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Category:Meeting Briefing Package/Handouts
MONTHYEARML24022A1192024-01-24024 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 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 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 ML22265A0982022-09-22022 September 2022 NRC Slides on Part 52 Lessons Learned Construction Initiative for Public Meeting on 9/27/2022 ML22265A0972022-09-22022 September 2022 Southern Nuclear Company Slides on Lessons Learned from Part 52 Implementation 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) 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 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 ML19295D4672019-10-30030 October 2019 Public Meeting for ITAAC Hearing Process, October 30, 2019 ML19239A1932019-08-29029 August 2019 SNC Slides for Public Pre-Submittal Meeting on August 29, 2019 (Eptd L-2019-LRM-0054) ND-19-0962, AP1000 Structural Reconciliation - Westinghouse Electric Company & Southern Nuclear Company Technical Exchange Meeting: August 13, 20192019-08-0202 August 2019 AP1000 Structural Reconciliation - Westinghouse Electric Company & Southern Nuclear Company Technical Exchange Meeting: August 13, 2019 ML19123A3562019-05-0202 May 2019 Public Meeting Summary - Vogtle Electric Generating Plant, Docket Nos. 50-424 and 50-425 ND-19-0152, Enclosure 2, Presentation Material: Functional Arrangement (FA) ITAAC, FA System Package Examples -Closed Meeting (Non-Proprietary)2019-02-14014 February 2019 Enclosure 2, Presentation Material: Functional Arrangement (FA) ITAAC, FA System Package Examples -Closed Meeting (Non-Proprietary) ML19025A0242019-01-25025 January 2019 SNC License Amendment Request for Proposed Changes to Emergency Response Organization Staffing and Augmentation 2024-01-08
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24022A1192024-01-24024 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 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 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 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 - ML22335A0372022-12-0101 December 2022 Dashboard Report 12-1-2022 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 ML22332A0012022-11-28028 November 2022 SNC Slides - Pre-Submittal Meeting on November 30, 2022 - Vogtle TS 5.5.11 License Amendment Request ML22319A1242022-11-15015 November 2022 NRC Slides for November 15, 2022 Public Meeting on Part 52 Lessons Learned 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 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 ML22265A0982022-09-22022 September 2022 NRC Slides on Part 52 Lessons Learned Construction Initiative for Public Meeting on 9/27/2022 ML22265A0972022-09-22022 September 2022 Southern Nuclear Company Slides on Lessons Learned from Part 52 Implementation for Public Meeting on 9/27/2022 ML22206A1712022-07-25025 July 2022 Dashboard Report 7-25-2022 ML22206A1682022-07-25025 July 2022 Dashboard Report 7-25-2022 ML22201A0442022-07-20020 July 2022 Voices Dashboard Report for Vogtle Unit 3 as of July 20, 2022 ML22138A3952022-05-24024 May 2022 Slides - SNC Slides - Pre-Submittal Meeting on May 24, 2022 - Vogtle RR RWST Suction Check Valves ML22144A0502022-05-24024 May 2022 Dashboard Report 5-24-2022 ML22144A0492022-05-24024 May 2022 Dashboard Report 5-24-2022 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 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 ML21193A0762021-07-0808 July 2021 ITAAC Related to Incore Instrument Thimble Assembly (Iita) ML21187A0972021-07-0808 July 2021 Late Filed Allegations (Lfa) Process ML21188A3612021-07-0606 July 2021 1Q 2021 Performance Summary U4 ML21188A3592021-07-0606 July 2021 1Q 2021 Performance Summary U3 ML21188A3622021-07-0606 July 2021 Archives ML21193A0772021-06-24024 June 2021 Exemption from Operator Written Examination and Operating Test for Unit 4 Licenses, 6-24-21 Pre-submittal Meeting ML21124A2522021-05-31031 May 2021 Request for Alternative to ASME Section XI and Section III Requirements for Repair of Reactor Vessel Head Penetrations - NRC Pre-submittal Meeting May 10, 2021 (EPID L-2021-LRM-0047) (Slides) ML21085A4902021-05-19019 May 2021 Risk-informed Resolution of Generic Letter 2004-02 ML21113A2272021-04-23023 April 2021 Readiness Group Public Meeting Presentation Slides - April 28, 2021 2024-01-08
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Lessons Learned from Part 52 Implementation TO M KO Z A K K O Z A K I N N O V AT I V E S A F E T Y S O L U T I O N S , I N C
Lessons Learned from Part 52 Implementation NOTABLE SUCCESSES CROP LESSONS LEARNED INSPECTION PROGRAM AND SIGNIFICANCE DETERMINATION PROCESS LESSONS LEARNED
Notable Successes IMC 2506-07.01: Construction Regulatory Oversight Framework The staff identified those aspects of licensee performance that are important to the mission and therefore merit regulatory oversight.
NRC met its mission to ensure public health and safety during the construction of Vogtle Unit 3 and continues to be effective while Unit 4 is under construction.
The cROP framework met its intended function
Notable Successes IMC 2506-07.17: ITAAC Closeout Process The results of the reviews of the ITAAC closure notifications (ICNs) by the staff and the documentation of the completion of the Construction Inspection Program for COL ITAAC facilitate the staff recommendation regarding the 10 CFR 52.103(g) finding on whether all the COL acceptance criteria are met.
Efficient and Effective implementation of the 10 CFR 52.103(g) finding process by both NRC and SNC
cROP Lessons Learned IMC 2506-03.01: The cROP is expected to be dynamic and to respond to changes in the nuclear power industry and construction experience. Therefore, the program office expects the regions and inspectors to identify challenges in implementing the program, and to recommend improvements to the program for consideration by the program office.
SNC recommended that industry lessons learned and ROP improvements be implemented in a timely manner for units under construction.
I endorse this recommendation. Consider more closely monitoring ROP improvements/revisions for timely incorporation into the cROP. Also, consider revising wording to expect all stakeholders to recommend improvements, not just regions and inspectors - and actively solicit and incorporate improvement recommendations
Inspection Program Lessons Learned 2506-07.07: The NRC staff can increase or decrease the number of construction activities and SSCs planned for inspection based on program results. The NRC staff will review and adjust the number of SSCs to be inspected as part of the annual performance review assessment process described in IMC 2505, Periodic Assessment of Construction Inspection Program Results. This can be done at any stage of the annual assessment process, including during continuous, quarterly, or end-of-cycle reviews.
Incorporate this assessment (and inspection) program flexibility into the inspection planning process, especially to gain efficiencies when construction projects extend beyond original completion schedules. For instance, per 2506-07.07 guidance, successfully completed inspections do not need to be repeated (e.g., foundations and concrete inspections at Vogtle 3 and 4).
Inspection Program Lessons Learned 2506-07.16 Construction Project Resource Estimate. The initial direct inspection effort estimate is 35,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> per unit over the life of the construction project. This estimate is based on the inspection hours that were expended during construction of the last several completed reactor units.
2506A03.03: Staffing levels at the construction resident offices will depend on many factors but will largely be based on the amount and type of ITAAC activities occurring on-site.
Resource estimate did not include indirect hours, which were approximately 3x direct hours. Indirect resource expenditures do not align with past NRC resource budget models and appears to be a direct correlation to the construction resident inspector office (CRO) staffing levels. Include indirect hours in construction project resource estimate. Consider a detailed review of CRO staffing levels and management of indirect hours and appropriately apply lessons learned to future construction projects.
Significance Determination Process Lessons Learned The SDP essentially begins with IMC 0613, Appendix B, Issue Screening.
Current screening does not provide licensee identification credit for potentially greater than green findings.
A goal of the cROP is to prevent latent construction deficiencies from impacting operations A licensee identified violation, when properly corrected, will not impact plant operations Screen licensee identified violations to a minor violation
Significance Determination Process Lessons Learned In the initial version of IMC 2505, the significance of findings was determined using a traditional enforcement approach. The staff provided a description of the construction assessment program to the Commission in SECY-08-0155, Update on the Development of the Construction Inspection Program for New Reactor Construction under 10 CFR Part 52, dated October 17, 2008.
On December 5, 2008, the Commission issued SRM M081022, which directed the staff to reconsider the construction assessment process as presented in IMC 2505 and propose policy options to the Commission. The Commission directed that the staff should address the inclusion in the construction oversight process of objective elements such as construction program performance indicators (PIs) and significance determination processes (SDPs) analogous to those used in the ROP.
Consider replacing the existing SDP with traditional enforcement as was originally intended for determining the significance of findings. This can be implemented within the cROP framework, but will most likely need Commission approval given the direction provided in SRM M081022.
Significance Determination Process Lessons Learned AP 1000 Construction Significance Determination Matrix Row 4 Green White Yellow Red Row 3 Green Green White Yellow Quality of Construction Row 2 Green Green Green White Row 1 Green Green Green Green Very Low Low Intermediate High System/Structure Risk Importance
Significance Determination Process Lessons Learned AP 1000 Construction Significance Determination Matrix has an unintended consequence Matrix Structure results in different significance for similar findings Example: preliminary significance for Vogtle Unit 3 electrical separation findings Consider eliminating the use of the Construction Significance Determination Matrix in the construction SDP.
Utilize risk-informed qualitative analyses to estimate the risk significance of inspection findings related to licensee performance in meeting construction Cornerstone objectives and performance expectations (see ROP deterministic SDPs in IMC 0609 Appendices). This approach can be applied to traditional enforcement severity level determinations.
Significance Determination Process Lessons Learned Ideas for risk-informed qualitative analyses Incorporate Matrix Y-axis - Focus on Quality of Construction vs Impairing Design Function Clarify guidance for Quality Assuarance Program breakdowns and incorporate into significance determination - must be present for escalated enforcement (greater than green/Severity Level III or higher)
Consider likelihood of subsequent licensee identification of a finding through remaining licensee processes, such as remaining QC inspections, ITAAC closure process, etc.
Conclusions The cROP worked as intended to ensure safety during construction - keep existing framework Capture NRC and licensee best practices from 10 CFR 52.103(g) finding Implement Traditional Enforcement for Significance Determination, if approved.
Regardless, utilize risk-informed qualitative analyses to estimate the risk significance Eliminate Construction Significance Determination Matrix to avoid unintended consequences