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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. 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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Pre-Submittal Meeting - 1R24 Pressurizer Nozzle Repair - RR-70 October 20, 2023
Agenda
- Pressurizer Leak Identification
- Pressurizer Nozzle Repair
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Background===
- Three pinhole leaks identified in nozzle weld
- Design history of the pressurizer thermowell was preemptively repaired in 1992
- Weld material is Alloy 82 3
Pressurizer Leak Identification Overview of the area 119 4
Pressurizer Leak Identification Visual inspection, confirmed boron with isotopic analysis PT exam identified three pin holes 119 5
Nozzle Design History (Pre 1992)
Nozzle - Alloy 600 Weld - Alloy 82/182 6
Nozzle Design History (Post 1992) 7
Pressurizer Nozzle Repair
- Remove existing Alloy 82 weld pad and Alloy 690 nozzle
- Roll expand Alloy 690 outer sleeve in penetration bore
- Perform surface examination on outer surface of pressurizer shell in preparation for new weld pad
- Deposit Alloy 52M weld pad in accordance with Code Case N-638-10
- Perform examination of final bore and J-groove weld prep
- Replacement Alloy 690 nozzle installation and welding
- Perform progressive surface examination of nozzle weld 8
Pressurizer Nozzle Repair 9
Code Requirements ASME Code,Section XI, 2013 Edition IWB-3522: Pressure retaining material leakage requires corrective action per IWA-5250 and acceptance per IWB-3142 Flaw Removal
- Corrective actions per IWA-5250, and IWA-4000 repair/replacement activities will eliminate the pressure boundary leakage by installation of the Alloy 52M welds and Alloy 690 nozzle
- Flaw removal required per IWA-4412/4420 10
Code Requirements ASME Code,Section XI, 2013 Edition Flaw Evaluation
- IWB-3142.1(b) states A component whose visual examination detects the relevant conditions described in the standards of Table IWB-3410-1 shall be unacceptable for continued service, unless such components are accepted by supplemental evaluation, accepted by corrective measures, or accepted by analytical evaluation.
- IWB-3420 states, Each detected flaw or group of flaws shall be characterized by the rules of IWA-3300 to establish the dimensions of the flaws.
- IWA-3300 Flaws detected by inservice examinations shall be sized 11
Proposed Alternative Pursuant to 10 CFR 50.55a(z)(1)
Flaw Removal and Flaw Evaluation
- As an alternative to flaw removal of the internal J-groove weld, to meet the applicable acceptance standards per IWA-4412/4420, assumed flaws in the original internal J-groove weld and autogenous weld will remain in place
- As an alternative to performing the nondestructive examination (NDE) required to characterize a flaw under IWB-3420, analyze a maximum postulated flaw that bounds the range of flaw sizes that could exist in the original internal J-groove weld 12
Proposed Alternative Pursuant to 10 CFR 50.55a(z)(1)
Welding
- In lieu of NB-4620 post weld heat treatment requirements, install Alloy 52M welded pad in accordance with ASME Case N-638-10, ambient temperature gas tungsten arc weld (GTAW) temper bead technique
- An alternative is proposed to N-638-10, Paragraph 4(a)(2), that requires the first three tempering layers are in place for 48-hour prior to performing NDE, APS proposes to perform the NDE after completion of the weld repair 13
Proposed Alternative Pursuant to 10 CFR 50.55a(z)(1)
Basis for Alternatives
- A review of previous analyses has been performed and confirmed that the As Left J-Groove Weld Analysis is acceptable for at least one operating cycle
- Potential loose parts assessment summarized in Relief Request
- Corrosion analysis to be provided 14
Proposed Alternative Pursuant to 10 CFR 50.55a(z)(1)
Duration of Proposed Alternative
- Relief is requested for the duration of the Unit 1 Cycle 25 which concludes Spring of 2025
- Separate relief request to be submitted for continued use of the nozzle repair for the life of the plant prior to the end of the cycle 15
Proposed Alternative Pursuant to 10 CFR 50.55a(z)(1)
Precedents - Flaw Evaluation and 48-Hour Hold
- NRC approval via verbal authorization on November 6, 2020 (ML20314A028) for Peach Bottom Atomic Power Station, Unit 2. Safety Evaluation April 23, 2021 (ML21110A680)
- NRC verbal authorization on April 15, 2012, for Quad Cities, Unit 2 (ML12107A472). Safety Evaluation January 30, 2013 (ML13016A454)
- NRC approval via a verbal authorization on May 17, 2017, for Limerick, Unit 2 (ML17137A307). Safety Evaluation August 14, 2017 (ML17208A090)
Schedule
- Proposed submittal date for RR-70
- October 23, 2023
- Requested verbal authorization target date
- October 27, 2023
- Proposed submittal date for final one-cycle flaw analytical evaluation, evaluation of repair, and corrosion evaluation days after the end of the Unit 1 outage 17
Questions