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MONTHYEARML1207501092012-03-15015 March 2012 Notice of Meeting with Tennessee Valley Authority to Discuss Pre-submittal Planning for Licensing Basis Change Regarding Hydrology for Watts Bar Nuclear Plant, Unit 1 Project stage: Request ML12097A3122012-03-29029 March 2012 3/29/2012 Meeting Slides - Pre-Submittal Meeting Regarding Watts Bar Unit 1 Hydrology Licensing Basis Change Project stage: Meeting ML12097A3062012-04-11011 April 2012 3/29/2012 Summary of Pre-Application Meeting with Tennessee Valley Authority on Changing the Licensing Basis for Hydrologic Engineering Project stage: Meeting ML12236A1672012-07-19019 July 2012 Application to Revise Watts Bar Nuclear Plant, Unit 1 Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis, TAC No. ME8200 (WBN-UFSAR-12-01) Project stage: Request ML12226A5612012-08-10010 August 2012 Application to Revise Sequoyah Nuclear Plant Units I and 2 Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis, (SQN-TS-12-02) Project stage: Request ML12226A5622012-08-10010 August 2012 Enclosure 1, Evaluation of Proposed Changes Attachment 1 Proposed SQN Units 1 and 2 UFSAR Text Changes (Markups), Page 2.4-1 Through 2.4-41 Project stage: Request ML12226A5632012-08-10010 August 2012 Enclosure 1, Evaluation of Proposed Changes Attachment 1 Proposed SQN Units 1 and 2 UFSAR Text Changes (Markups), Page 2.4-42 Through Enclosure 2 Project stage: Request ML12276A3752012-10-0101 October 2012 Notification of Completion of Review of Updated Hydrologic Analysis Results for Impact on Watts Bar Nuclear Plant (WBN) Units 1 and 2 Final Environmental Statements Project stage: Other ML12292A3962012-10-19019 October 2012 Forthcoming Meeting with Tennessee Valley Authority Regarding Hydrology Issues Project stage: Request ML12319A1722012-11-14014 November 2012 Meeting Notice with Tennessee Valley Authority to Discuss Hydrology Issues at Watts Bar Nuclear Plant, Unit 1 Project stage: Request ML12348A2082012-12-13013 December 2012 Meeting Slides Re TVA Hydrology Update Slides Project stage: Request ML13010A1372013-01-11011 January 2013 Summary of Meeting with TVA Regarding Hydrology Updates Project stage: Request ML13037A3262013-01-31031 January 2013 Submittal Date for Supplement to Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis (WBN-UFSAR-12-01) Project stage: Supplement CNL-14-026, Transmittal of Supplemental Clarification Information for the Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis, TAC No. ME8200 (WBN-UFSAR-12-01)2014-02-28028 February 2014 Transmittal of Supplemental Clarification Information for the Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis, TAC No. ME8200 (WBN-UFSAR-12-01) Project stage: Supplement 2012-03-29
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Category:Final Safety Analysis Report (FSAR)
MONTHYEARWBL-23-053, Updated Final Safety Analysis Report (UFSAR) Amendment 5, Redacted Version2023-11-0808 November 2023 Updated Final Safety Analysis Report (UFSAR) Amendment 5, Redacted Version ML23312A1462023-11-0808 November 2023 Updated Final Safety Analysis Report (UFSAR) Amendment 5 - Table of Contents ML20323A3182020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Table of Contents WBL-20-047, Amendment 3 to Updated Final Safety Analysis Report, Chapter 8, Electric Power (Redacted)2020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 8, Electric Power (Redacted) ML20323A3082020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 14, Initial Test Program ML20323A3142020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 3, Design of Structures, Components, Equipment, and Systems, Table of Contents to Sec 3.7 ML20323A3192020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 17, Quality Assurance ML20323A3172020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Division of Responsibility (Dor), Abbreviations ML20323A3112020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 4, Reactor ML20323A3222020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 13, Conduct of Operations ML21123A2262020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 3, Design of Structures, Components, Equipment, and Systems, Sections 3.8 to 3.12 (Redacted) ML20323A3152020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 11, Radioactive Waste Management ML20323A3032020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 9, Auxiliary System ML20323A3052020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 10, Main Steam and Power Conversion Systems ML20323A3002020-10-29029 October 2020 Submittal of Amendment 3 to Updated Final Safety Analysis Report ML20323A3202020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System ML21123A2252020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 2, Site Characteristics, Table of Contents to Sec 2.4 (Redacted) ML20323A3012020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Controls ML20323A3092020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 12, Radiation Protection ML20323A3162020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 15, Accident Analyses ML20323A3102020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 2, Sec 2.5, Geology, Seismology, and Geotechnical Engineering Summary of Foundation Conditions ML20323A3062020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant ML20323A3122020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 16, Technical Specifications ML20142A3892020-05-21021 May 2020 Wbnp PSAR, Chapter 12, Conduct of Operations L-19-022, Amendment 2 to Updated Final Safety Analysis Report, Chapter 8, Electric Power - Redacted2019-03-18018 March 2019 Amendment 2 to Updated Final Safety Analysis Report, Chapter 8, Electric Power - Redacted ML19060A1472019-02-19019 February 2019 Amendment 1 to USAR Chapter 2 Auxiliary System NRC Additional Redactions 2 of 5 ML19060A1762019-02-18018 February 2019 Amendment 1 to USAR Chapter 2 Auxiliary System NRC Additional Redactions 3 of 5 ML19060A1822019-02-18018 February 2019 Amendment 1 to USAR Chapter 2 Auxiliary System NRC Additional Redactions 5 of 5 ML19039A1042019-02-0808 February 2019 Amendment 1 to USAR Chapter 2 Auxiliary System NRC Additional Redactions 1 of 5 ML19060A1492019-02-0808 February 2019 Amendment 1 to USAR Chapter 2 Auxiliary System NRC Additional Redactions 4 of 5 ML17334A1602017-11-0202 November 2017 Amendment 1 to Updated Safety Analysis Report, Chapter 13, Conduct of Operations ML17334A1732017-11-0202 November 2017 Amendment 1 to Updated Safety Analysis Report, Chapter 8, Electric Power (Redacted) ML17334A1622017-11-0202 November 2017 Amendment 1 to Updated Safety Analysis Report, Chapter 14, Initial Test Program ML17334A1692017-11-0202 November 2017 Amendment 1 to Updated Safety Analysis Report, Chapter 4, Reactor ML17334A1562017-11-0202 November 2017 Amendment 1 to Updated Safety Analysis Report, Chapter 1, Introduction and General Description of Plant (Redacted) ML17334A1722017-11-0202 November 2017 Amendment 1 to Updated Safety Analysis Report, Chapter 7, Instrumentation and Controls ML17334A1582017-11-0202 November 2017 Amendment 1 to Updated Safety Analysis Report, Chapter 11, Radioactive Waste Management ML17334A1592017-11-0202 November 2017 Amendment 1 to Updated Safety Analysis Report, Chapter 12, Radiation Protection (Redacted) ML17334A1652017-11-0202 November 2017 Amendment 1 to Updated Safety Analysis Report, Chapter 17, Quality Assurance ML17334A1702017-11-0202 November 2017 Amendment 1 to Updated Safety Analysis Report, Chapter 5, Reactor Coolant System ML17334A1632017-11-0202 November 2017 Amendment 1 to Updated Safety Analysis Report, Chapter 15, Accident Analyses ML17334A1572017-11-0202 November 2017 Amendment 1 to Updated Safety Analysis Report, Chapter 10, Main Steam and Power Conversion Systems ML17334A1642017-11-0202 November 2017 Amendment 1 to Updated Safety Analysis Report, Chapter 16, Technical Specifications ML15279A3042015-09-11011 September 2015 Amendment 114 to Final Safety Analysis Report, Section 2.0 - Site Characteristics, Figure 2.5-554. Sheet 1 of 2 ML15279A3072015-09-11011 September 2015 Amendment 114 to Final Safety Analysis Report, Section 2.0 - Site Characteristics, Figure 2.5-556 ML15279A3182015-09-11011 September 2015 Amendment 114 to Final Safety Analysis Report, Section 2.0 - Site Characteristics, Figure 2.5-579 ML15279A3192015-09-11011 September 2015 Amendment 114 to Final Safety Analysis Report, Section 2.0 - Site Characteristics, Figure 2.5-583 ML15279A3082015-09-11011 September 2015 Amendment 114 to Final Safety Analysis Report, Section 2.0 - Site Characteristics, Figure 2.5-571. Sheet 1 of 4 ML15279A3052015-09-11011 September 2015 Amendment 114 to Final Safety Analysis Report, Section 2.0 - Site Characteristics, Figure 2.5-554. Sheet 2 of 2 ML15279A3252015-09-11011 September 2015 Amendment 114 to Final Safety Analysis Report, Section 2.0 - Site Characteristics, Figure 2.5-597 2023-11-08
[Table view] Category:Letter type:CNL
MONTHYEARCNL-24-047, Decommitment of Flood Mode Mitigation Improvement Systems2024-09-24024 September 2024 Decommitment of Flood Mode Mitigation Improvement Systems CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024 Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024 Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-24-061, Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08),2024-08-19019 August 2024 Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08), CNL-24-052, Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-06-27027 June 2024 Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) CNL-24-018, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS2024-06-25025 June 2024 License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS CNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-24-037, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 422024-04-22022 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 42 CNL-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-24-024, Hydrologic Engineering Center River Analysis System Project Milestone Status Update2024-04-17017 April 2024 Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-24-010, License Amendment Request to Recapture Low-Power Testing Time (WBN-TS-23-19)2024-04-17017 April 2024 License Amendment Request to Recapture Low-Power Testing Time (WBN-TS-23-19) CNL-24-004, Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13)2024-04-0404 April 2024 Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13) CNL-24-020, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements2024-04-0101 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements CNL-24-008, Guarantee of Payment of Deferred Premiums - 2023 Annual Report2024-03-27027 March 2024 Guarantee of Payment of Deferred Premiums - 2023 Annual Report CNL-24-007, Annual Insurance Status Report2024-03-27027 March 2024 Annual Insurance Status Report CNL-24-025, Notice of Intent to Pursue License Renewal for Watts Bar Nuclear Plant, Unit 1 - Submittal Schedule2024-03-25025 March 2024 Notice of Intent to Pursue License Renewal for Watts Bar Nuclear Plant, Unit 1 - Submittal Schedule CNL-24-031, Supplement to Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance2024-03-18018 March 2024 Supplement to Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance CNL-24-029, Response to Request for Additional Information Regarding Tennessee Valley Authority - Request for Exemption from Specific Requirements of 10 CFR Part 372024-03-14014 March 2024 Response to Request for Additional Information Regarding Tennessee Valley Authority - Request for Exemption from Specific Requirements of 10 CFR Part 37 CNL-24-028, Response to Request for Additional Information Regarding Watts Bar Nuclear Plant, Units 1 and 2, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2024-03-14014 March 2024 Response to Request for Additional Information Regarding Watts Bar Nuclear Plant, Units 1 and 2, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation CNL-24-012, Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance2024-02-28028 February 2024 Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance CNL-24-023, Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-17, Revision 252024-02-20020 February 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-17, Revision 25 CNL-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-24-016, Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-01-10010 January 2024 Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) CNL-23-052, Application to Adopt TSTF-427-A, Revision 2, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability2024-01-0909 January 2024 Application to Adopt TSTF-427-A, Revision 2, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability CNL-23-062, Application to Revise the Technical Specifications Section 3.8.2, AC Sources-Shutdown, to Remove Reference to the C-S Diesel Generator (WBN-TS-23-018)2024-01-0808 January 2024 Application to Revise the Technical Specifications Section 3.8.2, AC Sources-Shutdown, to Remove Reference to the C-S Diesel Generator (WBN-TS-23-018) CNL-23-005, Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis (WBN-19-011)2023-12-26026 December 2023 Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis (WBN-19-011) CNL-23-069, 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-23-001, Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01)2023-12-13013 December 2023 Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01) 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-23-059, 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-23-061, 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-23-057, 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-23-045, License Amendment Request to Revise Technical Specification Table 1.1-1 Regarding the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts (WBN-TS-23-010)2023-08-0707 August 2023 License Amendment Request to Revise Technical Specification Table 1.1-1 Regarding the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts (WBN-TS-23-010) 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-23-020, Application to Revise Technical Specifications to Adopt TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control (WBN-TS-22-06)2023-06-28028 June 2023 Application to Revise Technical Specifications to Adopt TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control (WBN-TS-22-06) 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-23-044, Transmittal of Revision 3 to WCAP-18774-P and WCAP-18774-NP, Addendum to the Rotterdam Dockyard Company Final Stress Report for 173 P.W.R. Vessels TVA III & IV (Report No. 30749-B-030, Rev. 3) - Evaluation of One Closure Stud Out2023-06-0101 June 2023 Transmittal of Revision 3 to WCAP-18774-P and WCAP-18774-NP, Addendum to the Rotterdam Dockyard Company Final Stress Report for 173 P.W.R. Vessels TVA III & IV (Report No. 30749-B-030, Rev. 3) - Evaluation of One Closure Stud Out 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-23-043, Emergency License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1.1-1, Modes (WBN-TS-23-09)2023-05-0404 May 2023 Emergency License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1.1-1, Modes (WBN-TS-23-09) 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-23-032, 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-23-033, 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-23-023, 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 2024-09-24
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L44 140228 002 Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-14-026 February 28, 2014 10 CFR 50.4 10 CFR 50.90 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Unit 1 Facility Operating License No. NPF-90 NRC Docket No. 50-390
Subject:
Transmittal of Supplemental Clarification Information for the Application to Revise Watts Bar Nuclear Plant Unit 1, Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis, TAC No. ME8200 (WBN-UFSAR-12-01)
Reference:
Application to Revise Watts Bar Nuclear Plant Unit 1 Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis, TAC No. ME8200 (WBN-UFSAR-12-01), dated July 19, 2012 (ADAMS Accession No. ML122360173)
By letter dated July 19, 2012 (Reference), Tennessee Valley Authority (TVA) submitted a license amendment request (LAR) to adopt a revised hydrologic analysis for the Watts Bar Nuclear Plant (WBN), Unit 1, Updated Final Safety Analysis Report (UFSAR). The LAR included proposed UFSAR markups to the wind wave runup information associated with the WBN Intake Pumping Station (IPS). This letter transmits updated information based on a functionality evaluation performed as part of the WBN corrective action program. The functionality evaluation conservatively assumed two credible potential pathways that could transfer exterior flood waters to the interior of the IPS versus the one pathway contained in the UFSAR LAR. One potential pathway is through an opening on the western face of the IPS.
The second potential (new) pathway is by the hydraulic head generated from wind-wave runup on the southern face of the IPS.
The enclosure to this letter provides a markup of the proposed revision to UFSAR Section 2.4.3.6, Coincident Wind Wave Activity that was provided in the referenced letter.
The attached supplemental information clarifies the credible potential pathway(s) as represented in the UFSAR. There is no change to the conservative assumption of 741.7 ft for Tennessee River maximum water surface elevation including the effects of coincident wind wave setup and runup.
U.S. Nuclear Regulatory Commission Page 2 February 28, 2014 Consistent with the standards set forth in 10 CFR 50.92(c), TVA has determined that the additional information as provided in this letter does not affect the no significant hazards considerations associated with the proposed amendment previously provided in the Reference letter. TVA has further determined that the proposed amendment still qualifies for a categorical exclusion from environmental review pursuant to the provisions of 10 CFR 51 .22(c)(9). Additionally, in accordance with 10 CFR 50.91(b)(1) , TVA is sending a copy of this letter and enclosure to the Tennessee Department of Environment and Conservation.
There are no regulatory commitments contained in this letter. Please address any questions regarding this matter to Edward D. Schrull at (423) 751-3850 .
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 27 day of February 2014.
ully,
~
. Shea V ce President, Nuclear Licensing
Enclosure:
Updated UFSAR Markups cc (Enclosure):
NRC Regional Administrator - Region II NRC Senior Resident Inspector - Watts Bar Nuclear Plant, Unit 1 Director, Division of Radiological Health - Tennessee State Department of Environment and Conservation
ENCLOSURE Watts Bar Nuclear Plant, Unit 1 Updated UFSAR Markups Please revise/replace UFSAR pages 2.4-29, 2.4-30, and 2.4-31 provided in Attachment 1 of the Reference indicated in this cover letter with the enclosed pages.
The changes to UFSAR Section 2.4.3.6 submitted in the Reference letter are:
- 1. Page 2.4-29
- Removes critical from the third (LAR proposed new text) paragraph in the section.
- 2. Page 2.4-30
- Removes critical from the last paragraph (LAR proposed new text) on the page.
- 3. Page 2.4-31
- Removes critical from the first paragraph (LAR proposed new text) on the page
- Revises the second paragraph (LAR proposed new text) to add the text, and the runup on the critical south face wall is 2.4 ft and reaches elevation 741.7 ft, The additional text clarifies that an assumed second internal flooding pathway exists through the south face wall of the IPS.
WBNP-The third candidate situation considered, failure of Douglas Dam during its PMF was shown in the original analysis to produce a flood crest at the plant site approximately 4.4 feet below the controlling PMF event. Dam safety modifications to Douglas Dam involved raising the height of the dam to prevent overtopping in the PMF and this eliminates failure of Douglas as a candidate situation.
The elevations from the potential controlling PMF events are compared in Table 2.4-7.
2.4.3.6 Coincident Wind Wave Activity Some wind waves are likely when the probable maximum flood crests at Watts Bar Nuclear Plant. The flood would be near its crest for a day beginning about 2 days after cessation of the probable maximum storm (Figure 2.4-572.4-25). The day of occurrence would be in the month of March or possibly the first week in April.
Figure 2.4-982.4-27 shows the main plant general grading plan. The Diesel Generator Buildings to the north and the pumping station to the eastsoutheast of the main building complex must be protected from flooding to assure plant safety. The Diesel Generator Buildings operating floors are at Elevationelevation 742.0 ft which are well above the maximum computed elevation including wind wave runup. The pumping station is shielded from direct wave action on all sides except to the south by either buildings, earth embankments, or the cooling towers. The maximum effective fetch of 1.3 miles occurs from both the southwest and northeast directions (Figure 2.4-67). This allows for the sheltering effect of several hills on the south riverbank which become islands at maximum flood levels.The electrical equipment room of the Intake Pumping Station will flood at elevation 728.0 ft. The Auxiliary and Control Buildings are allowed to flood.
All equipment required to maintain the plant safely during the flood is either designed to operate submerged, is located above the maximum flood level, or is otherwise protected. Those safety-related facilities, systems, and equipment located in the containment structure are protected from flooding by the Shield Building structure with those accesses and penetrations below the maximum flood level designed and constructed as watertight elements.
The maximum effective fetches for the structures are shown on Figure 2.4-28. Effective fetch accounts for the sheltering effect of several hills on the south riverbank which become islands at maximum flood levels. The maximum effective fetch in all cases, except for the west face of the Intake Pumping Station occurs from the northeast or east northeast direction. The maximum effective fetch for the west face of the Intake Pumping Station occurs from the west direction.
The Diesel Generator Building maximum effective fetch is 1.1 miles, and the critical west face of the Intake Pumping Station maximum effective fetch is 1.3 miles. The maximum effective fetch for the Auxiliary, Control, and Shield Buildings is 0.8 miles.
For the Watts Bar UFSARplant site, the two-year extreme wind for the season in which the PMF could occur was adopted to associate with the PMF crest as specified in Regulatory Guide 1.59.
The storm studies on which the PMF determination is based[4] show that the season of maximum rain depth is the month of March. Wind velocity was determined from a statistical analysis of maximum March winds observed at Chattanooga, Tennessee.
2.4-29
WBNP-Records of daily maximum average hourly winds for each direction are available at the Watts Bar site for the period May 23, 1973, through April 30, 1978. This record, however, is too short to use in a statistical analysis to determine the 2two-year extreme wind, as specified in ANSI Standard N170-1976, an appendix to Regulatory Guide 1.59. Further, the necessary 30-minute wind data are not available. To determine applicability of Chattanooga winds at the Watts Bar plant, a Kolmogorov-Smirnov (K-S) statistical test was applied to cumulative frequency distributions of daily maximum hourly winds for each direction at Chattanooga and Watts Bar. The winds compared were those recorded at Chattanooga during the period 1948-74 (the period when the necessary triple-register records were available for analysis) and the Watts Bar record. A concurrent record is not available; however, the K-S test showed that (except for the noncritical east direction) the record of daily maximum hourly velocities at Chattanooga were equal to or greater than that at Watts Bar. From this analysis it was concluded that use of the Chattanooga wind records to define seasonal maximum winds at the Watts Bar site is conservative.
The available data at Chattanooga included 30-minute and hourly winds by seasons and direction for the 27-year period 1948 through 1974. The March 30-minute wind data which was used directly in subsequent wind wave calculations were adjusted to 30 feet by the equation:
1/7 V30 = Vz (30 / Z) where:
V30 = wind speed at 30 feet Vz = wind speed at height Z above the ground The adjusted 30-minute wind data were analyzed for both the southwest and northeast directions.
The winds from the northeast are considerably less than those from the southwest; hence, the southwest direction is controlling. Figure 2.4-66 (historical information)2.4-29 shows the plot of the Chattanooga March maximum 30-minute winds from the critical southwest direction. The 2two-year, 30-minute wind speed is 21 miles per hour determined from a mathematical fit to the Gumbel distribution. This compares with 15 miles per hour determined for the March season from the noncontrolling northeast direction.
Wind wave calculations call for a 28-minute sustained wind. There is, however, no significant difference between a 2-year, 30-minute wind velocity and a 2-year, 28-minute wind velocity.
Thus, the 2-year, 30-minute, 21 mile per hour wind velocity was used to compute wind waves.
Computation of wind waves used the procedures of the Corps Of Engineers.[14] The critical direction for the PMF elevations is from the southwest with an effective fetch of 1.3 miles as shown in Figure 2.4-67. For a 28-minute sustained 21-mile-per-hour wind, 99.6% of the waves approaching the plant would be less than 2.0 feet high, crest to trough, resulting in maximum water elevation of 736.2.Wind speed was adjusted based on the effective fetch length for over water conditions. For the Diesel Generator Building, the adjusted wind speed is 23.8 miles per hour. The Intake Pumping Station maximum adjusted wind speed is 24.2 miles per hour for the critical west face. For the Auxiliary, Control, and Shield Buildings the adjusted wind speed is 23.4 miles per hour.
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WBNP-For waves approaching the Diesel Generator Building, the maximum wave height (average height of the maximum 1 percent of waves) would be 1.7 ft high, crest to trough, and the significant wave height (average height of the maximum 33-1/3 percent of waves) would be 1.0 ft high, crest to trough. The corresponding wave period is 2.0 seconds. For the Intake Pumping Station, the maximum wave height would be 2.2 ft and the significant wave height would be 1.3 ft, with a corresponding wave period of 2.3 seconds. For the critical west face, the maximum wave height would be 1.9 ft high, and the significant wave height would be 1.1 ft high. The corresponding wave period is 2.1 seconds. The maximum wave height approaching the Auxiliary, Control, and Shield Buildings would be 1.5 ft high, and the significant wave height would be 0.9 ft high. The corresponding wave period is 1.9 seconds.
Computation of wind setup used the procedures of the Corps Of Engineers[14]. The maximum wind setup is 0.1 ft for all structures. Computation of runup used the procedures of the Corps Of Engineers[14]. At the Diesel Generator Building, corresponding runup on the earth embankment with a 4:1 slope would be 2.0is 2.3 feet, reaching Elevation 736.9 and reaches elevation 741.6 ft, including wind setup. The runup on the southcritical west face wall of the pumping station would be to Elevation 736.9Intake Pumping Station is 2.1 ft and reaches elevation 741.74 ft, and the runup on the critical south face wall is 2.4 ft and reaches elevation 741.7 ft, including wind setup. The configuration of the north face of the Intake Pumping Station, opposite of the intake channel, allows higher runup of 3.4 ft. The remaining south and east faces allows runup of 2.4 ft. However, there are no credible entry points to the structure on the north, south, or east faces. Therefore, the runup on these faces is discounted. The runup on the walls of the Auxiliary, Control, and Shield Buildings is 1.7 ft and reaches elevation 741.0 ft, including wind setup.
Runup does not exceed the design basis flood level for any of the structures. Additionally, runup at the Diesel Generator Building is maintained on the slopes approaching the structure and is below all access points to the building. Runup has no consequence at the Shield Building because all accesses and penetrations below runup are designed and constructed as watertight elements.
Wind wave setup is not a problem since the wind direction is opposite to the flow of the river.
The static effect of wind waves was accounted for by taking the static water pressure from the maximum height of the runup. The dynamic effects of wind waves were accounted for as follows:
The dynamic effect of nonbreaking waves on the walls of safety-related structures was investigated using the RainflowSainflou method[15]. Concrete and reinforcing stresses were found to be within allowable limits.
The dynamic effect of breaking waves on the walls of safety-related structures was investigated using a method developed by D. D. Gaillard and D. A. Molitar[16]. The concrete and reinforcing stresses were found to be less than the allowable stresses.
The dynamic effect of broken waves on the walls of safety-related structures was investigated using the method proposed by the U.S. Army Coastal Engineering Research Center.[15] Concrete and reinforcing stresses were found to be within allowable limits.
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