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Category:Meeting Briefing Package/Handouts
MONTHYEARML24100A7672024-04-11011 April 2024 Meeting Slides - Preapplication with Constellation on Planned Fleet Alternative Request to Adopt OMN-2 ML24089A2612024-04-0909 April 2024 Slides - Constellation - Pre-Application Regarding Hooded Masks 4/9/2024 Meeting Slides (L-2024-LLM-0041) ML24060A1692024-03-0707 March 2024 NRC Slides for March 7, 2024 Regulatory Conference with Constellation Nuclear Regarding Braidwood BW240007, Attachment 5: BW-MISC-062 Rev. 0 - Braidwood Station Unit 2 Diesel Driven AFW MAAP Calculations2024-02-29029 February 2024 Attachment 5: BW-MISC-062 Rev. 0 - Braidwood Station Unit 2 Diesel Driven AFW MAAP Calculations ML24057A3032024-02-26026 February 2024 Attachment 1: Braidwood Station Regulatory Conference Information ML24057A3062024-02-24024 February 2024 Attachment 4: BW-SDP-006 Rev. 0 - Braidwood 2B AF Pump Fuel Oil Leak SOP Sensitivities ML24029A1742024-01-30030 January 2024 Constellation Pre-Application January 30, 2024, Meeting Slides - Proposed Alternative to Utilize Code Case N-932, Alternative Requirements for Acceptance of Containment Base Metal Corrosion or Erosion ML24057A3042024-01-22022 January 2024 Attachment 2: EC 640630 Rev. 000 - Documentation of Test Results with Diluted Lube Oil from Fuel In-Leakage - 28 AF Diesel Engine Past Operability ML24003A1812024-01-0808 January 2024 Handout - Byron-Braidwood Core Monitoring and Support System LAR Pre-Submittal Meeting January 8,2024 ML24057A3052023-12-12012 December 2023 Attachment 3: EC 640287 Rev. 000 - Past Operability Test Plan Acceptance Related to 2AF01PB-K ML23345A0362023-12-11011 December 2023 ATWS Uet December 11, 2023 Pre-submittal Meeting Slides ML23317A0712023-11-14014 November 2023 NRC Pre-Submittal Meeting on November 14th, 2023 - TSTF-591 and Selected 50.69 License Condition Updates (EPID L-2023-LLM-0098) (Slides) ML23272A0622023-09-29029 September 2023 Ultimate Heat Sink Temperature Tech Spec Limit Change ML23229A0132023-08-17017 August 2023 Relief Request for Alternative Requirements for Byron Unit 1 Reactor Pressure Vessel Inservice Inspection Intervals NRC Meeting Handout ML23229A4832023-08-17017 August 2023 RR 20-Year ISI Pre-Submittal NRC Meeting Handout ML23255A1042023-08-11011 August 2023 Slides - Constellation - Pre-Application EP 9/18/2023 Draft CEG Presubmittal SG Performance Monitoring Plan Meeting Handout ML23163A1642023-06-12012 June 2023 2022 Braidwood/Byron End-of-Cycle Meeting Presentation ML23033A6662023-02-0909 February 2023 Summary of Public Meeting with Constellation Energy Generation, LLC (Constellation) to Discuss Its Request for Alternatives for Certain Steam Generator Weld Inspections for Calvert Cliffs 1 & 2, Byron 1 & 2, Braidwood 1 & 2, and Ginna ML23033A6672023-01-30030 January 2023 Public Call with Constellation January 30, 2023 (Slides) ML22159A3332022-06-0909 June 2022 Presentation Slides for Braidwood and Byron 2021 End of Cycle Meeting ML21320A0672021-11-17017 November 2021 NRC Pre-Submittal Meeting - Braidwood, Unit 2, LAR for Removal of Unit 2 License Condition for Closure Stud Hole Location No. 35 (EPID L-2021-LRM-0089) (Slides) ML21314A4472021-11-10010 November 2021 Slides for Presubmittial Meeting for Proposed Alternative to Adopt ASME Code Case N-921 to Extend the Inservice Inspection Interval ML21166A3722021-06-15015 June 2021 End-of-Cycle Meeting Presentation ML21130A6252021-05-12012 May 2021 NRC Pre-Submittal Meeting - Braidwood LAR for Ultimate Heat Sink (EPID L-2021-LRM-0040) (Slides) ML21078A0952021-03-0808 March 2021 Session W20 - James Petty - Slide Deck 3 ML20258A0302020-09-22022 September 2020 Decommissioning Licensing Action Submittal Plan for Byron and Dresden Stations Early Shutdowns ML20261G7322020-09-16016 September 2020 Pre-Submittal Slides Extend 120-month Isi/Ist Interval Under 50.55a ML20209A5322020-07-24024 July 2020 2019 Braidwood and Byron End-of-Cycle Presentation ML20178A4202020-06-30030 June 2020 NEI Slides for June 30, 2020, Public Meeting on COVID-19 Response ML20175A8722020-06-23023 June 2020 Risk-Informed Inservice Inspection - U.S Nuclear Regulatory Commission (NRC) - Four Element Risk-Informed Approach ML20170B0212020-06-23023 June 2020 NRC Pre-Submittal Meeting Byron Unit 2 One-Time Deferral of Reactor Pressure Vessel Head Penetration Nozzle (Rpvhpn) Inspections ML20163A6552020-06-16016 June 2020 6-16-20 Byron Unit 2 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections ML20169A5592020-06-16016 June 2020 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections (Rev 1) ML20091L0432020-04-0101 April 2020 Public Meeting Handout for Braidwood, Unit 2, April 1, 2020 ML19318F9512019-11-20020 November 2019 Presentation Slides for November 20, 2019, Pre-Application Meeting - Request for Revision to Quality Assurance Program Internal Audit Frequency ML19317C9952019-11-12012 November 2019 In-Service Testing Supplemental Position Indication Relief Request NRC Pre-Application Meeting November 18, 2019 ML19161A2572019-06-0404 June 2019 BWR Fleet Msv/Srv - Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019 ML19151A6602019-05-31031 May 2019 BWR Fleet Mssv/Srv Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019 ML19022A2002019-01-23023 January 2019 Request for Use of ASME Code Case N-879 for Exelon Nuclear Power Plants ML18347B3142018-12-19019 December 2018 Bwrvip/Asme Relief Request Discussion December 19, 2018 ML18334A2162018-11-30030 November 2018 Presentation Slides: Exelon BWR MSIV (Boiling-Water Reactor - Main Steam Isolation Valve) Leakage Optimization for NRC Pre-Submittal Meeting of December 6, 2018 ML18319A1272018-11-19019 November 2018 Slides for 11/19/18 Public Meeting - Exelon Fleet LAR for Common Language for TS 5.7 High Radiation Areas ML18218A1122018-08-0808 August 2018 Reactor Pressure Vessel Head Penetration Nozzle Post Peening Follow-up Inspection Relief Requests for Byron Unit 2 and Braidwood Unit 1 ML18054B3592018-02-27027 February 2018 Slide: NRC Pre-Submittal Meeting for Exelon Fleet LAR to Relocate TS Unit Staff Qualification ANSI Requirements to the QATR, February 27, 2018, Profile Info: Submitted by Frank Mascitelli ML18018B4432018-01-25025 January 2018 Summary of December 17, 2017, Closed Meeting with Exelon Generation Company, LLC, Regarding Tvel Lead Test Assemblies to Be Placed in the Braidwood Reactor (EPID 000976/05000456/L-2017-LRM and 000976/05000457/L-2017-LRM-0047 ML17296A2032017-10-0303 October 2017 Accident Tolerant Fuel Lead Test Assembly Deployment ML17132A1772017-05-25025 May 2017 LAR for Control Room Cooling at Byron and Braidwood Stations ML17142A2382017-05-25025 May 2017 OEDO-17-00280 - Briefing Package for Drop-In Visit on June 9, 2017, by Senior Management of Exelon Generation Company, LLC with Chairman Svinicki, Commissioner Baran, and Commissioner Burns ML16334A4642016-12-0505 December 2016 Westinghouse Pre-Application Meeting: License Amendment Request to Modify Byron Station Facility Operating License in Support of the Molybdenum-99 Isotope Production Project - December 5, 2016 ML16327A3702016-11-25025 November 2016 Enclosure 3: Exelon Byron Station Design (Meeting Handout) 2024-04-09
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24310A0672024-11-0505 November 2024 Constellation NRC Pre-Submittal Meeting Slides - Proposed Alternative for Reactor Vessel Closure Stud Exam Optimization ML24100A7672024-04-11011 April 2024 Meeting Slides - Preapplication with Constellation on Planned Fleet Alternative Request to Adopt OMN-2 ML24089A2612024-04-0909 April 2024 Slides - Constellation - Pre-Application Regarding Hooded Masks 4/9/2024 Meeting Slides (L-2024-LLM-0041) ML24060A1692024-03-0707 March 2024 NRC Slides for March 7, 2024 Regulatory Conference with Constellation Nuclear Regarding Braidwood ML24057A3032024-02-26026 February 2024 Attachment 1: Braidwood Station Regulatory Conference Information ML24029A1742024-01-30030 January 2024 Constellation Pre-Application January 30, 2024, Meeting Slides - Proposed Alternative to Utilize Code Case N-932, Alternative Requirements for Acceptance of Containment Base Metal Corrosion or Erosion ML24003A1812024-01-0808 January 2024 Handout - Byron-Braidwood Core Monitoring and Support System LAR Pre-Submittal Meeting January 8,2024 ML23345A0362023-12-11011 December 2023 ATWS Uet December 11, 2023 Pre-submittal Meeting Slides ML23317A0712023-11-14014 November 2023 NRC Pre-Submittal Meeting on November 14th, 2023 - TSTF-591 and Selected 50.69 License Condition Updates (EPID L-2023-LLM-0098) (Slides) ML23272A0622023-09-29029 September 2023 Ultimate Heat Sink Temperature Tech Spec Limit Change ML23229A0132023-08-17017 August 2023 Relief Request for Alternative Requirements for Byron Unit 1 Reactor Pressure Vessel Inservice Inspection Intervals NRC Meeting Handout ML23229A1722023-08-17017 August 2023 RR Pen-75 Pre-Submittal NRC Meeting Handout ML23229A4832023-08-17017 August 2023 RR 20-Year ISI Pre-Submittal NRC Meeting Handout ML23255A1042023-08-11011 August 2023 Slides - Constellation - Pre-Application EP 9/18/2023 Draft CEG Presubmittal SG Performance Monitoring Plan Meeting Handout ML23163A1642023-06-12012 June 2023 2022 Braidwood/Byron End-of-Cycle Meeting Presentation NEI 99-01, Slides - Constellation - Pre-Application EP 2/23/2023 Meeting Slides2023-02-21021 February 2023 Slides - Constellation - Pre-Application EP 2/23/2023 Meeting Slides ML23033A6662023-02-0909 February 2023 Summary of Public Meeting with Constellation Energy Generation, LLC (Constellation) to Discuss Its Request for Alternatives for Certain Steam Generator Weld Inspections for Calvert Cliffs 1 & 2, Byron 1 & 2, Braidwood 1 & 2, and Ginna ML23033A6672023-01-30030 January 2023 Public Call with Constellation January 30, 2023 (Slides) ML22159A3332022-06-0909 June 2022 Presentation Slides for Braidwood and Byron 2021 End of Cycle Meeting ML22098A0512022-04-11011 April 2022 2 Cycle 25 High Burnup Lead Test Assembly NRC Pre-Submittal Meeting on April 22, 2022 (EPID L-2022-LRM-0022) (Slides) ML21320A0672021-11-17017 November 2021 NRC Pre-Submittal Meeting - Braidwood, Unit 2, LAR for Removal of Unit 2 License Condition for Closure Stud Hole Location No. 35 (EPID L-2021-LRM-0089) (Slides) ML21314A4472021-11-10010 November 2021 Slides for Presubmittial Meeting for Proposed Alternative to Adopt ASME Code Case N-921 to Extend the Inservice Inspection Interval ML21166A3722021-06-15015 June 2021 End-of-Cycle Meeting Presentation ML21162A3322021-06-11011 June 2021 BWR Fleet Relief Request Associated with RPV Instrument Nozzle Repairs ML21130A6252021-05-12012 May 2021 NRC Pre-Submittal Meeting - Braidwood LAR for Ultimate Heat Sink (EPID L-2021-LRM-0040) (Slides) ML21078A0952021-03-0808 March 2021 Session W20 - James Petty - Slide Deck 3 ML20258A0302020-09-22022 September 2020 Decommissioning Licensing Action Submittal Plan for Byron and Dresden Stations Early Shutdowns ML20261G7322020-09-16016 September 2020 Pre-Submittal Slides Extend 120-month Isi/Ist Interval Under 50.55a ML20209A5322020-07-24024 July 2020 2019 Braidwood and Byron End-of-Cycle Presentation ML20178A4202020-06-30030 June 2020 NEI Slides for June 30, 2020, Public Meeting on COVID-19 Response ML20175A8722020-06-23023 June 2020 Risk-Informed Inservice Inspection - U.S Nuclear Regulatory Commission (NRC) - Four Element Risk-Informed Approach ML20170B0212020-06-23023 June 2020 NRC Pre-Submittal Meeting Byron Unit 2 One-Time Deferral of Reactor Pressure Vessel Head Penetration Nozzle (Rpvhpn) Inspections ML20163A6552020-06-16016 June 2020 6-16-20 Byron Unit 2 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections ML20169A5592020-06-16016 June 2020 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections (Rev 1) ML20091L0432020-04-0101 April 2020 Public Meeting Handout for Braidwood, Unit 2, April 1, 2020 ML18347B3142018-12-19019 December 2018 Bwrvip/Asme Relief Request Discussion December 19, 2018 ML18334A2162018-11-30030 November 2018 Presentation Slides: Exelon BWR MSIV (Boiling-Water Reactor - Main Steam Isolation Valve) Leakage Optimization for NRC Pre-Submittal Meeting of December 6, 2018 ML18319A1272018-11-19019 November 2018 Slides for 11/19/18 Public Meeting - Exelon Fleet LAR for Common Language for TS 5.7 High Radiation Areas ML18218A1122018-08-0808 August 2018 Reactor Pressure Vessel Head Penetration Nozzle Post Peening Follow-up Inspection Relief Requests for Byron Unit 2 and Braidwood Unit 1 ML18086A8432018-03-27027 March 2018 NUREG-1021, Revision 11 Implementation ML18054B3592018-02-27027 February 2018 Slide: NRC Pre-Submittal Meeting for Exelon Fleet LAR to Relocate TS Unit Staff Qualification ANSI Requirements to the QATR, February 27, 2018, Profile Info: Submitted by Frank Mascitelli ML17291B0282017-10-17017 October 2017 Submittal of Slide Package Westinghouse Encore Lead Test Rod Program Byron Unit 2 (Proprietary/Non-Proprietary) ML17296A2032017-10-0303 October 2017 Accident Tolerant Fuel Lead Test Assembly Deployment ML17132A1772017-05-25025 May 2017 LAR for Control Room Cooling at Byron and Braidwood Stations ML16334A4452016-12-0505 December 2016 Pre-submittal Meeting Byron UT RR Presentation ML16077A1562016-03-22022 March 2016 Fleet: Pre-application Teleconference with Exelon to Discuss a Potential License Amendment Request Regarding Operating Training Standards ML16062A4222016-03-0202 March 2016 Meeting Slides for March 7, 2016 Public Meeting to Discuss Backfit Appeal ML15342A1012015-12-0909 December 2015 TORMIS Computer Code Methodology Public Meeting Slides ML15232A6832015-08-27027 August 2015 Stations Auxiliary Feedwater System - Unit Cross-tie License Amendment Request ML15209A9722015-07-30030 July 2015 Alloy 600 PWSCC Mitigation Plan for Reactor Vessel Head Penetration Nozzles Utilizing Cavitation Peening at Byron and Braidwood 2024-04-09
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Exelon Generation Alloy 600 PWSCC Mitigation Plan for Reactor Vessel Head Penetration Nozzles Utilizing Cavitation Peening at Byron and Braidwood NRC/Exelon Meeting, Rockville, MD B. Youman J. Feimster J. Wilson D. Gullott J. Krejcie December 10, 2014
Agenda
- Introductions and Opening Remarks
- Objective
- Braidwood / Byron PWSCC History
- AREVA RPV Head Penetration Peening Technology
- RPV Head Penetration Peening Benefits
- Peening Technical Basis
- Exelon Peening Mitigation Implementation Plan
- Implementation of Peening via 50.59 Process
- Post Peening Inspection Relief Requests
- NRC Interaction
- Summary 1
Objective
- Present Exelons initiative for Reactor Pressure Vessel (RPV) head PWSCC mitigation
- Introduce AREVA Peening process
- Provide benefits of Peening process
- Discuss Exelons integrated implementation plan including potential future inspection relief requests
- Obtain NRC feedback on Exelons initiative and identify technical and regulatory challenges
- Achieve an understanding of questions or concerns
- Discuss approach for resolving questions or concerns 2
Braidwood / Byron PWSCC History
- Braidwood and Byron RPV heads are B&W T-Cold Heads with the RPV head penetration nozzles fabricated using B&W tubular product
- Inspections to date have identified the following flaws:
- Byron Unit 2 - two nozzles (Spring 2007, Fall 2014)
- Byron Unit 1 - four nozzles (Spring 2011)
- Braidwood Unit 1 - one nozzle (Spring 2012)
- Each flaw has been repaired using an NRC approved embedded flaw overlay
- Under the current regulatory requirements, the three repaired RPV heads require ultrasonic examinations and bare metal visual inspections every refueling outage
- To date, the inspection program has not detected cracking symptoms on the Braidwood Unit 2 RPV head 3
Braidwood / Byron PWSCC History
- History of crack locations are shown below Existing Flaw / Repair Locations Byron Unit 2 (Spring 2007) #68 Byron Unit 1 (Spring 2011) #31, 43, 64, 76 Braidwood Unit 1 (Spring 2012 ) #69 Byron Unit 2 (Fall 2014) #6 4
Braidwood / Byron PWSCC History
- All cracks were outside diameter (OD) axial (toe of weld and below and propagated upwards, behind weld), with no leakage identified CRDM nozzle is nominally 4 inches OD and 2 3/4 ID with 5/8 wall thickness 5
Braidwood / Byron PWSCC History
- Exelons current method for addressing RPV head PWSCC induced flaws is to implement an embedded flaw weld overlay
- Reactive due to unknown scope prior to outage
- Significant dose, outage extension, and cost
- Fails to provide a complete solution for long term asset (i.e., RPV) management or improve reliability of non-repaired penetrations
- Potential discovery of new PWSCC induced flaws in the RPV head penetrations over the next 33 years (assuming License Renewal) is estimated to be between 11 (best case) and 84 (worst case)
- Therefore, Exelon is pursuing proactive RPV head penetration Peening technology with AREVA to improve the RPV head penetration integrity and mitigate PWSCC to reduce vulnerabilities 6
AREVA RPV Head Penetration Peening Technology
- Ultra high velocity jet results in pressure below vapor pressure in water resulting in vapor bubbles forming in the water (cavitation)
- Cavitation bubbles collapse at surface generating high pressures on the material
- The shockwaves caused by collapsing voids imparts compressive stresses in the surface layer of material
- The water-jet force does NOT perform the Peening
- The Peening is performed by the collapse of the vapor bubbles 7
AREVA RPV Head Penetration Peening Technology
- Cavitation Peening Process Diagram bubble 8
AREVA RPV Head Penetration Peening Technology
- Demonstration Video 9
AREVA RPV Head Penetration Peening Technology
- Extensive testing has shown cavitation Peening is an effective process that provides broad coverage in its application and extreme flexibility with applied geometries and process flow rates Given it is NOT the water-jet that is doing the Peening but the cavitation bubbles, the process ensures coverage overlap with wide tolerances on geometry length and flow-rates Documented test results confirm:
o Testing over a variety of flow-rates and distances to target provide the same beneficial results o Post peening benefits show final as left stresses regardless of initial residual stress state o Testing has shown higher stresses relax and respond faster to less initial residual tension state o Peening is effective over a wide applied angle between the water-jet and material being peened showing appropriate coverage on complicated geometries o Documented test results are available for review 10
AREVA RPV Head Penetration Peening Technology
- Cavitation Peening Surface Finish Visual inspection can be used to confirm Peening coverage The as left surface finish does not impact NDE inspection results Aggressive high temperature corrosion testing has validated resistance to PWSCC initiation Peened Non-Peened 11
RPV Head Penetration Peening Benefits
- Primary Safety Benefit
- Reduction in nozzle stresses significantly diminishes the potential for future PWSCC induced cracks and associated leakage paths
- RPV head is in a safer condition and more effectively protects the health and safety of the public
- Reduction in cumulative dose/exposure by not performing reactive repairs - ranges from 731 to 2,181 Rem
- Primary Commercial Benefit
- Extend life and improve reliability of RPV head
- Eliminate need for reactive repairs - savings range from $688M to
$1,200M
- Eliminate outage extensions for reactive repairs - ranges from 161 to 607 days
- Secondary benefits may include additional dose and outage savings related to reduced future inspections 12
Peening Technical Basis
- Initiation of PWSCC flaws requires tensile stress at the surface
- Peening techniques mitigate PWSCC by reversing the tensile stress at the surface, exposed to reactor coolant, to compressive residual stress
- Peening vendors and EPRI performed separate verification experiments, including corrosion cracking and stress relaxation tests, to confirm the effectiveness and sustainability of peening treatments
- Evaluations were conducted related to peening performance methods and effects
- Coverage, magnitude and depth of compressive stresses
- Retention of compressive stresses throughout plant life
- Verification of no unacceptable side effects
- Precludes the initiation of PWSCC 13
Peening Technical Basis
- Key supporting EPRI-MRP reference documents
- MRP-267, Revision 1, 2012, Technical Basis for PWSCC Mitigation by Surface Stress Improvement
- MRP-335, Revision 1, 2013, Topical Report for PWSCC Mitigation by Surface Stress Improvement
- MRP-2014-027, 2014, Supplemental Technical Basis for Peening of Alloy 600 RPVHPNs 14
Exelon Peening Mitigation Implementation Plan
- Exelon will mitigate RPV head penetrations using cavitation water jet Peening
- Contract has been awarded to AREVA with field development in progress
- Exelon will implement Peening during the 2016 and 2017 refueling outages
- Byron Unit 2 - Spring 2016
- Braidwood Unit 1 - Fall 2016
- Byron Unit 1 - Spring 2017
- Braidwood Unit 2 - Spring 2017
- Peening will be implemented as a special process in accordance with 10 CFR 50, Appendix B, Criterion IX
- Peening of the RPV head penetrations will be assessed in accordance with 10 CFR 50.59 15
Exelon Peening Mitigation Implementation Plan
- Scope of work includes the outer and inner surfaces of the susceptible Alloy 600 and 182/82 material in all the 79 nozzles in each of the Byron and Braidwood RPV heads:
53 CRDM nozzles 5 thermocouple nozzles 2 reactor vessel level indicating system (RVLIS) nozzles 18 spare nozzles 1 RPV head vent nozzle 16
Exelon Peening Mitigation Implementation Plan
- The minimum peened coverage areas:
The Peening shall extend at least .25 beyond all PWSCC susceptible material PWSCC susceptible material is defined as Alloy 182/82 and the heat affected zone of the Alloy 600 nozzles that are in contact with the primary water C
17
Exelon Peening Mitigation Implementation Plan
- Applying 10 CFR 50, Appendix B, Criterion IX Process
- Essential variables will be bounded (e.g., high pressure, nozzle stand off distance, back pressure, nozzle position, nozzle speed)
- Training and qualification will be conducted by process demonstration
- The qualification will include testing on mockups at the boundary extremes to demonstrate that the required results can be obtained even at the limits of the essential variables
- The qualification will be performed on full scale mockups with material and geometry constraints
- During implementation essential variables will be controlled/monitored to ensure acceptable results are achieved 18
Implementation of Peening via 10 CFR 50.59 Process
- Exelon intends to implement Cavitation Peening in accordance with 10 CFR 50.59 Cavitation Peening does not adversely affect SSCs nor their associated performance, FSAR design basis, or Technical Specifications Extensive testing has shown Cavitation Peening is less invasive than original grinding activities performed during fabrication and the Peening application process energy levels remain low Exelon will make 10 CFR 50.59 evaluation available for NRC review in advance of Peening implementation 19
Post Peening Inspection Relief Requests
- Exelon continues to evaluate the secondary benefit of RPV head penetration Peening related to reduced inspection frequency
- Changes in the inspection frequency specified in 10 CFR 50.55(a) require NRC approval of relief requests
- Exelon is evaluating an incremental relief request approach 20
NRC Interaction
- Exelon plans to move forward with the Cavitation Peening technology due to the safety and long term asset preservation benefits
- Since this will be the first application of RPV head penetration Peening to mitigate PWSCC in United States, Exelon wants to identify regulatory uncertainties
- Exelon supports open dialogue with NRC to understand/resolve regulatory issues Peening evaluated in accordance with 10 CFR 50.59, which will be made available to NRC for review prior to implementation Requirements during the Peening activity to support potential future relief requests related to post Peening inspection frequency Impact of NRC Testing Program scope on post Peening inspection relief o Available industry test results may reduce NRC Program scope and facilitate review of MRP-335 and CC-729-5 AREVA Half Nozzle repair methodology and subsequent relief request approval in lieu of embedded flaw weld overlay 21
Summary
- Application of the Peening technology on the Braidwood and Byron RPV head penetrations is a proactive approach to mitigate PWSCC
- Improves safety by reducing the potential for nozzle cracking and associated leakage
- Results in significant reduction in dose related to reactive repairs
- Exelon has confidence in the Peening technology based on industry testing, EPRI/MRP published documents and the process controls being implemented
- Exelon will proactively support resolution of NRC questions and ensure NRC remains informed of implementation plans 22