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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
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NearTermTaskForce Near-Term Task Force Recommendation 2.1 Seismic Hazard Evaluation EvaluationTennesseeValley Authority Tennessee Valley Authority July 1, 2014 References for Meeting*Licensee Presentation Slides -ML14182A099*NRC Presentation Slides -ML14182A103PbliMtiAd ML14167A164
- P u bli c M ee ti ng A gen d a -ML14167A164*Meeting Feedback Form (request from mfb@nrc.gov)
- May 9, 2014, NRC letter regarding Seismic Screening dPiititiRltftldtUS an d P r i or iti za ti on R esu lt s for cen t ra l an d eas t ern US Licensees(ML14111A147)*May 21, 2014, NRC memo providing preliminary staff groundmotionresponsespectraforcentraland ground motion response spectra for central and eastern Licensees(ML14136A126)*Meeting Summary to be issued within 30-day Meeting Introduction Purpose: support information exchange and begin dialog to havecommonunderstandingofthecausesoftheprimary have common understanding of the causes of the primary differences between the preliminary NRC and licensee
seismic hazard resultsBkdNRCdliiihdi B ac k groun d: NRC an d licensee se i sm i c h azar d requ i re resolution to support a final seismic screening decision and to support related follow-on submittals Outcomes: *Begin NRC and licensee resolution to support regulatory decisionsanddevelopmentofseismicriskevaluations decisions and development of seismic risk evaluations , as appropriate*Establish resolution path, including timelines and identificationofpotentialinformationneeds identification of potential information needs Look-ahead:
Potential Next Steps
- NRCwillconsiderthemeetinginformation NRC will consider the meeting information*Potential paths:
-Licenseesubmitssupplementalinformation Licensee submits supplemental information based on public meeting dialog
-NRC staff issues a re q uest for information q-Licensee sends a revision or supplement to the seismic hazard report*NRC completes screening review and issues the final screening determination ltt l e tt e r WattsBarNuclearPlant Watts Bar Nuclear Plant Rasool Anooshehpoor Office of ResearchJuly1,2014 July 1, 2014
Screening Gl G eo l ogy*The site is located in the Tennessee section of Valley andRidgeProvinceoftheAppalachianhighlands and Ridge Province of the Appalachian highlands.*In Tennessee, the Rome Formation and Conasauga, Knox and Chickamugagroups make up the majority of bdk b e d roc k.*Sedimentary rocks from Pennsylvanian to Cambrian a g e, predominant with those of Cambrian and gp Ordovician age.*Folds involving stratified Paleozoic rocks with great differencesinhardnessdifferences in hardness.*At Watts Bar the bedrock is 2000ft thick Middle Cambrian ConasaugaGroup (alternating shale and limestone) limestone)
.
Site Geology
~706 ft Control Point at 664 ft Control Point NRC Submittal SSE Control Point at elevation 664 ft.
SSE Control Point at elevation 664 ft.
V s Profile Development NRCCtilitt SubmittalShlitibd C on tinuous ve l oc it y measuremen t s at 7 boreholes in FSAR at the top 100 ftwere used to develop the V s p rofile. Shear wave ve l oc ities were b ase d on SASW and Birdwell velocity measurements (AMEC, 2013).
p V median=5704 ft/s, ln=0.134Thisisingeneralagreementwith This is in general agreement with the General Atomics (1974)
estimates.
Figure 2.5-70, FSAR (reproduced)
Shear wave velocity data from seven boreholes (FSAR)
V s Profiles Aleatory Uncertainty in V s Profiles NRC Submittal NRC30 Randomizations Using USGS "A" Site Conditions Submittal30 Randomizations Using USGS "A" Site Conditions ln= 0.25 Upper 50 ft.ln=0.15Below50ft.ln= 0.25 Upper 50 ft.ln=0.15Below50ft.ln 0.15 Below 50 ft.ln 0.15 Below 50 ft.
Epistemic Uncertainty in V s ProfilesNRCSubmittalApplied a scale factors of 1.14 to the base case profile at the Applied a scale factor of 1.25 to the base case p rofile for ptop 100 ft, and 1.31 from 100 ft to 1000 ft(Reference rock) pdevelopment of the upper and lower case profiles Watts Bar ComparisonSSE Control PointDe pth to VS-referenceNon-Linear/Dam p in g p pgLicenseeNRC StaffLicenseeNRC StaffLicenseeNRC StaffAt the base of the reactor foundationAt the base of
the reactor foundation1)592 ft 2)936 ft~1000 ftEPRI-Rock or Linear (low-strain EPRI-Linear, no damping foundation (el. 664 ft) foundation (el. 664 ft) strain EPRI Rock damping)NRCkappa,withonelayer(1000 ft)overref.rock Licensee kappa ProfilekappaBase0.0070.0100.016 Lower 0.0070.011 0.018 NRC kappa, with one layer (1000 ft) over ref. rock ProfileTotal kappa Upper500ft Balanc e P10.0120.0050.0065 Lower 0.0070.011 0.018Upper0.0060.0100.016 P20.012*1.680.0070.0144 P30.012/1.680.0040.0060 P40.0130.0050.0083 P50013*168000700168 P5 0.013*1.68 0.007 0.0168 P60.013/1.680.0040.0060Epistemic Uncertainty = 1.68
Primary DifferencesVelocity profiles:TVA used two sets of 3-velocity profiles. The reference rock depthisat592 ftinonecaseand936 ftintheother depth is at 592 ft in one case and 936 ft in the other.NRC used three velocity profiles and depth of 1000 ftto reference rock.Low strain damping: TVAused~3%dampingintheupper500ft.NRCusedkappa TVA used 3% damping in the upper 500 ft. NRC used kappa in the upper 1000ft to account for dampingTVA used a factor of 1.68 about P1 and P4 total kappasto accountforepistemicuncertainty.
account for epistemic uncertainty.
NRC calculated kappa for each of three profiles separately.
Epistemic Uncertainty in Shear Modulus and Damping Sensitivity Test Curves NRC Submittal M1EPRI Rock: 0 -500 ft M1EPRI Rock: 0 -500 ft M2 Linear &EPRI Rock Damping (~3%): 0 -500 ft M2Linear&EPRI Rock Damping (~3%): 0 -500 ftReference Rock at 1000 ftbelow control point. Reference Rock at 592 ftand 936 ftbelow control point for P1 and P4 fil Depth Randomization, ln=0.2 pro fil es.Depth Randomization, ln=0.2 Kappa and Epistemic Uncertainty NRCKappawascalculatedforeachbasecase SubmittalKappacalculatedforvelocityprofilesP1P2 Kappa was calculated for each base case profile.Kappa calculated for velocity profiles P1 , P2 , P3, P4, P5, and P6. Range of these kappas do not reflect epistemic uncertainty.
Profile kappaProfilekappa kappa (modified)
P10.0120.012 P2 0.013 0.020 (0.012 x1.68
)Profile kappa BaseCase 0.014 LBC 0.015 ()P30.011 0.007(0.012 ÷1.68)
P40.0130.013 P5 0.015 0.022(0.013 x1.68)
UBC 0.012 P6 0.012 0.008(0.013 ÷1.67)
AlifitiFti A mp lifi ca ti on F unc ti onsRock PGA = 0.3 g Comparison of Total Mean Soil Hazard by Spectral Frequency GMRS Comparison Primary Differences in Sensitivity TestVelocity profiles:TVA used two sets of 3-velocity profiles. The reference rock depthisat592 ftinonecaseand936 ftintheother depth is at 592 ft in one case and 936 ft in the other.NRC used three velocity profiles and depth of 1000 ftto reference rock.Low strain damping: BothTVAandNRCused
~3%dampingintheupper500ft.
Both TVA and NRC used 3% damping in the upper 500 ft. TVA used a factor of 1.68 about P1 and P4 total kappasto account for epistemic uncertainty. NRCcalculatedkappaforeachofthreeprofilesseparatelyNRC calculated kappa for each of three profiles separately.
Conclusions*GMRS are simila r*Watts Bar screens in for risk evaluation*Control Point hazard curves similar at 10 HzandPGA,differat1Hz Hz and PGA, differ at 1 Hz-Due to different assumptions of depth to bedrock *Need additional information to support licenseeassumptionfordepthtobedrock licensee assumption for depth to bedrock Browns Ferry Nuclear Power PlantiliIPEEE Screen ing Eva luat i on W ea kn esses i de n t ifi ed in IPEEE S ER/TEReaessesdetedS/
- Only low power injection systems selected
-Did not include hi g h pressure s ystems (HPCI/RCIC)gpy(/)-Not consistent with paths suggested in EPRI Np-6041 and other IPEEE submittals as "first line of defense" thatrespondsautomaticallythat responds automatically
-Increases demand/reliance on low pressure systems
- Automaticcircuitryfordepressurizationand
- Automatic circuitry for depressurization and initiation of low pressure injection not included
-Increases demand
/reliance on o perator actions
/p Browns Ferry Nuclear Power PlantiliIPEEE Screen ing Eva luat i on Conclusion Conclusion
- Based on weaknesses identified with the IPEEEtheIPEEEresultsarenotconsidered IPEEE , the IPEEE results are not considered adequate for screening purposesBFidiG2l*Browns Ferry is screene d i n as a Group 2 p lant