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MONTHYEARML14077A3712014-03-18018 March 2014 Notice of Public Meeting with Arizona Public Service Company to Discuss Extension of Authorized Repair to Palo Verde, Unit 3, Bottom-Mounted Instrumentation to End of Unit 3 Operating Life Project stage: Meeting ML14098A1832014-04-0202 April 2014 4/2/2014 Meeting Slide for Bottom-Mounted Instrument (Bmi) Relief Request 52 Pre-Submittal Meeting Project stage: Meeting ML14099A4692014-04-21021 April 2014 Summary of 4/2/2014 Pre-Application Meeting with Arizona Public Service Company to Discuss Extension of Authorized Repair to Palo Verde, Unit 3, Bottom Mounted Instrumentation to End-of-Unit Life Project stage: Meeting 2014-04-02
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Category:Meeting Briefing Package/Handouts
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[Table view] Category:Slides and Viewgraphs
MONTHYEARML24038A1742024-02-0707 February 2024 Pre-submittal Meeting Slides ML24019A1512024-01-22022 January 2024 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. 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[Table view] |
Text
Palo Verde Unit 3 Bottom-Mounted Instrument (BMI)
Relief Request 52 Pre-submittal Meeting April 2, 2014
Palo Verde Participants/Attendees Ken House* Director, Design Engineering Tom Weber* Department Leader, Nuclear Regulatory Affairs Mike Hooshmand Department Leader, Mechanical/Civil Design Engineering Doug Hansen Senior Consulting Engineer, Program Engineering/Principal Level III Winston Borrero Senior Consulting Engineer, Design Engineering Ed Fernandez* Senior Metallurgist, Engineering Programs / EPRI MRP Inspection Chairman Gene Montgomery* Senior Engineer, Design Engineering (Mechanical NSSS)
Doug Killian Technical Consultant, AREVA Ashok Nana Supervisory/Advisory Engineer, AREVA Delbert Elkinton Senior Regulatory Affairs Consultant 2 NOTE:
Introduction Tom Weber Department Leader Nuclear Regulatory Affairs
Agenda Introduction Tom Weber Testing/Examination Results Ed Fernandez Summary of Analyses Gene Montgomery Relief Request #52 Tom Weber Closing Comments Ken House 4
Desired Meeting Outcomes Awareness/understanding of:
- Actions completed since RR#51 Repair of nozzle Destructive examination and metallurgical results Engineering analyses
- Relief Request #52 APS/Palo Verde understands NRC questions related to this issue 5
Unit 3 Reactor Vessel BMI Nozzle #3 2010 2013 As Found 2013 As Left 6
Half-Nozzle Repair Industry proven permanent repair Weld pad with new A690 nozzle ASME Code compliant Relocated pressure 52M Filler boundary 7
APS Approach Two separate relief requests
- RR#51 for one operating cycle
- Boat sample results not available
- Plant specific analysis not available NRC verbal approval on November 21 RR#52 planned for May 2014 8
Boat Sample Destructive Exam (DE) and Metallurgical Results Ed Fernandez Senior Metallurgist, Engineering Programs EPRI MRP Inspection TAC Chairman
Collection of Boat Sample Targeted Areas
- RCS leak entrance point
- Weld defect
- Axial crack
- Area of high reflectivity
- Unaffected Alloy 600 and 182 material 10
BMI Nozzle #3 4
1 2 3
Deepest: 0.378 Longest: 1.88 Overall width: 72º (1.87) 11
Destructive Evaluation Plan Boat Sample 3/4 How did cracking begin?
3/4 Propagation mechanism(s) of the observed cracks?
3/4 Nature, extent, and role of the weld inclusion zone?
3/4 Assembled Industry Team
- EPRI, Westinghouse, AREVA, Industry Peers 3/4 Metallurgical Analysis
- Visual inspections
- X-ray radiography
- High Resolution Replication Weld
- Scanning Electron Microscopy (SEM)
- Energy Dispersive Spectroscopy (EDS)
Nozzle
- Metallography 12
Sectioning (Piece B)
Boat Sample - Investigate Void Weld Wetted surface Piece B As-polished Nozzle Cut #2 10% oxalic etch 13
Sectioning (Piece B) 320x Boat Sample - Investigate Void 25x 360x Piece B Tube Weld Cut #2 360x 14
Crack #4 opened in Piece C1 Sectioning (Piece C)
Boat Sample - Investigate Crack #4 PWSCC Cut #2 Void ends just past Crack #4 Nozzle Weld Nozzle 15
Destructive Exam - Observations Two crack types identified
- Single weld solidification crack - in top of void
- All other observed cracks are characteristic of PWSCC All cracks were found to be associated with the void Wetted-surface-connected crack not found in boat sample No detrimental residual chemicals 16
Stress and Supporting Analyses Gene Montgomery Sr. Engineer, Design Engineering
Unit 3 BMI Nozzle #3 Repair Analyses and Reports ASME Code Section III analysis Welding residual stress analysis RPV shell J-groove weld crack growth analysis Remnant nozzle crack growth analysis Remnant nozzle structural & frequency analysis Corrosion assessment report Loose parts evaluation report 18
ASME Section III Class 1 Stress Analysis Remnant Nozzle Reactor Vessel Bottom Head Remnant J-groove Weld Repair Nozzle All ASME Section III Class 1 stress and fatigue requirements are met for the new primary pressure boundary repair nozzle Results from operating transient cycles applied to this model are input into the remnant J-groove weld crack & remnant nozzle crack growth analysis 19
Welding Residual Stress Analysis Boat sample removal, remnant nozzle severance, and a hypothetical repair weld sequence in accordance with MRP-287 are included in the model Welding residual stresses are input to the remnant J-groove weld crack &
remnant nozzle crack growth analysis 20
Residual Hoop Stress (PSI) at 70° F 21
RPV Shell J-Groove Weld Crack Growth Analysis Uphill Crack Model 3-D explicit ANSYS finite element radial-axial crack tip models Flaw Stability and Crack Driving Force EPFM criteria are met using lower bound J-R curve (from RG 1.161) and safety factors consistent with RR 51.
Downhill Crack Model 22
Remnant Nozzle Structural Integrity and Frequency Analysis Limit Load analysis demonstrates structural integrity of the remnant nozzle by showing the nozzle remains intact under primary loads Natural frequency remains above excitation frequency for vortex shedding Longitudinal crack growth analysis demonstrates the remnant nozzle will remain intact 23
Corrosion Assessment Small gap exists between original Alloy 600 nozzle and new Alloy 690 nozzle following repair Low-alloy steel corrosion rate due to interaction with primary coolant in operating reactors has proven to be extremely small WCAP-15973 documents method for evaluating corrosion of low alloy steel following half-nozzle repairs Palo Verde plant-specific analyses followed the WCAP methodology and demonstrated that long term corrosion of the low-alloy steel has a negligible impact on the BMI repair design with 0.072 radial bore corrosion in 40 years 24
Loose Parts Evaluation Top Surface area = 4.2 in2 Top Surface area = 4.2 in2 Assumed Maximum/Minimum potential J-groove weld material loose parts from BMI Nozzle #3 used by Westinghouse to assess impact on fuel assemblies and RCS flow paths 25
Summary and Conclusions Palo Verde implemented a half-nozzle repair on Unit 3, Nozzle #3 Code compliant repair with PWSCC resistant material (Alloy 690)
Permanent repair backed by extensive industry experience Plant specific analyses account for BMI design inputs in geometry, materials, operating transients and design conditions Detailed finite element models were used to define the internal J-groove welding residual stresses and the operating stresses in the ASME III analysis Results from the ASME III analysis, the remnant RPV J-groove weld crack growth analysis and the remnant nozzle crack growth analysis justify operation through the end of licensed operating life 26
Relief Request #52 Tom Weber Department Leader, Nuclear Regulatory Affairs
Palo Verde Applicable ASME Codes Design Code for reactor vessel
- ASME III 1971 Edition, Winter 1973 Addenda Construction Code
- ASME III 1974 Edition, Winter 1975 Addenda Repairs/Replacements
- ASME XI 2001 Edition, 2003 Addenda Palo Verde 3rd ISI Interval
- Unit 1 thru 7-17-2018
- Unit 2 thru 3-17-2017
- Unit 3 thru 1-10-2018 28
APS Approach Two separate relief requests
- Relief Request #51 - Restart analysis Duration of current operating cycle #18 Verbally approved on November 21, 2013
- Relief Request #52 - Long-term evaluation Detailed analysis including fatigue crack growth Operation through remainder of licensed operating life (November 25, 2047) 29
Relief from ASME Code Removal of defects
- IWA 4421, Defects shall be removed or mitigated in accordance
- IWA 4422.1a, A defect is considered removed when it has been reduced to an acceptable size
- IWA 4422.1b, Alternately, the defect removal area and any remaining portion of the defect may be evaluated and the component accepted in accordance with the appropriate flaw evaluation provisions of Section XI 30
Relief from ASME Code Characterization of flaws in J-groove weld
- IWA 3100(a), Evaluation shall be made of flaws detected during an inservice examination as required by IWB-3000 for Class 1 pressure retaining components
- IWA 3300(b), Flaws shall be characterized in accordance with IWA-3310 through IWA-3390...
- IWA 3420, Each detected flaw or group of flaws shall be characterized by the rules of IWA-3300 to establish the dimensions of the flaws. These dimensions shall be used in conjunction with the acceptance standards of IWB-3500.
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Relief from ASME Code Successive examinations
- IWB 2420(b), If a component is accepted for continued service in accordance with IWB-3132.3 or IWB-3142.4, the areas containing flaws or relevant conditions shall be reexamined during the next three inspection periods listed in the schedule of the inspection program of IWB-2400 32
Proposed Alternative per 10 CFR 50.55a(a)(3)(i)
Completed ASME Code compliant repair on external surface of Unit 3 reactor vessel Relocated pressure boundary weld Analyzed a postulated maximum flaw in remnant J-groove weld 33 4/1/2014
Basis for Relief Request ASME Code compliant half-nozzle repair No demonstrated technology available for characterization of flaws in J-groove weld Analysis of postulated maximum flaw demonstrates remnant flaw remains acceptable for remainder of licensed operating life 34
Relief Request Summary Proposed ASME Code alternative provides an acceptable level of quality and safety Analyses of BMI nozzle support the relief request such that nozzle is acceptable for the remainder of the licensed operating life RR#52 submittal planned for May, 2014 Needed for restart following 18th refueling outage, Spring 2015 35
Closing Comments Ken House Director, Design Engineering
We SAFELY and efficiently generate electricity for the long term 37