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Category:Meeting Briefing Package/Handouts
MONTHYEARML23291A1562023-10-18018 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) 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 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 ML19298A0042019-09-12012 September 2019 Presentation Slides for 9/12/19 Public Meeting 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 ML19161A2392019-06-10010 June 2019 Plants Pre-Submittal Meeting for Proposed License Amendments Hydrological Analysis Updates June 10, 2019 ML19142A3602019-05-21021 May 2019 May 9, 2019 Summary of Public Meeting; Watts Bar Nuclear Plant ML19018A0072019-01-18018 January 2019 (WBN)Pre-Submittal Meeting for Proposed License Amendment Request Regarding a One-Time Change for the WBN Unit 2 Technical Specification (TS) 3.7.8, Essential Raw Cooling Water (ERCW) System. ML18291A5732018-10-18018 October 2018 Chilled Work Environment ML18291A5632018-10-18018 October 2018 Chilled Worked Environment Update ML18248A1052018-09-0505 September 2018 Presentation Slides - Watts Bar Nuclear Plant Units 1 and 2 Adoption of TSTF-425 Initiative 5b - Surveillance Frequency Control Program - September 6, 2018 ML18248A1022018-09-0505 September 2018 Presentation Slides - Watts Bar Nuclear Plant (WBN) Pre-Submittal Meeting for Proposed License Amendment Request Regarding Shutdown Board Cleaning - September 6, 2018 ML18248A1012018-09-0505 September 2018 Bar Nuclear Plant (WBN) Pre-Submittal Meeting for Proposed License Amendment Adoption of TSTF-500 ML18248A1072018-09-0505 September 2018 Presentation Slides - Watts Bar Nuclear Plant Units 1 and 2 Adoption of 10 CFR 50.69 - September 6, 2018 ML18164A3192018-06-18018 June 2018 Presentation Material for 6/19/18 Pre-submittal Meeting ML18024A7932018-01-25025 January 2018 Presentation Slides - Watts Bar Nuclear Plant Unit 2 Pre-Submittal Meeting for Proposed License Amendment Request Regarding the Use of PAD4TCD in the Large Break Loss of Coolant Accident Analysis 2023-09-27
[Table view] Category:Slides and Viewgraphs
MONTHYEARML23291A1562023-10-18018 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 ML20009C3962020-01-0808 January 2020 Pre-Submittal Telecon for Expedited License Amendment Request to Revise Technical Specification 3.3.5, LOP DG Start Instrumentation 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 ML19252A0522019-09-0909 September 2019 TVA Presentation Slides: Watts Bar Nuclear Plant (WBN) Application to Modify WBN Unit 1 and Unit 2 Technical Specification (TS) 3.6.15, Shield Building - September 11, 2019 ML19235A2712019-08-23023 August 2019 2019 TVA Watts Bar Nuclear Plant Public Meeting Slides 08-27-2019 (TVA Slides) ML19197A0932019-07-16016 July 2019 Presentation Slides - Watts Bar Nuclear Plant (WBN) Unit 2, Pre-Submittal Meeting for License Amendment Request Measurement Uncertainty Recapture (Mur) Power Update 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 2023-09-27
[Table view] |
Text
Information Exchange WBN Seismic Hazard 1
Information Exchange WBN Seismic Hazard
- NRC May 9 Prioritization Letter
- Seismic Risk Evaluation
- WBN Acknowledges
- Seismic risk evaluation by June 30, 2017
- NRC May 21 Support Document
- Preliminary graphical representation
- NRC staff GMRS differs from Licensee GMRS 2
Information Exchange WBN Seismic Hazard EPRI Maximum:
0.77g @ 15 Hz NRC Maximum:
0.98 @ 30 Hz 3
Information Exchange WBN Seismic Hazard
- WBN understanding of the causes of the primary differences between the preliminary NRC and licensee results.
- Elements of NRC staff preliminary assessment
- FSAR primary source for information on subsurface materials
- narrower velocity profile
>> 4,500 fps lower
>> 6,500 fps upper
- Hard rock at 1,000 ft.
- Use of EPRI rock curves and low strain damping values
- Kappa Values and weights 4
Information Exchange WBN Seismic Hazard
- WBN additional data for subsurface materials
- Expand site geologic profile due to current understanding of hard rock characteristics - shear wave velocity > 9200 fps.
- Reduce uncertainty throughout profile to basement >
10,000 ft.
- Support Development of Seismic Hazard input for SPRA 5
Information Exchange WBN Seismic Hazard
- Utilized Academic/Industry Expertise
- AMEC - Program Management; regional / local geology
- Dr. Robert Hatcher, Professor of Geology, University of Tennessee -
Knoxville
>> Regional / local geology
- Dr. Ken Stokoe, Professor of Civil Engineering, University of Texas -
Austin
>> Spectra Analysis Surface Wave (SASW) Survey
>> Rock Testing
- Ivan Wong (URS) and
>> Seismic Hazard & Evaluation of SASW / Rock Testing
- Walt Silva (PE&A)
>> Site Modeling/Characterization
- Facility Risk Consultants
>> 3rd party seismic consultant review 6
Information Exchange WBN Seismic Hazard Source: AMEC (2013) 7
Information Exchange WBN Seismic Hazard 8
Information Exchange WBN Seismic Hazard 9
Information Exchange WBN Seismic Hazard 10
Information Exchange WBN Seismic Hazard
- SASW Survey (8 test sites)
- Sites 6 & 7 profiled depths of approx. 1400 and 1700
- SASW Team believes results from Site 8 would have been similar had sufficient lateral space been available for a longer survey line.
- Achieving profile depths of 14001700 is uncommonly good results for SASW survey!
- 6 Intact Rock Cores (URC freefree unconfined resonant column tests)
- Pumpkin Valley Shale (2), Consauga Middle, Pond Springs Formation, Nolichucky Shale, and Rome Formation 11
Information Exchange WBN Seismic Hazard Source: AMEC (2013) 12
Information Exchange WBN Seismic Hazard
- Benefits Derived from SASW Survey / Rock Testing
- Provided shearwave velocity data for important geologic formations beneath the site
- Captured the variability in shearwave velocity beneath the site
- Provided sitespecific measurements which reduced the epistemic uncertainty in the profiles (1.25 where appropriate)
- Demonstrates that assumptions of shearwave velocities from the type of rock would have been misleading. For example, it was surprising that the Rome sandstone was as fast as it was and the dolomite slower than was thought. No substitute for real data!
- SASW measurements were performed to a depth up to 1700 ft right next to the reactor, some of the deepest measurements taken in the central and eastern US.
13
Information Exchange WBN Seismic Hazard Base Case 600 Lower Bound 600 Upper Bound 592 Base Case 936 Lower Bound 936 Upper Bound 936 Figure 2.3.21 Shearwave velocity profiles for Watts Bar Nuclear Plant (EPRI, 2014) 14
Information Exchange WBN Seismic Hazard
- Development Of Total Effective Kappa
- Following SPID Guidelines For Firm Rock Profile <
3,000 ft Deep
- Total Effective Kappa Based on Firm Rock Damping of 1.25% (QS = 40)
- Plus Hard Rock Contribution 0.006s
- Uncertainty In Depth To Hard Rock Accommodated With Two Mean Depths 600 ft, 900 ft
- Results In Six Kappa Estimates For BaseCase, Upper Range, LowerRange Profiles and Two Depths to Hard Rock 15
Information Exchange WBN Seismic Hazard
- Epistemic Uncertainty In BaseCase VS Profiles Of 1.25 Results In Narrow Range Of Kappa
- Following SPID Guidelines, Epistemic Uncertainty In Kappa Taken as ln 0.4 About Mean Estimate
- Shallow Profile 0.012s +/- , range 0.007s to 0.020s
- Deep Profile 0.013s +/- , range 0.008s to 0.022s 16
Information Exchange WBN Seismic Hazard
- Watts Bar developed a significantly enhanced site geological profile to support site characterization
- Supplemented by SASW survey to provide additional clarity for strata above Top of Hard Rock
- Accounts for variation in the top of the Rome Formation underlying WBN
- Rock testing of 6 intact cores to determine parameters for site characterization
- Site characterization and EPRI GMRS performed in conformance with SPID and is appropriate characterization of seismic hazard for Watts Bar site.
17
Information Exchange SQN Seismic Hazard 1
Information Exchange SQN Seismic Hazard
- NRC May 9 Prioritization Letter
- Seismic Risk Evaluation
- SQN Acknowledges
- Seismic risk evaluation by December 31, 2019
- NRC May 21 Support Document
- Preliminary graphical representation
- NRC staff GMRS differs from Licensee GMRS 2
Information Exchange SQN Seismic Hazard EPRI Maximum SA:
0.76g @ 20 Hz NRC Maximum SA:
0.84g @ 40 Hz 3
Information Exchange SQN Seismic Hazard
- SQN understanding of the causes of the primary differences between the preliminary NRC and licensee results.
- Elements of NRC staff preliminary assessment
- Use of EPRI rock curves and low strain damping values
- Kappa Values and weights 4
Information Exchange SQN Seismic Hazard
- SQN additional data for subsurface materials
- Expand site geologic profile due to current understanding of hard rock characteristics - shear wave velocity > 9200 fps.
- FSAR had limited rock characteristics data available at depth (> 103 ft)
- Definition of rock profile to basement 12,000 ft.
Information Exchange SQN Seismic Hazard
- Utilized Academic/Industry Expertise
- AMEC - Program Management; regional / local geology
- Dr. Robert Hatcher, Professor of Geology, University of Tennessee
- Knoxville
>> Regional / local geology
- Dr. Ken Stokoe, Professor of Civil Engineering, University of Texas
- Austin
>> Spectra Analysis Surface Wave (SASW) Survey @ WBN
>> Rock Testing
- Ivan Wong (URS)
>> Site Modeling/Characterization 6
Information Exchange SQN Seismic Hazard Source: AMEC (2013) 7
Information Exchange SQN Seismic Hazard Vs profiles for Sequoyah Site Vs (ft/sec) 0 1000 2000 3000 4000 5000 6000 7000 8000 9000 10000 0
500 1000 1500 2000 Base Case Profile 1 2500 Profile 2 Lower Bound Depth (ft) 3000 3500 Profile 3 Upper Bound 4000 4500 5000 5500 6000 6500 Figure 2.3.21 Shearwave velocity profiles for Sequoyah Nuclear Plant (EPRI, 2014) 8
Information Exchange SQN Seismic Hazard
- Development of Total Effective Kappa
- Following SPID Guidelines For Firm Rock Profile > 3,000 ft Deep
- Total Effective Kappa Based on Avg. VS over Top 100 ft, Surface Outcrop
- P1 6,000 ft/s, 0.012s
- P2 3,821 ft/s, 0.020s
- P3 9,285 ft/s, 0.006s Hard Rock
- Likely Conservative (low), 0 to 40 ft Soil, No Weathered Zone
- Range 0.006s to 0.020s Considered Sufficient Expression Of Epistemic Uncertainty 9
Information Exchange SQN Seismic Hazard
- Sequoyah developed an enhanced site geological profile
- Supplemented by regional geology maps, industry experts, and nearby SASW surveys
- EPRI GMRS and site characterization performed in conformance with SPID and is appropriate characterization of seismic hazard for Sequoyah site.
10
Information Exchange BFN Seismic Hazard 11
Information Exchange BFN Seismic Hazard
- NRC May 9 Prioritization Letter
- Seismic Risk Evaluation
- NRC May 21 Support Document
- Preliminary graphical representation
- NRC staff GMRS differs from Licensee GMRS 12
Information Exchange BFN Seismic Hazard Licensee Maximum SA:
0.58g @ 25 Hz NRC Maximum SA:
0.68g @ 40 Hz 13
Information Exchange BFN Seismic Hazard
- BFN understanding of the causes of the primary differences between the preliminary NRC and licensee results.
- Elements of NRC staff preliminary assessment
- Narrower velocity profile
- 7,000 fps lower bound
- 9,285 fps upper bound (hard rock)
- Use of EPRI rock curves and low strain damping values
- Kappa Values and weights 14
Information Exchange BFN Seismic Hazard
- BFN additional data for subsurface materials
- Expand site geologic profile due to current understanding of hard rock characteristics - shear wave velocity > 9200 fps.
- FSAR had limited rock characteristics data available at depth (> 200 ft)
- Definition of rock profile to basement 5,000 ft.
Information Exchange BFN Seismic Hazard
- Utilized Academic/Industry Expertise
- AMEC - Program Management; regional / local geology
- Dr. Robert Hatcher, Professor of Geology, University of Tennessee
- Knoxville
>> Regional / local geology
- Dr. Ken Stokoe, Professor of Civil Engineering, University of Texas
- Austin
>> Spectra Analysis Surface Wave (SASW) Survey @ WBN
>> Rock Testing
- Ivan Wong (URS)
>> Site Modeling/Characterization 16
Information Exchange BFN Seismic Hazard Source: AMEC (2013) 17
Information Exchange BFN Seismic Hazard Vs profiles for Browns Ferry Site Base Case Lower Bound Upper Bound Figure 2.3.21 Shearwave velocity profiles for Browns Ferry Nuclear Plant (EPRI, 2014) 18
Information Exchange BFN Seismic Hazard
- Development of Total Effective Kappa
- Following SPID Guidelines For Firm Rock Profile > 3,000 ft Deep
- Total Effective Kappa Based on Avg. Vs Over Top 100 ft, surface outcrop
- Profiles P1, P3 Hard Rock Near Surface, = 0.006s
- Profile P2 Vs(100 ft) 5,914 ft/s, = 0.012s
- Likely Conservative (low), 0 to 50 ft Soil, No Weathered Zone
- Range 0.006s to 0.012s Considered Sufficient Expression of Epistemic Uncertainty 19
Information Exchange BFN Seismic Hazard
- Browns Ferry developed an enhanced site geological profile
- Supplemented by regional geology maps and industry experts
- EPRI GMRS and site characterization performed in conformance with SPID and is appropriate characterization of seismic hazard for Browns Ferry site.
20
BFN Seismic Risk Evaluation Screening Results 21
- BFN understands the IPEEE evaluation did not meet NRC staffs expectation for screening purposes
- Prerequisite #3
- Adequacy Demonstration #3
- BFN adequacy review acknowledged the SER identified weakness and provided justification for addressing the weakness as part of the ESEP
- BFN has subsequently completed seismic capacity evaluations for the additional RCIC components
- Minimum HCLPF > 0.50g
Information Exchange BFN Seismic Hazard
- BFN reevaluated minimum HCLPF SSC (Auxiliary Diesel Generator Transformers)
- HCLPF > 0.30g in current configuration and replacement configuration
- BFN commitment to complete transformer replacement by Sept 30, 2014 to resolve PCB/IPEEE screening capacity
- TVA requests that the NRC staff reconsider the May 9, 2014 screening result that BFN screens in for seismic risk evaluation