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| {{#Wiki_filter:Watts Bar Nuclear Plant Units 1 & 2 | | {{#Wiki_filter:Watts Bar Nuclear Plant Units 1 & 2 May 20, 2024 Pre-Submittal Meeting for 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 |
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| Pre-Submittal Meeting for Proposed License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF -276- A, Revision 2, Regarding TS 3.8.1 AC Sources -
| | Agenda System Design and Operation Existing Surveillance Requirements Technical Evaluation Regulatory Precedent 2 |
| Operating to Clarify Requirements for Diesel Generator Testing
| | License Amendment Schedule Proposed Changes to Technical Specification Introduction Reason for Proposed Change |
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| May 20, 2024 Agenda Introduction
| | Introduction |
| | * TVA is submitting a license amendment request (LAR) for Renewed Facility Operating License Nos. NPF-90 and NPF-96 for Watts Bar Nuclear Plant (WBN), Units 1 and 2 To revise Technical Specification (TS) 3.8.1, AC Sources - Operating Surveillance Requirements (SRs) |
| | Proposed revisions to SRs 3.8.1.9, 3.8.1.10, and 3.8.1.14 to eliminate the specification of kVAR and to specify a power factor of 0.9 during emergency diesel generator surveillance testing Proposed revisions to SR 3.8.1.18 to allow for the surveillance to be performed in Modes 1, 2, 3, or 4 to reestablish operability provided an assessment of plant safety is performed |
| | * Proposed changes are consistent with NUREG-1431, Standard Technical Specifications (STS), Westinghouse Plants, Revision 5, and TSTF-276-A, Revision 2, Revise DG full load rejection test l 3 |
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| System Design and Operation | | System Design and Operation |
| | | * The WBN Units 1 and 2 Alternating Current (AC) Electrical Power Distribution System AC sources consist of the offsite power sources (preferred power sources, normal, and alternate(s)), and the onsite standby power sources (Train A and Train B DGs). |
| Existing Surveillance Requirements
| | * As required by Title 10 of the Code of Federal Regulations (10 CFR) 50, Appendix A, General Design Criteria (GDC) 17, the design of the AC electrical power system provides independence and redundancy to ensure an available source of power to the Engineered Safety Feature (ESF) systems. |
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| Reason for Proposed Change
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| Proposed Changes to Technical Specification
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| Technical Evaluation
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| Regulatory Precedent
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| License Amendment Schedule
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| 2 Introduction
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| * TVA is submitting a license amendment request (LAR) for Renewed Facility Operating License Nos. NPF-90 and NPF -96 for Watts Bar Nuclear Plant (WBN), Units 1 and 2
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| * To revise Technical Specification (TS) 3.8.1, AC Sources - Operating Surveillance Requirements (SRs)
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| * Proposed revisions to SRs 3.8.1.9, 3.8.1.10, and 3.8.1.14 to eliminate the specification of k VA R and to specify a power factor of 0.9 during emergency diesel generator surveillance testing
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| * Proposed revisions to SR 3.8.1.18 to allow for the surveillance to be performed in Modes 1, 2, 3, or 4 to reestablish operability provided an assessment of plant safety is performed
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| * Proposed changes are consistent with NUREG-1431, Standard Technical Specifications (STS), Westinghouse Plants, Revision 5, and TSTF-276-A, Revision 2, Revise DG full load rejection test
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| l 3 System Design and Operation
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| * The WBN Units 1 and 2 Alternating Current (AC) Electrical Power Distribution System AC sources consist of the offsite power sources (preferred power sources, normal, and alternate(s)), and the onsite standby power sources (Train A and Train B DGs). | |
| * As required by Title 10 of the Code of Federal Regulations (10 CFR) 50, Appendix A, General Design Criteria (GDC) 17, the design of the AC electrical power system provides independence and redundancy to ensure an available source of power to the Engineered Safety Feature (ESF) systems. | |
| * In the event of a loss of preferred power, the 6.9 kV shutdown boards are automatically connected to the DGs in sufficient time to provide for safe reactor shutdown and to mitigate the consequences of a design basis accident (DBA) such as a Loss of Coolant Accident (LOCA). | | * In the event of a loss of preferred power, the 6.9 kV shutdown boards are automatically connected to the DGs in sufficient time to provide for safe reactor shutdown and to mitigate the consequences of a design basis accident (DBA) such as a Loss of Coolant Accident (LOCA). |
| * The onsite Class 1E AC Distribution System supplies electrical power to four power trains, shared between the two units, with each train powered by an independent Class 1E 6.9kV shutdown board. Each 6.9 kV shutdown board has two separate and independent offsite sources of power as well as a dedicated onsite DG source. | | * The onsite Class 1E AC Distribution System supplies electrical power to four power trains, shared between the two units, with each train powered by an independent Class 1E 6.9kV shutdown board. Each 6.9 kV shutdown board has two separate and independent offsite sources of power as well as a dedicated onsite DG source. |
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| l 4 System Design and Operation
| | System Design and Operation |
| * Additional DG capabilities must be demonstrated to meet required surveillances | | * Additional DG capabilities must be demonstrated to meet required surveillances SR 3.8.1.9 DG single largest load rejection test, SR 3.8.1.10 DG full load rejection test, and SR 3.8.1.14 DG endurance and margin test. These surveillances are performed with the DG synchronized with offsite power. When the DG is not synchronized with offsite power, the power factor is determined by plant load and cannot be adjusted. |
| * SR 3.8.1.9 DG single largest load rejection test, SR 3.8.1.10 DG full load rejection test, and SR 3.8.1.14 DG endurance and margin test. These surveillances are performed with the DG synchronized with offsite power. When the DG is not synchronized with offsite power, the power factor is determined by plant load and cannot be adjusted.
| | SR 3.8.1.18 demonstrates sufficient load sequence time delay exists for the DG to restore frequency and voltage prior to applying the next load block and that safety analysis assumptions regarding ESF equipment time delays are not violated. |
| * SR 3.8.1.18 demonstrates sufficient load sequence time delay exists for the DG to restore frequency and voltage prior to applying the next load block and that safety analysis assumptions regarding ESF equipment time delays are not violated.
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| l 5 Existing Surveillance Requirements
| | Existing Surveillance Requirements |
| * TS 3.8.1, AC Sources - Operating, SR 3.8.1.9, SR 3.8.1.10, and SR 3.8.1.14, state that when a DG is synchronized with offsite power for load rejection or endurance and margin testing, the SR shall be performed at a power factor of 0.8 and 0.9. | | * TS 3.8.1, AC Sources - Operating, SR 3.8.1.9, SR 3.8.1.10, and SR 3.8.1.14, state that when a DG is synchronized with offsite power for load rejection or endurance and margin testing, the SR shall be performed at a power factor of 0.8 and 0.9. |
| * SR 3.8.1.10 and SR 3.8.1.14 each have a required DG k VA R operating band during performance of the surveillance test. | | * SR 3.8.1.10 and SR 3.8.1.14 each have a required DG kVAR operating band during performance of the surveillance test. |
| * SR 3.8.1.10 band is 2970 k VA R and 3300 k VA R for the entire surveillance test
| | SR 3.8.1.10 band is 2970 kVAR and 3300 kVAR for the entire surveillance test SR 3.8.1.14 band is 3465 kVAR and 3630 kVAR for at least the first 2 hours and then 2970 kVAR and 3300 kVAR for the remainder of the surveillance test |
| * SR 3.8.1.14 band is 3465 k VA R and 3630 k VA R for at least the first 2 hours and then 2970 k VA R and 3300 k VA R for the remainder of the surveillance test
| | * Note for SR 3.8.1.18 states that this surveillance shall not be performed in Mode 1, 2, 3, or 4 and that credit may be taken for unplanned events that satisfy this SR. |
| * Note for SR 3.8.1.18 states that this surveillance shall not be performed in Mode 1, 2, 3, or 4 and that credit may be taken for unplanned events that satisfy this SR. | | l 6 |
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| l 6 Reason for Proposed Change
| | Reason for Proposed Change |
| * The k VA R requirements in the WBN Units 1 and 2 SRs 3.8.1.10 and 3.8.1.14 were added during the development of the initial Unit 1 TS | | * The kVAR requirements in the WBN Units 1 and 2 SRs 3.8.1.10 and 3.8.1.14 were added during the development of the initial Unit 1 TS kVAR requirements for DG surveillances have never been included in Standard TS There are no requirements pertaining to kVAR testing in Regulatory Guide 1.9 |
| * k VA R requirements for DG surveillances have never been included in Standard TS
| | * When a DG is synchronized with offsite power, a power factor of 0.9 is representative of the inductive loading the DG would experience under design basis accident conditions When the DG is not synchronized with offsite power, the power factor is determined by plant load and cannot be adjusted Under certain grid conditions, the specified power factor may not be achievable The proposed change allows the surveillances to be performed at a power factor as close as practicable to 0.9 l 7 |
| * There are no requirements pertaining to k VA R testing in Regulatory Guide 1.9
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| * When a DG is synchronized with offsite power, a power factor of 0.9 is representative of the inductive loading the DG would experience under design basis accident conditions | |
| * When the DG is not synchronized with offsite power, the power factor is determined by plant load and cannot be adjusted
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| * Under certain grid conditions, the specified power factor may not be achievable
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| * The proposed change allows the surveillances to be performed at a power factor as close as practicable to 0.9
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| l 7 Reason for Proposed Change
| | Reason for Proposed Change |
| * The proposed Note for SR 3.8.1.18 would allow performance of this the surveillance in Modes 1, 2, 3, or 4 to reestablish operability provided an assessment of plant safety is performed | | * The proposed Note for SR 3.8.1.18 would allow performance of this the surveillance in Modes 1, 2, 3, or 4 to reestablish operability provided an assessment of plant safety is performed Allows for flexibility in the performance of the surveillance with the appropriate considerations for the potential outcomes and transients associated with a failed surveillance, a successful surveillance, and a perturbation of the offsite or onsite system when they are tied together or operated independently for the surveillance; as well as the operator procedures available to cope with these outcomes. |
| * Allows for flexibility in the performance of the surveillance with the appropriate considerations for the potential outcomes and transients associated with a failed surveillance, a successful surveillance, and a perturbation of the offsite or onsite system when they are tied together or operated independently for the surveillance; as well as the operator procedures available to cope with these outcomes.
| | * The changes being proposed align the WBN Units 1 and 2 TS with TSTF-276-A, Revision 2, and the NUREG-1431, Revision 5, Standard TS relative to DG surveillance testing l 8 |
| * The changes being proposed align the WBN Units 1 and 2 TS with TSTF-276-A, Revision 2, and the NUREG-1431, Revision 5, Standard TS relative to DG surveillance testing | |
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| l 8 Proposed Changes to Technical Specification Watts Bar Unit 1 is provided and typical of Watts Bar Unit 2
| | 9 Proposed Changes to Technical Specification Watts Bar Unit 1 is provided and typical of Watts Bar Unit 2 |
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| 99 Proposed Change to Technical Specification Watts Bar Unit 1 is provided and typical of Watts Bar Unit 2
| | 10 10 Proposed Change to Technical Specification Watts Bar Unit 1 is provided and typical of Watts Bar Unit 2 |
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| 1010 Technical Evaluation
| | Technical Evaluation |
| * A power factor of 0.9 is normally achieved when performing this surveillance test while synchronized with offsite power | | * A power factor of 0.9 is normally achieved when performing this surveillance test while synchronized with offsite power |
| * When grid voltage is higher than typical, the additional field excitation current required to achieve a power factor 0.9 results in ESF bus voltage exceeding the maximum steady state voltage limit. | | * When grid voltage is higher than typical, the additional field excitation current required to achieve a power factor 0.9 results in ESF bus voltage exceeding the maximum steady state voltage limit. |
| * Increased grid voltage typically occurs when the plant is shutdown and the loads on the associated ESF transformer are too light to lower the voltage and achieve a 0.9 power factor.
| | Increased grid voltage typically occurs when the plant is shutdown and the loads on the associated ESF transformer are too light to lower the voltage and achieve a 0.9 power factor. |
| * Under these conditions, the power factor would be maintained as close as practicable to a 0.9 power factor while still maintaining acceptable voltage limits on the ESF busses.
| | Under these conditions, the power factor would be maintained as close as practicable to a 0.9 power factor while still maintaining acceptable voltage limits on the ESF busses. |
| * In other circumstances, the grid voltage may be such that the DG excitation levels needed to obtain a power factor of 0.9 may not cause unacceptable voltages on the emergency busses, but the excitation levels are greater than those recommended for the DG. | | * In other circumstances, the grid voltage may be such that the DG excitation levels needed to obtain a power factor of 0.9 may not cause unacceptable voltages on the emergency busses, but the excitation levels are greater than those recommended for the DG. |
| * In such cases, the power factor would be maintained as close as practicable to 0.9 without exceeding DG excitation limits.
| | In such cases, the power factor would be maintained as close as practicable to 0.9 without exceeding DG excitation limits. |
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| l 11 Technical Evaluation
| | Technical Evaluation |
| * To confirm that the proposed power factor of 0.9 represents a worst-case power factor for WBN Units 1 and 2, a review was performed of the calculated power factors for each DG during the limiting event of a loss of offsite power (LOOP) coincident with a LOCA. | | * To confirm that the proposed power factor of 0.9 represents a worst-case power factor for WBN Units 1 and 2, a review was performed of the calculated power factors for each DG during the limiting event of a loss of offsite power (LOOP) coincident with a LOCA. |
| * The kW and kVA values associated with the limiting LOOP with a LOCA event time confirm that application of a 0.9 power factor is appropriate for WBN.
| | The kW and kVA values associated with the limiting LOOP with a LOCA event time confirm that application of a 0.9 power factor is appropriate for WBN. |
| * The change to Note for SR 3.8.1.18 allows performance of this surveillance in Modes 1, 2, 3, or 4 to reestablish operability provided an assessment of plant safety is performed. | | * The change to Note for SR 3.8.1.18 allows performance of this surveillance in Modes 1, 2, 3, or 4 to reestablish operability provided an assessment of plant safety is performed. |
| * Measured against the avoided risk of a plant shutdown and startup to determine that plant safety is maintained or enhanced when the surveillance is performed in MODE 1, 2, 3, or 4.
| | Measured against the avoided risk of a plant shutdown and startup to determine that plant safety is maintained or enhanced when the surveillance is performed in MODE 1, 2, 3, or 4. |
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| l 12 Regulatory Precedent
| | Regulatory Precedent |
| * The following licensees have submitted similar license amendment requests which have been reviewed and approved by the NRC | | * The following licensees have submitted similar license amendment requests which have been reviewed and approved by the NRC Perry Unit 1 - ML23353A001 issued February 21, 2024 Wolf Creek - ML16081A194 issued April 15, 2016 Palo Verde - ML071060322 issued May 16, 2007 l 13 |
| * Perry Unit 1 - ML23353A001issued February 21, 2024
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| * Wolf Creek - ML16081A194 issued April 15, 2016
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| * Palo Verde - ML071060322 issued May 16, 2007
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| l 13 License Amendment Schedule | |
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| Pre-submittal Meeting with NRC May 20, 2024
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| Submit LAR to NRC June 28, 2024
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| Requested NRC Review and Approval June 2025
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| 14}} | | License Amendment Schedule 14 Pre-submittal Meeting with NRC May 20, 2024 Submit LAR to NRC June 28, 2024 Requested NRC Review and Approval June 2025}} |
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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:Meeting Notice
MONTHYEARPMNS20241383, 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
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
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
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
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
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
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
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
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
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
ML21096A1772021-04-0606 April 2021
Teleconference with Tennessee Valley Authority Regarding Watts Bar Nuclear Plant, Unit 1, Proposed Alternative Request
ML21083A0632021-03-24024 March 2021
Teleconference with Tennessee Valley Authority Regarding Watts Bar Nuclear Plant, Unit 1, Proposed Alternative Request
PMNS20210104, Meeting with Tennessee Valley Authority Regarding Planned License Amendment Request for Watts Bar Nuclear Plant, Unit 22021-02-0101 February 2021
Meeting with Tennessee Valley Authority Regarding Planned License Amendment Request for Watts Bar Nuclear Plant, Unit 2
ML21019A0152021-01-19019 January 2021
Teleconference with Tennessee Valley Authority Regarding Watts Bar Nuclear Plant, Unit 2, Planned Steam Generator License Amendment Requests
ML20349A3132020-12-14014 December 2020
Teleconference Call with Tennessee Valley Authority Regarding Planned License Amendment Requests Related to the Watts Bar Nuclear Plant, Unit 2 Steam Generator Replacement
ML20342A3592020-12-0707 December 2020
Teleconference Call with Tennessee Valley Authority Regarding Planned License Amendment Request for Watts Bar Nuclear Plant, Unit 2
ML20315A3992020-11-10010 November 2020
Teleconference Call with Tennessee Valley Authority Regarding Planned License Amendment Request for Watts Bar Nuclear Plant, Unit 2
ML20295A5382020-10-21021 October 2020
Teleconference Call with Tennessee Valley Authority Regarding a Non-Conservative Technical Specification for the Watts Bar Nuclear Plant
ML20279A2882020-10-0505 October 2020
Teleconference Call with Tennessee Valley Authority Regarding a Non-Conservative Technical Specification for the Watts Bar Nuclear Plant
ML20167A1202020-06-30030 June 2020
Public Meeting Notice - Notice of Predecisional Enforcement Conference (Pec) Between U.S. Nuclear Regulatory Commission (NRC) and Tennessee Valley Authority (TVA) (EA-20-006, EA-20-007)
2024-08-06
[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 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
2024-08-15
[Table view] |
Text
Watts Bar Nuclear Plant Units 1 & 2 May 20, 2024 Pre-Submittal Meeting for 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
Agenda System Design and Operation Existing Surveillance Requirements Technical Evaluation Regulatory Precedent 2
License Amendment Schedule Proposed Changes to Technical Specification Introduction Reason for Proposed Change
Introduction
Proposed revisions to SRs 3.8.1.9, 3.8.1.10, and 3.8.1.14 to eliminate the specification of kVAR and to specify a power factor of 0.9 during emergency diesel generator surveillance testing Proposed revisions to SR 3.8.1.18 to allow for the surveillance to be performed in Modes 1, 2, 3, or 4 to reestablish operability provided an assessment of plant safety is performed
- Proposed changes are consistent with NUREG-1431, Standard Technical Specifications (STS), Westinghouse Plants, Revision 5, and TSTF-276-A, Revision 2, Revise DG full load rejection test l 3
System Design and Operation
- The WBN Units 1 and 2 Alternating Current (AC) Electrical Power Distribution System AC sources consist of the offsite power sources (preferred power sources, normal, and alternate(s)), and the onsite standby power sources (Train A and Train B DGs).
- As required by Title 10 of the Code of Federal Regulations (10 CFR) 50, Appendix A, General Design Criteria (GDC) 17, the design of the AC electrical power system provides independence and redundancy to ensure an available source of power to the Engineered Safety Feature (ESF) systems.
- In the event of a loss of preferred power, the 6.9 kV shutdown boards are automatically connected to the DGs in sufficient time to provide for safe reactor shutdown and to mitigate the consequences of a design basis accident (DBA) such as a Loss of Coolant Accident (LOCA).
- The onsite Class 1E AC Distribution System supplies electrical power to four power trains, shared between the two units, with each train powered by an independent Class 1E 6.9kV shutdown board. Each 6.9 kV shutdown board has two separate and independent offsite sources of power as well as a dedicated onsite DG source.
l 4
System Design and Operation
- Additional DG capabilities must be demonstrated to meet required surveillances SR 3.8.1.9 DG single largest load rejection test, SR 3.8.1.10 DG full load rejection test, and SR 3.8.1.14 DG endurance and margin test. These surveillances are performed with the DG synchronized with offsite power. When the DG is not synchronized with offsite power, the power factor is determined by plant load and cannot be adjusted.
SR 3.8.1.18 demonstrates sufficient load sequence time delay exists for the DG to restore frequency and voltage prior to applying the next load block and that safety analysis assumptions regarding ESF equipment time delays are not violated.
l 5
Existing Surveillance Requirements
- SR 3.8.1.10 and SR 3.8.1.14 each have a required DG kVAR operating band during performance of the surveillance test.
SR 3.8.1.10 band is 2970 kVAR and 3300 kVAR for the entire surveillance test SR 3.8.1.14 band is 3465 kVAR and 3630 kVAR for at least the first 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and then 2970 kVAR and 3300 kVAR for the remainder of the surveillance test
- Note for SR 3.8.1.18 states that this surveillance shall not be performed in Mode 1, 2, 3, or 4 and that credit may be taken for unplanned events that satisfy this SR.
l 6
Reason for Proposed Change
- The kVAR requirements in the WBN Units 1 and 2 SRs 3.8.1.10 and 3.8.1.14 were added during the development of the initial Unit 1 TS kVAR requirements for DG surveillances have never been included in Standard TS There are no requirements pertaining to kVAR testing in Regulatory Guide 1.9
- When a DG is synchronized with offsite power, a power factor of 0.9 is representative of the inductive loading the DG would experience under design basis accident conditions When the DG is not synchronized with offsite power, the power factor is determined by plant load and cannot be adjusted Under certain grid conditions, the specified power factor may not be achievable The proposed change allows the surveillances to be performed at a power factor as close as practicable to 0.9 l 7
Reason for Proposed Change
- The proposed Note for SR 3.8.1.18 would allow performance of this the surveillance in Modes 1, 2, 3, or 4 to reestablish operability provided an assessment of plant safety is performed Allows for flexibility in the performance of the surveillance with the appropriate considerations for the potential outcomes and transients associated with a failed surveillance, a successful surveillance, and a perturbation of the offsite or onsite system when they are tied together or operated independently for the surveillance; as well as the operator procedures available to cope with these outcomes.
- The changes being proposed align the WBN Units 1 and 2 TS with TSTF-276-A, Revision 2, and the NUREG-1431, Revision 5, Standard TS relative to DG surveillance testing l 8
9 Proposed Changes to Technical Specification Watts Bar Unit 1 is provided and typical of Watts Bar Unit 2
10 10 Proposed Change to Technical Specification Watts Bar Unit 1 is provided and typical of Watts Bar Unit 2
Technical Evaluation
- A power factor of 0.9 is normally achieved when performing this surveillance test while synchronized with offsite power
- When grid voltage is higher than typical, the additional field excitation current required to achieve a power factor 0.9 results in ESF bus voltage exceeding the maximum steady state voltage limit.
Increased grid voltage typically occurs when the plant is shutdown and the loads on the associated ESF transformer are too light to lower the voltage and achieve a 0.9 power factor.
Under these conditions, the power factor would be maintained as close as practicable to a 0.9 power factor while still maintaining acceptable voltage limits on the ESF busses.
- In other circumstances, the grid voltage may be such that the DG excitation levels needed to obtain a power factor of 0.9 may not cause unacceptable voltages on the emergency busses, but the excitation levels are greater than those recommended for the DG.
In such cases, the power factor would be maintained as close as practicable to 0.9 without exceeding DG excitation limits.
l 11
Technical Evaluation
- To confirm that the proposed power factor of 0.9 represents a worst-case power factor for WBN Units 1 and 2, a review was performed of the calculated power factors for each DG during the limiting event of a loss of offsite power (LOOP) coincident with a LOCA.
The kW and kVA values associated with the limiting LOOP with a LOCA event time confirm that application of a 0.9 power factor is appropriate for WBN.
- The change to Note for SR 3.8.1.18 allows performance of this surveillance in Modes 1, 2, 3, or 4 to reestablish operability provided an assessment of plant safety is performed.
Measured against the avoided risk of a plant shutdown and startup to determine that plant safety is maintained or enhanced when the surveillance is performed in MODE 1, 2, 3, or 4.
l 12
Regulatory Precedent
- The following licensees have submitted similar license amendment requests which have been reviewed and approved by the NRC Perry Unit 1 - ML23353A001 issued February 21, 2024 Wolf Creek - ML16081A194 issued April 15, 2016 Palo Verde - ML071060322 issued May 16, 2007 l 13
License Amendment Schedule 14 Pre-submittal Meeting with NRC May 20, 2024 Submit LAR to NRC June 28, 2024 Requested NRC Review and Approval June 2025
