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MONTHYEARML20125A3242020-05-0505 May 2020 Pre-Submittal Meeting Slides for License Amendment Request - Main Control Room Chiller Completion Time Extension Project stage: Meeting ML20135H2702020-05-28028 May 2020 Summary of May 5, 2020, Teleconference Call with Tennessee Valley Authority Regarding a Planned License Amendment Request for Watts Bar Nuclear Plant, Units 1 and 2 Project stage: Meeting 2020-05-28
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Category:Meeting Agenda
MONTHYEARML24323A0622024-11-19019 November 2024 Pre-Submittal Meeting for Proposed Alternative Request WBN-2-ISI-02 PMNS20241383, Meeting with Tennessee Valley Authority to Discuss a Proposed Alternative Request for Watts Bar Nuclear Plant, Unit 22024-11-0707 November 2024 Meeting with Tennessee Valley Authority to Discuss a Proposed Alternative Request for Watts Bar Nuclear Plant, Unit 2 PMNS20241229, Meeting with Tennessee Valley Authority to Discuss a Proposed License Amendment Request for Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 22024-10-0303 October 2024 Meeting with Tennessee Valley Authority to Discuss a Proposed License Amendment Request for Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2 ML24228A2312024-08-15015 August 2024 TVA Meeting Slides for August 19 Public Meeting Re QAPD Supplement ML24225A2542024-08-14014 August 2024 August 14, 2024 - TVA Pre-Sub Meeting Presentation - Sequoyah, Units 1 and 2; Watts Bar, Units 1 and 2 - License Amendment Request to Revise TS 3.5.2 ECCS - Operating PMNS20240978, Meeting with Tennessee Valley Authority to Discuss a Proposed Sequoyah Nuclear Plant and Watts Bar Nuclear Plant License Amendment Request to Revise Technical Specs 3.5.2, Note 1 Related to the Residual Heat Removal System2024-08-13013 August 2024 Meeting with Tennessee Valley Authority to Discuss a Proposed Sequoyah Nuclear Plant and Watts Bar Nuclear Plant License Amendment Request to Revise Technical Specs 3.5.2, Note 1 Related to the Residual Heat Removal System PMNS20241000, Meeting with Tennessee Valley Authority to Discuss Proposed Changes to the Nuclear Quality Assurance Program2024-08-0606 August 2024 Meeting with Tennessee Valley Authority to Discuss Proposed Changes to the Nuclear Quality Assurance Program PMNS20240831, Meeting with Tennessee Valley Authority to Discuss Proposed Changes to the Nuclear Quality Assurance Program2024-06-24024 June 2024 Meeting with Tennessee Valley Authority to Discuss Proposed Changes to the Nuclear Quality Assurance Program PMNS20240663, Meeting with Tennessee Valley Authority to Discuss a Proposed License Amendment Request to Revise the Watts Bar Nuclear Plant, Units 1 and 2, Technical Specifications2024-05-0909 May 2024 Meeting with Tennessee Valley Authority to Discuss a Proposed License Amendment Request to Revise the Watts Bar Nuclear Plant, Units 1 and 2, Technical Specifications PMNS20240568, Meeting with Tennessee Valley Authority to Discuss a Proposed License Amendment Request to Revise the Watts Bar Nuclear Plant, Units 1 and 2, Technical Specifications2024-04-24024 April 2024 Meeting with Tennessee Valley Authority to Discuss a Proposed License Amendment Request to Revise the Watts Bar Nuclear Plant, Units 1 and 2, Technical Specifications PMNS20240350, Annual Assessment Virtual Public Meeting2024-03-11011 March 2024 Annual Assessment Virtual Public Meeting PMNS20240344, Annual Assessment Public Poster Session and Open House Meeting2024-03-0707 March 2024 Annual Assessment Public Poster Session and Open House Meeting ML24044A0872024-02-14014 February 2024 TVA Slides - Watts Bar Nuclear Plant Pre-Submittal Meeting for License Amendment Request to Revise TS 3.7.11, Main Control Room Area Chilled Water System PMNS20240088, Meeting with Tennessee Valley Authority to Discuss a Proposed License Amendment Request to Revise the Watts Bar Nuclear Plant Technical Specifications2024-01-30030 January 2024 Meeting with Tennessee Valley Authority to Discuss a Proposed License Amendment Request to Revise the Watts Bar Nuclear Plant Technical Specifications PMNS20231329, Meeting with Tennessee Valley Authority to Discuss Proposed License Amendment Request for the Browns Ferry, Sequoyah, and Watts Bar Nuclear Plants2023-11-28028 November 2023 Meeting with Tennessee Valley Authority to Discuss Proposed License Amendment Request for the Browns Ferry, Sequoyah, and Watts Bar Nuclear Plants ML23291A1562023-10-18018 October 2023 NRC Pre-Submittal Meeting Watts Bar & Sequoyah LAR, TVA Presentation Slides PMNS20231126, Meeting with Tennessee Valley Authority to Discuss a Proposed License Amendment Request for Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 22023-10-18018 October 2023 Meeting with Tennessee Valley Authority to Discuss a Proposed License Amendment Request for Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2 PMNS20231024, Meeting with Tennessee Valley Authority to Discuss a Proposed License Amendment Request for the Watts Bar Nuclear Plant, Units 1 and 22023-09-18018 September 2023 Meeting with Tennessee Valley Authority to Discuss a Proposed License Amendment Request for the Watts Bar Nuclear Plant, Units 1 and 2 PMNS20230916, Meeting with Tennessee Valley Authority to Discuss a Proposed License Amendment Request for the Watts Bar Nuclear Plant, Units 1 and 22023-08-31031 August 2023 Meeting with Tennessee Valley Authority to Discuss a Proposed License Amendment Request for the Watts Bar Nuclear Plant, Units 1 and 2 ML23178A0832023-07-10010 July 2023 Pre-submittal Meeting Slides for License Amendment Request to Revise Technical Specification Table 1.1-1 Regarding the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs PMNS20230795, Meeting with Tennessee Valley Authority to Discuss a Proposed License Amendment Request for the Watts Bar Nuclear Plant, Units 1 and 22023-06-30030 June 2023 Meeting with Tennessee Valley Authority to Discuss a Proposed License Amendment Request for the Watts Bar Nuclear Plant, Units 1 and 2 PMNS20230712, Meeting with Tennessee Valley Authority to Discuss Proposed License Amendment Request for the Browns Ferry, Sequoyah, and Watts Bar Nuclear Plants2023-06-12012 June 2023 Meeting with Tennessee Valley Authority to Discuss Proposed License Amendment Request for the Browns Ferry, Sequoyah, and Watts Bar Nuclear Plants PMNS20230549, Annual Assessment Virtual Meeting for the 2022 Assessment Period2023-04-25025 April 2023 Annual Assessment Virtual Meeting for the 2022 Assessment Period PMNS20230446, Annual Assessment Public Poster Session and Openhouse Meeting2023-04-17017 April 2023 Annual Assessment Public Poster Session and Openhouse Meeting ML23044A5182023-02-15015 February 2023 Pre-Submittal Meeting Slides for Expedited License Amendment Request Re Main Control Room Chiller Completion Time Extension ML23041A3562023-02-15015 February 2023 February 15, 2023 Pre-submittal Meeting for Expedited License Amendment Request Main Control Room (MCR) Chiller Completion Time Extension (EPID L-2022-LRM-0098) (Slides) PMNS20230127, Meeting with Tennessee Valley Authority Regarding Proposed License Amendment Request for Watts Bar Nuclear Plant, Units 1 and 2, to Increase the Allowable Number of Tritium Producing Burnable Absorber Rods2023-02-13013 February 2023 Meeting with Tennessee Valley Authority Regarding Proposed License Amendment Request for Watts Bar Nuclear Plant, Units 1 and 2, to Increase the Allowable Number of Tritium Producing Burnable Absorber Rods PMNS20221292, Meeting with Tennessee Valley Authority to Discuss Proposed License Amendment Request2023-01-11011 January 2023 Meeting with Tennessee Valley Authority to Discuss Proposed License Amendment Request ML22318A1042022-11-14014 November 2022 Pre-submittal Meeting for American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative WBN-2-ISI-01 Slide Presentation PMNS20221152, Meeting with Tennessee Valley Authority to Discuss a Proposed Alternative Request for Watts Bar Nuclear Plant, Unit 22022-11-0303 November 2022 Meeting with Tennessee Valley Authority to Discuss a Proposed Alternative Request for Watts Bar Nuclear Plant, Unit 2 PMNS20220956, Meeting with Tennessee Valley Authority to Discuss Proposed License Amendment Request2022-09-20020 September 2022 Meeting with Tennessee Valley Authority to Discuss Proposed License Amendment Request PMNS20220531, Meeting with Tennessee Valley Authority to Discuss a Proposed License Amendment Request for Sequoyah and Watts Bar Nuclear Plants2022-05-19019 May 2022 Meeting with Tennessee Valley Authority to Discuss a Proposed License Amendment Request for Sequoyah and Watts Bar Nuclear Plants PMNS20220379, Meeting with Tennessee Valley Authority to Discuss a Proposed Exemption Request for Watts Bar Nuclear Plant, Unit 22022-04-0808 April 2022 Meeting with Tennessee Valley Authority to Discuss a Proposed Exemption Request for Watts Bar Nuclear Plant, Unit 2 PMNS20220314, Meeting with Tennessee Valley Authority to Discuss a Proposed Alternative Request for Sequoyah and Watts Bar Nuclear Plants2022-03-31031 March 2022 Meeting with Tennessee Valley Authority to Discuss a Proposed Alternative Request for Sequoyah and Watts Bar Nuclear Plants PMNS20220285, Annual Assessment Meeting2022-03-29029 March 2022 Annual Assessment Meeting PMNS20211575, Pre-Submittal Meeting with Tennessee Valley Authority Regarding Watts Bar Nuclear Plant, Unit 1, Proposed License Amendment Request2022-01-18018 January 2022 Pre-Submittal Meeting with Tennessee Valley Authority Regarding Watts Bar Nuclear Plant, Unit 1, Proposed License Amendment Request PMNS20211571, Meeting with Tennessee Valley Authority Regarding Watts Bar Nuclear Plant, Units 1 and 2, Tritium Producing Burnable Absorption Rods2022-01-0606 January 2022 Meeting with Tennessee Valley Authority Regarding Watts Bar Nuclear Plant, Units 1 and 2, Tritium Producing Burnable Absorption Rods PMNS20211507, Pre-Submittal Meeting with Tennessee Valley Authority Regarding Watts Bar Nuclear Plant, Unit 2, Capsule Withdrawal2021-12-0101 December 2021 Pre-Submittal Meeting with Tennessee Valley Authority Regarding Watts Bar Nuclear Plant, Unit 2, Capsule Withdrawal ML21281A2282021-10-13013 October 2021 Tennessee Valley Authority Fleet Pre-Submittal Meeting for License Amendment Request to Change Emergency Action Level Scheme Presentation - October 13, 2021 (EPID L-2021-LRM-0096) (Slides) PMNS20211154, Meeting with Tennessee Valley Authority Regarding a Proposed Fleet Amendment Request2021-09-21021 September 2021 Meeting with Tennessee Valley Authority Regarding a Proposed Fleet Amendment Request PMNS20211126, Meeting with Tennessee Valley Authority Regarding Watts Bar Nuclear Plant, Unit 22021-09-0808 September 2021 Meeting with Tennessee Valley Authority Regarding Watts Bar Nuclear Plant, Unit 2 ML21231A0972021-08-18018 August 2021 TVA Slides - Pre-Submittal Meeting for Proposed LAR Regarding Application to Modify Watts Bar Units 1 and 2 Technical Specification 3.7.8, Essential Raw Cooling Water (ERCW) System, to Support Permanent Shutdown Board Cleaning PMNS20210945, Meeting with Tennessee Valley Authority Regarding Watts Bar Nuclear Plant, Unit 22021-08-0606 August 2021 Meeting with Tennessee Valley Authority Regarding Watts Bar Nuclear Plant, Unit 2 PMNS20211003, Meeting with Tennessee Valley Authority Regarding Watts Bar Nuclear Plant, Units 1 and 22021-08-0505 August 2021 Meeting with Tennessee Valley Authority Regarding Watts Bar Nuclear Plant, Units 1 and 2 PMNS20210829, Meeting with Tennessee Valley Authority Regarding Watts Bar Nuclear Plant, Unit 22021-07-12012 July 2021 Meeting with Tennessee Valley Authority Regarding Watts Bar Nuclear Plant, Unit 2 ML21189A0982021-07-0808 July 2021 Teleconference with Tennessee Valley Authority Regarding Watts Bar Nuclear Plant, Unit 2, PMNS20210702, Closed Meeting with Representatives from the Tennessee Valley Authority to Discuss a Planned Request for Exemption2021-05-25025 May 2021 Closed Meeting with Representatives from the Tennessee Valley Authority to Discuss a Planned Request for Exemption ML21117A1582021-04-27027 April 2021 Teleconference with Tennessee Valley Authority Regarding Watts Bar Nuclear Plant, Units 1 and 2, Proposed License Amendment Request PMNS20210392, Annual Assessment Meeting2021-04-12012 April 2021 Annual Assessment Meeting ML21096A1312021-04-0707 April 2021 Pre-submittal Meeting for Inservice Testing (IST) Program Request for One-Time Extension of Test Frequency of WBN Unit 1 Group 6 Relief Valves 2024-08-06
[Table view] Category:Meeting Briefing Package/Handouts
MONTHYEARML24320A1062024-11-20020 November 2024 Pre-Submittal Meeting Presentation, November 20, 2024, Pmns 20241350 ML24323A0622024-11-19019 November 2024 Pre-Submittal Meeting for Proposed Alternative Request WBN-2-ISI-02 ML24312A0532024-11-0707 November 2024 FLEX HP Pump SDP for Nextera RUG Meeting - 11.7.2024 - Rev. 0 ML24312A1432024-11-0707 November 2024 SDP for Nextera RUG Meeting - 11.7.2024 - Rev. 0 ML24284A0042024-10-16016 October 2024 Application to Use Online Monitoring Methodology for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant Session Slides ML24228A2312024-08-15015 August 2024 TVA Meeting Slides for August 19 Public Meeting Re QAPD Supplement ML24225A2542024-08-14014 August 2024 August 14, 2024 - TVA Pre-Sub Meeting Presentation - Sequoyah, Units 1 and 2; Watts Bar, Units 1 and 2 - License Amendment Request to Revise TS 3.5.2 ECCS - Operating ML24137A2872024-05-16016 May 2024 Pre-Submittal Meetingfor Proposed 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 ML24127A0412024-05-0606 May 2024 May 6, 2024 Meeting Slides ML24067A2832024-03-27027 March 2024 2023 Browns Ferry, Sequoyah and Watts Bar Annual Assessment Public Meeting Presentation Slides ML24044A0872024-02-14014 February 2024 TVA Slides - Watts Bar Nuclear Plant Pre-Submittal Meeting for License Amendment Request to Revise TS 3.7.11, Main Control Room Area Chilled Water System ML23291A1562023-10-18018 October 2023 NRC Pre-Submittal Meeting Watts Bar & Sequoyah LAR, TVA Presentation Slides ML23264A0412023-09-27027 September 2023 NRC Pre-Submittal Meeting WBN Rebaseline LAR, TVA Presentation Slides ML23251A1212023-09-12012 September 2023 RHR Flow Rate Reduction During Mode 6 Operation at 23 Ft. Refueling Water Level Technical Specification Change NON-PROPRIETARY Slides ML23251A1252023-09-12012 September 2023 Pre-submittal Meeting for License Amendment Request, Modify the Watts Bar Nuclear Plant Unit 1 and Unit 2 Technical Specification Surveillance Requirement 3.9.5.1 ML23178A0832023-07-10010 July 2023 Pre-submittal Meeting Slides for License Amendment Request to Revise Technical Specification Table 1.1-1 Regarding the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs ML23128A2882023-05-0808 May 2023 TVA Nuclear Plants -2022 EOC Media Slides ML23052A0362023-02-22022 February 2023 February 22, 2023, Pre-Submittal Meeting for the License Amendment Request for Increased Tritium Production at Watts Bar (EPID L-2023-LRM-0010) - Meeting Slides ML23041A3562023-02-15015 February 2023 February 15, 2023 Pre-submittal Meeting for Expedited License Amendment Request Main Control Room (MCR) Chiller Completion Time Extension (EPID L-2022-LRM-0098) (Slides) ML23044A5182023-02-15015 February 2023 Pre-Submittal Meeting Slides for Expedited License Amendment Request Re Main Control Room Chiller Completion Time Extension ML22318A1042022-11-14014 November 2022 Pre-submittal Meeting for American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative WBN-2-ISI-01 Slide Presentation ML22157A4132022-06-0606 June 2022 Plants - Pre-Submittal Teleconference for Proposed Amendment Request Regarding the Change for the Sequoyah and Watts Bar Nuclear Plants Technical Specification 3.4.12 Meeting Slides ML22102A3032022-04-12012 April 2022 Pre-submittal Meeting for Request for Exemption from Requirements of 10 CFR 26.205(d)(4) and 10 CFR 26.205(d)(6) Slide Presentation ML22080A1662022-03-21021 March 2022 TVA Nuclear Plants -2021 EOC Media Loop Slides for Automatic Play ML21343A0282021-12-14014 December 2021 TVA Slide Presentation Regarding Pre-Submittal Meeting for Proposed Revision to Capsule Withdrawal Schedule ML21281A2282021-10-13013 October 2021 Tennessee Valley Authority Fleet Pre-Submittal Meeting for License Amendment Request to Change Emergency Action Level Scheme Presentation - October 13, 2021 (EPID L-2021-LRM-0096) (Slides) ML21250A3652021-09-0808 September 2021 Meeting Slides - Watts Bar Nuclear Plant Unit 2, Presubmittal Teleconference for Proposed License Amendment to Revise the Updated Final Safety Analyses Report (UFSAR) to Use a Tube Support Plate Locking/Displacement Analysis ML21217A2872021-08-19019 August 2021 TVA Slides - Pre-Submittal Meeting for Proposed License Amendment Request Re Application to Modify Technical Specification 3.7.8 Essential Raw Cooling Water (ERCW) System, to Support Permanent Shutdown Board ML21229A1992021-08-19019 August 2021 Mid-Cycle SG Outage Strategy (EPID L-2021-LRM-0067) (Slides) ML21231A0972021-08-18018 August 2021 TVA Slides - Pre-Submittal Meeting for Proposed LAR Regarding Application to Modify Watts Bar Units 1 and 2 Technical Specification 3.7.8, Essential Raw Cooling Water (ERCW) System, to Support Permanent Shutdown Board Cleaning ML21117A0722021-04-27027 April 2021 Meeting Slides for April 28, 2021 Meeting with TVA ML21096A1312021-04-0707 April 2021 Pre-submittal Meeting for Inservice Testing (IST) Program Request for One-Time Extension of Test Frequency of WBN Unit 1 Group 6 Relief Valves ML21041A1552021-02-11011 February 2021 Meeting Slides for February 11, 2021 Meeting with TVA ML20345A0262020-12-10010 December 2020 Replacement Steam Generator Project Planned License Amendment Request (Lars). LAR Descriptions and Submittal Schedule Meeting Slides ML20329A3722020-11-24024 November 2020 Pre-Submittal Teleconference for Proposed License Amendment Request Regarding Technical Specification 5.9.9, Steam Generator Tube Inspection Report, to Use Popcd Methodology ML20302A1232020-10-28028 October 2020 Pre-Submittal Meeting Slides Non-Voluntary Application to Modify WBN Unit 1 and Unit 2 TS Surveillance Requirement 3.6.15.4, Shield Building ML20239A8672020-08-27027 August 2020 Pre-Submittal Meeting Slides License Amendment Request for Technical Specification 5.7.2.19 ML20175A0552020-06-23023 June 2020 TVA Slides for June 23, 2020, Emergency Plan Change Presubmittal Meeting ML20125A3242020-05-0505 May 2020 Pre-Submittal Meeting Slides for License Amendment Request - Main Control Room Chiller Completion Time Extension ML20049G1822020-02-18018 February 2020 February 20, 2020 - Pre-submittal Meeting Presentation - Transition to Westinghouse Fuel ML20009C3962020-01-0808 January 2020 Pre-Submittal Telecon for Expedited License Amendment Request to Revise Technical Specification 3.3.5, LOP DG Start Instrumentation ML19347B0722019-12-12012 December 2019 TVA and Xcel Energy Slides for Joint Presubmittal Meeting to License Amendment Requests to Adopt WCAP-17661, Revision 1 ML19282A0082019-10-0909 October 2019 TVA Slides for Pre-Submittal Meeting for License Amendment Request to Correct Unbalanced Voltage Relay Instrumentation Values ML19298A0042019-09-12012 September 2019 Presentation Slides for 9/12/19 Public Meeting ML19255H5522019-09-12012 September 2019 August 27, 2019, Summary of Public Meeting - Tennessee Valley Safety Conscious Work Environment Update at Watts Bar, Docket 50-390 and 50-391 ML19252A0532019-09-0909 September 2019 TVA Presentation Slides: Watts Bar Nuclear Plant Pre-Submittal Meeting for License Amendment Request Revised Offsite Electrical Power Sources ML19235A2882019-08-23023 August 2019 2019 WBN SCWE Public Meeting Slides 8-27-2019 (NRC Slides) ML19235A2712019-08-23023 August 2019 2019 TVA Watts Bar Nuclear Plant Public Meeting Slides 08-27-2019 (TVA Slides) ML19178A2462019-07-0101 July 2019 Presentation Material for July 1, 2019 Pre-submittal Meeting with TVA on Full Spectrum LOCA Methodology for Watts Bar, Units 1 and 2 ML19161A2412019-06-11011 June 2019 Pre-Application Meeting for Proposed License Amendment Request (LAR) Regarding Change to the WBN Unit 2 Technical Specifications (TS) 3.4.17, Steam Generator Tube Integrity and 5.7.2.12 Steam Generator Program 2024-08-15
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24320A1062024-11-20020 November 2024 Pre-Submittal Meeting Presentation, November 20, 2024, Pmns 20241350 ML24323A0622024-11-19019 November 2024 Pre-Submittal Meeting for Proposed Alternative Request WBN-2-ISI-02 ML24312A0532024-11-0707 November 2024 FLEX HP Pump SDP for Nextera RUG Meeting - 11.7.2024 - Rev. 0 ML24312A1432024-11-0707 November 2024 SDP for Nextera RUG Meeting - 11.7.2024 - Rev. 0 ML24284A0042024-10-16016 October 2024 Application to Use Online Monitoring Methodology for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant Session Slides ML24228A2312024-08-15015 August 2024 TVA Meeting Slides for August 19 Public Meeting Re QAPD Supplement ML24225A2542024-08-14014 August 2024 August 14, 2024 - TVA Pre-Sub Meeting Presentation - Sequoyah, Units 1 and 2; Watts Bar, Units 1 and 2 - License Amendment Request to Revise TS 3.5.2 ECCS - Operating ML24184B9162024-07-10010 July 2024 U.S. NRC Meeting Slides for Meeting with Tennessee Valley Authority Regarding NRC Questions Regarding Scope of Nuclear Quality Assurance Program ML24137A2872024-05-16016 May 2024 Pre-Submittal Meetingfor Proposed 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 ML24127A0412024-05-0606 May 2024 May 6, 2024 Meeting Slides ML24067A2832024-03-27027 March 2024 2023 Browns Ferry, Sequoyah and Watts Bar Annual Assessment Public Meeting Presentation Slides ML23291A1562023-10-18018 October 2023 NRC Pre-Submittal Meeting Watts Bar & Sequoyah LAR, TVA Presentation Slides ML23264A0412023-09-27027 September 2023 NRC Pre-Submittal Meeting WBN Rebaseline LAR, TVA Presentation Slides ML23251A1252023-09-12012 September 2023 Pre-submittal Meeting for License Amendment Request, Modify the Watts Bar Nuclear Plant Unit 1 and Unit 2 Technical Specification Surveillance Requirement 3.9.5.1 ML23251A1212023-09-12012 September 2023 RHR Flow Rate Reduction During Mode 6 Operation at 23 Ft. Refueling Water Level Technical Specification Change NON-PROPRIETARY Slides ML23178A0832023-07-10010 July 2023 Pre-submittal Meeting Slides for License Amendment Request to Revise Technical Specification Table 1.1-1 Regarding the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs ML23128A2882023-05-0808 May 2023 TVA Nuclear Plants -2022 EOC Media Slides ML23052A0362023-02-22022 February 2023 February 22, 2023, Pre-Submittal Meeting for the License Amendment Request for Increased Tritium Production at Watts Bar (EPID L-2023-LRM-0010) - Meeting Slides ML23044A5182023-02-15015 February 2023 Pre-Submittal Meeting Slides for Expedited License Amendment Request Re Main Control Room Chiller Completion Time Extension ML23041A3562023-02-15015 February 2023 February 15, 2023 Pre-submittal Meeting for Expedited License Amendment Request Main Control Room (MCR) Chiller Completion Time Extension (EPID L-2022-LRM-0098) (Slides) ML23010A2542023-01-12012 January 2023 Pre-submittal Meeting for Expedited License Amendment Request Main Control Room (MCR) Chiller Completion Time Extension -- Meeting Slides ML22318A1042022-11-14014 November 2022 Pre-submittal Meeting for American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative WBN-2-ISI-01 Slide Presentation ML22157A4132022-06-0606 June 2022 Plants - Pre-Submittal Teleconference for Proposed Amendment Request Regarding the Change for the Sequoyah and Watts Bar Nuclear Plants Technical Specification 3.4.12 Meeting Slides ML22103A0852022-04-14014 April 2022 And Watts Bar Plant Pre-submittal Meeting for Inservice Testing (IST) Program Request for Alternative for the Motor Driven Auxiliary Feedwater Pump Testing Following Maintenance During an Outage Per ISTB-3310 ML22102A3032022-04-12012 April 2022 Pre-submittal Meeting for Request for Exemption from Requirements of 10 CFR 26.205(d)(4) and 10 CFR 26.205(d)(6) Slide Presentation ML22080A1662022-03-21021 March 2022 TVA Nuclear Plants -2021 EOC Media Loop Slides for Automatic Play ML22035A0002022-02-0404 February 2022 February 8, 2022, Pre-Submittal Meeting Slides Regarding Proposed Change to Modify the Allowable Value for Technical Specification Table 3.3.2-1, Function 6.e(1) ML22013A6432022-01-19019 January 2022 TVA Slides - Watts Bar Nuclear Plant (WBN) Schedule for the Development of a License Amendment Request (LAR) for Increased Tritium Production at WBN ML21343A0282021-12-14014 December 2021 TVA Slide Presentation Regarding Pre-Submittal Meeting for Proposed Revision to Capsule Withdrawal Schedule ML21281A2282021-10-13013 October 2021 Tennessee Valley Authority Fleet Pre-Submittal Meeting for License Amendment Request to Change Emergency Action Level Scheme Presentation - October 13, 2021 (EPID L-2021-LRM-0096) (Slides) ML21250A3652021-09-0808 September 2021 Meeting Slides - Watts Bar Nuclear Plant Unit 2, Presubmittal Teleconference for Proposed License Amendment to Revise the Updated Final Safety Analyses Report (UFSAR) to Use a Tube Support Plate Locking/Displacement Analysis ML21229A1992021-08-19019 August 2021 Mid-Cycle SG Outage Strategy (EPID L-2021-LRM-0067) (Slides) ML21217A2872021-08-19019 August 2021 TVA Slides - Pre-Submittal Meeting for Proposed License Amendment Request Re Application to Modify Technical Specification 3.7.8 Essential Raw Cooling Water (ERCW) System, to Support Permanent Shutdown Board ML21231A0972021-08-18018 August 2021 TVA Slides - Pre-Submittal Meeting for Proposed LAR Regarding Application to Modify Watts Bar Units 1 and 2 Technical Specification 3.7.8, Essential Raw Cooling Water (ERCW) System, to Support Permanent Shutdown Board Cleaning ML21096A1312021-04-0707 April 2021 Pre-submittal Meeting for Inservice Testing (IST) Program Request for One-Time Extension of Test Frequency of WBN Unit 1 Group 6 Relief Valves ML21096A1002021-04-0606 April 2021 Annual Assessments ML21041A1552021-02-11011 February 2021 Meeting Slides for February 11, 2021 Meeting with TVA ML21019A5692021-01-19019 January 2021 Pre-Submittal Teleconference for Proposed License Amendment Requests (Lars) for the WBN Unit 2 Replacement Steam Generator (RSG) Project ML20352A0362020-12-17017 December 2020 Pre-Submittal Teleconference for Proposed License Amendment to Revise the Updated Final Safety Analysis Report (UFSAR) to Use an Alternate Probability of Detection (POD) ML20329A3722020-11-24024 November 2020 Pre-Submittal Teleconference for Proposed License Amendment Request Regarding Technical Specification 5.9.9, Steam Generator Tube Inspection Report, to Use Popcd Methodology ML21050A1562020-10-21021 October 2020 Graizer - Presentation - Analysis of TVAs Watts Bar Nuclear Power Plant Strong-Motion Records of the M 4.4 December 12, 2018 Decatur Tennessee Earthquake ML20239A8672020-08-27027 August 2020 Pre-Submittal Meeting Slides License Amendment Request for Technical Specification 5.7.2.19 ML20220A2022020-08-0707 August 2020 Pre-Submittal Meeting Slides - Proposed License Approach Regarding a Change for Watts Bar Nuclear Plant Units 1 & 2 Technical Specification 3.3.2 Table 1 Function 6.e Auxiliary Feedwater Auto-Start from Loss of Main Feedwater Pumps(Epid L-2 ML20209A0702020-07-27027 July 2020 Pre-submittal Meeting for Inservice Testing (IST) Program Request for Relief from Increased Frequency Testing of Residual Heat Removal (RHR) Pump 1B-B Meeting Slides ML20169A5222020-06-25025 June 2020 Pre-Submittal Meeting for License Amendment Request (LAR) Revised Steam Generator (SG) Inspection Intervals and TSTF-510 ML20175A0552020-06-23023 June 2020 TVA Slides for June 23, 2020, Emergency Plan Change Presubmittal Meeting ML20148M1452020-05-27027 May 2020 (Wbn)Proposed License Approach Regarding a Change for the WBN Units 1& 2 Technical Specification (TS) 3.3.2 Table 1 Function 6.e Auxiliary Feedwater Auto-Start from Loss of Main Feedwater Pumps ML20147A0132020-05-26026 May 2020 NRC Slides Final WBN-1 TS 3.3.3 LAR ML20134J0102020-05-14014 May 2020 Pre-Submittal Meeting for License Amendment Request Technical Specification 5.9.6 Add NRC-approved Neutron Fluence Calculational Methodology ML20125A3242020-05-0505 May 2020 Pre-Submittal Meeting Slides for License Amendment Request - Main Control Room Chiller Completion Time Extension 2024-08-15
[Table view] |
Text
Watts Bar Nuclear Plant (WBN)
Pre-Submittal Meeting for License Amendment Request Main Control Room Chiller Completion Time Extension May 5, 2020
Opening Remarks
Background
Control Room Emergency Air Temperature Control System (CREATCS) Design CREATCS Modification TS 3.7.11, Required Action A.1 Main Control Room (MCR) Cooling Temporary Chilled Water Equipment TS 3.7.11, Required Action E.1 Summary of Compensatory Actions Precedent Schedule Milestones Closing Remarks Agenda l 2
Opening Remarks The purpose of this meeting is to discuss a proposed license amendment for WBN Units 1 and 2.
TVA is requesting a license amendment for a one-time change to WBN Units 1 and 2 Technical Specification (TS) 3.7.11, Control Room Emergency Air Temperature Control System (CREATCS), Required Actions A.1 and E.1 to support modifications to the CREATCS chillers.
This presentation will discuss the basis for the proposed TS changes and the modifications that are planned to be made to the CREATCS chillers and proposed compensatory measures.
l 3
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Background===
The CREATCS chiller units are scheduled to be replaced to improve their efficiency.
The CREATCS provides cooling to the common MCR, therefore, inoperability of the CREATCS affects operation of both Units.
The Nuclear Regulatory Commission (NRC) previously issued a similar license amendment for WBN Unit 1 on February 8, 2011 (ML110190280) to allow one CREATCS train to be inoperable for up to 60 days while performing the modifications to the CREATCS chillers.
However, the modifications to the WBN Unit 1 CREATCS chillers were not performed due to issues with the seismic qualification of the replacement chiller units.
Documented in NRC Inspection Report 390/2014005 and 390/2014501 (ML15040A425).
The new chillers will be nuclear grade safety-related which addresses the corrective actions and lessons learned from the previous modification.
l 4
CREATCS Design The CREATCS provides temperature control for the MCR during normal operation and following isolation of the MCR.
The CREATCS consists of two independent and redundant trains that provide cooling of recirculated MCR air. Fresh air is also introduced into the MCR through the CREATCS.
Each train consists of an air-handling unit (AHU), water chiller, chilled water pump, and associated piping, ductwork, instrumentation, and controls to provide for MCR temperature control.
WBN has a common MCR for Units 1 and 2 located in the Control Building.
The design basis of the CREATCS is to maintain the MCR temperature for 30 days of continuous occupancy.
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CREATCS Design l 6 AHU AHU
CREATCS Modification The proposed permanent modifications are limited to replacement of each of the CREATCS chiller packages.
The CREATCS AHUs, chilled water pumps and chilled water piping will not be changed during this modification.
During CREATCS chiller replacement, the affected CREATCS train will be inoperable.
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Train A Chiller Replacement Duration l 8
- Activity performed in parallel with chiller replacement activities
- Activity performed in parallel with piping re-installation activities
Train B Chiller Replacement Duration l 9
- Activity performed in parallel with chiller replacement activities
- Activity performed in parallel with piping re-installation activities
Figure of Train A CREATCS Orientation l 10
TS 3.7.11, Required Action A.1 TS 3.7.11, Required Action A.1 provides a 30 day Completion Time to restore a CREATCS train to operable status if one train has been declared inoperable.
To accomplish these chiller replacements, TVA proposes that the TS 3.7.11 Required Action A.1 Completion Time for restoration of one inoperable CREATCS train be extended from 30 days to 60 days.
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Proposed Technical Specification Change l 12 Units 1 and 2 - TS 3.7.11 Footnote for Action A.1
MCR Cooling During CREATCS chiller replacement, the affected CREATCS train is inoperable. However, train components remain functional with the exception of the chilled water pump and the chiller unit.
To provide defense in depth for cooling the MCR, a temporary chiller unit will be installed and connected to the functional CREATCS AHU.
The temporary chiller unit will operate during the modification to maintain the MCR temperature below limits.
If the temporary chiller unit fails, the Operable CREATCS train will automatically start on high AHU temperature, or may be manually started to maintain the MCR temperature.
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MCR Cooling The Operable CREATCS train (in standby) will automatically start after a 30-second delay for the following occurrences:
(1) high air inlet temperature to the operating AHU, (2) low discharge airflow from the operating AHU, or (3) low differential pressure across the operating chilled water pump.
Failure of the operating train for any of these cases is alarmed in the MCR.
During the CREATCS chiller replacement modification, the low differential pressure start signal from the inoperable CREATCS train will be defeated to allow the temporary chiller system to provide the chilled water to that train.
The chilled water pump is out of service during the chiller replacement.
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MCR Cooling The remaining two start signals will continue to function as designed, providing a diverse means to automatically start the standby Operable CREATCS train. This adequately supports the design function to ensure that a suitable environment is maintained for personnel and equipment in the MCR.
In addition to the automatic start signals, the temperature in the MCR is monitored every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> per the Technical Requirements Manual Section 3.7.5, Area Temperature Monitoring.
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Temporary Chilled Water Equipment A temporary non-safety related chiller system will be installed and used to support MCR cooling during the CREATCS chiller replacements.
This temporary system is capable of providing adequate cooling to maintain the MCR within its normal temperature band.
The temporary chiller system is robust and reliable as demonstrated by its operation during other maintenance activities.
The major components of the temporary chiller system include:
Air cooled chilled water package Chilled water pump Power supply, cables, and connections Chilled water supply and return hoses Demineralized water source Engineered penetrations with isolation valves Backup diesel generator (DG) with fuel tank l 16
Temporary Chilled Water Equipment l 17
Temporary Chilled Water Equipment The temporary chiller system will use a 150-ton (minimum) capacity portable air-cooled chiller, a 500 gallons per minute (gpm) chilled water pump or pumps, temporary chilled water supply and return hoses, temporary penetration configurations and associated isolation valves, temporary chilled water connections to the appropriate AHU, and a 320kW DG.
TVA performed a calculation that considered operational heat loads, the nominal rating of the temporary chiller unit, and nominal temporary chilled water pump ratings.
The calculation determined that MCR temperatures would remain below 80°F.
These components are on stand-alone skid mounted packages and will be located in the yard west of the Auxiliary Building and in the Control Building Supply and return hoses will be used for routing the chilled water from the temporary chilled water package to the AHUs in the Control Building.
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Temporary Chilled Water Equipment Existing sleeves located on Elevation 755.0 which are part of the MCR boundary will be used for routing the chilled water supply and return hoses to the appropriate MCR AHU located in the Mechanical Equipment Room.
Two manual isolation valves, one for each penetration through the MCR boundary will be provided for isolation purposes.
The valves at the penetrations are qualified for seismic retention to maintain the integrity of the MCR boundary.
The temporary hoses, pipe, and fittings are qualified for adequate pressure to protect against rupture and pipe whip.
A combustible loading evaluation has been performed to ensure the materials associated with this temporary modification do not substantially increase fire risks within the Control Building.
Spill containment will be provided beneath the chiller skid.
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Temporary Chilled Water Equipment The temporary non safety related chiller system and chilled water pump will be powered from non-safety related 480V AC sources located within the station area.
The temporary chilled water system has a temporary 320 kW DG dedicated to it so that it can operate independently of site power.
The temporary chiller is not proposed as a safety related substitute for the permanent CREATCS chillers. Therefore, for this one-time TS extension request, the installation of the temporary chiller system, without the application of all safety related design criteria associated with weather and missile protection, is appropriate.
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Control Room Habitability The CREATCS together with the Main Control Room Habitability System (MCRHS) provides for the safe uninterrupted occupancy of the MCR Habitability Zone (MCRHZ) during an accident and subsequent recovery period The MCRHZ is unaffected by the temporary chilled water system.
No changes to the ductwork, AHU characteristics, or the various system air flows serving the MCRHZ.
No changes to the emergency air cleaning system and no impact to post accident dose analysis.
The temporary chiller system and associated equipment will have no interface with the MCRHZ isolation, and therefore, will not impact the ability to isolate the MCRHZ or the ability of the emergency air cleanup system to function as designed.
Penetrations used for the temporary chiller supply and return hoses are limited in size to remain below the MCR boundary unfiltered inleakage criteria.
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TS 3.7.11, Required Action E.1 TS 3.7.11, Required Action E.1 addresses a condition with two trains of CREATCS inoperable.
It requires immediate entry into Limiting Condition for Operation (LCO) 3.0.3, with subsequent Unit shutdown.
Because WBN has a common MCR for both Units, this would require a dual Unit shutdown.
During CREATCS chiller replacement, the affected CREATCS train will be inoperable.
If the other CREATCS train should be declared inoperable due to a failure or during post modification testing, LCO 3.0.3 is required to be entered immediately.
A four-day delay is requested prior to entering LCO 3.0.3 based on corrective maintenance repair times.
MCR temperature will be monitored hourly to ensure it remains below 90°F.
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Proposed Technical Specification Change l 23 Units 1 and 2 - TS 3.7.11 Footnote for Action E.1
Corrective Maintenance Time for CREATCS l 24 Date Corrective Maintenance Issue Unavailability Time (Hours:Mins)
Unavailability Time (Days) 11/8/19 MCR Chiller A TCV failed 51:19 2.14 11/5/19 MCR Chiller A TCV failed 49:11 2.05 3/31/19 MCR Chiller B Air Handling Unit (AHU) motor failure 70:45 2.95 3/28/19 MCR Chiller B AHU motor failure 74:10 3.09 7/9/18 MCR Chiller B not cooling 88:00 3.67 4/12/17 MCR Chiller A oil temperature issue 77:20 3.22 3/8/16 MCR Chiller A Oil Cooler Temperature Control Valve (TCV) failure 64:43 2.70 10/8/15 MCR Chiller B Essential Raw Cooling Water (ERCW) leak on oil return line (rework from repair made during week) 25:29 1.06 9/30/15 MCR Chiller B ERCW copper pipe rupture 64:52 2.70 3/1/15 MCR Chiller A ERCW TCV failed 31:00 1.29
TS 3.7.11, Required Action E.1 The proposed footnote to TS 3.7.11, Condition E, is based on verifying that the MCR temperature is less than or equal to 90°F.
The temperature limit for MCR equipment operability is 104°F.
The 90°F temperature limit provides margin between the normal MCR operating temperature of 75°F and a limit that ensures that the equipment operability limit of 104°F is not exceeded.
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TS 3.7.11, Required Action E.1 The proposed footnote for TS 3.7.11, Required Action E.1 requires that operators monitor the MCR temperature every hour and verify the MCR temperature is less than or equal to 90°F.
To support the one-hour frequency for temperature monitoring TVA evaluated the effect of a loss of cooling on the MCR temperature by performing an analysis of the heatup of the MCR and surrounding areas.
Two cases were evaluated Normal operating heat loads, summertime maximum outdoor temperatures, one AHU operating, no chillers in operation LOCA heat loads, summertime maximum outdoor temperatures, no AHUs running, no chillers in operation The calculation demonstrates that the temperature increase from 75°F (normal MCR operating temperature) to 104°F takes approximately 5.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for the normal operating heat load case and 4.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for the LOCA heat load case.
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TS 3.7.11, Required Action E.1 The one-hour frequency for temperature monitoring is adequate based on the heat-up calculations for the MCR and the indications available in the MCR.
With hourly temperature monitoring, a degraded condition would be identified before equipment temperature limits were reached and Unit shutdown activities would be initiated.
Additionally, with operators continually stationed in the MCR, temperature increases of this magnitude would most likely be identified before the hourly monitoring requirement.
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TS 3.7.11, Required Action E.1 Maintaining MCR temperatures at or below 104°F will ensure that the safety-related functions are operable.
Since this proposed change maintains the CREATCS function for a limited period of time and supports plant safety functions, there is no adverse impact to nuclear safety.
The proposed change will allow both Units to continue power operation and not be subjected to an unnecessary shutdown when sufficient cooling is available to maintain an acceptable MCR environment.
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TS 3.7.11, Required Action E.1 The proposed delayed entry into LCO 3.0.3 would be used if the operable CREATCS train became inoperable unexpectedly. It is also proposed that the delayed entry into LCO 3.0.3 be used to support post modification testing.
Delayed entry into LCO 3.0.3 is needed to allow stabilization of the water and air flow from the modified CREATCS train during post modification testing. This impact is due to the automatic start signals from the modified train requiring the operable train to start inappropriately and repeatedly.
For example, during testing of the modified train, there may be cooling water flow and air flow anomalies that would signal the operable train to start unnecessarily This type of entry into TS 3.7.11, Condition E would only be used in direct support of post modification testing and only when the potential for anomalous water and/or air flow in the modified CREATCS train is possible.
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Summary of Compensatory Actions A temporary, non-safety related chiller system with a temporary DG to provide power to the temporary chiller system will be installed and operated as described.
Instructions for operation of the temporary cooling equipment will be provided.
During replacement of the CREATCS chillers, TVA will employ a graded approach to defense-in-depth and protected equipment strategies based on the operating status of the affected unit. The risk of the activity will be assessed and managed, including the use of physical barriers as needed.
Additionally, TVA procedures preclude work on or near protected equipment and limit access to the area to emergency situations and non-intrusive monitoring of running equipment per operator rounds.
During replacement of the CREATCS chillers, no elective maintenance will be performed on TS related support equipment for the Operable CREATCS chiller except for any required TS Surveillance Requirements.
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Precedent NRC license amendment for WBN Unit 1 dated February 8, 2011 (ML110190280)
NRC approved a 60-day extension to the TS 3.7.11, Required Action A.1 Completion Time NRC license amendment for Sequoyah Nuclear Plant, Units 1 and 2, dated May 21, 2004 (ML041460534)
NRC approved a 7-day extension to the 3.7.15.b Completion Time NRC license amendment for Surry Power Station, Unit Nos. 1 and 2 dated January 23, 2008 (ML0734800287)
NRC approved a 14 and 45-day extension to the Completion Time for one train of switchgear room air conditioning NRC license amendment for Seabrook Station, Unit No. 1 dated September 17, 1999 (ML011920184)
NRC approved a 60-day extension to the Completion Time for one train of control room air conditioning l 31
Schedule Milestones May 5, 2020 - LAR Pre-Submittal Meeting with NRC May 2020 - LAR Submittal - Request NRC approval within 12 months of submittal with 30-day implementation June 2020 - Telecon or meeting to discuss any NRC questions May 2021 - NRC Approval of LAR (Requested) l 32
Closing Remarks l 33