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[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 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 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 Dominions Presentation on Surrys 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); 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Modeling FLEX in Surry Power Station Internal Events and Flooding PRA Bill Webster - Dominion Energy
- 2017 PSA Paper Implementation of FLEX Strategies in Surry PRA by Aram Hakobyan, Craig Nierode 1
Overview
Purpose - Discuss the benefit of crediting FLEX in the Surry Power Station internal events and flooding PRA models
Discussion points
Surry Features including key plant modification
Internal Flooding Scenario
FLEX Modeling - Flooding
FLEX Modeling - SBO
Key Assumptions
Operator Actions
Results/Data Sensitivities 2
Surry Power Station
Surry Risk Profile (before FLEX implementation)
Internal Flooding 47%
Station Blackout 39%
Small LOCA 4%
Rx Vessel Failure 3%
Medium LOCA 2%
Main Steam Line Break 2%
ISLOCA 1%
Transients 1%
SGTR 1%
Surry Unit 1 CDF Contributions CDF = 1.0E-05/yr
Internal Flooding Scenario
- Turbine Building (TB) Flooding
- Propagates to emergency switchgear room (ESGR)
- Causes complete loss of AC and DC power - T(0)
- Turbine-Driven Auxiliary Feedwater (TDAFW) pump is credited (starts and continues to run)
- Instrumentation for SG level control is not available (needs to be restored prior to SG overfill in approximately 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />)
ESGR Dike
Key Plant Modification
- FLEX plant modification installed UPS on Appendix R Remote Monitoring Panel (RMP)
- UPS provides 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> power to RMP after loss of power and ability to install portable 120V power for continued operation.
- RMP provides both units key instrumentation (steam generator level/pressure, RCS temperature, pressurizer pressure, Gammametrics) 7
Remote Monitoring Panel
Surry FLEX Equipment
- BDB High Capacity diesel-driven pumps (2)
- 120/240 VAC generators (3)
- Other supporting equipment (e.g. hauling equipment)
Note: Equipment Stored in a protected structure on site
Surry Plant Features
- No significant RCP seal leakage is expected upon loss of seal cooling
- RCS injection is not required for successful mitigation of an ELAP event
- Assumption is supported by MAAP analysis
- After 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, there is plenty of water inventory in the RCS
Surry Plant Features (cont.)
- Remote Monitoring Panel with uninterrupted power supply (UPS) system
- UPS external battery lasts 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
- Power supply for instrumentation
- Provides water supply to TDAFW pump from the FP tanks after depletion of emergency condensate storage tank (ECST)
FLEX Implementation (Internal Flooding)
- Operators perform the following steps
- Declare ELAP on loss of AC and DC power after ESGR is flooded, per ECA 0.0 - Loss of All AC Power
- Relocate from the Main Control Room to the Remote Monitoring Panel (RMP) per FSG 7 Loss of Vital Instrument or Control Power
- Start powering the RMP and vital instrumentation from the UPS system by turning the selector switch to BDB position
- Control TDAFWP locally to ensure no Steam Generator Overfill
- Initiate cooldown per ECA 0-0
FLEX Implementation (Internal Flooding)
- The UPS system is designed to provide uninterrupted power to the RMP for at least 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
- Meanwhile, a BDB portable generator is brought from the on-site storage facility and connected to the existing electrical connections on the RMP
FLEX Internal Flooding
FLEX Implementation (Station Blackout)
- Operators perform the following steps
- Determine whether power can be restored within 45 minutes
- Declare ELAP if power cannot be restored per ECA 0-0
- Load shed DC buses to preserve the charge on the DC batteries for vital instrumentation per FSG-4
- DC batteries are estimated to last 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> with successful load shed
FLEX Implementation (Station Blackout)
Bring in a BDB portable generator from the on-site storage facility and connect it to the existing electrical connections Relocate to RMP after batteries are depleted if DC load shed fails AFW flow rate is locally throttled to prevent SG overfill
FLEX - Station Blackout
Analysis Assumptions
- After battery depletion and loss of SG level control, SGs are overfilled and TDAFW pumps fails
- If DC bus load shed fails in the SBO scenario, there is not enough time to bring in and connect the portable generator before battery depletion, and relocation to RMP becomes necessary
- DC power is unavailable in the Flooding scenario with failed ESGR
Analysis Assumptions (cont.)
- No test and maintenance term is modeled for the portable generator because there are other generators that can be used to power vital instrumentation
- If TDAFW pump is unavailable or fails, it is assumed that mitigation is unsuccessful and core damage occurs
- If the RCP seals fail catastrophically (low probability event), then FLEX mitigation strategy is unsuccessful
Analysis Assumptions (cont.)
No Phase III FLEX equipment is credited The PRA model was adjusted to account for the slight detrimental impact of the FLEX procedures.
RCS makeup with a portable FLEX pump is not modeled Failure rate data for the BDB portable generator was assumed to be the same as that of Emergency Diesel Generator
- Additional portable generators are available but not modeled if failure occurs
- Sensitivity study performed to determine the impact of this assumption
Operator Actions Modeled Throttle AFW Flow
- For both Flooding and SBO events
- Failure results in SG overfill and loss of TDAFW pump leading to core damage Deep DC Load Shed
- Only for SBO event
- Failure results in early battery depletion and requires relocation to RMP Establish Remote Monitoring Panel
- For both Flooding and SBO events
- Failure results in core damage
Operator Actions Modeled (cont.)
- Establish Portable Generator Power to RMP or other 120/480 electrical connections
- For both Flooding and SBO
- Failure results in loss of long-term instrumentation leading to core damage
- Align AFW Suction to Fire Water
- For both Flooding and SBO
- Failure results in long-term heat removal leading to core damage
Results Station Blackout 26%
Internal Flooding 17%
Small LOCA 15%
Rx Vessel Failure 11%
Medium LOCA 10%
Main Steam Line Break 7%
ISLOCA 4%
Transients 4%
SGTR 3%
Loss of Offsite Power 2%
ATWS 1%
Surry Unit 1 CDF Contributions CDF = 2.5E-06/yr
Results (cont.)
- From 1.0E-05/year to 2.5E-06/year
- Combined contribution to CDF from SBO and Flooding scenarios dropped from 86% to 43%
- Significant improvement on MSPI margins
- New significant contributors emerged
- SLOCA
- Reactor Vessel Failure
- MLOCA
Data Sensitivity
- Model two portable generators each capable of providing enough power supply for instrumentation
- EDG failure rate increased by a factor of 5 for every failure mode
- CCF modeled for every failure mode assuming non-staggered testing
- Results show minor CDF reduction
Conclusion Implementation of FLEX strategies in Surry PRA provided significant risk benefit.
The main reason for this benefit was that Surry PRA was dominated by TB flooding propagating into ESGR, and Station Blackout scenarios
- Final CDF contributions from both scenarios dropped significantly The risk reduction was achieved without any credit for FLEX AFW or RCS pumps The use of EDG failure rates for portable generators is appropriate until enough test data have been obtained
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