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Category:Meeting Briefing Package/Handouts
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Ross-Lee Summary of the August 21, 2002, Meeting Between the Nuclear Regulatory Commission Staff and Dominion Virginia Power ML0215103002002-05-29029 May 2002 May 29, 2002, Slides from Public Meeting: Preliminary Results of Environmental Review, Surry Units 1 and 2 ML0213404582002-05-16016 May 2002 Training Managers Conference Handouts ML0205303982002-01-0808 January 2002 Attachment to the 01/08/2002 Mtg with NEI, Southern Nuclear Operating Company (Snc), Florida Power and Light Company (Fpl), Virginia Electric and Power Company (Vepco), Duke Energy Corporation (Duke), and Exelon Generation Company (Exelon) 2023-04-14
[Table view] Category:Slides and Viewgraphs
MONTHYEARML23338A1522023-12-0707 December 2023 Public Meeting Slides for North Anna and Surry Emergency Plan Augmentation Times License Amendment Request ML23103A3482023-04-14014 April 2023 Annual Assessment Meeting Presentation for North Anna and Surry 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 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 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 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 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) 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 ML16124A7592016-05-0303 May 2016 April 12, 2016 Summary of Public Meeting - Surry, Units 1 and 2 ML14176A0922014-06-25025 June 2014 6/25/2014, Dominion Public Meeting Presentation for Surry GMRS Profile ML13151A1022013-05-31031 May 2013 Summary of Public Meeting with Virginia Electric and Power Company, to Discuss Annual Assessment of Surry Power Stationfor the Period of January 1, 2012 December 31, 2012 ML12129A2532012-05-0808 May 2012 EOC Poster Boards 2011 ML12115A0732012-04-19019 April 2012 RCS Standpipe White Violation Slides ML1110304092011-04-13013 April 2011 Annual Assessment Meeting Summary Slides ML1011005472010-04-20020 April 2010 NRC Strategic Plan Posters ML11228A2312009-08-13013 August 2009 State-of-the-Art Reactor Consequence Analyses (Soarca); Semi-Annual Briefing for Commission Tas ML0912702462009-05-0404 May 2009 NPS Hostile Action Drill - Protective Action Decision Considerations ML11228A2302009-04-14014 April 2009 State-of-the-Art Reactor Consequence Analyses; Semi-Annual Briefing for Commission Technical Assistants ML11228A2292008-12-17017 December 2008 Soarca Seismic Issue; Briefing for the Commissioners' Technical Assistants ML12024A3792008-11-0505 November 2008 Soarca Comparison to NUREG-1150, Res/Dra ML11228A2282008-09-10010 September 2008 State-of-the-Art Reactor Consequence Analyses (Soarca); Semi-Annual Briefing for Commission Technical Assistants ML0822614842008-08-13013 August 2008 Keys to Surry Power Station'S NRC Exam ML11228A2272008-06-0202 June 2008 State-of-the-Art Reactor Consequence Analyses; Briefing for Commission Technical Assistants ML0811301672008-04-15015 April 2008 Annual Assessment Meeting Slides - Reactor Oversight Program - Cy 2007 ML0730400332007-11-0101 November 2007 Public Meeting Slides for Meeting with Dominion Nuclear ML0634704322006-12-0606 December 2006 December 6, 2006, Surry Public Meeting Regarding Chilled Water Piping ML0611100852006-04-19019 April 2006 NRC Cy 2005 Annual Assessment Meeting, Surry Power Station ML0529005282005-09-27027 September 2005 Meeting Summary, Use of Nuhoms Fuel Storage System Under General License at Surry - 10CFR50.68 Implications ML0525604472005-08-17017 August 2005 B&W Owners Group Reactor Vessel Working Group Summary of the Plans of the B&Wog Reactor Vessel Integrity Program ML0509704632005-03-30030 March 2005 Presentation Slides for Surry 03/30/2005 NRC Cy 2004 Regulatory Performance Meeting ML0510302122005-03-30030 March 2005 NRC Cy 2004 Annual Assessment Meeting, Surry Plant, 03/30/2005 ML0521403292005-03-0909 March 2005 RIC 2005 Presentation - A3 - Donald G. Harrison - 50.69 ML0421800892004-08-0404 August 2004 VIPRE-D Topical Report DOM-NAF-2 Meeting with NRC ML0410401122004-04-0808 April 2004 Annual Assessment Meeting with NRC Re Reactor Oversight Program - Cy 2004 ML0410401342004-04-0101 April 2004 Regulatory Conference NRC Triennial Fire Protection Inspection Findings, Surry Power Station, Units 1 and 2 ML0402307032004-01-14014 January 2004 Summary of Meeting to Discuss Surry Power Station Performance Improvements (Slides) ML0403502122003-08-13013 August 2003 DRS Open Items Status 2023-04-14
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Surry Power Station Resolution of Tornado Wind Nonconformances Proposed License Amendment Request NRC Pre-Submittal Meeting May 20, 2021
Agenda
- Identified Analyses Deficiencies
- Basis for Current Operability
- License Amendment Request
- Turbine Building
- Fuel-Handling Trolley Support Structure
- Scope of LAR Implementation
Purpose of Submittal
- To modify the Surry Licensing Basis to affirm the technical adequacy of the current designs for two civil structures for protection against tornado winds
- Turbine Building Steel Superstructure
- Fuel Building - Fuel Handling Trolley Support Structure (FHTSS) 3
Current Licensing Basis
- UFSAR Section 15.2.3
- 360 mph (300 mph rotational speed + 60 translational speed)
- Pressure drop 3 psi in 3 seconds
- 1200 ft diameter with radius of max winds = 200 ft
- UFSAR Ch. 15, Table 15.2-1
- Not a Tornado Criterion T structure, but By design, building collapse will not damage any Class I structures and components during earthquake, or tornado-resistant structures and components during tornado
- UFSAR Ch. 15, Table 15.2-1
- Structure is designated Tornado Criterion T for protection against tornado winds 4
Identified Analyses Deficiencies
- The Turbine Building steel superstructure cannot be demonstrated by analysis to provide adequate protection against collapse under UFSAR tornado wind speeds, which could impact safety-related equipment in the basement
- Existing design calculation for 300 mph tornado wind speed vs 360 mph in UFSAR
- FHTSS cannot be demonstrated by analysis to be acceptable for UFSAR tornado wind speeds
- Calculation of FB steel structure addresses 360 mph for low-bay portion of the structure, but calculation did not consider high-bay portion, which is the FHTSS (Structural Bents 3 & 4) 5
Basis for Current Operability
- Turbine Building (Operable but Not Fully Qualified)
- Credit existing 2D analysis by plant A/E for 300 mph winds
- Reasonable expectation that structural collapse from excessive story drift is impeded by interaction of steel superstructure with Turbine pedestals
- FHTSS (Operable but Not Fully Qualified)
- Consequences of postulated collapse of the structure concluded to be bounded by design basis fuel handling accident (UFSAR Section 14.4.1.3, Fuel-Handling Accident in the Spent-Fuel Pool)
- Reasonable expectation that structure could sustain an EF3 tornado without collapse 6
License Amendment Request Turbine Building
- Reason for License Amendment
- To reduce UFSAR tornado wind speed from 360 mph to 250 mph based on crediting more recent meteorological / climate data for purposes of affirming license basis requirement for protection against collapse under tornado winds
- NRC approval required per 10 CFR50.59(c)(2)(viii) for change in an element of a method of evaluation used to establish that the structure will satisfy its design requirement (tornado wind speed)
- Apply wind loads based on 250-mph tornado wind speeds
- Analyze the structure for protection against collapse of the turbine deck 7
License Amendment Request Turbine Building
- Details of Analysis Performed
- Reviewed updated tornado data in the most recent reports /
studies endorsed by NRC (e.g., NUREG/CR-4461, Rev. 1 and 2, RG. 1.76, Rev. 1) and justified reducing the UFSAR tornado wind speed from 360 mph to 250 mph for Surry Power Station
- Developed three-dimensional finite element model of the Turbine Building steel superstructure to evaluate the effects of 250-mph tornado wind loads along the four cardinal directions in order to address the concerns related to collapse of the steel superstructure and the resulting damage to safety-related equipment in the Turbine Building 8
License Amendment Request Turbine Building
- Under the effect of the 250-mph tornado wind speed:
- The lateral drift ratio of the operating floor remained under 1%.
- The stress level in all steel members and RC slab and wall elements remained below the acceptable stress limits.
- All girder-to-column and girder-to-girder connections are acceptable based on AISC 15th edition combined stress criteria.
- This assessment confirmed that the safety-related equipment in the TB will not be damaged if the TB is subjected to a tornado with sustained winds up to 250 mph in any of the four cardinal directions.
9
License Amendment Request Fuel Handling Trolley Support Structure
- Reason for License Amendment
- To change the licensing basis for the structure to apply a risk-informed approach that shows acceptable levels of risk in terms of damage to spent fuel assemblies
- NRC approval required for change in method used to affirm acceptability of the structure to satisfy licensing requirements for protection against tornado winds
- Risk-informed approach to demonstrate minimal risk of fuel damage in SFP due to possible collapse of the FHTSS under tornado winds
- Follows RG 1.174 approach to demonstrate acceptably small change in risk 10
License Amendment Request Fuel Handling Trolley Support Structure
- Details of Analysis Performed
- Developed 3-D FEA model of the FHTSS
- Constructed a mean fragility curve for failure of the FHTSS as a function of wind speed
- Calculated tornado wind speed corresponding to 50% probability of failure
- Open-frame analysis of FHTSS framing following ASCE guidance to characterize drag coefficients and estimate the total applied wind force
- Estimate nominal (un-factored) member strength based on AISC 15th Ed. and using median material properties
- Determine the wind speed that results in the maximum interaction (demand to capacity) ratio of 1.0 (or slightly less)
- Justify use of generic composite variability (0.175) based on industry research
- Convolved the mean fragility curve with the NUREG/CR-4661, Rev. 2 wind hazard (initiating event probabilities) in order to calculate a risk of damage to fuel in the Spent Fuel Pool
- Demonstrated that the risk is within acceptable thresholds consistent with RG 1.174 11
License Amendment Request Fuel Handling Trolley Support Structure
- Structural Fragility Results
- Median-based Tornado Wind Speed Capacity =
210 mph
- Composite variability =
0.175
- The maximum interaction ratio under 210 mph wind speed is 0.95.
12
License Amendment Request Fuel Handling Trolley Support Structure
- Fuel damage was assumed for any plastic deformation of the FHTSS that occurs
- Overall risk associated with the wind speed effecting the FHTSS that will cause fuel damage is 1.97E-06 / reactor year based on conservative analysis
- This risk fell into the Region II of R.G.
1.174, where the application needs to show that the total CDF is <1.0E-4 per reactor year to be considered reasonable Risk Criteria Risk Metric Value R.G. 1.174 criteria
- NRC study* corroborates that the base FDF due to Wind Speed 1.97E-06 1.0E-6 to 1.0E-5 risk is in the range of applicability of RG Total Fuel Risk 1.97E-06 <1.0E-4 1.174
- Kelly, G., Palla, R., Cheok, M., & Parry, G., Insights from a comprehensive evaluation of risk at spent fuel pools at decommissioning nuclear power plants in the US. 9 international conference on nuclear engineering, France, 2001 13
Scope of LAR Implementation
- Conforming Changes to UFSAR
- Descriptions of TB and FHTSS analyses performed to be inserted within Chapter 15.2, Structural Design Criteria, Sections 15.2.3, Tornado Criteria to clarify the bases for structural acceptability of the existing designs with respect to tornado wind design
- Edits to Table 15.2-1, Structures, Systems, and Components Designed for Seismic and Tornado Criteria to clarify bases for classifications as denoted within Section 15.2.3 for each respective structure 14
Proposed Milestones
- Submit LAR to NRC July 30, 2021
- Requested approval July 2022
- Implement amendment 60 days after approval 15
Acronyms / References Acronym Definition Acronym Definition A/E Architect / Engineer IR Interaction Ratio AISC American Institute of Steel LAR License Amendment Request Construction ASCE American Society of Civil mph miles per hour Engineers CDF Core Damage Frequency NRC Nuclear Regulatory Commission CE Civil Engineering psi pounds per square inch ETE Engineering Technical RG Regulatory Guide Evaluation FEA Finite Element Analysis SFP Spent Fuel Pool FDF Fuel Damage Frequency TB Turbine Building FHTSS Fuel-Handling Trolley UCR UFSAR Change Request Support Structure ft foot / feet UFSAR Updated Final Safety Analysis Report 16