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Category:Meeting Briefing Package/Handouts
MONTHYEARML24311A1872024-11-0707 November 2024 V.C. Summer EDG SDP for Nextera RUG Meeting - 11.7.2024 - Rev. 0 ML24250A1072024-09-0505 September 2024 Pre-Submittal Meeting Slides for VCS COLR Relocation and WCAP-17661 LAR - 9-9-24 ML24102A0212024-04-10010 April 2024 V. C. Summer 2023 Annual Assessment Public Meeting Presentation Slides - April 22, 2024 ML24008A2112024-01-25025 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) ML23313A1292023-11-0909 November 2023 Environmental Scoping Meeting for V.C. Summer Subsequent License Renewal Application - November 14 Meeting Slides ML23131A4182023-05-25025 May 2023 V.C. Summer Nuclear Station 2022 Annual Assessment Meeting.Pptx ML22115A0502022-04-21021 April 2022 VC Summer, 2021 Annual Assessment Meeting ML20091G7232020-03-31031 March 2020 V.C. Summer 2019 Assessment Meeting Presentation ML18144A1482018-05-24024 May 2018 Public Meeting Summary - Virgil C. Summer Nuclear Station Docket No. 50-395 ML14323A4522014-11-19019 November 2014 V.C. Summer Construction Update ML14266A3912014-09-23023 September 2014 September 23, 2014, Category 1 Public Meeting with V. C. Summer - Presentation Slides ML14232A5372014-08-21021 August 2014 8-21-14 CIP Mtg Slides - FFD and ITAAC ML14219A4762014-08-0707 August 2014 Operating Experience on Initial Test Program ML14106A4762014-04-16016 April 2014 End of Cycle 2013 Public Meeting Memo ML14057A4202014-02-27027 February 2014 Public Meeting 2/27/2014 VCS Construction Update ML14028A4272014-01-23023 January 2014 Vendor Inspection Finding & ITAAC (Pdf) ML13309A8592013-11-0505 November 2013 V. C. Summer Construction Status and Lesson Learned AD Torres ML13170A1302013-06-18018 June 2013 Public Slide - NFPA 805 Transient Combustible Controls ML13170A1192013-06-18018 June 2013 Public Slide - Control Room Evacuation Due to Fire, Based on NFPA 805 ML13123A1472013-05-0303 May 2013 Summary of Category 1 Public Meeting with South Carolina Electric and Gas,Virgil C. Summer Nuclear Station, Units 2 and 3, Annual Assessment ML13098A8042013-03-26026 March 2013 Combined Emergency Plan Review ML12228A6292012-08-16016 August 2012 Report ITAAC Presentation ML12157A0452012-06-0404 June 2012 5/24/2012 - Summary of Category 3 Public Meeting - Virgil C. Summer Nuclear Station Unit 1 Annual Assessment and NRC Construction Oversight of Units 2 and 3 Combined Licenses ML11350A0902011-12-20020 December 2011 Draft VC Summer Public Meeting 20 Dec 2011 ML11242A0502011-08-30030 August 2011 Slides - Licensee Perspective on ITAAC Completion Process NRC Commission Briefing ML1120707792011-07-26026 July 2011 Enclosure 3: Presentation Slides/Handouts ML1115204732011-06-0101 June 2011 Meeting Summary - V. C. Summer - Presentation Slides ML1016705202010-06-17017 June 2010 Fire Protection Screening Criteria - V.C. Summer Nuclear Station ML1012600092010-05-0505 May 2010 Meeting Posters ML1012600102010-05-0505 May 2010 Meeting Slides ML0911000692009-04-17017 April 2009 Summary of Meeting with Public/Open House to Discuss NRC Reactor Oversight Process and the Annual Assessment of the Virgil C. Summer Nuclear Station ML0835204162008-12-16016 December 2008 Public Meeting Summary, Virgil C. Summer Nuclear Station, Docket No. 05-395 ML0811405532008-04-23023 April 2008 V. C. Summer Nuclear Station, Slides - Refuel 17 Plans ML0723400122007-08-22022 August 2007 Public Outreach Meeting South Carolina E&G Summer Nuclear Power Plant Combined License Application ML0715806282007-05-31031 May 2007 Enclosure 8 - OBE Exceedance Issues ML0713500662007-05-0202 May 2007 Meeting Handout on RF16 Outage Review V.C. Summer ML0713501092007-05-0202 May 2007 Meeting Handout on Summary of HP Performance During RF16 ML0713501062007-05-0202 May 2007 Meeting Handout on CRDM Canopy Seal Clamp Installation ML0713501022007-05-0202 May 2007 Meeting Handout on RB Tendon/Iwe/Iwl Inspection ML0713500972007-05-0202 May 2007 Meeting Handout on Alternate Safety Power Source - Summer ML0706703232007-03-0101 March 2007 (Westinghouse AP1000) ML0629904782006-10-24024 October 2006 VC Summer, Enclosure to Meeting Summary, September 13, 2006, Meeting with South Carolina Electric & Gas, on Generic Letter 96-06 (TAC M96872) ML0707202262006-06-22022 June 2006 Sce&G VC Summer Site - Site Characterization Visit (Handouts) ML0609405532006-03-20020 March 2006 Meeting Summary - Enclosure 2. Handouts for Meeting with South Carolina Electric & Gas Company Re Results of Root Cause Evaluation for the High Failure Rate on the January 10, 2006, Operator Licensing Initial Written Examination ML0600304352005-12-30030 December 2005 Rii Presentation Revised - RF-15 Outage Information IR 05000395/20050072005-03-10010 March 2005 Final Significance Determination for a Green Finding (NRC IR 05000395/2005007 Virgil C. Summer Nuclear Station) ML0409805332004-03-11011 March 2004 RIC 2004 Presentation - T11 - Alexander Marion - Emergent Technical Topics ML0404902122004-01-28028 January 2004 Handouts from 01/28/04 Management Meeting ML0328101372003-10-0606 October 2003 Presentation Slides for Post-Refueling Outage Meeting 2024-09-05
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24311A1872024-11-0707 November 2024 V.C. Summer EDG SDP for Nextera RUG Meeting - 11.7.2024 - Rev. 0 ML24250A1072024-09-0505 September 2024 Pre-Submittal Meeting Slides for VCS COLR Relocation and WCAP-17661 LAR - 9-9-24 ML24101A0642024-04-22022 April 2024 2023 Annual Public Assessment Meeting Presentation Slides ML24008A2112024-01-25025 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) 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 ML23131A4182023-05-25025 May 2023 V.C. Summer Nuclear Station 2022 Annual Assessment Meeting.Pptx ML22115A0502022-04-21021 April 2022 VC Summer, 2021 Annual Assessment Meeting ML20091G7232020-03-31031 March 2020 V.C. Summer 2019 Assessment Meeting Presentation ML18144A1482018-05-24024 May 2018 Public Meeting Summary - Virgil C. Summer Nuclear Station Docket No. 50-395 ML18067A1212018-03-15015 March 2018 March 15, 2018, Public Meeting Presentation Regarding NFPA-805 Application ML17087A1542017-03-28028 March 2017 Response to Request for Additional Information on VC Summer Sfpli - Elevation View ML14323A4522014-11-19019 November 2014 V.C. Summer Construction Update ML14266A3912014-09-23023 September 2014 September 23, 2014, Category 1 Public Meeting with V. C. Summer - Presentation Slides ML14232A5372014-08-21021 August 2014 8-21-14 CIP Mtg Slides - FFD and ITAAC ML14219A4762014-08-0707 August 2014 Operating Experience on Initial Test Program ML14057A4202014-02-27027 February 2014 Public Meeting 2/27/2014 VCS Construction Update ML14028A4272014-01-23023 January 2014 Vendor Inspection Finding & ITAAC (Pdf) ML13309A8592013-11-0505 November 2013 V. C. Summer Construction Status and Lesson Learned AD Torres ML13170A1302013-06-18018 June 2013 Public Slide - NFPA 805 Transient Combustible Controls ML13170A1192013-06-18018 June 2013 Public Slide - Control Room Evacuation Due to Fire, Based on NFPA 805 ML13123A1472013-05-0303 May 2013 Summary of Category 1 Public Meeting with South Carolina Electric and Gas,Virgil C. Summer Nuclear Station, Units 2 and 3, Annual Assessment ML13098A8042013-03-26026 March 2013 Combined Emergency Plan Review ML12228A6292012-08-16016 August 2012 Report ITAAC Presentation ML12157A0452012-06-0404 June 2012 5/24/2012 - Summary of Category 3 Public Meeting - Virgil C. Summer Nuclear Station Unit 1 Annual Assessment and NRC Construction Oversight of Units 2 and 3 Combined Licenses ML11350A0902011-12-20020 December 2011 Draft VC Summer Public Meeting 20 Dec 2011 ML11242A0502011-08-30030 August 2011 Slides - Licensee Perspective on ITAAC Completion Process NRC Commission Briefing ML1120707792011-07-26026 July 2011 Enclosure 3: Presentation Slides/Handouts ML1115204732011-06-0101 June 2011 Meeting Summary - V. C. Summer - Presentation Slides ML1016705202010-06-17017 June 2010 Fire Protection Screening Criteria - V.C. Summer Nuclear Station ML1012600102010-05-0505 May 2010 Meeting Slides ML1012600092010-05-0505 May 2010 Meeting Posters ML0835204162008-12-16016 December 2008 Public Meeting Summary, Virgil C. Summer Nuclear Station, Docket No. 05-395 ML11216A2292008-12-0202 December 2008 0523 - R504P - Westinghouse Advanced Technology - 07.2 VC Summer Inadvertent Criticality ML0811405532008-04-23023 April 2008 V. C. Summer Nuclear Station, Slides - Refuel 17 Plans ML0723400122007-08-22022 August 2007 Public Outreach Meeting South Carolina E&G Summer Nuclear Power Plant Combined License Application IR 05000395/20075022007-07-30030 July 2007 Summary of Public Meeting - Virgil C. Summer Nuclear Station, to Discuss Significance on Apparent Violation Documented in Inspection Report 50-395-07-502 ML0715806282007-05-31031 May 2007 Enclosure 8 - OBE Exceedance Issues ML0713500662007-05-0202 May 2007 Meeting Handout on RF16 Outage Review V.C. Summer ML0713500972007-05-0202 May 2007 Meeting Handout on Alternate Safety Power Source - Summer ML0713501022007-05-0202 May 2007 Meeting Handout on RB Tendon/Iwe/Iwl Inspection ML0713501062007-05-0202 May 2007 Meeting Handout on CRDM Canopy Seal Clamp Installation ML0713501092007-05-0202 May 2007 Meeting Handout on Summary of HP Performance During RF16 ML0706703232007-03-0101 March 2007 (Westinghouse AP1000) ML0627602452006-09-27027 September 2006 V. C. Summer Nuclear Station RF-16 Outage Information ML0618002632006-09-18018 September 2006 Crack Growth Rates in a PWR Environment of Nickel-Base Alloys from Davis-Besse and V. C. Summer Plants ML0707202262006-06-22022 June 2006 Sce&G VC Summer Site - Site Characterization Visit (Handouts) ML0615106012006-05-23023 May 2006 EPRI HRA Users Group Review of Draft NUREG-1842 2024-09-05
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Text
Vendor Inspection Findings &
ITAAC Defining Material and Extent of Forward Projection 1/23/2014
Agenda
- Relevant Definitions
- IMC 0617 Terminology Comparison
- 2 Examples
- Extent of Forward Projection
- Background
- Potential Interpretations
- 2 Examples
Relevant Definitions
- ITAAC Finding (IMC 2507) An inspection finding that is material to the ITAAC acceptance criteria.
(IMC 2506) - a finding that is identified through the implementation of the construction inspection program that is associated with a specific ITAAC and is material to the ITAAC acceptance criteria.
information that has a natural tendency or capability to influence an agency decision maker in either determining whether the prescribed inspection, test, or analysis was performed as required, or finding that the prescribed acceptance criterion is met
IMC 0617 Terminology
- E.8.2: Does the issue, if left uncorrected, represent a condition adverse to quality that renders the quality of a structure, system, or component (SSC) or activity, unacceptable or indeterminate?
- E.8.3: Does the issue, if left uncorrected, represent a failure to establish, implement or maintain a process, program, procedure, or quality oversight function that could render the quality of the SCC or activity unacceptable or indeterminate?
- E.8.4: If left uncorrected, could the issue adversely affect the closure of an Inspection, Test, Analyses, and Acceptance Criteria (ITAAC)?
2 Examples from Licensee Letter ML13156A136 Referenced ITAAC for 1st Example ITAAC Design Commitment Inspections, Tests, Acceptance Criteria No. Analyses 2.2.01.0 5. The seismic Category I ii) Type tests, ii) A report exists and 5.ii equipment identified in analyses, or a concludes that the seismic (2.2.02.05 a.ii, Table 2.2.1 1 can withstand combination of type Category I equipment can 2.2.05.05 seismic design basis loads tests and analyses of withstand seismic design a.ii, without loss of structural seismic Category I basis dynamic loads 2.3.07.05. integrity and safety equipment will be without loss of structural ii, 2.7.01.05. function. performed. integrity and safety ii also) function.
2 Examples from Licensee Letter 1st Example Inspection Limitorque Actuator Seismic Qualification NON 99901412/2012-201-02 (Summary Letter Pg 7)
NON Accelerometers for vibrational aging were calibrated from 25 to Summary 500 Hz, but used over a frequency range of 5 to 100 Hz.
By using accelerometers outside of the calibrated range, it cannot be assured that equivalent fatigue effects were produced to plant operating conditions, and the seismic qualification does not meet requirements.
Comment It is clear that this condition materially affects the acceptance criteria that the equipment can withstand seismic design basis loads. (If the condition were not corrected, the acceptance criteria would not be met.)
2nd Example from Licensee Letter Referenced ITAAC ITAAC Design Commitment Inspections, Tests, Acceptance Criteria No. Analyses 2.2.03.0 2.a) The components Inspection will be The ASME Code Section III 2a identified in Table 2.2.3-1 conducted of the as- design reports exist for as ASME Code Section III built components as the as-built components are designed and documented in the identified in Table 2.2.3-1 constructed in accordance ASME design as ASME Code Section III.
with ASME Code Section III reports.
requirements.
2.2.03.0 5.a) The seismic Category I ii) Type tests, ii) A report exists and 5a.ii equipment identified in analyses, or a concludes that the seismic Table 2.2.3-1 can combination of type Category I equipment can withstand seismic design tests and analyses of withstand seismic design basis loads without loss of seismic Category I basis dynamic loads safety function. equipment will be without loss of safety performed. function.
2 nd Example from Licensee Letter Inspection Enertech Check Valve Inspection NON 99901377/2012-2012-02 (Summary Letter pg 13)
NON Inspection of QME-1 active safety function testing of nozzle check valves.
Summary Commercial Grade Dedication of procured calibration services and certain non-pressure boundary items did not include adequate technical evaluations. The testing did not include all QME-1-2007 specified operating conditions.
if left uncorrected, these issues could call into question the validity of the qualification testing of the as-built check valves to ensure they perform their safety-related function and change position under design basis conditions in accordance with ASME Code Section III and ITAAC 2.2.03.05a.ii and 2.2.03.02a.
Comment It is not clear how these conditions materially affect the acceptance criteria that the valves can withstand seismic design basis loads, since the valves are qualified by analysis only, and do not utilize this QME testing.
Likewise for fabrication in accordance with ASME Code Section III. (If the condition were not corrected, how does this result in the conclusion that acceptance criteria are not met?). There are no ITAAC for QME-1 testing of these valves.
Background on Forward Projection
- Based on review of current inspection guidance and recent Vendor Inspection Reports, it is not clear to what degree (if any) vendor Notices of Nonconformance are/will be projected forward to determine potential future effects on ITAAC acceptance criteria.
If {condition} > Then {effect} >> Then {material effect on AC}
Potential Interpretations Potential Interpretation Description No Forward Projection Each Condition or NON is assessed as it exists at the current time. Secondary or Tertiary effects are not projected. The current condition is directly compared to the Acceptance Criteria and asked, If this condition were not corrected, are the Acceptance Criteria not met?
Subjective The inspector considers potential downstream effects or secondary/tertiary follow-on effects of the condition, as well as Licensee processes in place to identify and correct the condition prior to ITAAC completion, and determines if the condition could have a material effect on the acceptance criteria in the future.
Other Discussion at Meeting
1st Example from Recent Inspections Referenced ITAAC ITAAC Design Commitment Inspections, Tests, Acceptance Criteria No. Analyses 2.1.02.1 12.a) The automatic i) Tests or type tests i) A test report exists and 2ai depressurization valves of motor-operated concludes that each (2.2.02.11 ai, identified in Table 2.1.2-1 valves will be motor-operated valve 2.2.03.11 perform an active safety- performed that changes position as ai, and related function to change demonstrate the indicated in Table 2.1.2-1 2.3.06.12 position as indicated in the capability of the under design conditions.
ai as well) table. valve to operate under its design conditions.
1st Example from Recent Inspections Inspection Motor Operated Valve QME-1 Flow Testing NON 99900905/2012-201-01 NON Due to test lab capacity, partial stroke segments were used Summary during steam and water flow testing instead of a continuous stroke. The team found that the qualification plan did not provide written justification that this test method demonstrates valve performance consistent with a continuous valve stroke as intermittent partial stroking of the valve could cloak problems with the valve that might exist during a continuous stroking cycle.
Comment This condition was assessed as it exists, with no forward projection. To paraphrase: This condition (partial stroking without written justification) if left uncorrected, would have a material effect on the conclusion that each MOV changes position as indicated under design conditions.
2nd Example from Recent Inspections Referenced ITAAC ITAAC Design Commitment Inspections, Tests, Acceptance Criteria No. Analyses 2.1.02.1 12.a) The automatic v) Inspection will be v) Inspection will be 2a.v depressurization valves performed for the performed for the identified in Table 2.1.2-1 existence of a report existence of a report perform an active safety- verifying that the as- verifying that the as-built related function to change built squib valves are squib valves are bounded position as indicated in the bounded by the by the tests or type tests.
table. tests or type tests.
2nd Example from Recent Inspections Inspection Squib Valve Actuator Qualification NON 99900080/2013-201-02 NON Review of the manufacturing controls used on explosive Summary powder for the qualification cartridges determined that not all critical characteristics of the explosive powder mix were identified, nor has the vendor instituted controls sufficient to ensure the absence of contaminants from the explosive powder mix through inspections, tests, or analysis. This was assessed as having a material effect on the acceptance criteria that, the as-built squib valves are bounded by the tests or type tests.
Comment This condition in its current state affects only the qualification cartridges. The type tests were not complete, and the as-built valves were not fabricated or installed. This finding projects forward that the condition (process deficiency) will be used on the as-built valves, and will cause the future valves to not be bounded by the tested conditions.
Discussion/Questions