 -
Periodic Schedule Update for Revision of Loss-of-Coolant Accident Mass and Energy Release Calculations Related to Containment Integrity Response Analyses, dated March 10, 2017 (ML17069A391)
- 4. TVA letter to NRC, CNL-17-103, Sequoyah Nuclear Plant, Units 1 and 2 -
Second Periodic Schedule Update for Revision of Loss-of-Coolant Accident Mass and Energy Release Calculations Related to Containment Integrity Response Analyses, dated August 24, 2017 (ML17257A330)
- 5. TVA letter to NRC, CNL-18-031, Sequoyah Nuclear Plant, Units 1 and 2 -
Third Periodic Schedule Update for Revision of Loss-of-Coolant Accident Mass and Energy Release Calculations Related to Containment Integrity Response Analyses, dated February 28, 2018 (ML1860A334)
U.S. Nuclear Regulatory Commission CNL-18-109 Page 2 August 24, 2018 In Reference 1, Tennessee Valley Authority (TVA) submitted license amendment request (LAR) SQN-TS-12-04 for Sequoyah Nuclear Plant (SQN), Units 1 and 2. The proposed changes were to revise SQN Units 1 and 2 Technical Specifications (TSs) 3/4.6.5, "Ice Condenser" (currently TS 3.6.12, "Ice Bed"), to increase the total ice weight from 2,225,880 pounds to 2,540,808 pounds to address a non-conservatism with respect to the required total ice weight.
In Reference 2, TVA withdrew LAR SQN-TS-12-04 and stated that a new LAR would be submitted, if necessary, using the revised SQN containment integrity response analyses.
Reference 2 also committed to provide periodic schedule updates to the Nuclear Regulatory Commission (NRC) for revising the LOCA mass and energy release calculations and the associated SQN containment integrity response analyses every six months until the non-conservative TS condition is resolved.
In References 3, 4, and 5, TVA provided the first, second, and third six-month updates, respectively. The enclosure to this letter provides the fourth and final six-month update.
Based on the results of the updated containment analysis, TVA has determined that the current SQN TS 3.6.12 Surveillance Requirements are conservative and adequate to ensure the operability of the SON ice bed . As such, the TS changes proposed in Reference 1 are not required . The updated containment analysis will be adopted as the SON analysis of record as a result of revising the Updated Final Safety Analysis Report (UFSAR) and associated TS Bases in accordance with TVA procedures for control of the UFSAR and TS Bases.
This letter serves as notification of the completion of the commitment in Reference 2. There are no new regulatory commitments contained in this submittal. Please address any questions regarding this submittal to Edward Schrull at (423) 751-3850.
Respectfully,
~810--
E. K. Henderson Director, Nuclear Regulatory Affairs
Enclosure:
Periodic Schedule Update for Revision of Loss-of-Coolant Accident Mass and Energy Release Calculations Related to Containment Integrity Response Analyses cc: (w/Enclosure)
NRC Regional Administrator - Region II NRC Senior Resident Inspector - Sequoyah Nuclear Plant NRC Project Manager - Sequoyah Nuclear Plant
Enclosure Periodic Schedule Update for Revision of Loss-of-Coolant Accident Mass and Energy Release Calculations Related to Containment Integrity Response Analyses The table below includes the milestones for the revised loss-of-coolant accident (LOCA) mass and energy release calculations and associated containment integrity response analyses utilizing the new Westinghouse WCOBRA/TRAC model. All milestones have been completed.
Phase 1 Target Milestones Schedule Date 1 Project Customer Kickoff June 2016 (Complete) 2 Input Request Letter to TVA August 2016 (Complete) 3 TVA issuance of analytical input summary (AIS) September 2016 (Complete) 4 Completion of WCOBRA/TRAC Model July 2017 (Complete) 5 Issuance of preliminary containment response results November 2017 (Complete) 6 TVA issuance of Phase 2 guidance on margin allocation February 2018 (Complete)
Phase 2 Target Milestones Schedule Date 7 Issuance of draft LOCA M&E and Containment Integrity March 2018 (Complete) analysis report 8 TVA reviews the draft Containment Integrity analysis April 2018 (Complete) report and provides owners review comments 9 Issuance of final Containment analysis report plus FSAR, June 2018 (Complete)2 Accident Analysis Parameter Checklist, Technical Specification markups (if necessary)1
- 1. As noted in the cover letter, TVA determined that no changes to the SQN Technical Specifications are required.
- 2. The original completion date for this milestone was May 2018. Due to resolution of TVA comments, the final report was not issued until June 15, 2018.
CNL-18-109 Page E1 of 1