|
|
(2 intermediate revisions by the same user not shown) |
Line 15: |
Line 15: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:NRC Public Meeting Fukushima Near-Term Task Force Recommendation 2.1SeismicRe | | {{#Wiki_filter:NRC Public Meeting Fukushima Near-Term Task Force Recommendation 2.1 Seismic Re-evaluation and Screening Results Surry Power Station - Units 1 and 2 Mill t Millstone Unit U it 2 Dominion June 25, 2014 |
| -evaluationandScreeningResults Seismic Re-evaluation and Screening ResultsSurry Power Station -Units 1 and 2 MilltUit2 Millstone Unit 2DominionJune25,2014 June 25, 2014 AgendaAgenda *SurryGMRSDifferences Surry GMRS Differences*Introduction
| |
| *NRCandEPRIGMRS NRC and EPRI GMRSand Surry SSE Comparison*Velocity Profiles*Basis for Kappa
| |
| *Basis for Depth to Hard Rock S*Summary *ConclusionMilltUit2DftRAI2*Millstone Unit 2 -Draft RAIs Introduction Introduction*Dominion followed the NRC-endorsed industry guidance (EPRI1025287SPID)todeveloptheSurryground (EPRI 1025287 -SPID) to develop the Surry ground motion response spectrum (GMRS) in response to the NRC 10CFR 50.54(f) request for information letter*Dominion submitted the GMRS/hazard curves and screening results for Surry Power Station Units 1 and 2 onMarch312014 on March 31, 2014*The objective of this meeting is to discuss the identified differences between the Surry submittal and NRC confirmatory results, i.e., shear wave velocity profiles,
| |
|
| |
|
| total effective kappa and depth to hard rock
| | Agenda |
| *Dominionwillpresentthebasisforthe information 3*Dominion will present the basis for the information provided in the submittal related to these differences Surry GMRS and SSE CiComparison*Surry is a low seismic hazard site (SSE spectral peak < 0.23g at 5% damping)*GMRS (Dominion) enveloped by SSE*GMRS (NRC) <0.29g (est.) spectral peak*NRC GMRS confirmatory analysis differences-Shear Wave Velocity (Vs) Profiles-Total Kappa Value (0.027s [NRC] vs. 0.034s [Dominion])-Depth to Hard Rock (1460' [NRC] vs. 1700' [Dominion]) | | * Surry GMRS Differences |
| 4 GMRS and SSE CiComparison5 VsProfiles Vs Profiles*Basis for Shear Wave Velocity (Vs) Profiles
| | * Introduction |
| -Site-specific geotechnical profile data from Report Table 2.3.2-1SSEcontrolpointatsurface(26
| | * NRC and EPRI GMRS and Surry SSE Comparison |
| '6El)-SSE control point at surface (266 El.)-Vs values
| | * Velocity Profiles |
| *Compactedfill | | * Basis for Kappa |
| -16'-1000fpsCompacted fill 16 1000 fps*Upper 140' -based on sampler penetration tests (hammer blows)*Uncertaintyfactorof157appliedbasedonlimiteddata
| | * Basis for Depth to Hard Rock |
| *Uncertainty factor of 1.57 applied based on limited data-Profiles reflect site-specific estimated Vs values | | * Summary S |
| -Nogradientappliedsincesoftsoilsite(consistent 6No gradient applied since soft soil site (consistent with SPID)
| | * Conclusion |
| VsProfiles Vs Profiles7 VsProfiles Vs Profiles8 CalculationofKappa Calculation of Kappa*Basis For Estimate of Total Effective Kappa-Kappa = 0.034s based on SPID Appendix B.5.1.3.1 guidancefor soil site with <3,000 ft depth to hard rock
| | * Millstone Mill t U Unit it 2 - Draft D ft RAIs RAI 2 |
| -Contributions from soil ( 1,600 ft) plus underlying hard rock
| |
| -Soil contribution from empirical relation based
| |
|
| |
|
| on soil depth 9-Hard rock contribution 0.006s DepthtoHardRock Depth to Hard Rock*Surry Screening Report: 'Hard rock' (i.e., shear wave litV9200ft/)ltitd 1700'velocity, Vs, >9200 ft/sec) elevation reported as -1700'*Based on review of USGS Professional Paper No. 1612 (Feb22,2000) 1(Feb 22, 2000)*Extrapolation of borehole 60 (Hog Island) [Plate 4] -
| | Introduction |
| indicates 'crystalline basement rocks' reached at
| | * Dominion followed the NRC-endorsed industry guidance (EPRI 1025287 - SPID) to develop the Surry ground motion response spectrum (GMRS) in response to the NRC 10CFR 50.54(f) request for information letter |
| 'approximately -1600
| | * Dominion submitted the GMRS/hazard curves and screening results for Surry Power Station Units 1 and 2 on March 3131, 2014 |
| '*Additional 100' depth to Vs=9200 ft/sec was assumed in ordertoaccountforlikelyweatheringeffectsduringthe order to account for likely weathering effects during the period the Potomac formation was being deposited 1USGS Professional Paper No. 1612, The Effects of the Chesapeake Bay Impact Crater on the Geological Framework and Correlation of H ydrogeologicUnits of the Lower York-James Peninsula
| | * The objective of this meeting is to discuss the identified differences between the Surry submittal and NRC confirmatory results, i.e., shear wave velocity profiles, total effective kappa and depth to hard rock |
| , Virginia.10ygg,g DepthtoHardRock Depth to Hard Rock11 DepthtoHardRock Depth to Hard Rock12 SummarySummary*SurryGMRSandscreeningresultsdeveloped Surry GMRS and screening results developed based on the NRC-endorsed EPRI SPID | | * Dominion will present the basis for the information provided in the submittal related to these differences 3 |
|
| |
|
| Guidance*Surry Vs profiles are based on site-specific data and develo ped consistent with SPID p*Surry site kappa value consistent with SPID Appendix B methodolo gyppgy*Surry site depth to hard rock is based on a reasonable inter pretation of available data 13p Conclusion Conclusion
| | Surry GMRS and SSE C |
| *SurryGMRSandscreeningresultsare Surry GMRS and screening results are consistent with industry guidance | | Comparison i |
| *Surryscreensoutfromperformanceoffurther Surry screens out from performance of further seismic risk assessment, high frequency confirmation, and s pent fuel pool evaluation pp*Expedited Seismic Evaluation Process (ESEP) is not re quired per the Au gmented Approach qpgppguidance (EPRI 3002000704) 14 MillstoneUnit2 Millstone Unit 2*TheMillstoneUnit2GMRSandscreening The Millstone Unit 2 GMRS and screening submittal provided the screening results based | | * Surry is a low seismic hazard site (SSE spectral peak < 0.23g at 5% damping) |
| | * GMRS (Dominion) enveloped by SSE |
| | * GMRS (NRC) <0.29g (est.) spectral peak |
| | * NRC GMRS confirmatory analysis differences |
| | - Shear Wave Velocity (Vs) Profiles |
| | - Total Kappa Value (0.027s [NRC] vs. 0.034s [Dominion]) |
| | - Depth to Hard Rock (1460 [NRC] vs. 1700 [Dominion]) |
| | 4 |
|
| |
|
| on comparison of the GMRS to the IPEEE HCLPF spectrum (IHS) per the SPID guidance*NRC has drafted two re quests for additional qinformation related to the Millstone Unit 2 submittal*Dominion has reviewed these requests and is providing information for discussion 15 MillstoneUnit2 Millstone Unit 2*Request 1q-In the IPEEE adequacy review supporting IHS screening, HCLPF capacity calculations could not be located for resolution of two items:
| | GMRS and SSE C |
| (1) Battery Racks DB1 and DB2
| | Comparison i |
| , and (2) Chilled ()y,()Water Surge Tank. The submittal indicates that calculations were subsequently reconstituted for these components with
| | 5 |
|
| |
|
| acceptable results.-Provide a detailed description of the methods and inputs for the evaluation of the battery racks and chilled water surge tank performed for the submittal p-Provide a detailed description of any modifications to these components performed to support the reconstitution of the
| | Vs Profiles |
| | * Basis for Shear Wave Velocity (Vs) Profiles |
| | - Site-specific geotechnical profile data from Report Table 2.3.2-1 |
| | - SSE control point at surface (266 (26 6 El El.)) |
| | - Vs values |
| | * Compacted fill - 16 16 - 1000 fps |
| | * Upper 140 - based on sampler penetration tests (hammer blows) |
| | * Uncertainty factor of 1 1.57 57 applied based on limited data |
| | - Profiles reflect site-specific estimated Vs values |
| | - No gradient applied since soft soil site (consistent with SPID) 6 |
|
| |
|
| calculations 16 MillstoneUnit2 Millstone Unit 2*Request 1 Discussion q-The calculations were reconstituted for these components to resolve comments from the IPEEE adequacy review.Themethodsusedinthesetworecentcalculationsare
| | Vs Profiles 7 |
| -The methods used in these two recent calculations are consistent with the Seismic Margin Assessment (SMA) methodology in EPRI NP-6041 SL, Rev. 1 and were independentlyreviewedThecapacitiesofbothitemsare independently reviewed. The capacities of both items are >0.25g, therefore plant HCLPF remains unchanged.-There were no new modifications to improve the HCLPF of the batteryracksorthechilledwatersurgetankcomponentsafter battery racks or the chilled water surge tank components after the IPEEE submittal and closure of IPEEE open issues.
| |
| 17 MillstoneUnit2 Millstone Unit 2*Request2Request 2-The Millstone Unit 2 IPEEE submittal included "Opportunities for Safety Enhancements" and identified valve 2-CHW-11 as an item to be resolved.
| |
| This air operated valve has a heavy yoke that is
| |
|
| |
|
| independently braced.py-Provide a detailed description of how this item was resolved and its safety significance related to the lHCLPFf02 plant HCLPF of 0.25g18 MillstoneUnit2 Millstone Unit 2*Request 2 Discussion
| | Vs Profiles 8 |
| -The vital chilled water s ystem (CHW) provides chilled water for y()pthe DC Switchgear Room HVAC system, which is a support system. Valve 2-CHW-11 provides isolation from the non-seismic portion of the system.-The CHW system is a two-train system and failure of 2-CHW-11 only affects one train. The room cooling support function is
| |
|
| |
|
| maintained b y the redundant train. Therefore, valve 2-CHW-11 yhas low safety significance.-Valve 2-CHW-11 is top-braced at the valve actuator. The top bracing, and pipe supports in the vicinit y of the valve
| | Calculation of Kappa |
| , are g,ppppy,anchored to the same structure and stresses due to differential
| | * Basis For Estimate of Total Effective Kappa |
| | - Kappa = 0.034s based on SPID Appendix B.5.1.3.1 guidance for soil site with <3,000 ft depth to hard rock |
| | - Contributions from soil ( 1,600 ft) plus underlying hard rock |
| | - Soil contribution from empirical relation based on soil depth |
| | - Hard rock contribution 0.006s 9 |
|
| |
|
| displacement are minimal.
| | Depth to Hard Rock |
| -Thevalvewasanalyzedinthisconfigurationandconfirmedto 19The valve was analyzed in this configuration and confirmed to meet the design basis requirements as part of the USI A-46 | | * Surry Screening Report: Hard rock (i.e., shear wave velocity, l it V Vs, >9200 9200 ft/sec) ft/ ) elevation l ti reported t d as -17001700 |
| | * Based on review of USGS Professional Paper No. 1612 (Feb 22, 2000)1 |
| | * Extrapolation of borehole 60 (Hog Island) [Plate 4] - |
| | indicates crystalline basement rocks reached at approximately -1600 |
| | * Additional 100 depth to Vs=9200 ft/sec was assumed in order to account for likely weathering effects during the period the Potomac formation was being deposited 1 USGS Professional Paper No. 1612, The Effects of the Chesapeake Bay Impact Crater on the Geological Framework and Correlation of Hydrogeologic y g g Units of the Lower York-James Peninsula,, Virginia. |
| | g 10 |
|
| |
|
| program.}} | | Depth to Hard Rock 11 |
| | |
| | Depth to Hard Rock 12 |
| | |
| | Summary |
| | * Surry GMRS and screening results developed based on the NRC-endorsed EPRI SPID Guidance |
| | * Surry Vs profiles are based on site-specific data and developed p consistent with SPID |
| | * Surry site kappa value consistent with SPID Appendix pp B methodology gy |
| | * Surry site depth to hard rock is based on a reasonable interpretation p of available data 13 |
| | |
| | Conclusion |
| | * Surry GMRS and screening results are consistent with industry guidance |
| | * Surry screens out from performance of further seismic risk assessment, high frequency confirmation, and spent p fuel p pool evaluation |
| | * Expedited Seismic Evaluation Process (ESEP) is not required q p per the Augmented g Approach pp guidance (EPRI 3002000704) 14 |
| | |
| | Millstone Unit 2 |
| | * The Millstone Unit 2 GMRS and screening submittal provided the screening results based on comparison of the GMRS to the IPEEE HCLPF spectrum (IHS) per the SPID guidance |
| | * NRC has drafted two requests q for additional information related to the Millstone Unit 2 submittal |
| | * Dominion has reviewed these requests and is providing information for discussion 15 |
| | |
| | Millstone Unit 2 |
| | * Request q 1 |
| | - In the IPEEE adequacy review supporting IHS screening, HCLPF capacity calculations could not be located for resolution of two items: ((1)) Batteryy Racks DB1 and DB2,, and (2) |
| | ( ) Chilled Water Surge Tank. The submittal indicates that calculations were subsequently reconstituted for these components with acceptable results. |
| | - Provide a detailed description of the methods and inputs for the evaluation of the battery racks and chilled water surge tank performed for the submittal p |
| | - Provide a detailed description of any modifications to these components performed to support the reconstitution of the calculations 16 |
| | |
| | Millstone Unit 2 |
| | * Request q 1 Discussion |
| | - The calculations were reconstituted for these components to resolve comments from the IPEEE adequacy review. |
| | - The methods used in these two recent calculations are consistent with the Seismic Margin Assessment (SMA) methodology in EPRI NP-6041 SL, Rev. 1 and were independently reviewed reviewed. The capacities of both items are |
| | >0.25g, therefore plant HCLPF remains unchanged. |
| | - There were no new modifications to improve the HCLPF of the battery racks or the chilled water surge tank components after the IPEEE submittal and closure of IPEEE open issues. |
| | 17 |
| | |
| | Millstone Unit 2 |
| | * Request 2 |
| | - The Millstone Unit 2 IPEEE submittal included Opportunities for Safety Enhancements and identified valve 2-CHW-11 as an item to be resolved. |
| | This air operated valve has a heavy yoke that is independently p y braced. |
| | - Provide a detailed description of how this item was resolved and its safety significance related to the plant l HCLPF off 0.25g 02 18 |
| | |
| | Millstone Unit 2 |
| | * Request 2 Discussion |
| | - The vital chilled water system y ((CHW)) p provides chilled water for the DC Switchgear Room HVAC system, which is a support system. Valve 2-CHW-11 provides isolation from the non-seismic portion of the system. |
| | - The CHW system is a two-train system and failure of 2-CHW-11 only affects one train. The room cooling support function is maintained by y the redundant train. Therefore, valve 2-CHW-11 has low safety significance. |
| | - Valve 2-CHW-11 is top-braced at the valve actuator. The top g, and pipe bracing, p p supports pp in the vicinity y of the valve,, are anchored to the same structure and stresses due to differential displacement are minimal. |
| | - The valve was analyzed in this configuration and confirmed to meet the design basis requirements as part of the USI A-46 program. 19}} |
|
---|
Category:Meeting Briefing Package/Handouts
MONTHYEARML24283A1442024-10-16016 October 2024 Main Steam Line Break Accident Analysis LAR Pre-Application Meeting ML24183A2082024-07-11011 July 2024 Presubmittal Presentation: TS 3.7, 3.14 Change for Extended AOT During Outage and SW Piping Maintenance, Cfrp SW Application - Slides ML24108A0712024-04-30030 April 2024 Combined - 2023 Annual Assessment Public Meeting Slides ML23338A1522023-12-0707 December 2023 Public Meeting Slides for North Anna and Surry Emergency Plan Augmentation Times License Amendment Request ML23254A0562023-09-13013 September 2023 Presentation Material for 9/13/23 Pre-Submittal Meeting License Amendment Request to Support Cycle Reloads Using Framatome Gaia Fuel ML23103A3482023-04-14014 April 2023 Annual Assessment Meeting Presentation for North Anna and Surry ML22277A8412022-10-18018 October 2022 Presentation Material for 10/18/22 Pre-Submittal Meeting Licensing Requests to Implement Framatome Gaia Fuel ML22243A0322022-09-0707 September 2022 Presentation Material for 9/7/22 Pre-Submittal Meeting Supplement to the Spent Fuel Pool Criticality Safety Analysis ML22236A0602022-08-29029 August 2022 Presentation Material for 8/29/22 Pre-Submittal Meeting Reactor Pressure Vessel Head Peening Follow-Up Exam Deferral ML22215A2872022-08-0909 August 2022 Presentation Material for 8/9/22 Pre-Submittal Meeting Containment Recirc Spray System Flow Test Alternative Request ML22097A2262022-04-13013 April 2022 Presubmittal Presentation April 13, 2022 One-time TS Change of AOT for Unit 2 AFW Piping Replacement ML22082A1482022-03-23023 March 2022 Annual Assessment Meeting for Millstone Power Station - Webinar Presentation (NRC) ML22055B1132022-03-0202 March 2022 Technical Support Center (TSC) Relocation Proposed License Amendment Request - NRC Pre-Submittal Meeting, March 2, 2022 ML21134A1632021-05-20020 May 2021 Resolution of Tornado Wind Nonconformances Proposed License Amendment Request NRC Pre-Submittal Meeting - May 20, 2021 ML21127A1362021-05-13013 May 2021 May 13, 2021 NRC Pre-Submittal Meeting - Surry Power Station New Fuel Storage and Spent Fuel Pool Criticality Analysis Proposed License Amendment Request ML21076A3322021-03-18018 March 2021 3/18/21 - Annual Assessment Meeting for Millstone Power Station - Presentation Slides ML21034A5972021-02-10010 February 2021 External Presentation Am Atkinson_Nrc ISG-06 Meeting Dominion Digital IC Project 02102021 ML20307A1772020-11-0404 November 2020 NRC Presentation North Anna Power Station, Units 1 and 2 Subsequent License Renewal Review ML20309A5912020-10-14014 October 2020 Pre-Submittal Meeting for License Amendment Requests to Implement Batch Framatome 15 X 15 AGORA-5A-I (Agora) Fuel at Surry Power Station Units 1 and 2 (SPS) - Slides ML20226A4112020-08-19019 August 2020 Presentation Material for 8/19/20 Pre-Submittal Meeting Biennial Emergency Preparedness Exercise Date Change Exemption Request ML20176A2762020-06-29029 June 2020 Presentation Material for 6/29/20 Pre-Submittal Meeting Proposed License Amendment Request for Measurement Uncertainty Recapture Power Uprate ML20143A0772020-05-26026 May 2020 Presentation Material for 5/26/20 Pre-Submittal Meeting Steam Generator Examination Frequency Alternative Request ML20111A0352020-04-20020 April 2020 Annual Assessment Meeting for Millstone Power Station - NRC Presentation Slides ML20098B6022020-04-0707 April 2020 Annual Assessment Meeting Presentation ML20098B7292020-04-0707 April 2020 Sur 2019 Annual Assessment Meeting Presentation ML19311C5292019-11-0707 November 2019 Dsies Slides for Nov. 7, 2019 Public Meeting ML19143A4722019-06-0303 June 2019 Presentation Material for 6/03/19 Pre-Submittal Meeting Integrated Leak Rate Test Extension License Amendment Request ML19128A4072019-05-0909 May 2019 Presentation Material for 5/09/19 Pre-Submittal Meeting TS Coolant Activity Changes, License Amendment Request ML19063D9452019-03-0707 March 2019 Presentation Material for 3/07/19 Pre-Submittal Meeting License Amendment Request to Revise Technical Specification 3.8.1.1 ML19022A2432019-01-22022 January 2019 Presentation Material for 1/22/19 Pre-Submittal Meeting Fillet Weld Preheat Alternative Request ML19007A2162019-01-0808 January 2019 Subsequent License Renewal Environmental Scoping Meeting, Surry Power Station, Unit Nos. 1 and 2, January 8, 2018 ML18320A2502018-11-20020 November 2018 50.90 License Amendment Request - Dominion Fleet EAL Scheme Changes, November 20, 2018 Public Meeting ML18310A1812018-11-0808 November 2018 Presentation Material for 11/08/18 Pre-Submittal Meeting 10 CFR 50.69 Risk Informed Approach License Amendment Request ML18141A3072018-05-21021 May 2018 18 - SLR Status ML18108A2072018-04-10010 April 2018 04/10/2018 Public Teleconference Meeting Slides MPS3 C Charging Pump ML18032A5842018-02-0707 February 2018 SLR Pre-Application 02/07/2018 Meeting - Dominion Energy Slides ML17320A2012017-11-15015 November 2017 Modeling FLEX in Surry Power Station Internal Events and Flooding PRA ML17230A1282017-08-31031 August 2017 Connecticut, Inc. Presentation Slides for Pre-submittal Meeting on August 31, 2017 ML17200C9572017-07-18018 July 2017 Connecticut, Inc. Presentation Slides for Pre-submittal Meeting on July 18, 2017 ML16320A5232016-09-0707 September 2016 Pre-Submittal Meeting with Surry Power Station Regarding Carbon Fiber Reinforced Polymer Alternative Request ML16272A3472016-08-10010 August 2016 08/10/2016 - NEI Supplemental Material 1 (BADGER Measurement of Carborundum B-10 Areal Density) ML16272A3462016-08-10010 August 2016 08/10/2016 - NEI Supplemental Material 2 (Estimate of BADGER System Uncertainty Using Millstone Unit 1 2013) ML16124A7592016-05-0303 May 2016 April 12, 2016 Summary of Public Meeting - Surry, Units 1 and 2 ML16125A0092016-05-0303 May 2016 2016/05/03 Presentation Slides for Pre-Submittal Teleconference for Realistic Large Break LOCA License Amendment Request ML15353A0022015-12-17017 December 2015 /12/17 Presentation Slides for Pre-Submittal Teleconference - Proposed LAR for Spent Fuel Pool Heat Load Analysis in Response to Confirmatory Order EA-13-188 ML15344A2942015-12-10010 December 2015 /12/10 Presentation Slides for Pre-Submittal Teleconference - Proposed LAR for Charging System in Response to Confirmatory Order EA-13-188 ML15314A1022015-10-20020 October 2015 2015/10/20 Pre-Submittal Teleconference Meeting Slides: Proposed License Amendment Request for EAL Changes, RCS Sampling Methodology Revision ML15198A3432015-06-22022 June 2015 2015/06/22 Pre-Submittal Teleconference Meeting Slides: LOCA Analyses Supporting MPS2 Upgrade to Areva Standard CE14 Htp Fuel Assembly ML15155B3692015-05-21021 May 2015 Connecticut, Inc. Presentation Slides for Pre-submittal Meeting on May 21, 2015 ML14176A0922014-06-25025 June 2014 6/25/2014, Dominion Public Meeting Presentation for Surry GMRS Profile 2024-07-11
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24283A1442024-10-16016 October 2024 Main Steam Line Break Accident Analysis LAR Pre-Application Meeting ML24183A2082024-07-11011 July 2024 Presubmittal Presentation: TS 3.7, 3.14 Change for Extended AOT During Outage and SW Piping Maintenance, Cfrp SW Application - Slides ML24135A0812024-05-14014 May 2024 5/16/2024, Annual Assessment Meeting for Millstone Power Station - NRC Presentation Slides ML24108A0712024-04-30030 April 2024 Combined - 2023 Annual Assessment Public Meeting Slides ML23338A1522023-12-0707 December 2023 Public Meeting Slides for North Anna and Surry Emergency Plan Augmentation Times License Amendment Request ML23254A0562023-09-13013 September 2023 Presentation Material for 9/13/23 Pre-Submittal Meeting License Amendment Request to Support Cycle Reloads Using Framatome Gaia Fuel ML23103A3482023-04-14014 April 2023 Annual Assessment Meeting Presentation for North Anna and Surry ML23073A0042023-03-14014 March 2023 Annual Assessment Meeting for Millstone Power Station - NRC Presentation Slides ML22277A8412022-10-18018 October 2022 Presentation Material for 10/18/22 Pre-Submittal Meeting Licensing Requests to Implement Framatome Gaia Fuel ML22243A0322022-09-0707 September 2022 Presentation Material for 9/7/22 Pre-Submittal Meeting Supplement to the Spent Fuel Pool Criticality Safety Analysis ML22236A0602022-08-29029 August 2022 Presentation Material for 8/29/22 Pre-Submittal Meeting Reactor Pressure Vessel Head Peening Follow-Up Exam Deferral ML22215A2872022-08-0909 August 2022 Presentation Material for 8/9/22 Pre-Submittal Meeting Containment Recirc Spray System Flow Test Alternative Request ML22097A2262022-04-13013 April 2022 Presubmittal Presentation April 13, 2022 One-time TS Change of AOT for Unit 2 AFW Piping Replacement ML22091A0902022-04-0101 April 2022 Combined 2021 Assessment Meeting Slides ML22082A1482022-03-23023 March 2022 Annual Assessment Meeting for Millstone Power Station - Webinar Presentation (NRC) ML22055B1132022-03-0202 March 2022 Technical Support Center (TSC) Relocation Proposed License Amendment Request - NRC Pre-Submittal Meeting, March 2, 2022 ML21134A1632021-05-20020 May 2021 Resolution of Tornado Wind Nonconformances Proposed License Amendment Request NRC Pre-Submittal Meeting - May 20, 2021 ML21127A1362021-05-13013 May 2021 May 13, 2021 NRC Pre-Submittal Meeting - Surry Power Station New Fuel Storage and Spent Fuel Pool Criticality Analysis Proposed License Amendment Request ML21076A3322021-03-18018 March 2021 3/18/21 - Annual Assessment Meeting for Millstone Power Station - Presentation Slides ML21034A5972021-02-10010 February 2021 External Presentation Am Atkinson_Nrc ISG-06 Meeting Dominion Digital IC Project 02102021 ML20307A1772020-11-0404 November 2020 NRC Presentation North Anna Power Station, Units 1 and 2 Subsequent License Renewal Review ML20309A5912020-10-14014 October 2020 Pre-Submittal Meeting for License Amendment Requests to Implement Batch Framatome 15 X 15 AGORA-5A-I (Agora) Fuel at Surry Power Station Units 1 and 2 (SPS) - Slides ML20226A4112020-08-19019 August 2020 Presentation Material for 8/19/20 Pre-Submittal Meeting Biennial Emergency Preparedness Exercise Date Change Exemption Request ML20176A2762020-06-29029 June 2020 Presentation Material for 6/29/20 Pre-Submittal Meeting Proposed License Amendment Request for Measurement Uncertainty Recapture Power Uprate ML20143A0772020-05-26026 May 2020 Presentation Material for 5/26/20 Pre-Submittal Meeting Steam Generator Examination Frequency Alternative Request ML20098B6022020-04-0707 April 2020 Annual Assessment Meeting Presentation ML20098B7292020-04-0707 April 2020 Sur 2019 Annual Assessment Meeting Presentation ML19311C5292019-11-0707 November 2019 Dsies Slides for Nov. 7, 2019 Public Meeting ML19296D7862019-11-0606 November 2019 Dseis Slides for November 7, 2019 Public Meeting ML19248C7352019-09-0909 September 2019 CFR 50.69 License Amendment Request Pre-Submittal Meeting with NRC - September 9, 2019 ML19143A4722019-06-0303 June 2019 Presentation Material for 6/03/19 Pre-Submittal Meeting Integrated Leak Rate Test Extension License Amendment Request ML19128A4072019-05-0909 May 2019 Presentation Material for 5/09/19 Pre-Submittal Meeting TS Coolant Activity Changes, License Amendment Request ML19022A2432019-01-22022 January 2019 Presentation Material for 1/22/19 Pre-Submittal Meeting Fillet Weld Preheat Alternative Request ML19007A2162019-01-0808 January 2019 Subsequent License Renewal Environmental Scoping Meeting, Surry Power Station, Unit Nos. 1 and 2, January 8, 2018 ML18141A3072018-05-21021 May 2018 18 - SLR Status ML18102A5692018-04-17017 April 2018 Dominion'S Presentation on Surry'S SLRA Safety Meeting-Final (for April 17, 2018) ML18108A2072018-04-10010 April 2018 04/10/2018 Public Teleconference Meeting Slides MPS3 C Charging Pump ML18086A7742018-02-21021 February 2018 LOR Program Biennial Inspection 71111.11B Exam Overlap Issues ML18032A5842018-02-0707 February 2018 SLR Pre-Application 02/07/2018 Meeting - Dominion Energy Slides ML17320A2012017-11-15015 November 2017 Modeling FLEX in Surry Power Station Internal Events and Flooding PRA ML17230A1282017-08-31031 August 2017 Connecticut, Inc. Presentation Slides for Pre-submittal Meeting on August 31, 2017 ML17200C9572017-07-18018 July 2017 Connecticut, Inc. Presentation Slides for Pre-submittal Meeting on July 18, 2017 ML16272A3462016-08-10010 August 2016 08/10/2016 - NEI Supplemental Material 2 (Estimate of BADGER System Uncertainty Using Millstone Unit 1 2013) ML16272A3472016-08-10010 August 2016 08/10/2016 - NEI Supplemental Material 1 (BADGER Measurement of Carborundum B-10 Areal Density) ML16124A7592016-05-0303 May 2016 April 12, 2016 Summary of Public Meeting - Surry, Units 1 and 2 ML16125A0092016-05-0303 May 2016 2016/05/03 Presentation Slides for Pre-Submittal Teleconference for Realistic Large Break LOCA License Amendment Request ML15353A0022015-12-17017 December 2015 /12/17 Presentation Slides for Pre-Submittal Teleconference - Proposed LAR for Spent Fuel Pool Heat Load Analysis in Response to Confirmatory Order EA-13-188 ML15344A2942015-12-10010 December 2015 /12/10 Presentation Slides for Pre-Submittal Teleconference - Proposed LAR for Charging System in Response to Confirmatory Order EA-13-188 ML15314A1022015-10-20020 October 2015 2015/10/20 Pre-Submittal Teleconference Meeting Slides: Proposed License Amendment Request for EAL Changes, RCS Sampling Methodology Revision ML15198A3432015-06-22022 June 2015 2015/06/22 Pre-Submittal Teleconference Meeting Slides: LOCA Analyses Supporting MPS2 Upgrade to Areva Standard CE14 Htp Fuel Assembly 2024-07-11
[Table view] |
Text
NRC Public Meeting Fukushima Near-Term Task Force Recommendation 2.1 Seismic Re-evaluation and Screening Results Surry Power Station - Units 1 and 2 Mill t Millstone Unit U it 2 Dominion June 25, 2014
Agenda
- Basis for Depth to Hard Rock
- Millstone Mill t U Unit it 2 - Draft D ft RAIs RAI 2
Introduction
- Dominion followed the NRC-endorsed industry guidance (EPRI 1025287 - SPID) to develop the Surry ground motion response spectrum (GMRS) in response to the NRC 10CFR 50.54(f) request for information letter
- Dominion submitted the GMRS/hazard curves and screening results for Surry Power Station Units 1 and 2 on March 3131, 2014
- The objective of this meeting is to discuss the identified differences between the Surry submittal and NRC confirmatory results, i.e., shear wave velocity profiles, total effective kappa and depth to hard rock
- Dominion will present the basis for the information provided in the submittal related to these differences 3
Surry GMRS and SSE C
Comparison i
- Surry is a low seismic hazard site (SSE spectral peak < 0.23g at 5% damping)
- GMRS (NRC) <0.29g (est.) spectral peak
- NRC GMRS confirmatory analysis differences
- Shear Wave Velocity (Vs) Profiles
- Total Kappa Value (0.027s [NRC] vs. 0.034s [Dominion])
- Depth to Hard Rock (1460 [NRC] vs. 1700 [Dominion])
4
GMRS and SSE C
Comparison i
5
Vs Profiles
- Basis for Shear Wave Velocity (Vs) Profiles
- Site-specific geotechnical profile data from Report Table 2.3.2-1
- SSE control point at surface (266 (26 6 El El.))
- Vs values
- Compacted fill - 16 16 - 1000 fps
- Upper 140 - based on sampler penetration tests (hammer blows)
- Uncertainty factor of 1 1.57 57 applied based on limited data
- Profiles reflect site-specific estimated Vs values
- No gradient applied since soft soil site (consistent with SPID) 6
Vs Profiles 7
Vs Profiles 8
Calculation of Kappa
- Basis For Estimate of Total Effective Kappa
- Kappa = 0.034s based on SPID Appendix B.5.1.3.1 guidance for soil site with <3,000 ft depth to hard rock
- Contributions from soil ( 1,600 ft) plus underlying hard rock
- Soil contribution from empirical relation based on soil depth
- Hard rock contribution 0.006s 9
Depth to Hard Rock
- Surry Screening Report: Hard rock (i.e., shear wave velocity, l it V Vs, >9200 9200 ft/sec) ft/ ) elevation l ti reported t d as -17001700
- Based on review of USGS Professional Paper No. 1612 (Feb 22, 2000)1
- Extrapolation of borehole 60 (Hog Island) [Plate 4] -
indicates crystalline basement rocks reached at approximately -1600
- Additional 100 depth to Vs=9200 ft/sec was assumed in order to account for likely weathering effects during the period the Potomac formation was being deposited 1 USGS Professional Paper No. 1612, The Effects of the Chesapeake Bay Impact Crater on the Geological Framework and Correlation of Hydrogeologic y g g Units of the Lower York-James Peninsula,, Virginia.
g 10
Depth to Hard Rock 11
Depth to Hard Rock 12
Summary
- Surry GMRS and screening results developed based on the NRC-endorsed EPRI SPID Guidance
- Surry Vs profiles are based on site-specific data and developed p consistent with SPID
- Surry site kappa value consistent with SPID Appendix pp B methodology gy
- Surry site depth to hard rock is based on a reasonable interpretation p of available data 13
Conclusion
- Surry GMRS and screening results are consistent with industry guidance
- Surry screens out from performance of further seismic risk assessment, high frequency confirmation, and spent p fuel p pool evaluation
- Expedited Seismic Evaluation Process (ESEP) is not required q p per the Augmented g Approach pp guidance (EPRI 3002000704) 14
Millstone Unit 2
- The Millstone Unit 2 GMRS and screening submittal provided the screening results based on comparison of the GMRS to the IPEEE HCLPF spectrum (IHS) per the SPID guidance
- NRC has drafted two requests q for additional information related to the Millstone Unit 2 submittal
- Dominion has reviewed these requests and is providing information for discussion 15
Millstone Unit 2
- In the IPEEE adequacy review supporting IHS screening, HCLPF capacity calculations could not be located for resolution of two items: ((1)) Batteryy Racks DB1 and DB2,, and (2)
( ) Chilled Water Surge Tank. The submittal indicates that calculations were subsequently reconstituted for these components with acceptable results.
- Provide a detailed description of the methods and inputs for the evaluation of the battery racks and chilled water surge tank performed for the submittal p
- Provide a detailed description of any modifications to these components performed to support the reconstitution of the calculations 16
Millstone Unit 2
- The calculations were reconstituted for these components to resolve comments from the IPEEE adequacy review.
- The methods used in these two recent calculations are consistent with the Seismic Margin Assessment (SMA) methodology in EPRI NP-6041 SL, Rev. 1 and were independently reviewed reviewed. The capacities of both items are
>0.25g, therefore plant HCLPF remains unchanged.
- There were no new modifications to improve the HCLPF of the battery racks or the chilled water surge tank components after the IPEEE submittal and closure of IPEEE open issues.
17
Millstone Unit 2
- The Millstone Unit 2 IPEEE submittal included Opportunities for Safety Enhancements and identified valve 2-CHW-11 as an item to be resolved.
This air operated valve has a heavy yoke that is independently p y braced.
- Provide a detailed description of how this item was resolved and its safety significance related to the plant l HCLPF off 0.25g 02 18
Millstone Unit 2
- The vital chilled water system y ((CHW)) p provides chilled water for the DC Switchgear Room HVAC system, which is a support system. Valve 2-CHW-11 provides isolation from the non-seismic portion of the system.
- The CHW system is a two-train system and failure of 2-CHW-11 only affects one train. The room cooling support function is maintained by y the redundant train. Therefore, valve 2-CHW-11 has low safety significance.
- Valve 2-CHW-11 is top-braced at the valve actuator. The top g, and pipe bracing, p p supports pp in the vicinity y of the valve,, are anchored to the same structure and stresses due to differential displacement are minimal.
- The valve was analyzed in this configuration and confirmed to meet the design basis requirements as part of the USI A-46 program. 19