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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 August 19, 2021 Watts Bar Nuclear Plant (WBN)
Pre-Submittal Meeting for Proposed License Amendment Request Regarding Application to Modify Watts Bar Nuclear Plant Units 1 and 2 Technical Specifications (TS) 3.7.8, Essential Raw Cooling Water (ERCW) System, to Support Permanent Shutdown Board Cleaning
Agenda
- Overview of the 6.9 kilovolt (kV) Shutdown Board (SDBD)
Maintenance Activities
Opening Remarks
- This license amendment request (LAR) proposes a permanent extension of the WBN Units 1 and 2 Technical Specification (TS) 3.7.8 Essential Raw Cooling Water (ERCW) System completion time from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 7 days to perform scheduled maintenance activities on a 6.9kV SDBD and associated 480V boards and motor control centers (MCC) when a WBN unit is in a outage and is defueled.
- Due to the commonality of the WBN 6.9kV SDBD loads, performing maintenance on a 6.9kV SDBD during a WBN refueling outage affects the ERCW system on the operating unit.
- With regard to the ERCW system currently, WBN TS require two ERCW pumps aligned to separate 6.9kV SDBDs to be operable per train, with two trains required for each unit.
Consequently, this requires all four 6.9 kV SDBDs to be operable to support the ERCW pump TS requirement.
- This change is needed to support the shutdown board cleaning planned for the WBN Unit 1 Cycle 18 refueling outage (U1R18) scheduled for spring 2023.
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Background===
- WBN Unit 2 License Amendment 35 dated February 24, 2020 (ML20024F835),
revised WBN Unit 2, Technical Specification 3.7.8 to extend the allowed Completion Time to restore one ERCW System train to operable status from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to seven days, on a one-time basis.
- The revision to WBN Unit 2 TS 3.7.8 was contingent on the following:
Only applicable during the Unit 1 spring 2020 outage but no later than May 31, 2020.
Only applicable when Unit 1 is defueled.
Only applicable during planned maintenance on 6.9 kV SDBD 1 A-A and associated 480 V boards and MCC.
UHS Temperature of 71°F.
- Similar changes are needed to the Unit 1 and 2 TS 3.7.8 to support future and ongoing maintenance of the 6.9 kV SDBDs and associated 480 V boards and MCCs for both units.
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System Overview
- The ERCW System is a common two-train system with each train having the capability to provide the required cooling water for both units under any credible plant condition.
- These ERCW System trains are independent and redundant.
- Each train of the ERCW system has four pumps total. As noted in the bases of WBN TS 3.7.8, for operating modes 1-4, two ERCW pumps aligned to separate 6.9kV SDBDs are required to be operable per train, with two trains required for each unit.
- The ERCW system has been analyzed for "worst case" heat loads under combinations of maximum river water temperature, design basis accident conditions, normal cooldown requirements, power train failures, for both units.
- The ERCW system has sufficient pump capacity for cooling water flows under all conditions and the system is arranged in such a way that even a complete header loss can be isolated in a manner that does not jeopardize plant safety.
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System Overview (contd) l 6
System Overview (contd) l 7 ERCW Pump Motor Electrical Board Alignment
Overview of 6.9kV SDBD Maintenance
- Maintenance activities performed during a 6.9kV SDBD board outage include:
Breaker compartment inspections Indicating light resistor replacements Fuse blocks Relays and instruments
Circuit breaker interface inspections and adjustments Primary/Secondary disconnects Shutter inspection Breaker position and interface measurements and adjustments
Bus inspections and tests As-found and as-left insulation resistance (megger) testing Torque checks l 8
Overview of 6.9kV SDBD Maintenance (contd) l 9 Shutdown Board Maintenance Timeline Activity Duration 1
Install Clearance 6 Hours 2
Ground Installation 4.5 Hours 3
Breaker Compartment Inspections 42 Hours 4
Circuit Breaker Interface Inspections and Adjustments 34 Hours 5
Bus Inspections and Tests 8 Hours 6
Ground Removal 4.5 Hours 7
Release Clearance 6 Hours Total 105 Hours 105 Hours are needed to support the SDBD board outage activities.
Remaining duration of the TS change allows for a contingency should the maintenance activities identify the need for an unexpected repair.
Proposed Technical Specification Changes for WBN Unit 2 l 10 TS 3.7.8 Condition A is modified as follows:
> Delete current Note 1 which states: Only applicable during the Unit 1 spring 2020 outage (U1R16), but no later than May 31, 2020.
> Note 2 is re-sequenced to Note 1: Only applicable when Unit 1 is defueled.
> Note 3 is re-sequenced as Note 2 and is revised to state: Only applicable during planned maintenance of a Unit 1 6.9kV SDBD and the associated 480V boards and motor control centers.
> Revise the UHS temperature in the Completion Time for Required Action A.1 and for Required Action A.2 from 71ºF to 78ºF.
> Minor correction to Condition C to note that it applies to all of Condition A.
Proposed Technical Specification Changes for WBN Unit 2 l 11
l 12 Proposed Technical Specification Changes for WBN Unit 2
Proposed Technical Specification Changes for WBN Unit 1 l 13 Similar to the changes to the WBN Unit 2 TS New WBN Unit 1 TS 3.7.8 Condition A to increase the completion time for an inoperable ERCW Train from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 7 days with the following Notes:
- 1. Only applicable when WBN 2 unit is defueled.
- 2. Only applicable during planned maintenance of a Unit 2 6.9kV SDBD and the associated 480V boards and MCC.
Both Notes are required to be met in order to use Condition A.
The Required Actions and Completion Times of WBN Unit 1 TS 3.7.8 Condition A are modified to be consistent with the WBN Unit 2 TS.
WBN Unit 1 TS 3.7.8 Conditions B and C are modified identical to the WBN Unit 2 TS changes.
Proposed Technical Specification Changes for WBN Unit 1 l 14
Proposed Technical Specification Changes for WBN Unit 1 l 15
Proposed WBN UFSAR Change (for NRC Information Only)
WBN UFSAR Section 9.2.1.3 will be revised to reflect the new ERCW system alignments needed to support SDBD maintenance (as indicated in the revised TS 3.7.8 Bases) l 16
Proposed WBN UFSAR Change (for NRC Information Only)
WBN UFSAR Section 9.2.1.3 will be revised to reflect the new ERCW system alignments needed to support SDBD maintenance (as indicated in the revised TS 3.7.8 Bases) l 17
Basis for Proposed TS Changes l 18
- TVA employs a graded approach to defense in depth (DID) and protected equipment strategies when equipment is removed from service NPG-SPP-07.0 Work Management This program incorporates risk assessment methodologies and contingency processes to maximize personnel safety, plant safety, plant reliability, and worker productivity during plant modifications, maintenance, and testing.
Includes both Online Work Management and Outage Management NPG-SPP-07.1 On Line Work Management provides the guidance for the implementing work management process that promotes personnel/nuclear safety, access plant risk, maximize plant reliability, and improve schedule credibility/stability.
NPG-SPP-07.2 Outage Management provides guidance for the development and risk assessment of the outage schedule NPG-SPP-07.3.4 Protected Equipment Provides guidance for protecting plant equipment in order to minimize the potential for adverse operational events.
Basis for Proposed Change (contd) l 19
Engineering analyses have been performed with a single ERCW pump powered from the 6.9kV SDBD in operation under the following bases:
Design basis accident on the WBN operating unit Loss of offsite power WBN Unit in a outage with 100 hour0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> limit prior to irradiated fuel movement (WBN TS 3.9.10)
WBN outage unit is defueled Unnecessary ERCW cooling loads isolated on the WBN outage Unit.
A 6.9kV SDBD and associated 480V boards are out of service The ERCW train not impacted by the maintenance activities assumed failed UHS temperature of 78°F Each SDBD outage scenario is evaluated This analyses conclude that a single ERCW pump powered from the available 6.9kV SDBD can supply sufficient heat removal, while maintaining the outlet piping thermal stress temperature limits
Technical Evaluation
- Hydraulic Proto-Flo model is used for the ERCW analyses Proto-Flo model was modified to reflect the ERCW one pump configuration powered from the available 6.9kV SDBD Reconfigured flow rates were compared to the analyzed flow rates for required equipment For components where flow rates are less than analyzed; ERCW temperature versus ERCW flow curves were developed to determine the maximum allowable temperature for the one pump ERCW operation.
o PROTO-HX was used to determine the ERCW temperature required for available flow rate for heat exchangers and discharge piping temperature limits o
Heat transfer analyses were used for the shutdown board room and electric board room chiller performance The UHS temperature of 78°F ensures the required ERCW loads have sufficient cooling, while maintaining the outlet piping thermal stress temperature limits.
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Technical Evaluation (contd) l 21
- Conservatism in the analyses include ERCW minimum pump performance curve by specifying a lower bounding head versus flow curve relative to the vendor pump curves.
Predicted flow rates for a single ERCW pump performance are reduced by 5% in the ERCW hydraulic analyses to account for analysis uncertainties 100 gallon per minute (gpm) system leakage loss is assumed in the analyses. This accounts for any unidentified system leakage which is in excess of typical system leakage under normal operating conditions.
- Hardware change supporting/credited in the ERCW analyses To improve ERCW flow margin, the component cooling system (CCS) train B heat exchanger post accident flow control valve will being replaced and relocated to improve flow balance between the two ERCW discharge headers This new valve installation is scheduled for implementation in U1R17 (Fall 2021)
Technical Evaluation (contd) l 22 A review of the past six years of plant data has shown that the ERCW spring and fall seasonal maximum temperatures remain below the proposed limit of 78ºF.
Technical Evaluation (contd) l 23 Further review of the histogram for WBN spring outage timeframes show the spring seasonal temperature history relative to the proposed SDBD cleaning maximum ERCW temperature analytical limit of 78°F. Spring outages are typically in the March to May timeframe
Technical Evaluation (contd) l 24 Further review of the histogram for WBN fall outage timeframes show the fall seasonal temperature history relative to the proposed SDBD cleaning ERCW temperature limit of 78°F.
Fall outages typically begin in the late September-early October timeframe
Precedent
- As previously noted, this LAR is similar in nature to the NRC-approved one-time revision to WBN Unit 2, TS 3.7.8 to extend the allowed Completion Time to restore one ERCW System train to operable status from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to seven days to support maintenance on the WBN Unit 1 6.9 kV SDBD 1A-A and associated 480 V boards and MCCs (ML20024F835).
- The proposed LAR is also consistent with the license amendment approved by the NRC for the Sequoyah Nuclear Plant (SQN), that also made a change to TS 3.7.8 for SQN Units 1 and 2 (ML16225A276), which added a new Condition A to TS 3.7.8 with a completion time of seven days and a limiting UHS temperature of 79°F.
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Schedule Milestones
- September 30, 2021 - LAR Submittal - Request NRC approval within 12 months of submittal with 30-day implementation
- September 30, 2022 - NRC Approval of LAR (Requested)
- WBN Unit 1 Cycle 18 refueling outage (U1R18) scheduled for spring 2023 l 26
Closing Remarks Proposed WBN TS change is needed to support scheduled maintenance activities of the 6.9kV SDBDs during refueling outages at WBN.
Due to the commonality of the 6.9kV SDBDs, performing maintenance on a 6.9kV SDBD during a WBN Unit refueling outage affects operability of the ERCW system for the operating WBN Unit.
The change will extend the WBN TS 3.7.8 completion time from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 7 days to support maintenance activities on a SDBD when the other WBN Unit is in operation provided UHS temperature is 78°F.
This change is needed to support the U1R18 outage scheduled for Spring 2023.
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