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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)
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
ML13170A1192013-06-18018 June 2013
Public Slide - Control Room Evacuation Due to Fire, Based on NFPA 805
ML13170A1302013-06-18018 June 2013
Public Slide - NFPA 805 Transient Combustible Controls
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
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
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
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
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
ML0609702982006-03-31031 March 2006
NRC Cy 2005 Annual Assessment Meeting, Virgil C. Summer Nuclear Station
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
2024-01-25
[Table view] |
Text
V. C. Summer Nuclear Station RF-15 Outage Information
Introduction- Jeff Archie Refuel 15- Alan Torres Corrective Action- Dave Lavigne
Refuel-15 Goals 3/4 Duration: 35 Days 3/4 Human Performance Events: <1 3/4 Recordable Injuries: < 1 3/4 Significant/Noteworthy Events: 0 3/4 Post 100% - 90 Day Capacity: 96%
3/4 Dose: 110 REM (to be adjusted based on source term)
Refuel-15 Major Modifications 3/4 Main Generator Rewind 3/4 RWST Automatic Swapover Logic 3/4 B RHR Pump Improved Shaft Design 3/4 CCW Crosstrain Relief Valve 3/4 IPCS Replacement
Refuel-15 Major Modifications 3/4 B RCP Flange Bolt Replacement 3/4 RBCU Fan Motor Upgrades 3/4 Install New 115KV Safety Power Feed to XSW-1DX (Initial Work) *
- To Provide for Decreased Core Damage Frequency
Refuel-15 Items of Interest 3/4 Reactor Vessel Visual Inspection 3/4 Pressurizer Nozzle Inspection 3/4 Flow Accelerated Corrosion Expansion 3/4 Emergency Feed Piping Cleaning and Inspection
Refuel-15 Items of Interest 3/4 Fuel Leak Inspection z Vendor Completed Root Cause
- Cause found to be improper chiller operation z Flow Validation z Enhanced Visual Inspection
Refuel 15 3/4 Critical Path Activities z Main Generator Rewind z B RCP Flange Leak Repair z Steam Generator Work (All Three SGs)
- 100% Primary Side Tube Inspection
- Install/Remove Nozzle Dams
Main Generator Rewind
Close-fitting slot wedges, with radial filler strips and conforming strips, are used to anchor the bar in place.
The wedges butt end-to-end in the slot. Side ripple springs are provided to suppress bar movement in the core slots.
The side ripple springs exert a sideways force on the bars, while the wedges, fillers and top ripple springs exert a radial force on the bars.
Photo 1 shows the existing generator windings with the generator rotor removed.
Photo 2 shows the endwindings being cut off of the old windings to facilitate bar removal.
Photo 7 shows the new windings fully installed and painted.
Reactor Coolant Pump Flange Gasket Replacement
Main Flange Leakage during RF14 Main Flange Leakage on B RCP located just below CCW inlet line. Not considered pressure boundary leakage, but is RCS leakage.
Main Flange Bolts are carbon steel and susceptible to Boric Acid corrosion; all other RCP materials are stainless steel.
Leakage Location on B RCP The leakage was initially discovered in RF14, so attempts were made to eliminate the leakage by de-tensioning the 24 main flange bolts then re-stretching them to tighten the joint. The leakage returned during startup, therefore gasket replacement is necessary.
RCP Internal Components Te eliminate main flange leakage, pump internals must be removed and two gaskets must be replaced.
Main Flange Gasket Locations Thermal Barrier Turning Vane Diffuser Diffuser Adapter Problems with Turning Vane to Thermal barrier bolts or Diffuser Adapter cap screws could lead to replacement of entire assembly during RF15.
RCP-3
B RHR Pump Modification
Brief Overview of RHR Project 3/4 A RHR Pump Modification (RF-14) z Spacer coupling z Upper & lower Hub Assembly z ALARA estimate 2.75 R, Actual .725 R 3/4 A RHR vent addition (RF-14) z ALARA estimate 1.1 R, Actual .590 R 3/4 B RHR to Be Performed in RF-15
Modified 8X20 WD/WDF Bearing Housing 18 by 18 seal opening Support stand with an 18 X 18 opening
The Spacer Coupling Upper (Driver)
Hub Assembly Lower (Pump)
Hub Assembly
Steam Generator Inspections
Program Enhancements
Refuel-15 Program Improvements 3/4 Program Changes z ISP-27, Electrical Safety z FME Controls z Confined Space Program z Contractor Controls
RF-15 Performance Improvements 3/4 Operating Experience Books 3/4 Daily Talking Points 3/4 Weekly Outage Newsletter 3/4 Rewarded Behaviors Program Utilize Human Performance Error Reduction Tools
Observations & Trending 3/4 Focused observations will be conducted during RF-15 based on challenges identified in RF-14 3/4 Feedback and Coaching is expected 3/4 Trend Wall insights using CER and Observation data will be communicated weekly
QUESTIONS
