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Category:Meeting Briefing Package/Handouts
MONTHYEARML24200A2312024-07-22022 July 2024 Constellations Pre-Submittal Meeting Presentation About Peach Bottom ECCS Compensated Level System Replacement Project - July 22, 2024 ML24137A1882024-05-16016 May 2024 Annual Assessment Meeting for Pa/Md/Ny/Nj Nuclear Power Plants - NRC Presentation Slides ML24131A1282024-05-14014 May 2024 Lessons Learned for ECCS Digital I&C License Amendment ML24134A2032024-05-14014 May 2024 Lessons Learned for ECCS Digital I&C License Amendment - Rev 0 ML24121A1862024-05-14014 May 2024 Attachment 3: Peach Bottom ECCS Compensated Level System Replacement Project Presentation Material (Non-Proprietary 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 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) ML23255A1042023-08-11011 August 2023 Slides - Constellation - Pre-Application EP 9/18/2023 Draft CEG Presubmittal SG Performance Monitoring Plan Meeting Handout ML23170A0082023-06-29029 June 2023 Decommissioning Presentation for NRC Pre-submittal Meeting, June 29, 2023 ML23157A0352023-06-0606 June 2023 Annual Assessment Meeting for Pa/Md/Ny/Nj Nuclear Power Plants - NRC Presentation Slides ML23094A1492023-04-11011 April 2023 Licensee Presentation on Whr Exemption Request for Public Meeting on April 11, 2023 ML23076A0442023-03-16016 March 2023 Pb U2 Scram Barrier Presentation KT Session 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 ML21165A1942021-06-16016 June 2021 Joint Annual Assessment Meeting for Pa/Md/Nj/Ny Nuclear Power Plants - Webinar Presentation ML21165A2882021-06-16016 June 2021 Joint Annual Assessment for Pa/Md/Nj/Ny Nuclear Power Plants - Webinar Presentation (Updated) ML21095A0162021-04-0505 April 2021 2021 RIC Session T12 - DOE-Sponsored Light Water Reactor Sustainability Program ML20261G7322020-09-16016 September 2020 Pre-Submittal Slides Extend 120-month Isi/Ist Interval Under 50.55a ML20178A4202020-06-30030 June 2020 NEI Slides for June 30, 2020, Public Meeting on COVID-19 Response ML20170B0212020-06-23023 June 2020 NRC Pre-Submittal Meeting Byron Unit 2 One-Time Deferral of Reactor Pressure Vessel Head Penetration Nozzle (Rpvhpn) Inspections ML20175A8722020-06-23023 June 2020 Risk-Informed Inservice Inspection - U.S Nuclear Regulatory Commission (NRC) - Four Element Risk-Informed Approach 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) ML20168A3192020-06-15015 June 2020 Joint Annual Assessment Meeting for Pa/Md Power Plants - Webinar Presentation 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 ML19308B9262019-11-0505 November 2019 ACRS Plant License Renewal Subcommittee - Peach Bottom Atomic Power Station Units 2 and 3 Subsequent License Renewal Safety Evaluation Report (SER) with Confirmatory Item ML19256E3852019-09-12012 September 2019 SLR Dseis Public Meeting Sept 12 2019 - Scott Portzline - Former Three Mile Island Alert Presentation ML19256E3522019-09-12012 September 2019 Slides - Peach Bottom SLRA Dseis Public Meeting - Sep 12 2019 ML19157A0542019-06-0606 June 2019 Joint Annual Assessment Meeting (Webinar) for Pennsylvania Power Plants - NRC Presentation Slides 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 ML19084A0982019-03-22022 March 2019 Potential Topics for Pre-Application Meetings for Peach Bottom SLRA 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 ML18144A6932018-05-31031 May 2018 License Amendment Request for Expanded Actions for LEFM Flow Meter Conditions - NRC Pre-Submittal Meeting May 31, 2018 ML18141A3072018-05-21021 May 2018 18 - SLR Status 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 ML17320A2002017-11-15015 November 2017 Insights from Implementing FLEX in the Peach Bottom Seismic PRA Model ML17257A1612017-09-19019 September 2017 September 19, 2017 Pre-application Public Meeting Presentation on Peach Bottom Subsequent License Renewal Application 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 ML16077A1562016-03-22022 March 2016 Fleet: Pre-application Teleconference with Exelon to Discuss a Potential License Amendment Request Regarding Operating Training Standards ML16075A3292016-03-16016 March 2016 OEDO-16-00165 - Briefing Package for Drop-In Visit on March 23, 2016, by Senior Management of Exelon Generation Company, LLC with the NRC Executive Director for Operations ML12159A2662012-06-11011 June 2012 County Generating Station Pre-Application Meeting Extended Power Uprate: Replacement Steam Dryers. June 11, 2012 ML12130A0992012-05-0909 May 2012 Annual Assessment Meeting Slides Presentation Rev. 0, 2012 ML12130A1172012-05-0909 May 2012 Pb 2012 Public Mtg Attendance Sheet April 2012 ML1208701402012-03-27027 March 2012 Licensee Slides for Exelon Fleet Pre-Submittal Public Meeting 4-10-12 Licensed Operator Eligibility Requirements LAR ML12262A4762012-02-22022 February 2012 TMI Alert Portzline Presentation NUREG-0654 Public Mtg ML1110800952011-04-14014 April 2011 NRC Slides for Peach Bottom Public Meeting on April 13, 2011 2024-07-22
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24200A2312024-07-22022 July 2024 Constellations Pre-Submittal Meeting Presentation About Peach Bottom ECCS Compensated Level System Replacement Project - July 22, 2024 ML24137A1882024-05-16016 May 2024 Annual Assessment Meeting for Pa/Md/Ny/Nj Nuclear Power Plants - NRC Presentation Slides ML24134A2032024-05-14014 May 2024 Lessons Learned for ECCS Digital I&C License Amendment - Rev 0 ML24121A1862024-05-14014 May 2024 Attachment 3: Peach Bottom ECCS Compensated Level System Replacement Project Presentation Material (Non-Proprietary Information) ML24131A1282024-05-14014 May 2024 Lessons Learned for ECCS Digital I&C License Amendment 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 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) ML23251A0782023-09-0606 September 2023 DRE1 Decom Pre-Submittal Slides ML23255A1042023-08-11011 August 2023 Slides - Constellation - Pre-Application EP 9/18/2023 Draft CEG Presubmittal SG Performance Monitoring Plan Meeting Handout ML23170A0082023-06-29029 June 2023 Decommissioning Presentation for NRC Pre-submittal Meeting, June 29, 2023 ML23157A0352023-06-0606 June 2023 Annual Assessment Meeting for Pa/Md/Ny/Nj Nuclear Power Plants - NRC Presentation Slides ML23094A1492023-04-11011 April 2023 Licensee Presentation on Whr Exemption Request for Public Meeting on April 11, 2023 ML23076A0442023-03-16016 March 2023 Pb U2 Scram Barrier Presentation KT Session 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 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 ML21165A1942021-06-16016 June 2021 Joint Annual Assessment Meeting for Pa/Md/Nj/Ny Nuclear Power Plants - Webinar Presentation ML21165A2882021-06-16016 June 2021 Joint Annual Assessment for Pa/Md/Nj/Ny Nuclear Power Plants - Webinar Presentation (Updated) ML21162A3322021-06-11011 June 2021 BWR Fleet Relief Request Associated with RPV Instrument Nozzle Repairs ML20261G7322020-09-16016 September 2020 Pre-Submittal Slides Extend 120-month Isi/Ist Interval Under 50.55a ML20178A4202020-06-30030 June 2020 NEI Slides for June 30, 2020, Public Meeting on COVID-19 Response ML20170B0212020-06-23023 June 2020 NRC Pre-Submittal Meeting Byron Unit 2 One-Time Deferral of Reactor Pressure Vessel Head Penetration Nozzle (Rpvhpn) Inspections ML20175A8722020-06-23023 June 2020 Risk-Informed Inservice Inspection - U.S Nuclear Regulatory Commission (NRC) - Four Element Risk-Informed Approach ML20163A6542020-06-18018 June 2020 2020 NRC Annual Assessment Webinar Presentation - Pennsylvania and Maryland Facilities (Beaver Valley, Calvert Cliffs, Limerick, Peach Bottom, Susquehanna) 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) 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 ML20168A3192020-06-15015 June 2020 Joint Annual Assessment Meeting for Pa/Md Power Plants - Webinar Presentation ML19308B9262019-11-0505 November 2019 ACRS Plant License Renewal Subcommittee - Peach Bottom Atomic Power Station Units 2 and 3 Subsequent License Renewal Safety Evaluation Report (SER) with Confirmatory Item ML19256E3522019-09-12012 September 2019 Slides - Peach Bottom SLRA Dseis Public Meeting - Sep 12 2019 ML19256E3852019-09-12012 September 2019 SLR Dseis Public Meeting Sept 12 2019 - Scott Portzline - Former Three Mile Island Alert Presentation ML19157A0542019-06-0606 June 2019 Joint Annual Assessment Meeting (Webinar) for Pennsylvania Power Plants - NRC Presentation Slides 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 ML18275A3712018-09-25025 September 2018 Subsequent License Renewal Environmental Scoping Meeting 9-25-18 ML18141A3072018-05-21021 May 2018 18 - SLR Status 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 ML18017A1172018-01-18018 January 2018 NRC PBAPS SLRA Pre-Submittal Meeting Jan 2018 PM Copy ML17320A2002017-11-15015 November 2017 Insights from Implementing FLEX in the Peach Bottom Seismic PRA Model ML17257A1612017-09-19019 September 2017 September 19, 2017 Pre-application Public Meeting Presentation on Peach Bottom Subsequent License Renewal Application ML16106A2792016-04-15015 April 2016 Meeting Slides for License Amendment Request for Measurement Uncertainty Recapture Uprate NRC Pre-Submittal Meeting April 26, 2016 ML16077A1562016-03-22022 March 2016 Fleet: Pre-application Teleconference with Exelon to Discuss a Potential License Amendment Request Regarding Operating Training Standards ML13255A3762013-09-16016 September 2013 Soarca Peach Bottom Uncertainty Analysis (UA) Acrc Briefing - Sept 2013 ML12159A2662012-06-11011 June 2012 County Generating Station Pre-Application Meeting Extended Power Uprate: Replacement Steam Dryers. June 11, 2012 ML12130A0992012-05-0909 May 2012 Annual Assessment Meeting Slides Presentation Rev. 0, 2012 ML12124A0782012-04-26026 April 2012 Power Point Presentation: Peach Bottom - Timing and Criteria for RCS Failure ML1208701402012-03-27027 March 2012 Licensee Slides for Exelon Fleet Pre-Submittal Public Meeting 4-10-12 Licensed Operator Eligibility Requirements LAR NRC-2012-0022, Comment (18) of Scott D. Portzline on Behalf of Three Mile Island Alert, on State of the Art Reactor Consequence Analyses (Soarca) Reports2012-02-28028 February 2012 Comment (18) of Scott D. Portzline on Behalf of Three Mile Island Alert, on State of the Art Reactor Consequence Analyses (Soarca) Reports ML12262A4762012-02-22022 February 2012 TMI Alert Portzline Presentation NUREG-0654 Public Mtg ML1110800952011-04-14014 April 2011 NRC Slides for Peach Bottom Public Meeting on April 13, 2011 ML1011100672010-04-20020 April 2010 NRC Slides for Peach Bottom Atomic Power Station Annual Assessment Meeting April 19, 2010 2024-07-22
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Advisory Committee on Reactor Safeguards Plant License Renewal Subcommittee Peach Bottom Atomic Power Station Units 2 and 3 Subsequent License Renewal Safety Evaluation Report (SER) with Confirmatory Item November 5, 2019 Bennett Brady, Senior Project Manager Office of Nuclear Reactor Regulation
Presentation Outline
- Overview of Safety Review of Peach Bottom SLRA
- SER Section 2, Scoping and Screening Review
- SER Section 4, Time-Limited Aging Analyses
- Closure of Confirmatory Item
- Specific Areas of Review - Reactor Vessel and Internals, Irradiated Concrete, and Electrical Cables
- Region Presentation on Inspections and Plant Material Conditions
Overview of Safety Review of Peach Bottom SLRA Unit Initial Initial License Renewed Expiration Subsequent License License Renewal License Date Renewal Application Application 2 10/25/1973 07/02/2001 05/07/2003 08/08/2033 07/10/2018 3 07/02/1974 07/02/2001 05/07/2003 07/02/2034 07/10/2018
- Application Submitted - July 10, 2018
- Acceptance Determination - September 6, 2018
- Safety Evaluation Report with Confirmatory Item -
October 7, 2019 3
Audits and Inspections Dates Location Operating September 17-27, Rockville, MD Experience Audit 2018 November 13, In-office Audit 2018 - April 29, Rockville, MD 2019 4
SER Overview
- SER with Confirmatory Item Issued October 7, 2019
- Confirmatory Item (CI) 3.0.3.2.3-1 BWR Vessel Internals
- Requests for Additional Information (RAIs)
- 48 RAIs issued, 4 of which were follow-up RAIs 5
SER Section 2 Structures and Components Subject to Aging Management Review (AMR)
- Section 2.1 Scoping and Screening Methodology
- Section 2.2 Plant Level Scoping Results
- Sections 2.3, 2.4, 2.5, Scoping and Screening Results 6
SER Section 3 Aging Management Review (AMR)
- Section 3.0 Use of the Generic Aging Lessons Learned Report
- Section 3.2 Engineered Safety Features
- Section 3.3 Auxiliary Systems
- Section 3.4 Steam and Power Conversion Systems
- Section 3.5 Containment, Structures and Component Supports
- Section 3.6 Electrical and Instrumentation and Control Commodities 7
SER Section 3 3.0.3 - Aging Management Programs (AMPs)
SLRA - Original Disposition of AMPs SER - Final Disposition of AMPs
- 11 new GALL programs 8 consistent 8 consistent 3 consistent with 3 consistent with enhancements enhancements
- 35 existing GALL programs
- 35 existing GALL programs
- 8 consistent - 8 consistent
- 27 consistent with - 27 consistent with enhancements/exceptions enhancements/exceptions
- 1 plant-specific with enhancement enhancement evaluated against Appendix A1 of the SRP-SLR 8
SER Section 4 Time-Limited Aging Analyses (TLAAs)
- 4.1 Identification of TLAAs
- 4.2 Reactor Vessel and Internals Neutron Embrittlement Analyses
- 4.3 Metal Fatigue Analyses
- 4.4 Environmental Qualification of Electric Equipment
- 4.5 Concrete Containment Tendon Prestress Analysis
- 4.7 Other Plant-Specific TLAAs 9
Confirmatory Item 3.0.3.2.3-1 BWR Vessel Internals Issue: SLRA, AMP B.2.1.7 BWR Vessel Internals proposed to either:
- install core plate wedges or
Staff determined the second option - a future inspection plan - does not provide sufficient information for the staffs evaluation.
Resolution: Applicant enhances AMP B.2.1.7, in accordance with BWRVIP-25, Revision 1, to:
- inspect core plate rim hold-down bolts, or
- demonstrate instead via analysis that the installation of wedges and inspections of the core plate rim hold-down bolts are not required.
The staff determined each of the three proposed options was acceptable.
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Specific Areas of SLRA Review
- Irradiated Concrete and Containment
- Electrical Cable Qualification and Condition Assessment 11
RPV Neutron Embrittlement at High Fluence
- Neutron fluence of PBAPS Units 2 and 3 at 80 years estimated at 2.23 x 1018 n/cm2
- Not considered high fluence
- Reactor Vessel Material Surveillance Program (B.2.1.20) enhancement
- Unit 2: withdraw 120 degree capsule (reconstituted specimens) at 60-62 EFPY
- Unit 3: withdraw 120 degree capsule at 60-62 EFPY
- Evaluation of time-limited aging analyses in SLRA Section 4.2
- Implements Regulatory Guide 1.99, Revision 2, including consideration of surveillance program data 12
Reactor Internals Irradiation-Assisted Stress Corrosion Cracking (IASCC)
- IASCC of reactor vessel internals managed by:
- BWR Vessel Internals program (B.2.1.7)
- VT-1 and EVT-1 examinations to detect cracks
- Water Chemistry program (B.2.1.2)
- SLRA Section 4.2.14 Core Shroud IASCC and Embrittlement Analysis
- License renewal application (for 60 years) Section 4.3.2.2 identified a threshold value of 5.0E+20 n/cm2 (E > 1 MeV) for IASCC and embrittlement
- Fluence for core shroud and top guide projected to exceed this value for 80 years
- Dispositioned in accordance with 10 CFR 54.21(c)(1)(iii)
- Inspections of core shroud (BWRVIP-76-R1-A) and top guide (BWRVIP-26-A) 13
Irradiation of Concrete and Steel 14
Irradiation of Concrete and Steel Concrete
- The shield wall concrete provides radiation shielding and only the lower 10 ft of the wall concrete performs a structural function
- SRP-SLR thresholds are not exceeded at the peak location
- A plant-specific program is not needed Steel
- 80-yr nil-ductility transition temperature (NDTT) is less than the lowest service temperature (LST) of 100° F
- Loss of fracture toughness is not an aging effect that needs to be managed for the RPV structural steel component supports 15
Electrical Cable Qualification and Condition Assessment
- Peach Bottom has installed the Smartcover' system on electrical cable manholes to monitor water accumulation:
- Float-less transmitter design for level monitoring and alarm
- Self-monitoring capability
- Alarms are generated to alert operators if high water level is sensed or a malfunction occurs
- Staff accepted five-year inspection frequency as an exception for annual inspection per GALL-SLR
- Exelon used the provisions of re-analysis per 10 CFR 50.49 to monitor and extend the qualified life of the cables
- The staff audited the re-analysis methods and calculations and confirmed consistency with current rules and guidelines 16
SLRA Review Conclusion
- On the basis of its review of the SLRA and the resolution of the confirmatory item, the staff determined that the requirements of 10 CFR 54.29(a) have been met for the subsequent license renewal of Peach Bottom Atomic Power Station Units 2 and 3.
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Region I AMP Inspections License Renewal Inspection Program for Period of Extended Operations Inspection Dates Results U2 IP 71003 4Q 2012 No Findings Phase 1 ML13029A013 U3 IP 71003 Not performed N/A Phase 1 U2 IP 71003 March 2013 No Findings Phase 2 ML13071A608 U3 IP71003 4Q 2014 No Findings Modified Phase 2 ML14121A474 U2 and U3 IP71003 4Q 2018 No Findings Phase 4 ML18355A401 18
Region I AMP Inspections AMPs Reviewed During 71004 Phase 4 Inspection
- Maintenance Rule Structural Monitoring Program (existing)
- Ventilation System Inspection and Testing Activities (enhanced)
- Outdoor, Buried and Submerged Component Inspection Activities (enhanced)
- Fire Protection Activities (enhanced)
- In-accessible Medium Voltage Cables not subject to 10 CFR 50.49 Environmental Qualification Requirements (New) 19
Region I AMP Inspections ROP Baseline Inspections Inspection Date Age Management Program IP71111.08 ISI Annually alternate units Reactor Pressure Vessel and Internals ISI Program IP71111.07T Heat Sink 2013, 2016, 2019 GL 89-13 Activities Heat Exchanger Inspection Activities IP71111.21M DBAI 4Q 2017 Ensure the selected SSCs that are subject (operating in the post-40-year licensing period) to aging management review pursuant to 10 CFR Part 54 are being managed for aging in accordance with appropriate aging management programs.
IP71152 PI&R Sample 1Q 2018 The structural monitoring program did not Maintenance Rule Structural Monitoring Program match the procedural requirements for all elements IP71152 PI&R Sample 4Q 2015 Review of Unit 2 Torus Coating Defects Torus Water Chemistry IP71152 PI&R Sample 2Q 2018 Inaccessible Medium-Voltage Cables not subject to 10 CFR Cable reliability program 50.49 Environmental Qualification Requirements IP71152 PI&R Sample 4Q 2018 External flood seal Maintenance Rule Structural Monitoring Program IP71152 PI&R Sample 2Q 2019 U-3, Static O-Ring Pressure Switch Failure 10 CFR 50.49 Environmental Qualification Requirements 20
Region I AMP Inspections Resident Inspector Insight and Inspection Results
- No findings from License Renewal Program inspections and the AMPs being appropriately implemented
Region Conclusion
- Regional Inspections The inspectors found the aging management programs were being implemented in accordance with the license condition. The region will continue to monitor AMPs using the baseline Reactor Oversight Process.
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Summary Conclusion
- Completes the staffs presentation on the safety review of the Peach Bottom SLRA as documented in the Safety Evaluation Report with Confirmatory Item and the Region I presentation on inspections and plant material conditions