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Category:Meeting Briefing Package/Handouts
MONTHYEARML24008A2112024-01-25025 January 2024 Evaluation of Seismic Risk for V. C. Summer Under the Process for Ongoing Assessment of Natural Hazard Information (Poanhi) - January 25, 2024 (Slides) ML24008A2182024-01-25025 January 2024 Seismic Data to Support Public Meeting with Dominion Regarding NRC Staff Evaluation of Seismic Risk at V.C. Summer Generating Station - January 25, 2024 (Tables) ML24022A1192024-01-24024 January 2024 Slides - SNC Slides - Pre-Submittal Meeting on January 24, 2024 - Vogtle 3 & 4 Explosively Actuated Valves Relief Request ML23361A0812024-01-0808 January 2024 SNC Slides - Pre-Submittal Public Meeting on January 8, 2024 Related to Fleet QATR ML24004A1852024-01-0404 January 2024 SNC Slides - Pre-Submittal Public Meeting on January 8, 2024 Related to Fleet QATR Revised ML23313A1292023-11-0909 November 2023 Environmental Scoping Meeting for V.C. Summer Subsequent License Renewal Application - November 14 Meeting Slides ML23257A2322023-09-28028 September 2023 SNC Presentation - Pre-Submittal Meeting on September 28, 2023 - Proposed Vogtle 3 and 4 TS 3.7.6 LAR ML23137A1162023-06-0202 June 2023 Draft Slides for Advisory Committee on Reactor Safeguards Subcommittee Meeting Regarding Use of Accident Tolerant Fuel Lead Test Assemblies ML23131A4182023-05-25025 May 2023 V.C. Summer Nuclear Station 2022 Annual Assessment Meeting.Pptx ML23094A1402023-04-0404 April 2023 4 -- 2022 Aam Slides ML23055A0402023-02-24024 February 2023 VEGP, Unit 4, Potential License Amendment Request for Prior to Initial Criticality Overview Presentation ML23033A0232023-02-0202 February 2023 Dashboard Report 2-2-2023 ML22329A0192022-12-0101 December 2022 Southern Nuclear Company Slides - Pre-Submittal Meeting on December 1, 2022 - Vogtle SR 3.4.14.1 LAR and Alternative Relief Request 1 ML22335A0372022-12-0101 December 2022 Dashboard Report 12-1-2022 ML22332A0012022-11-28028 November 2022 SNC Slides - Pre-Submittal Meeting on November 30, 2022 - Vogtle TS 5.5.11 License Amendment Request ML22332A5372022-11-28028 November 2022 Draft LAR 23-001 for 12-8-22 Public Meeting ML22319A1232022-11-15015 November 2022 Kozak Slides for November 15, 2022 Public Meeting on Part 52 Lessons Learned ML22319A0052022-11-15015 November 2022 NEI Slides for November 15 2022 Public Meeting on Part 52 Lessons Learned ML22319A1242022-11-15015 November 2022 NRC Slides for November 15, 2022 Public Meeting on Part 52 Lessons Learned ML22251A0002022-09-30030 September 2022 Pre-Submittal Meeting on September 13, 2022 - Vogtle Online Monitoring LAR ML22265A0972022-09-22022 September 2022 Southern Nuclear Company Slides on Lessons Learned from Part 52 Implementation for Public Meeting on 9/27/2022 ML22265A0982022-09-22022 September 2022 NRC Slides on Part 52 Lessons Learned Construction Initiative for Public Meeting on 9/27/2022 ML22138A3952022-05-24024 May 2022 Slides - SNC Slides - Pre-Submittal Meeting on May 24, 2022 - Vogtle RR RWST Suction Check Valves ML22137A2812022-05-23023 May 2022 Slides - SNC Slides - Pre-Submittal Meeting on May 23, 2022 - Vogtle TS 3.8.1 and TSTF-163 LAR ML22126A0102022-05-11011 May 2022 Pre-Submittal Meeting on May 11, 2022 - Vogtle ATF LTAs LAR and Exemption Requests - Licensing Questions ML22123A3332022-05-10010 May 2022 Pre-Submittal Meeting 2: TSTF-51, TSTF-471, TSTF-490, and Alternative Source Term License Amendment Request - May 10, 2022 (EPID L-2022-LRM-0033)(slides) ML22115A0502022-04-21021 April 2022 VC Summer, 2021 Annual Assessment Meeting ML22110A1702022-04-20020 April 2022 4 2022 Annual Assessment Meeting.Final ML22021B6472022-01-27027 January 2022 Pre-Submittal for Westinghouse Increased Enrichment Accident Tolerant Fuel Lead Test Assemblies (EPID L-2022-LRM-0003) (Slides) ML21306A0242021-11-30030 November 2021 SNC Pre-Submittal Meeting for LAR to Relocate Augmented Piping Inspection Program Details from TSs to a Licensee Controlled Document for Farley Nuclear Plant, Units 1 & 2; and Vogtle Electric Generating Plant, Units 1 & 2 (EPID L-2021-LRM-0 ML21333A2172021-11-29029 November 2021 Readiness Group Presentation During 12-2-21 Public Meeting ML21230A2842021-08-18018 August 2021 SNC Slides - Vogtle MSIV Elimination LAR - Pre-submittal Meeting Part 2 - 08-25-2021 ML21187A0972021-07-0808 July 2021 Late Filed Allegations (Lfa) Process ML21193A0762021-07-0808 July 2021 ITAAC Related to Incore Instrument Thimble Assembly (Iita) ML21172A1312021-07-0101 July 2021 Pre-Submittal Meeting Alternate Source Term and TSTF-490 ML21193A0772021-06-24024 June 2021 Exemption from Operator Written Examination and Operating Test for Unit 4 Licenses, 6-24-21 Pre-submittal Meeting ML21085A4902021-05-19019 May 2021 Risk-informed Resolution of Generic Letter 2004-02 ML21064A3652021-03-0101 March 2021 Dashboard Report 3-1-2021 ML21027A2062021-02-28028 February 2021 Fixed 8-Hour Emergency Light Deviation Pre-Submittal Meeting, February 2021 (Slides) ML21057A0182021-02-26026 February 2021 Pre-Submittal Meeting Revise Technical Specification 3.2.1 Heat Flux Hot Channel Factor (Fq(Z)) (EPID L-2021-LRM-0023) (Slides) ML21036A1172021-02-0505 February 2021 SNC Slides - Pre-Submittal Meeting on February 16, 2021 - Beacon LAR ML20343A0742020-12-0202 December 2020 Dashboard Report 12-2-2020 ML20318A1032020-11-12012 November 2020 SNC ERO Staffing LAR RAI Responses ML20314A0962020-11-0202 November 2020 Dashboard Report 11/02/2020 ML20217L4312020-08-13013 August 2020 Edwin I Hatch, Units 1 and 2; and Vogtle Electric Plant, Units 1, 2, 3, and 4 - Meeting Slides a License Amendment Request for the Emergency Plan (EPID Nos L-2020-LLA-0150 and L-2020-LLA-051 ML20136A2832020-05-15015 May 2020 4 EOC Slides ML20114E3032020-04-23023 April 2020 Risk-Informed GL 2004--02 Pre-Submittal NRC Meeting - May 2020 ML20091G7232020-03-31031 March 2020 V.C. Summer 2019 Assessment Meeting Presentation ML20007D6772020-01-0808 January 2020 AP1000 Public Presentation Entitled Reactor Oversight Process (ROP) for Inspecting Vogtle Site with AP1000 Design ML19303A0252019-11-0404 November 2019 Risk-Informed GSI-191 NRC Public Meeting 2024-01-08
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24008A2112024-01-25025 January 2024 Evaluation of Seismic Risk for V. C. Summer Under the Process for Ongoing Assessment of Natural Hazard Information (Poanhi) - January 25, 2024 (Slides) ML24008A2182024-01-25025 January 2024 Seismic Data to Support Public Meeting with Dominion Regarding NRC Staff Evaluation of Seismic Risk at V.C. Summer Generating Station - January 25, 2024 (Tables) ML24022A1192024-01-24024 January 2024 Slides - SNC Slides - Pre-Submittal Meeting on January 24, 2024 - Vogtle 3 & 4 Explosively Actuated Valves Relief Request ML23361A0812024-01-0808 January 2024 SNC Slides - Pre-Submittal Public Meeting on January 8, 2024 Related to Fleet QATR ML24004A1852024-01-0404 January 2024 SNC Slides - Pre-Submittal Public Meeting on January 8, 2024 Related to Fleet QATR Revised ML23325A2452023-11-13013 November 2023 Enclosure 2 - Dominion Slides ML23313A1292023-11-0909 November 2023 Environmental Scoping Meeting for V.C. Summer Subsequent License Renewal Application - November 14 Meeting Slides ML23312A0202023-11-0808 November 2023 Environmental Scoping Meeting for V.C. Summer Subsequent License Renewal Application-Virtual Meeting Slides ML23304A2682023-11-0707 November 2023 License Amendment Request to Revise the Ultimate Heat Sink Mission Time Pre Submittal Meeting on November 7, 2023 ML23311A2452023-11-0707 November 2023 Pre-Submittal Meeting on November 7, 2023 - License Amendment Request to Revise the Ultimate Heat Sink Mission Time (Slides) ML23293A0052023-10-20020 October 2023 Lessons Learned from the ITAAC Hearing Process for Vogtle 3 and 4 ML23257A2322023-09-28028 September 2023 SNC Presentation - Pre-Submittal Meeting on September 28, 2023 - Proposed Vogtle 3 and 4 TS 3.7.6 LAR ML23137A1162023-06-0202 June 2023 Draft Slides for Advisory Committee on Reactor Safeguards Subcommittee Meeting Regarding Use of Accident Tolerant Fuel Lead Test Assemblies ML23131A4182023-05-25025 May 2023 V.C. Summer Nuclear Station 2022 Annual Assessment Meeting.Pptx ML23094A1402023-04-0404 April 2023 4 -- 2022 Aam Slides ML23072A1802023-03-13013 March 2023 2023 RIC Powerpoint Slide Presentation, Vogtle 3: Journey from Construction to Operations ML23055A0402023-02-24024 February 2023 VEGP, Unit 4, Potential License Amendment Request for Prior to Initial Criticality Overview Presentation ML23033A0232023-02-0202 February 2023 Dashboard Report 2-2-2023 ML22329A0192022-12-0101 December 2022 Southern Nuclear Company Slides - Pre-Submittal Meeting on December 1, 2022 - Vogtle SR 3.4.14.1 LAR and Alternative Relief Request 1 ML22335A0372022-12-0101 December 2022 Dashboard Report 12-1-2022 ML22335A5542022-12-0101 December 2022 Slides - SNC Slides - Pre-Submittal Meeting on December 1, 2022 - Vogtle SR 3.4.14.1 LAR and Alternative Relief Request - ML22332A0012022-11-28028 November 2022 SNC Slides - Pre-Submittal Meeting on November 30, 2022 - Vogtle TS 5.5.11 License Amendment Request ML22319A1232022-11-15015 November 2022 Kozak Slides for November 15, 2022 Public Meeting on Part 52 Lessons Learned ML22319A0052022-11-15015 November 2022 NEI Slides for November 15 2022 Public Meeting on Part 52 Lessons Learned ML22319A1242022-11-15015 November 2022 NRC Slides for November 15, 2022 Public Meeting on Part 52 Lessons Learned ML22278A0382022-10-0505 October 2022 Dashboard Report 10-5-2022 ML22251A0002022-09-30030 September 2022 Pre-Submittal Meeting on September 13, 2022 - Vogtle Online Monitoring LAR ML22265A0972022-09-22022 September 2022 Southern Nuclear Company Slides on Lessons Learned from Part 52 Implementation for Public Meeting on 9/27/2022 ML22265A0982022-09-22022 September 2022 NRC Slides on Part 52 Lessons Learned Construction Initiative for Public Meeting on 9/27/2022 ML22206A1682022-07-25025 July 2022 Dashboard Report 7-25-2022 ML22206A1712022-07-25025 July 2022 Dashboard Report 7-25-2022 ML22201A0442022-07-20020 July 2022 Voices Dashboard Report for Vogtle Unit 3 as of July 20, 2022 ML22144A0492022-05-24024 May 2022 Dashboard Report 5-24-2022 ML22144A0502022-05-24024 May 2022 Dashboard Report 5-24-2022 ML22138A3952022-05-24024 May 2022 Slides - SNC Slides - Pre-Submittal Meeting on May 24, 2022 - Vogtle RR RWST Suction Check Valves ML22137A2812022-05-23023 May 2022 Slides - SNC Slides - Pre-Submittal Meeting on May 23, 2022 - Vogtle TS 3.8.1 and TSTF-163 LAR ML22126A0102022-05-11011 May 2022 Pre-Submittal Meeting on May 11, 2022 - Vogtle ATF LTAs LAR and Exemption Requests - Licensing Questions ML22123A3332022-05-10010 May 2022 Pre-Submittal Meeting 2: TSTF-51, TSTF-471, TSTF-490, and Alternative Source Term License Amendment Request - May 10, 2022 (EPID L-2022-LRM-0033)(slides) ML22126A0012022-05-0606 May 2022 SNC Slides - Pre-Submittal Meeting on May 11, 2022 - Vogtle ATF LTAs LAR and Exemptions ML22115A0502022-04-21021 April 2022 VC Summer, 2021 Annual Assessment Meeting ML22110A1702022-04-20020 April 2022 4 2022 Annual Assessment Meeting.Final ML22060A0062022-02-28028 February 2022 4Q 2021 Performance Summary U3 ML22021B6472022-01-27027 January 2022 Pre-Submittal for Westinghouse Increased Enrichment Accident Tolerant Fuel Lead Test Assemblies (EPID L-2022-LRM-0003) (Slides) ML22026A0582022-01-26026 January 2022 Dashboard Report 1-26-2022 ML21306A0242021-11-30030 November 2021 SNC Pre-Submittal Meeting for LAR to Relocate Augmented Piping Inspection Program Details from TSs to a Licensee Controlled Document for Farley Nuclear Plant, Units 1 & 2; and Vogtle Electric Generating Plant, Units 1 & 2 (EPID L-2021-LRM-0 ML21333A2172021-11-29029 November 2021 Readiness Group Presentation During 12-2-21 Public Meeting ML21230A2842021-08-18018 August 2021 SNC Slides - Vogtle MSIV Elimination LAR - Pre-submittal Meeting Part 2 - 08-25-2021 ML21197A0032021-08-0606 August 2021 Slides - SNC Slides - Pre-Submittal Meeting on August 13, 2021 - Vogtle TS 3.3.1 and 3.3.2 LAR ML21187A0972021-07-0808 July 2021 Late Filed Allegations (Lfa) Process ML21193A0762021-07-0808 July 2021 ITAAC Related to Incore Instrument Thimble Assembly (Iita) 2024-01-08
[Table view] |
Text
Ope ating Experience Operating E pe ience 8/7/2014 1
OpE shows Initial Testing Important to . . .
Verify V if plant l built b il as designed, d i d validate lid design d i Identify inadequacies, adverse system interactions.
OpE for Initial Testing is considered because . . .
Regulatory R l commitments i - DCD Experiences from Part 50 Plant Startup Industry d Operating Lessons - Plant l Events 8/7/2014 2
Design Control Document Section 14.2.5, Rev 19 Utilization Utili ti off Reactor R t Operating O ti & Startup St t Experience E i in i
Development of Test Program Past PWR Operating Experience & Testing Experience Used to Develop Initial Test Program Other Sources of OpE Used in AP1000 ITP Question: How is this being done for Vogtle?
Summer?
8/7/2014 3
Safety Culture in Pre-operational Phases of Nuclear Power P Plant Pl Projects P j dated d d 2012 Source: IAEA Safety Report Series - # 74
(
(Publication 1555))
Safety culture includes questioning attitude, organizational i i l learning, l i proactive i approach h
Operating Experience is important component of O
Organizational i ti lL Learning i
Proper safety perspective for Initial Testing - one that proves SSCs are functional 8/7/2014 4
INTERNATIONAL p
2011 European Summaryy Report p g on Construction and Commissioning International reporting System (IRS) - Web Search 18 hits DOMESTIC NRC Circulars & Information Notices - 16 hits NRC Licensee Event Reports LERs - 155 hits NUREG 1055 Improving Quality in Design / Construction of NPPs , 1984 NUREG NUREG-1275 V l Volume 1 - IRS Summary S Report R
NUREG-0969 , Zimmer Project, 1983 INDUSTRY INPO Documents and References - SOERs, SERs WEB SEARCHES Industry, Domestic, International 8/7/2014 5
p Preoperational Testingg Lessons Learned Adequate Planning for Preoperational Test execution Plan Transition from Construction to Testing System & Organizational Turnover Adequate Test Procedure Quality assures Fidelity between Preoperational/Startup Tests and Designg Basis Documents - DCDs FSAR 8/7/2014 6
Preoperational Testing Lessons Learned Functional F ti l testing t ti iis fi finall barrier b i tto reveall construction deficiencies resulting in SSCs unable bl to t perform f design d i ffunctionti 8/7/2014 7
European Commission Joint Research Center Summary S Report R t on Nuclear N l Power P Plants Pl t Construction, C t ti Commissioning and Manufacturing Events, 2011 Analysis to identify events from construction and commissioning of NPPs Three sources of information NRC Licensee Event Reports (LERs)- 309 LERs applicable Incident Reporting System S stem (IRS)-247 (IRS) 24 reports applicable Working Group on Regulation for New Reactors (WGRNR)
- 26 WGRNR events were applicable to study 8/7/2014 8
European Commission Joint Research Center Summary S Report R t Major M j Conclusions C l i Items most affected by construction or commissioning deviations are I&C (19%), electrical components (17%),
welds (14%), valves (10%) and pipes (9%).
Average detection time of the initial defect is about 8 years after the start of commercial operation.
Common cause failures can be high for some materials:
more than 50 % for civil work and fire protection, 45 % for electrical components (the average is 34 %)
8/7/2014 9
International Lessons Learned . . .
European E Commission C i i Joint J i t Research R h Center C t Summary Report Major Conclusions More than 75 % of the events are found fortuitously, and the rate of detection is particularly high for civil work, electrical components components, I&C, I&C pipes and valves.
valves Some items such as civil work (structure, anchorages, supports)) andd electrical l i l components exhibit hibi allll three:
h a long detection time, a high rate of common cause failure g rate of fortuitous detection.
and a high 8/7/2014 10
International Lessons Learned . . .
European E Commission C i i Joint J i t Research R h Center C t Summary Report Major Conclusions The conclusions emphasize the need to minimize the number of deficiencies during construction construction, manufacturing and commissioning of a new reactor, as they can be major latent failures for a long time and can have safety consequences after f reactors start to operate.
8/7/2014 11
q Inadequate p Pre-Operational g Results in Plant Testing Operation with SSCs not functioning per design BWR: HPCI/RCIC flow not calibrated correctly since startup LER 353/2-2007-03 PWR: Protection Instrument Calibration Graphs inadequate since startup LER 305/2009-06 8/7/2014 12
q Inadequate p Pre-Operational g Results in Plant Testing Operation with SSCs not functioning per design PWR: Inadequate PMT of frequency relay setting results in dual unit loss of offsite power LER 413/2012-01 BWR: wiring errors in EDG control logic circuit results in inability to locally operate EDG from the Safe Shutdown Panel LER 324/2008-06 8/7/2014 13
OpE Shows Effective Preoperational Testing Important to . . .
Identify unrecognized Intersystem Dependencies Identify Single Point Vulnerabilities Avoid Unwanted Consequences Plant events - domestic & foreign g (next
( slides))
Scrams with complications Multiple train failures Increases in Core Damage Frequency 8/7/2014 14
Reactor Transients, LOOPS and Scrams with Complications Recent nuclear plants events involve examples where multiple trains of equipment were affected by single event or common cause failure Other significant events involve the common cause failure of non-non safety related electrical equipment The h events provide d insights h on potentiall failure f l modes d that h could ld be avoided with proper attention to design and testing during the construction and initial testing phases 8/7/2014 15
Reactor Transients, LOOPS and Scrams with Complications BWR Dual Unit Scram & LOOP 2013 Deficient D fi i electrical l i l connections i i the in h switchyard i h d grounding di system due to poor workmanship existing since original construction LER 373/2013-02 BWR Scram with Complications 2013 Proper P postt modification difi ti ttesting ti should h ld id identify tif single i l point i t vulnerability in non-safety systems that impacts plant safety LER 293/2013-01 8/7/2014 16
Reactor Transients, LOOPS and Scrams with Complications Foreign g BWR Scram,, LOOP & Complicated p LOOP 2006 Preoperational testing should identify EDS design vulnerabilities such as proper phase connections of protection relays.
y IN 2006-18.
PWR Scram, 345kV Open Phase & Fault 2012 Preoperational testing should verify design of the under-voltage protection intended to identify degraded grid conditions LER 454/2012-01 8/7/2014 17
Four Recent Significant Events Highlight that. . .
Plant Pl t events t are causedd by b single i l point i t vulnerabilities & common mode failures Events result from design errors, inadequate designg modifications and reviews,, and inadequate work control or work practices Events caused by unrecognized workmanship or installation errors from original construction.
8/7/2014 18
Four Recent Significant Events highlight that. . .
Functional testing is the final barrier to reveal construction deficiencies Robust and comprehensive p test p program g can identify design and installation deficiencies Proper consideration of Operational Experience helps assure Initial Testing is effective 8/7/2014 19
Q Questions?
ti ?
8/7/2014 20
NRC Inspection Procedures for New Reactor Plant Initial Test Programs
- IP 70367, Part 52, Inspection of Preoperational Test Program
- IP 70702, 0 0 , Inspection spect o o of Preoperational eope at o a Test est Program Performance
- NRC AP1000 Preoperational Test Program Inspection Planning Tool
- IP 72401, Part 52, Inspection of the Startup Test Program
- IP 72304, 72304 St Startup t T Testing ti ffor th the AP1000, AP1000 TTestt Procedure Review, Test Witnessing and Test Results Evaluation (under final review for issuance)