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| {{#Wiki_filter:NRC Public Meeting Fukushima Near-Term Task Force Recommendation 2.1SeismicRe-evaluationandScreeningResults Seismic Re-evaluation and Screening ResultsSurry Power Station -Units 1 and 2 MilltUit2 Mill s t one U n it 2 DominionJune25,2014 June 25, 2014 Agenda Agenda *SurryGMRSDifferences Surry GMRS Differences*Introduction | | {{#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 |
| *NRCandEPRIGMRS NRC and EPRI GMRSand Surry SSE Comparison*Velocity Profiles*Basis for Kappa
| |
| *Basis for Depth to Hard Rock S*S ummary *ConclusionMilltUit2DftRAI 2*Mill s t one U n it 2 -D ra ft RAI s 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
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| *Dominionwillpresentthebasisforthe information 3*Dominion will present the basis for the information provided in the submittal related to these differences Surry GMRS and SSE Ci C ompar i son*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])
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| 4 GMRS and SSE Ci C ompar i son 5 VsProfiles Vs Profiles*Basis for Shear Wave Velocity (Vs) Profiles
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| -Site-specific geotechnical profile data from Report Table 2.3.2-1SSEcontrolpointatsurface(26
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| '6El)-SSE control point at surface (266 El.)-Vs values
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| *Compactedfill
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| -16'-1000fps Compacted fill 16 1000 fps*Upper 140' -based on sampler penetration tests (hammer blows)*Uncertaintyfactorof157appliedbasedonlimiteddata
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| *Uncertainty factor of 1.57 applied based on limited data-Profiles reflect site-specific estimated Vs values
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| -Nogradientappliedsincesoftsoilsite(consistent 6 No gradient applied since soft soil site (consistent with SPID)
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| VsProfiles Vs Profiles 7 VsProfiles Vs Profiles 8 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
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| -Contributions from soil ( 1,600 ft) plus underlying hard rock
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| -Soil contribution from empirical relation based
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| 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've l oc it y, V s, >9200 ft/sec) e l eva tion repor t e d 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] -
| | Agenda |
| indicates 'crystalline basement rocks' reached at
| | * Surry GMRS Differences |
| 'approximately -1600
| | * Introduction |
| '*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 y dro g eolo gicUnits of the Lower York-James Peninsula
| | * NRC and EPRI GMRS and Surry SSE Comparison |
| , Vir g inia.10ygg ,g DepthtoHardRock Depth to Hard Rock 11 DepthtoHardRock Depth to Hard Rock 12 Summary Summary*SurryGMRSandscreeningresultsdeveloped Surry GMRS and screening results developed based on the NRC-endorsed EPRI SPID
| | * Velocity Profiles |
| | * Basis for Kappa |
| | * Basis for Depth to Hard Rock |
| | * Summary S |
| | * Conclusion |
| | * Millstone Mill t U Unit it 2 - Draft D ft RAIs RAI 2 |
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| Guidance*Surry Vs profiles are based on site-specific data and develo ped consistent with SPID p*Surry site kappa value consistent with SPID A pp endix B methodolo gyppgy*Surry site depth to hard rock is based on a reasonable inter p retation of available data 13 p Conclusion Conclusion
| | Introduction |
| *SurryGMRSandscreeningresultsare Surry GMRS and screening results are consistent with industry guidance | | * 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 |
| *Surryscreensoutfromperformanceoffurther Surry screens out from performance of further seismic risk assessment, high frequency confirmation, and s p ent fuel p ool evaluation pp*Expedited Seismic Evaluation Process (ESEP) is not re q uired p er the Au g mented A pp roach qpgpp guidance (EPRI 3002000704) 14 MillstoneUnit2 Millstone Unit 2*TheMillstoneUnit2GMRSandscreening The Millstone Unit 2 GMRS and screening submittal provided the screening results based | | * 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 |
|
| |
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| on comparison of the GMRS to the IPEEE HCLPF spectrum (IHS) per the SPID guidance*NRC has drafted two re q uests for additional q information related to the Millstone Unit 2 submittal*Dominion has reviewed these requests and is providing information for discussion 15 MillstoneUnit2 Millstone Unit 2*Re q uest 1 q-In the IPEEE adequacy review supporting IHS screening, HCLPF capacity calculations could not be located for resolution of two items:
| | Surry GMRS and SSE C |
| (1) Batter y 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
| | * 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 |
|
| |
|
| acceptable results.-Provide a detailed description of the methods and inputs for the evaluation of the battery racks and chilled water surge tank p erformed for the submittal p-Provide a detailed description of any modifications to these components performed to support the reconstitution of the
| | GMRS and SSE C |
| | Comparison i |
| | 5 |
|
| |
|
| calculations 16 MillstoneUnit2 Millstone Unit 2*Re q uest 1 Discussion q-The calculations were reconstituted for these components to resolve comments from the IPEEE adequacy review.Themethodsusedinthesetworecentcalculationsare
| | Vs Profiles |
| -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. | | * Basis for Shear Wave Velocity (Vs) Profiles |
| 17 MillstoneUnit2 Millstone Unit 2*Request2 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.
| | - Site-specific geotechnical profile data from Report Table 2.3.2-1 |
| This air operated valve has a heavy yoke that is
| | - 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 |
|
| |
|
| inde p endentl y braced.py-Provide a detailed description of how this item was resolved and its safety significance related to the lHCLPFf02 p l ant HCLPF o f 0.2 5g 18 MillstoneUnit2 Millstone Unit 2*Request 2 Discussion
| | Vs Profiles 7 |
| -The vital chilled water s y stem (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 bracin g, and p i p e su pports in the vicinit y of the valve
| | Vs Profiles 8 |
| , are g,ppppy,anchored to the same structure and stresses due to differential
| |
|
| |
|
| displacement are minimal.
| | Calculation of Kappa |
| -Thevalvewasanalyzedinthisconfigurationandconfirmedto 19 The valve was analyzed in this configuration and confirmed to meet the design basis requirements as part of the USI A-46 | | * 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 |
|
| |
|
| program.}} | | 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 |
| | * 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}} |
|
|---|
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Category:Slides and Viewgraphs
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2024-07-11
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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
