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Category:Letter
MONTHYEARIR 05000277/20240022024-08-14014 August 2024 Integrated Inspection Report 05000277/2024002 and 05000278/2024002 ML24225A1692024-08-12012 August 2024 10 CFR 50.46 Annual Report ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, “Revise Risk Informed Completion Time (RICT) Program” Revision 0 and Revise 10 CFR 50.69 License Condition ML24214A3232024-08-0101 August 2024 Response to Request for Additional Information - Request for Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations ML24208A0962024-07-25025 July 2024 57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification ML24206A1252024-07-24024 July 2024 Revision of Three Procedures and Two Forms That Implement the Radiological Emergency Response Plan (RERP) ML24191A0612024-07-0606 July 2024 Independent Spent Fuel Storage Installation (ISFSI) - Annual Radioactive Effluent Release Report ML24178A4142024-06-26026 June 2024 Revision of One Procedure and One Form That Implement the Radiological Emergency Response Plan (RERP) ML24178A3672024-06-26026 June 2024 Correction to 2023 Annual Radioactive Effluent Release Report – Report 47 ML24177A1512024-06-24024 June 2024 Post Accident Monitoring Instrumentation Report ML24166A1172024-06-20020 June 2024 Regulatory Audit Summary Regarding Proposed Alternative Schedule to Complete Decommissioning Beyond 60 Years RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000277/20243012024-06-13013 June 2024 Initial Operator Licensing Examination Report 05000277/2024301 and 05000278/2024301 RS-24-058, Regarding Subsequent License Renewal Environmental Review2024-06-0505 June 2024 Regarding Subsequent License Renewal Environmental Review ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities ML24150A2722024-05-29029 May 2024 Annual Radiological Environmental Operating Report 81, January 1, 2023 Through December 31, 2023 ML24150A0032024-05-28028 May 2024 Request for Exemptions from 10 CFR 50.82(a)(8)(i)(A) and 10 CFR 50.75(h)(1)(iv) and Proposed Amendment to the Decommissioning Trust Agreement RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report ML24134A1792024-05-13013 May 2024 Supplemental Information in Support of Request for Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations IR 05000277/20240012024-05-13013 May 2024 Integrated Inspection Report 05000277/2024001 and 05000278/2024001 IR 05000277/20245012024-05-0808 May 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000277/2024501 and 05000278/2024501 RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests ML24121A1832024-04-30030 April 2024 Pre-Submittal Meeting Presentation Material Peach Bottom ECCS Compensated Level System Replacement Project ML24118A0032024-04-27027 April 2024 2023 Annual Radioactive Effluent Release Report - Report 47 ML24120A2762024-04-23023 April 2024 Independent Spent Fuel Storage Installation (ISFSI) Facility - Annual Radioactive Effluent Release Report 66 January 1, 2023 Through December 31, 2023 CNL-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24107A2462024-04-15015 April 2024 Submittal of Changes to Technical Specifications Bases ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition ML24102A0472024-04-11011 April 2024 Operator Licensing Examination Approval RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report RS-24-023, Report on Status of Decommissioning Funding.2024-03-22022 March 2024 Report on Status of Decommissioning Funding. ML24022A2262024-01-22022 January 2024 (PBAPS) Unit 3 - Submittal of the Inservice Inspection (ISI) Owner'S Activity Report (OAR) for the 24th Refueling Outage for Unit 3 ML23346A2412024-01-17017 January 2024 Staff Assessment of Updated Seismic Hazards Following the NRC Process for the Ongoing Assessment of Natural Hazards Information (EPID L-2019-PMP-0061) - Letter IR 05000277/20234022024-01-11011 January 2024 Security Baseline Inspection Report 05000277/2023402 and 05000278/2023402 and Independent Spent Fuel Storage Installation Security Inspection 07200029/2023401 ML23354A1922024-01-0505 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) ML23355A0622023-12-18018 December 2023 Independent Spent Fuel Storage Installation (Isfsi), Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 ML23334A2502023-11-30030 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23270C0072023-11-29029 November 2023 Notice of Proposed Amendment to Decommissioning Trust Agreement ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums ML23305A3472023-11-0101 November 2023 Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) IR 05000277/20230032023-10-30030 October 2023 Integrated Inspection Report 05000277/2023003 and 05000278/2023003 and Exercise of Enforcement Discretion ML23286A0012023-10-13013 October 2023 Reply to a Notice of Violation (NOV) - NOV 05000277, 05000278/2023010-01 RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans ML23271A1342023-10-11011 October 2023 Dtf Analysis Letter IR 05000277/20244012023-10-0505 October 2023 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000277/2024401 and 05000278/2024401 2024-08-09
[Table view] Category:Report
MONTHYEARML24177A1512024-06-24024 June 2024 Post Accident Monitoring Instrumentation Report ML23346A2392024-01-17017 January 2024 Seismic Hazard Report by the Office of Nuclear Reactor Regulation ML23334A2502023-11-30030 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation NMP1L3469, Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits2022-06-30030 June 2022 Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits CCN:22-15, (Pbaps), Units 1, 2, and 3 - Annual Commitment Revision Report for the Period 01/01/21 Through 12/31/212022-01-31031 January 2022 (Pbaps), Units 1, 2, and 3 - Annual Commitment Revision Report for the Period 01/01/21 Through 12/31/21 RS-21-001, Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping2021-01-0404 January 2021 Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping ML20329A3452020-11-24024 November 2020 Relief Request Associated with N-16A Reactor Pressure Vessel Instrument Nozzle Repairs - Submittal of Analyses ML20314A0282020-11-0606 November 2020 Verbal Relief for Penetration Nozzle ML20303A1752020-10-23023 October 2020 Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting ML19053A4692019-06-10010 June 2019 Staff Review of Seismic Probabilistic Risk Assessment Associated with Reevaluation Seismic Hazard Implementation of the Near Term Task Force Recommendation 2.1: Seismic ML19007A3302019-01-0707 January 2019 Final Report PBAPS Thermal Study ML18354B0662018-12-20020 December 2018 Summary of Monitoring Well Installation Details RS-18-113, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident...2018-09-28028 September 2018 Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident... RS-18-098, Seismic Probabilistic Risk Assessment Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from ...2018-08-28028 August 2018 Seismic Probabilistic Risk Assessment Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from ... ML18093A3822018-03-30030 March 2018 Decommissioning Status Report - 2017 RS-18-002, Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2018-01-0505 January 2018 Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) ML17093A6972017-03-30030 March 2017 Decommissioning Status Report - 2016 ML19064B2232017-02-24024 February 2017 Final Report for Post-EPU Thermal and Biological Monitoring Peach Bottom Atomic Power Station ML17027A0152017-01-27027 January 2017 ISFSI - Biennial 1OCFR 50.59 and 10CFR 72.48 Reports for the Period 1/1/2015 Through 12/31/2016 and Annual Commitment Revision Report for the Period 1/1/16 Through 12/31/16 ML16342B6212016-12-0707 December 2016 Results of Visual Inspections of Replacement Steam Dryer RS-16-103, Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal2016-06-30030 June 2016 Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal ML16048A4412016-02-17017 February 2016 Transmittal of Extended Power Uprate: Results of Replacement Steam Dryer Power Ascension Testing ML19064B2162015-12-31031 December 2015 Data Report or Intake Screen Sampling at Peach Bottom Atomic Power Station in 2015 ML15275A1682015-10-0202 October 2015 Attachment 2, LTR-BWR-ENG-15-076-NP, Revision 1, Replacement Steam Dryer Report at Predicted EPU Conditions (Non-Proprietary) and Attachment 3, Affidavit ML15233A0952015-08-20020 August 2015 Revision 0 to LTR-BWR-ENG-15-076-NP, Replacement Steam Dryer Report at Predicted EPU Conditions ML15219A6182015-08-0707 August 2015 Extended Power Uprate: Results of Unit 2 Replacement Steam Dryer Power Ascension Testing ML15051A2622015-04-20020 April 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations Related to Recommendation 2.1 ML15097A0762015-04-0606 April 2015 Soarca Peach Bottom 2005 Site File ML15096A0082015-04-0505 April 2015 Extended Power Uprate: Response to Replacement Steam Dryer Requests for Additional Information ML15026A4692015-02-12012 February 2015 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to EA-13-109 (Severe Accident Capable Hardened Vents) ML15029A6402015-01-29029 January 2015 Mellla+ License Amendment Request Supplement 1 Supplemental Reload Licensing Report ML15028A3812015-01-28028 January 2015 Independent Spent Fuel Storage Installation (ISFSI) - Biennial 10 CFR 50.59 and 10CFR 72.48 Reports for the Period 1/1/2013 Through 12/31/2014 and Annual Commitment Revision Report for Period 1/1/14 - 12/31/14 ML19064B2142014-12-31031 December 2014 Data Report or Intake Screen Sampling at Peach Bottom Atomic Power Station in 2014 RS-14-300, Expedited Seismic Evaluation Process Report (CEUS Sites), Response to Nrg Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1..2014-12-19019 December 2014 Expedited Seismic Evaluation Process Report (CEUS Sites), Response to Nrg Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1.. RS-14-277, Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 12014-09-24024 September 2014 Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1 ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 ML14119A0572014-06-17017 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident (Tac Nos. MF0261 and MF0262) ML14086A6242014-04-30030 April 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident (MF0157 and MF0158) ML14105A3852014-04-11011 April 2014 Attachment 8: WCAP-17635-NP, Rev. 3, Comprehensive Vibration Assessment Program ML14105A3882014-04-11011 April 2014 Attachment 11: WCAP-17655-NP, Rev. 4, Replacement Steam Dryer Power Ascension Program Description for Extended Power Uprate ML14105A3872014-04-11011 April 2014 Attachment 10: WCAP-17654-NP, Rev. 4, Replacement Steam Dryer Power Ascension Program Description for Extended Power Uprate ML14105A3862014-04-11011 April 2014 Attachment 9: WCAP-17649-NP, Rev. 2, ASME Code Stress Report (Enclosure B.3) ML14072A0262014-03-31031 March 2014 WCAP-17655-NP, Rev 3,Peach Bottom Unit 3 Replacement Steam Dryer Power Ascension Program Description for Extended Power Uprate. ML14072A0252014-03-31031 March 2014 WCAP-17654-NP, Rev 3, Peach Bottom Unit 2 Replacement Steam Dryer Power Ascension Program Description for Extended Power Uprate. ML14072A0242014-03-31031 March 2014 WCAP-17609-NP, Rev 2, Peach Bottom Units 2 and 3 Replacement Steam Dryer Structural Evaluation for High-Cycle Acoustic Loads. ML14072A0232014-03-31031 March 2014 WCAP-17635-NP, Rev 2, Peach Bottom Atomic Power Station Unit 2 and Unit 3 Replacement Steam Dryer Comprehensive Vibration Assessment Program. ML19007A3282014-02-28028 February 2014 Final Report for the Thermal Study to Support a 316(a) Demonstration ML19064B2202014-02-28028 February 2014 Final Report for the Thermal Study to Support a 316(a) Demonstration: Peach Bottom Atomic Power Station Part 1 of 2 ML14070A1462014-02-28028 February 2014 WCAP-17639-NP, Revision 3, Instrumentation Description for the Peach Bottom Unit 2 Replacement Steam Dryer. ML14070A1452014-02-28028 February 2014 WCAP-17626-NP, Revision 1, Processing of Peach Bottom Unit 2 and Unit 3 MSL Strain Gauge Data and Computation of Predicted EPU Signature. 2024-06-24
[Table view] Category:Miscellaneous
MONTHYEARML24177A1512024-06-24024 June 2024 Post Accident Monitoring Instrumentation Report ML23334A2502023-11-30030 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation CCN:22-15, (Pbaps), Units 1, 2, and 3 - Annual Commitment Revision Report for the Period 01/01/21 Through 12/31/212022-01-31031 January 2022 (Pbaps), Units 1, 2, and 3 - Annual Commitment Revision Report for the Period 01/01/21 Through 12/31/21 ML20303A1752020-10-23023 October 2020 Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting ML18093A3822018-03-30030 March 2018 Decommissioning Status Report - 2017 ML17093A6972017-03-30030 March 2017 Decommissioning Status Report - 2016 ML19064B2232017-02-24024 February 2017 Final Report for Post-EPU Thermal and Biological Monitoring Peach Bottom Atomic Power Station ML17027A0152017-01-27027 January 2017 ISFSI - Biennial 1OCFR 50.59 and 10CFR 72.48 Reports for the Period 1/1/2015 Through 12/31/2016 and Annual Commitment Revision Report for the Period 1/1/16 Through 12/31/16 ML16342B6212016-12-0707 December 2016 Results of Visual Inspections of Replacement Steam Dryer RS-16-103, Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal2016-06-30030 June 2016 Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal ML19064B2162015-12-31031 December 2015 Data Report or Intake Screen Sampling at Peach Bottom Atomic Power Station in 2015 ML15051A2622015-04-20020 April 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations Related to Recommendation 2.1 ML15097A0762015-04-0606 April 2015 Soarca Peach Bottom 2005 Site File ML15096A0082015-04-0505 April 2015 Extended Power Uprate: Response to Replacement Steam Dryer Requests for Additional Information ML15026A4692015-02-12012 February 2015 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to EA-13-109 (Severe Accident Capable Hardened Vents) ML15028A3812015-01-28028 January 2015 Independent Spent Fuel Storage Installation (ISFSI) - Biennial 10 CFR 50.59 and 10CFR 72.48 Reports for the Period 1/1/2013 Through 12/31/2014 and Annual Commitment Revision Report for Period 1/1/14 - 12/31/14 ML14119A0572014-06-17017 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident (Tac Nos. MF0261 and MF0262) ML14086A6242014-04-30030 April 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident (MF0157 and MF0158) ML19064B2202014-02-28028 February 2014 Final Report for the Thermal Study to Support a 316(a) Demonstration: Peach Bottom Atomic Power Station Part 1 of 2 ML14070A1432014-02-28028 February 2014 WCAP-17590-NP, Revision 2, Peach Bottom Units 2 and 3, Replacement Steam Dryer, Acoustic Load Definition. ML14070A1442014-02-28028 February 2014 WCAP-17649-NP, Revision 1, Peach Bottom Units 2 and 3 ASME Code Stress Report. ML14070A1452014-02-28028 February 2014 WCAP-17626-NP, Revision 1, Processing of Peach Bottom Unit 2 and Unit 3 MSL Strain Gauge Data and Computation of Predicted EPU Signature. ML14070A1462014-02-28028 February 2014 WCAP-17639-NP, Revision 3, Instrumentation Description for the Peach Bottom Unit 2 Replacement Steam Dryer. ML19064B2332013-12-0606 December 2013 Data Report or Intake Screen Sampling at Peach Bottom Atomic Power Station in 2013 RS-13-085, Response to March 12, 2012, Request for Information Per 10 CFR 50.54(f) Recommendations of the Near- Term Task Force Review of Insights from Fukushima Dai-ichi Accident, Enclosure 5, Recommendation 9.3, Emergency...2013-04-30030 April 2013 Response to March 12, 2012, Request for Information Per 10 CFR 50.54(f) Recommendations of the Near- Term Task Force Review of Insights from Fukushima Dai-ichi Accident, Enclosure 5, Recommendation 9.3, Emergency... ML13109A0522013-04-18018 April 2013 Revised Gnf Response to NRC RAI 44 for License Amendment Request for Use of Neutron Absorbing Spent Fuel Pool Rack Inserts, Attachment 3, Enclosures 2, 3 and 4 ML19064B2372013-02-25025 February 2013 Entrainment Characterization Study 2012 IR 05000456/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee ML13008A2192013-01-31031 January 2013 U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000454/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000461/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000237/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000373/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000352/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000219/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000277/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000254/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000272/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000289/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee NEI 99-04, Peach Bottom, Units 1, 2 and 3 and Independent Spent Fuel Storage Installation - Biennial 10CFR 50.59 and 10CFR 72.48 Reports for the Period 1/1/2011 Through 12/31/2012 and Annual Commitment Revision Report for the Period 1/1/12 Through 122013-01-28028 January 2013 Peach Bottom, Units 1, 2 and 3 and Independent Spent Fuel Storage Installation - Biennial 10CFR 50.59 and 10CFR 72.48 Reports for the Period 1/1/2011 Through 12/31/2012 and Annual Commitment Revision Report for the Period 1/1/12 Through 12/ ML19064B2302012-12-0707 December 2012 Data Report or Intake Screen Sampling at Peach Bottom Atomic Power Station in 2012 ML13003A0262012-11-16016 November 2012 Report No. MPR-3812, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Page C-372 Through End ML13003A0252012-11-16016 November 2012 Report No. MPR-3815, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Cover Through Page B-104 ML13003A0272012-11-16016 November 2012 Report No. MPR-3815, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Page C-1 Through Page C-76 ML13003A0282012-11-16016 November 2012 Report No. MPR-3815, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Page C-77 Through Page C-156 ML13003A0292012-11-16016 November 2012 Report No. MPR-3815, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Page C-157 Through Page C-249 ML13003A0302012-11-16016 November 2012 Report No. MPR-3815, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Page C-250 Through Page C-333 ML13003A0312012-11-16016 November 2012 Report No. MPR-3815, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Page C-334 Through Page C-399 ML13003A0322012-11-16016 November 2012 Report No. MPR-3815, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Page C-400 Through End ML13003A0332012-11-16016 November 2012 Report No. MPR-3812, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Cover Through Page B-104 2024-06-24
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Exelon Ge n e r a t ion. December 7, 2016 U.S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington DC 20555-0001 Peach Bottom Atomic Power Station, Unit 2 Renewed Facility Operating License No. DPR-44 NRC Docket No. 50-277 DPR-44 Operating License 2.C(15)(g)
Subject:
Results of Visual Inspections of Unit 2 Replacement Steam Dryer
References:
- 1. WCAP-17635-P, Rev. 3, Peach Bottom Atomic Power Station Unit 2 and Unit 3 Replacement Steam Dryer Comprehensive Vibration Assessment program (CVAP), April 2014 2. PBAPS Extended Power Uprate License Amendment Request -Supplement 24 -Response to Request for Additional Information, dated April 11, 2014 3. NRC -Issuance of Amendments
-PBAPS Units 2 and 3 Extended Power Uprate, License Amendments 293/296 (including NRC Safety Evaluation Report), dated August 25, 2014 Enclosed is a summary of the results of the visual inspections of the Unit 2 Replacement Steam Dryer that were performed during the recent refueling outage {P2R21 }. The inspections are required to be performed following the guidelines of WCAP-17635-P in accordance with Operating License Section 2.C{15)(f).
This first report is being submitted pursuant to Operating License Condition 2.C{15}{g) which requires that the results of the inspection be submitted in a report within 90 days following startup from each of the first two respective refueling outages. The inspection was performed in accordance with WCAP-17635, Rev. 3 (Reference 1} which was submitted to the NRC in the Reference 2 letter and referenced by the NRC in the NRC Safety Evaluation Report for Extended Power Uprate (Reference 3). If you have any questions concerning this letter, please contact Sandra Kame at (717) 456-3022.
Michael J. Massaro Site Vice President Peach Bottom Atomic Power Station CCN: 16-101 Attachment
-Unit 2 License Condition 2.C(15}{g} Replacement Steam Dryer Inspection Results cc: Regional Administrator, Region I, USNRC USNRC Senior Resident Inspector, PBAPS R. R. Janati, Pennsylvania Bureau of Radiation Protection S. T. Gray, State of Maryland Attachment
-Results of Visual Inspection for PBAPS Unit 2 Replacement Steam Dryer Page 1 of6 ATTACHMENT Unit 2 License Condition 2.C(15)(g)
Replacement Steam Dryer Inspection Results Attachment
-Results of Visual Inspection for PBAPS Unit 2 Replacement Steam Dryer Page2of6 Peach Bottom Unit 2 Steam Dryer Inspection Results from the First Refueling Outage Following Installation of Steam Dryer and Implementation of Extended Power Uprate Purpose: This report provides the results of the visual inspections of the Replacement Steam Dryer (RSD) as required by the Peach Bottom Unit 2 Renewed Facility Operating License No DPR-44, License Condition 2.C(15)(g).
This license condition requires that the results of the inspection be submitted in a report within 90 days following startup from each of the first two respective refueling outages. Summary: The Unit 2 Replacement Steam Dryer was inspected during the fall 2016 refueling outage, P2R21, from October 26th through November 4th, 2016. This was the first refueling outage following installation of the RSD in November 2014 and operation at Extended Power Uprate (EPU) conditions since May 2015. The inspections were performed in accordance with the requirements of the WCAP-17635-P and recommendations from the manufacturer, Westinghouse.
The inspection scope was defined based upon Operating Experience (OE) for the Westinghouse steam dryer design from previous installations, h i gh cyclical stress locations determined from the dryer acoustic analysis, similarities to BWRVIP-139-A inspection locations and finally, by higher stress locations where solution annealing of structural welds had not been performed.
The guidelines for the dryer inspection are defined in WCAP-17635-P Section 5. Table 5-1 provides the inspection locations for the Unit 2 RSD following the first cycle of operation at EPU conditions.
A general visual examination (VT-3) was performed on the entire RSD. The baseline inspection included the top of the RSD (including the outside of the skirt), underside of the RSD, lifting rods, hold down rods, support ring, outer ring top cage, W and U channel guides, support ring, vertical drain channels, outer, middle and inner hoods. All observations were acceptable for the structural components and welds inspected.
There were indications on four welds that required further evaluation.
These welds are non-structural and were not explicitly modeled or analyzed as part of the structural qualification of the steam dryer. The summary results of the inspections can be found in the table below. NRI = No Relevant Indication RI= Relevant Indication Inspection Location Method Inspection Condition Report Disposition Result (if RI) General Inspection of Top of the Replacement VT-3 NRI Steam Dryer (to include outside of skirt) General Inspection on Underside of VT-3 NRI Replacement Steam Dryer Hold Down Rods (HDRs) (and welded VT-3, NRI attachments to the top plate of the dryer) VT-1 Lifting Rods Top Ends (and welded attachments VT-3, NRI to the top plate of the dryer) VT-1 Hold Down Rods (and welded attachments to the VT-3 , RI support ring) VT-1 2734507 Use-as-is Lifting Rods Top Ends (and welded attachments VT-3, NRI to the support ring) VT-1 Attachment
-Results of Visual Inspection for PBAPS Unit 2 Replacement Steam Dryer Page 3of6 Inspection Location Method Inspection Condition Report Disposition Result (if RI) Support Ring VT-3 NRI Outer, middle, inner hoods VT-3 NRI Outer Ring Top Cage VT-3 NRI Vertical Drain Channels VT-3 NRI Skirt (Outside)
VT-3 NRI Skirt (Inside) VT-3 NRI Visual examinations (VT-1) were performed on welds associated with the RSD. As described in WCAP-17635-P, the steam dryer is octagonal (high symmetry) and VT-1 inspections were performed on a section of the octagon. If any flaws were identified, the comparable locations on the other sections of the dryer were examined in the same outage. The results of the VT-1 inspections can be found in the table below: Inspection Condition Weld Designation Description Report Disposition Result (if RI) AA 335740 W1 0 W channel to ring NRI AA 335740 W2 90 U channel to ring NRI AA 335740 W3 112.5 Vertical drain channel to ring NRI AA 335740 W4 135 Upper Dryer to lower dryer NRI circumferential weld AA 335740 W5 112.5 Site Drain Channel Piece Welds NRI AA 335740 W6 LR 142.25 Lifting rod bracket to top of dryer NRI AA 335740 W6 HOR Hold down rod bracket to top of NRI 142.25 drver AA 3357 40 W7 LR 142.25 Lifting rod bracket to ring NRI connection AA 335740 W7 HOR Hold down rod bracket to ring RI 37.75 connection 2734507 Use-as-is AA 335740 W7 HOR Hold down rod bracket to ring RI 142.25 connection 2734507 Use-as-is AA 335740 W7 HOR Hold down rod bracket to ring RI 217.75 connection 2734507 Use-as-is AA 335740 W7 HOR Hold down rod bracket to ring RI 322.25 connection 2734507 Use-as-is AA 335740 wa LR Lifting rod bracket to rod NRI 142.25 AA 335740 wa HOR Hold down rod bracket to rod NRI 142.25 AA 335740 W9 LR 138.5 Lifting rod top to rod NRI AA 335740 W10 HOR Hold down rod top to rod NRI 146 AA 335740 W14 90 Horizontal shims to block NRI Weld Designation AA 335741 W3 112.5 AA 335741 W5112.5 AA 335741 W9 112.5 AA 335741 W11112.5 AA 335741 W13 90 AA 335741 W15112.5 AA 335741 W18 112.5 AA 335741 W20 112.5 AA 335741 W21 112.5 AA 335741 W2290 AA 335741 W2390 AA 335741 W24 112.5 AA 335741 W2690 AA 335741 W2790 AA 335741 W28 112.5 AA 335741 W29 112.5 Inner AA 335741 W29 112.5 Middle AA 335741 W29 112.5 Outer AA 335741 W3090 AA 335741 W3290 AA 335741 W35112.5 AA 335741 W36 112.5 AA 335741 W37 112.5 AA 335741 W38 112.5 AA 335741 W39 112.5 AA 335741 W41 157.5 Inner AA 335741 W41 157.5 Outer AA 362220 W 1 55 Attachment
-Results of Visual Inspection for PBAPS Unit 2 Replacement Steam Dryer Page 4 of6 Inspection Condition Description Report Disposition Result (if RI) Inner panel to inner inner corner NRI Inner panel to inner outer corner NRI Middle panel to middle inner NRI corner Middle panel to middle outer NRI corner Toplnnerhoodtoinnerpanel NRI lnnerhoodtoinnerhood NRI Outer panel to outer inner corner NRI Outer panel to outer outer corner NRI Outer corner top cap all around+ NRI Top middle hood to middle panel NRI Bottom middle hood to outer NRI oanel Middle hood to Middle hood NRI Top outer hood to outer panel NRI Bottom outer hood to support ring NRI Outer hood to Outer hood NRI Top ring girder to panel and NRI corner and corner cap Top ring girder to panel and NRI corner and corner cao Top ring girder to panel and NRI corner and corner cao Seismic Block (Outer Welds) NRI Shims NRI Inner corner to top inner hood NRI Middle corner to top middle hood NRI Outer corner to top outer hood NRI Middle corner to bottom hood NRI Outer corner to bottom hood NRI Instrumentation mast bracket NRI Instrumentation mast bracket NRI Two halves of main ring NRI Weld Designation AA 335756 W5W8W18 90 AA 335757 W5W8W18 90 AA 335758 W5W8W18 90 AA 335758 W 13 90 AA335762 W2 112.5 AA 335742 W1 0 AA 335742 W2 90 AA335742 W3 135 AA335742 W4 112.5 AA 335742 W5 0 AA335742 W6 90 AA335742 W7 135 AA 335742 W8 90 AA 3357 42 W9 112.5 AA 335742 W10 112.5 AA 335743 W8 112.5 AA335757 W10 90 AA 362066 W1 0 AA 362066 W2 90 AA 362066 W3 135 AA362066 W4 90 AA 362066 W5 112.5 AA 362066 W6 112.5 AA 362222 W1 45 AA 362221 W1 45 Inspection Results: Attachment
-Results of Visual Inspection for PBAPS Unit 2 Replacement Steam Dryer Page 5 of6 Inspection Condition Description Report Disposition Result (if RI) Inner top channel to top strip NRI Middle top channel to top strip NRI Outer top channel to top strip NRI Outer perf plate to top strip NRI Girders to center ring NRI Middle ring to lower W channel NRI Middle ring to lower U channel NRI Middle ring to lower part outer NRI walls Middle ring to lower part vert drain NRI channels Middle ring to upper W channel NRI Middle ring to upper U channel NRI Middle ring to upper outer walls NRI W and U channels to upper outer NRI walls Middle ring to upper vert drain NRI channels Vert drain channels to upper outer NRI walls Outer Trough to Spoke NRI Trough Plate to Side plate NRI W channel to lower ring NRI U channel to lower ring NRI Lower ring to walls above NRI W and U channels to walls NRI Drain channels to walls NRI Lower ring to drain channels NRI Welds Lower Ring Together NRI Middle ring welded together NRI Indications were identified in weld AA335740 W7 fillet weld at the hold down rod interface to the support ring for all four (4) hold down rod locations at 37.75, 142.25 , 217.75 and 322.25 degree azimuths (Ref. IR 2734507).
Indications have been dispositioned as use-as-is.
The ind i cations do not adversely affect the Attachment
-Results of Visual Inspection for PBAPS Unit 2 Replacement Steam Dryer Page 6 of6 steam dryer's structural integrity.
These welds are non-structural and were not explicitly modeled or analyzed as part of the structural qualification of the steam dryer. All hold down rod weld locations are scheduled for re-inspection during the Unit 2 P2R22 in 2018 to determine if any changes have occurred.
No other recordable indications were identified during the inspection process. Disposition of Indications:
During P2R21, cracks were observed at the AA335740 W7 fillet weld at the hold down rod interface to the support ring for all four (4) hold down rod locations at 37.75, 142.25, 217.75 and 322.25 degree azimuths.
The non-structural fillet welds (AA335740 W7) of the hold down rod are for positioning and anti-rotation during construction.
In that function, as construction welds, they do not carry primary load. The hold down rod function does not depend on the non-structural AA335740 W7 fillet weld. During plant operation, the positioning at the bottom of the hold down rod is guaranteed by the threaded bottom part; and the rotation is maintained on top by the top bracket and its structural hold down rod top to rod AA335740 W10 weld. The AA 335740 W7 non-structural welds are not credited to show ASME Ill Code compliance for the hold down function.
The purpose for including this weld in the inspection plan was primarily due to its inclusion in BWRVIP-139-A, which requires inspection of similar locations on GE steam dryer based on previous operating experience.
Based on review of the purpose of the fillet weld, the critical aspect of the inspection for the hold down rod attachment to the ring is the integrity of the threaded connection at the ring attachment location.
The inspection has confirmed no crack extension into the rod and no crack extension into the rod is anticipated.
The top bracket with its structural welds AA335740 W10 maintains position, prevents rotation and assures thread engagement, thus eliminating any risk for loose parts. The design stress margins for the top bracket remain unchanged by the cracking of the construction fillet welds at the bottom support ring location.
No repair is required to the non-structural welds at the bottom of the hold down rods. The AA335740 W7 locations will be re-inspected during P2R22 to confirm no crack extension into the hold down rod at the ring attachment location or crack initiation at the upper bracket welds. These conditions do not impact the HDRs ability to perform their function of preventing uncontrolled lift off after stream line break in faulted condition.
No linear indications (fatigue or IGSCC cracks) were identified on any of the lifting rods or at the top of the hold down rod assemblies.
As such, there is no degradation mechanism present that could impact the integrity of the attachment weld to the top of the HOR bracket, or the integrity of the HOR itself.
Conclusion:
A complete baseline inspection of the Peach Bottom Unit 2 Steam Dryer was performed during the fall 2016 refueling outage 21. The baseline inspection included successful visual inspection of all of the inspection locations required by the Facility Operating License Condition 2.C(15)(f) for inspection of the Replacement Steam Dryer. All observations were acceptable for the structural components and welds inspected.
There were four non-structural welds found with cracks that were dispositioned acceptable is. These welds were not explicitly modeled or analyzed as part of the structural qualification of the dryer. The subsequent inspection scope of the steam dryer will be performed during the Unit 2 P2R22 in 2018 and the results will be provided at that time consistent with the Peach Bottom Operating License.