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Category:Slides and Viewgraphs
MONTHYEARML24312A1432024-11-0707 November 2024 SDP for Nextera RUG Meeting - 11.7.2024 - Rev. 0 ML24312A0532024-11-0707 November 2024 FLEX HP Pump 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 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 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 Tva'S 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 ML20112F5302020-04-21021 April 2020 TVA Nuclear Plants -2019 EOC Media Loop Slides for Automatic Play (Final) ML20049G1822020-02-18018 February 2020 February 20, 2020 - Pre-submittal Meeting Presentation - Transition to Westinghouse Fuel 2024-08-15
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Ice Condenser Ice Condenser Purpose Ice Condenser Overview TS Surveillances - Proposed Change History - Basis for Change Questions 2
Ice Condenser Overview Passive Heat Removal System Contains at least 2,750,700 lbs of ice Two main regions Ice Bed and Upper Plenum Ice bed separated from containment by lower inlet doors Ice bed separated from upper plenum by intermediate deck doors Upper plenum separated from containment by top deck doors 3
Ice Condenser Overview (Cont.)
4
Ice Condenser Overview (Cont.)
5
Ice Condenser Overview (Cont.)
Lower Door Turning Vanes 6
Ice Condenser TS Surveillances Three Lower Inlet Door Surveillances (3.6.12.3, 4, & 5) 3.6.12.3 - Visually inspect each door 3.6.12.4 - Torque to begin to open door 3.6.12.5 - Torque to open & close door Frequency Once per 3 months in first year Once per 18 months 7
Ice Condenser TS Surveillances (Cont.)
Proposed change allows first cycle operation until the end of the cycle aligned with the power ascension program Approximately 10 month long cycle Surveillance changes SR 3.6.12.3 Verify, by visual inspection, each inlet Twice during door is not impaired by ice, frost, or the first cycle debris. after receipt of the license AND 18 months 8
Ice Condenser TS Surveillances (Cont.)
Surveillance changes (cont.)
SR 3.6.12.4 Verify torque required to cause each Twice during inlet door to begin to open is 675 in-lb. the first cycle after receipt of the license AND 18 months SR 3.6.12.5 Perform a torque test on a sampling of Twice during 50% of the inlet doors. the first cycle after receipt of the license AND 18 months 9
Ice Condenser Basis For Change Basis for Change Doors simple & highly reliable Nine Ice Condenser Units with 20 to +30 years of operation Operating experience shows very few failures First cycle failures SR 3.6.12.3 - None SR 3.6.12.4 - 2 (1975 & 1978)
SR 3.6.12.5 - 1 (1996)
Prevents an otherwise unnecessary plant shutdown Three month Specification frequency was used to establish an operating history for new plant type design 10
Summary Revise Frequency for Surveillances 3.6.12.3, 4, & 5 Doors simple and highly reliable Supported by many years of operating experience Prevents an unnecessary plant shutdown 11
Ice Condenser Questions 12
Ice Condenser Ice Condenser Purpose Ice Condenser Overview TS Surveillances - Proposed Change History - Basis for Change Questions 2
Ice Condenser Overview Passive Heat Removal System Contains at least 2,750,700 lbs of ice Two main regions Ice Bed and Upper Plenum Ice bed separated from containment by lower inlet doors Ice bed separated from upper plenum by intermediate deck doors Upper plenum separated from containment by top deck doors 3
Ice Condenser Overview (Cont.)
4
Ice Condenser Overview (Cont.)
5
Ice Condenser Overview (Cont.)
Lower Door Turning Vanes 6
Ice Condenser TS Surveillances Three Lower Inlet Door Surveillances (3.6.12.3, 4, & 5) 3.6.12.3 - Visually inspect each door 3.6.12.4 - Torque to begin to open door 3.6.12.5 - Torque to open & close door Frequency Once per 3 months in first year Once per 18 months 7
Ice Condenser TS Surveillances (Cont.)
Proposed change allows first cycle operation until the end of the cycle aligned with the power ascension program Approximately 10 month long cycle Surveillance changes SR 3.6.12.3 Verify, by visual inspection, each inlet Twice during door is not impaired by ice, frost, or the first cycle debris. after receipt of the license AND 18 months 8
Ice Condenser TS Surveillances (Cont.)
Surveillance changes (cont.)
SR 3.6.12.4 Verify torque required to cause each Twice during inlet door to begin to open is 675 in-lb. the first cycle after receipt of the license AND 18 months SR 3.6.12.5 Perform a torque test on a sampling of Twice during 50% of the inlet doors. the first cycle after receipt of the license AND 18 months 9
Ice Condenser Basis For Change Basis for Change Doors simple & highly reliable Nine Ice Condenser Units with 20 to +30 years of operation Operating experience shows very few failures First cycle failures SR 3.6.12.3 - None SR 3.6.12.4 - 2 (1975 & 1978)
SR 3.6.12.5 - 1 (1996)
Prevents an otherwise unnecessary plant shutdown Three month Specification frequency was used to establish an operating history for new plant type design 10
Summary Revise Frequency for Surveillances 3.6.12.3, 4, & 5 Doors simple and highly reliable Supported by many years of operating experience Prevents an unnecessary plant shutdown 11
Ice Condenser Questions 12