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Category:Slides and Viewgraphs
MONTHYEARML24038A1742024-02-0707 February 2024
Pre-submittal Meeting Slides
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Slides - Modification of Browns Ferry Technical Specifications to Eliminate LCO 3.3.2.1 Actions C.2.1.1 and C.2.1.2 for Rod Worth
ML24003A8532024-01-0303 January 2024
January 4, 2024 Presubmittal Meeting Presentation-Risk Informed Process for Evaluations (RIPE) License Amendment Request for Safety Injection Tank (SIT) LCO (EPID: L?2023?LRM-0108)
ML23296A0162023-10-20020 October 2023
October 20, 2023 Presubmittal Meeting Presentation - 1R24 Pressurizer Nozzle Repair - RR-70 (EPID: L?2023?LLR-0057)
ML23240A3232023-08-31031 August 2023
APS Presentation Slides for Pre-Submittal Meeting on 8/31/23, Alloy-600 Management Program Plan
ML23192A0102023-07-11011 July 2023
NRC RIPE 7-11-23 Public Meeting Presentation Slides
ML23144A0252023-05-25025 May 2023
APS Presentation Slides for Pre-Submittal Meeting on 5/25/23, Przr Surge Line
ML23093A0252023-04-30030 April 2023
April 5, 2023, Presubmittal Meeting Presentation - Containment Temperature and Safety Injection Tank Volume Requirements LAR
ML23055B0572023-03-0101 March 2023
March 1, 2023 Presubmittal Meeting Presentation - Request for Use of Mururoa V4F1 and MTH2 Supplied Air Suits (EPID: L?2023?LRM-0012)
ML22312A5952022-11-0808 November 2022
Independent Spent Fuel Storage Installation, Submittal of Annual Financial Reports 2021
ML22299A1812022-10-26026 October 2022
Presubmittal Meeting Presentation - License Amendment Request - Adoption of TSTF-107-A Separate Control Rods That Are Untrippable Versus Inoperable and Change to TS 3.1.5 Condition B (EPID: L?2021?LRM-0081)
ML22096A0052022-04-0606 April 2022
TSTF-487 LAR Pre-submittal Public Meeting Presentation Slides
ML22025A0012022-01-25025 January 2022
1/25/22 Pre-submittal Meeting Presentation Slides for RR-69 to Extend Containment Tendon Inspection by Three Months Beyond 2/8/22
ML21342A0502021-12-0808 December 2021
TSTF-567 LAR Pre-submittal Public Meeting Presentation Slides
ML21320A1032021-11-17017 November 2021
RIPE Exemption 11-17-21 Pre-submittal Public Meeting Presentation Slides
ML21278B0912021-10-0606 October 2021
Presubmittal Meeting with Arizona Public Service Company Regarding Relief Request No. 68 for Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (EPID L-2021-LRM-0104) (Slides)
ML21243A5432021-09-0101 September 2021
Request for Partial Exemption from 10 CFR 50.62(c)(1) Risk-Informed Process for Evaluations (RIPE)
ML21194A2502021-08-10010 August 2021
RIC 2021 - Ai EPRI-Artificial Intelligence and Development at EPRI
ML21165A1832021-06-14014 June 2021
RR-67 6-16-21 Pre-Submittal Public Meeting Presentation Slides
ML21131A0132021-05-13013 May 2021
License Transfer from Pnm to SRP, 5-13-21 Pre-submittal Public Meeting Presentation Slides
ML21130A6462021-05-13013 May 2021
Pre-Submittal Meeting with NRC on May 13, 2021 Application for Transfer of Minority Interests in Palo Verde Nuclear Generating Station, Units 1 and 2 Subject to Expiring Leases
ML21055A8502021-02-24024 February 2021
Public Meeting Summary
ML21025A0032021-01-26026 January 2021
Risk-Informed Process for Evaluations (RIPE) - NEI Public Meeting Presentation Slides
ML21025A0042021-01-25025 January 2021
Risk-Informed Process for Evaluations (RIPE) - NRC Public Meeting Presentation Slides
ML21011A2752021-01-0606 January 2021
License Amendment Request (LAR) to Revise Containment Leakage Rate Testing Program Frequencies - NRC Pre-Submittal Meeting, January 6, 2021 (Presentation Slides)
ML20171A2352020-06-24024 June 2020
Inservice Testing - Supplemental Position Indication Relief Request - NRC Pre-Application Meeting - June 24, 2020
ML19060A2982019-03-0101 March 2019
Transmittal of Audit Presentation Slides Regarding License Amendment Request and Exemption Request to Support the Implementation of Framatome CE16HTP Fuel
ML17003A0762017-01-10010 January 2017
Regulatory Audit Report for the November 2-3, 2016, Audit at the Westinghouse Facility in Rockville, MD, for the License Amendment and Exemption Requests Associated with Next Generation Fuel (CAC Nos. MF8076-MF8081)
ML17003A0352017-01-0404 January 2017
Summary of Pre-Application Meeting with Arizona Public Service to Discuss a Proposed Second Emergency License Amendment Request to Revise Technical Specification 3.8.1, AC (Alternating Current) Sources - Operating, for Palo Verde Nuclear
ML17003A0332016-12-29029 December 2016
Enclosure 2 - APS Meeting Slides
ML17003A0862016-11-0303 November 2016
Enclosure 2 Slides Regulatory Audit Report for November 2-3, 2016
ML16253A4112016-09-0707 September 2016
Palo Verde Nuclear Generating Station Generic Letter 2004-02 - September 7, 2016
ML16083A4722016-03-24024 March 2016
NRC Subsequent Pre-Submittal Meeting Next Generation Fuel - Palo Verde, Units 1, 2, and 3
ML16014A1102016-01-20020 January 2016
Draft APS Slides for January 20, 2015, Public Meeting with APS Regarding Upcoming Next Generation Fuel License Amendment Request for Palo Verde, Units 1, 2, and 3
ML15348A0542015-12-15015 December 2015
Slides for December 17, 2015 Public Meeting with APS on Resolution of GL 2004-02
ML15244B2632015-08-27027 August 2015
Slides for Public Meeting with Arizona Public Service Company to Discuss License Amendment Request for Palo Verde Regarding Revised Methodology for Spent Fuel Pool Criticality Analysis
ML15236A1342015-08-26026 August 2015
Presentation Slides for Public Meeting with Arizona Public Service Generic Letter 2004-02 for Palo Verde Nuclear Generating Station, Units 1, 2, and 3
ML15159B2972015-06-0909 June 2015
Near-Term Task Force Recommendation 2.1 (R2.1) Seismic Hazard Evaluation - Arizona Public Service, Palo Verde Nuclear Generating Station Public Meeting - June 9, 2015
ML15156B3312015-06-0909 June 2015
Public Meeting Slides on R2.1 Seismic Hazard Re-Evaluation
ML15134A3592015-05-11011 May 2015
5/11/2015, Meeting Slide Regarding Pre-Submittal Meeting for Palo Verde Unit 1, 2, and 3 Updated Spent Fuel Pool Criticality Analysis
ML15126A2072015-05-11011 May 2015
Presentation Slides for Prelicensing Meeting with Arizon Public Service Company to Discuss License Amendment Request for Palo Verde, Units 1, 2, and 3,
ML15103A2882015-04-0909 April 2015
Presentation on Potential Relief Request About Pressure Boundary Leakage on Reactor Coolant Pump 2A Pipe Nozzle
ML15070A2522015-02-18018 February 2015
Pre-Submittal Public Meeting Final Slides on Risk-Informed Completion Times.
ML15042A4152015-02-11011 February 2015
Pre-Submittal Public Meeting Draft Slides on Risk- Informed Completion Times
ML14184B4112014-06-11011 June 2014
Nrc/Nei/Utility MTG 6/11/14
ML14149A5092014-04-23023 April 2014
4/23/14 Meeting Slide for Palo Verde Nuclear Generating Station, Units 1, 2, and 3 Re. Sig Tube Inspection
ML14098A1832014-04-0202 April 2014
4/2/2014 Meeting Slide for Bottom-Mounted Instrument (Bmi) Relief Request 52 Pre-Submittal Meeting
ML13309A7202013-11-0505 November 2013
Meeting Presentation for November 5, 2013 Public Meeting Regarding Incorporation of NEI 11-04 Into the QA Program at Palo Verde Nuclear Generating Station, Units 1, 2, and 3
ML13308B3322013-11-0404 November 2013
Meeting Presentation for November 4, 2013 Public Meeting Regarding Bmi Leakage
ML13197A0952013-07-11011 July 2013
7/11/13 Meeting Slides - Implementation of STAR Program and Replacement of the 2/3 Cycle Mtc Measurement
2024-02-07
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NEI Gas/Void Workshop Palo Verde Nuclear Generating Station Optira Unit 1 SI Pipe Insulation ON/OFF Study Savannah, GA January 2010
Palo Verde Nuclear Generating Station (PVNGS)
Optira p (Omaha,
( , NE))
Laser Scanning Insulation ON/OFF Study
Palo Verde Nuclear Generating Station (PVNGS)
- Safety Injection System Engineer
Optira San Jose, CA
- Chief Operating Officer
- gconklin@Optira.com
- 408-615-0120 408 615 0120
PVNGS - CE System 80 2 Identical Emergency Core Cooling System (ECCS)
Trains Separate suction feed from the Refueling Water Tank (RWT)
Separate suction feed from the Containment Recirculation Sump 1 High Pressure Safety Injection (HPSI) pump per train 1 Low Pressure Safety Injection (LPSI) pump per train 1 Containment Spray (CS) pump per train
Resulting Actions from Generic Letter 2008-2008-01 Extensive laser scanning of the SI piping to determine pipe slope and high points To minimize T i i i subsequent b cost, Unit U i 1 was completely laser scanned with insulation on and then off (insulation removed on horizontal piping only)
Resulting Actions from Generic Letter 2008-2008-01 PVNGS uses 3 types of insulation on the SI system.
Aluminum clad Calcium Silicate (CalSil) in the Auxiliary Building Stainless Steel Reflective Mirror (RMI) in the Containment Building Aluminum clad Formed Fiberglass (FFG) in the Essential Pipe Tunnel
Resulting Actions from Generic Letter 2008-2008-01 Laser Scanned approximately 4800 feet of SI piping 3300 Auxiliary Building (CalSil) 1300 Containment (RMI) 200 Essential Pipe Tunnel (FFG)
Comparison performed on approximately 3500 feet of SI piping 2200 Auxiliary Building (CalSil) 1100 Containment (RMI) 200 Essential Pipe Tunnel (FFG)
Resulting Actions from Generic Letter 2008- 2008-01 Pipe Diameters Scanned Aux Suction - 24 (Sump), 20 (RWT), 18, 16, 14, 10 Discharge - 20 20,, 12 12,, 10 10,, 66,, 44,, 33,, 22 CNTMT Suction - 24 (Sump), 16 (SDC)
Discharge - 14, 12, 10, 3 Essential Pipe Tunnel Suction - 20 (RWT)
Resulting Actions from Generic Letter 2008-2008-01 Optira performed a statistical (least squared linear regression test) comparison for the 3 individual types of insulation (Al clad Calcium Silicate (CalSil),
(CalSil) Al clad formed fiberglass (FFG) and Reflective Mirror (RMI))
Data Collection Data Collected with Phase-Phase-Based 3D Laser Scanners.
Lasers validated twice daily by modeling Optira designed calibration artifacts traceable to NIST Entire SI system placed on plant grid coordinates using Total Station Survey System Acceptable tolerance limits at +/-
+/-3mm and below
Data Extraction Leica Cyclone-Cyclone-MODEL v.6 Double Entry Method In--house Data Entry Application In Microsoft SQL Server 2005 Segment Centerline Endpoints WITH Insulation WITHOUT Insulation
Typical One Line Drawing One Line Drawings are AutoCAD views of a system by elevation and used to depict and then calculate high points along a centerline of pipe along that system.
Data Processing In-house Data Transform Application In-Normalized Data for each Type [ 0, 1 ]
Microsoft Excel Analysis Pack Add Add--in Regression Case 1 as real value Case 2 as sample value Intra Partitions based on residual clustering
Model Validation R values extremely good But, R alone is not enough Graphical model confirmation Regression Model plots stacked Visually, the sample data fits the modeled values
Resulting Actions from Generic Letter 2008-2008-01 Least squared linear regression test demonstrated CalSil and FFG were excellent predictors of the un-insulated pipes high point having accuracy between 99.89 99 89 and 99.99 99 99 percent, while the RMI insulation proved less than 45.00 percent accurate based on the Adjusted R from the respective regression models
Regression Fits RMI Model CalSil Model 0.08 1.2 0.07 1
0.06 0.8 0.05 0.04 Expected Expected 0.6 S S(B) 0.03 0.4 0.02 0.2 0.01 0
0 0 0.02 0.04 0.06 0.08 0 0.05 0.1 0.15 0.2 0.25
QUESTIONS
