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MONTHYEARML1025700842009-11-19019 November 2009 Calculation CC-AA-309-1001, Rev. 5, to Establish Limiting Demand for N(2) for the CAD System & the Sgig System for Dual Unit Operation. Project stage: Other ML1017901142010-06-25025 June 2010 License Amendment Request for Non-Conservative Technical Specification Associated with the Amount of Liquid Nitrogen Storage Project stage: Request ML1023100792010-08-16016 August 2010 Supplemental Information for License Amendment Request Concerning Non-Conservative Technical Specification Associated with Amount of Liquid Nitrogen Storage Project stage: Supplement ML1035403112010-12-20020 December 2010 Draft Request for Additional Information Regarding License Amendment Request Related to Liquid Nitrogen Storage Peach Bottom Atomic Power Station, Units 2 and 3 Project stage: Draft RAI ML1102801032011-01-26026 January 2011 Response to Request for Additional Information, License Amendment Request Concerning Non-Conservative Technical Specification Associated with the Amount of Liquid Nitrogen Storage Project stage: Response to RAI ML1106011012011-03-10010 March 2011 Request for Additional Information Regarding License Amendment Request Related to Liquid Nitrogen Storage Project stage: RAI 2010-06-25
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Category:Letter
MONTHYEARML24022A2262024-01-22022 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 ML23265A1502023-09-22022 September 2023 License Amendment Request Revise a License Condition and Certain Technical Specifications to Remove Restrictions in Support of Decommissioning Activities ML23264A8682023-09-21021 September 2023 Independent Spent Fuel Storage Installation Registration of Dry Storage Canister WC-EOS-37PTH-008-B4L, WC-EOS-37PTH-007-B4L, and WC-EOS-37PTH-002-B4L IR 05000277/20230102023-09-15015 September 2023 Biennial Problem Identification and Resolution Inspection Report 05000277/2023010 and 05000278/2023010 and Notice of Violation ML23251A2022023-09-11011 September 2023 Cover Letter W/Report LR-N23-0045, and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement2023-09-0808 September 2023 and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement IR 05000277/20230052023-08-31031 August 2023 Updated Inspection Plan for Peach Bottom Atomic Power Station, Units 2 and 3 (Report 05000277/2023005 and 05000278/2023005) ML23158A1952023-08-30030 August 2023 R. E. Ginna - Issuance of Amendments to Adopt TSTF-273-A, Revision 2, Safety Function Determination Program Clarifications ML23232A0012023-08-19019 August 2023 Revision of One Procedure That Implements the Radiological Emergency Response Plan (Rerp). Includes EPP 06-009, Rev. 13 IR 05000277/20230112023-08-15015 August 2023 Comprehensive Engineering Team Inspection Report 05000277/2023011 and 05000278/2023011 ML23226A1112023-08-14014 August 2023 10 CFR 50.46 Annual Report IR 05000277/20230022023-08-0808 August 2023 Integrated Inspection Report 05000277/2023002 and 05000278/2023002 RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023 Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor IR 05000277/20230402023-07-17017 July 2023 95001 Inspection Supplemental Report 05000277/2023040 and Follow-Up Assessment Letter ML23188A0532023-07-0707 July 2023 Registration of Use of Independent Spent Fuel Storage Installation (ISFSI) Casks ML23186A1272023-07-0606 July 2023 Response to Disputed Non-Cited Violation Documented in Peach Bottom Atomic Power Station, Units 2 and 3, Inspection Report 05000277/2022004 and 05000278/2022004 ML23178A0352023-06-27027 June 2023 Senior Reactor and Reactor Operator Initial License Examinations RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23151A4162023-05-31031 May 2023 Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) for Wolf Creek Generating Station (WCGS) ML23150A2052023-05-30030 May 2023 Independent Spent Fuel Storage Installation (Isfsi), Annual Radiological Environmental Operating Report 80 January 1, 2022 Through December 31, 2022 RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling ML23142A1602023-05-23023 May 2023 Summary of April 11, 2023, Public Observation Meeting with Constellation Energy Generation, LLC Re Proposed Exemption Request from Work Hour Requirements ML23132A1582023-05-18018 May 2023 Correction to Technical Specification 3.4.7 (Page 3.4-16) Issued in Amendment No. 337 ML23132A1532023-05-12012 May 2023 Transmittal of 2022 Annual Financial Reports WM 23-0009, Financial Assurance Requirements for Decommissioning Nuclear Power Reactors 10 CFR 50.75(f)(1)2023-05-10010 May 2023 Financial Assurance Requirements for Decommissioning Nuclear Power Reactors 10 CFR 50.75(f)(1) IR 05000277/20230012023-05-0808 May 2023 Integrated Inspection Report 05000277/2023001 and 05000278/2023001 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI 2024-01-05
[Table view] Category:Report
MONTHYEARML23346A2392024-01-17017 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) ML14105A3862014-04-11011 April 2014 Attachment 9: WCAP-17649-NP, Rev. 2, ASME Code Stress Report (Enclosure B.3) 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 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. 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. 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. 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. ML19007A3282014-02-28028 February 2014 Final Report for the Thermal Study to Support a 316(a) Demonstration 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. ML14070A1442014-02-28028 February 2014 WCAP-17649-NP, Revision 1, Peach Bottom Units 2 and 3 ASME Code Stress Report. ML14070A1432014-02-28028 February 2014 WCAP-17590-NP, Revision 2, Peach Bottom Units 2 and 3, Replacement Steam Dryer, Acoustic Load Definition. 2024-01-17
[Table view] Category:Miscellaneous
MONTHYEARML23334A2502023-11-30030 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 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. ML14070A1442014-02-28028 February 2014 WCAP-17649-NP, Revision 1, Peach Bottom Units 2 and 3 ASME Code Stress Report. ML14070A1432014-02-28028 February 2014 WCAP-17590-NP, Revision 2, Peach Bottom Units 2 and 3, Replacement Steam Dryer, Acoustic Load Definition. 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 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 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 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 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 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 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 ML13003A0342012-11-16016 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-1 Through Page C-67 2023-11-30
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{{#Wiki_filter:Exelonii Nu Nuclear wwwexeloncorp.com WWWtX(cflcOtpCO1fl Exel n Exekn l Nucl Nuclear kTH1eI t PJ\ iq 10 CFR 50.90 10 CFR 50.90 January 26, 2011 U.S. Nuclear Regulatory Commission AnN:
ATTN: Document Control Desk Washington, D.C. 20555-0001 Peach Bottom Atomic Power Station, Units 2 and 33 Renewed Facility Operating License Nos. Nos. DPR-44 and and DPR-56 DPR-56 NRC Docket Nos. 50-277 and 50-278
Subject:
. Response to Request for Additional Information License Amendment Request Concerning Non-Conserv ative Technical Non-Conservative Specification Associated with the Amount of Liquid Nitrogen Storage
References:
- 1) Letter from P. B. Cowan (Exelon Generation Company, LLC) to U.S. U.S. Nuclear Nuclear Regulatory Commission - License Amendment Request for Non-Conserv
- ative Non-Conservative Technical Specification Associated with the Amount of Liquid Nitrogen Nitrogen Storage - dated June 25, 2010 (ML1O1
- 790114)
(ML101790114)
- 2) Letter from J. D. Hughey (U.S. Nuclear Regulatory Commission Commission)) to M. J.
J.
Pacilio (Exelon Generation Company, LLC), Peach "Peach Bottom Atomic Power Supplemental Information Needed for Acceptance of Station, Units 2 and 3: Supplemental Requested Licensing Action Re: Liquid Nitrogen Storage (TAG (TAC Nos. ME41 ME4131 31 ME4132), dated JUly and ME4132), II (ML102110061)
July 30, 2010 (ML102110061)
- 3) Letter from P. B. Cowan (Exelon Generation Company, LLC) to U.S. Nuclear Supplemental Information for License Amendment Regulatory Commission - Supplemental Non-Conservative Technical Specification Associated with the Request for Non-Conservative Amount of Liquid Nitrogen Storage - dated August 16,
- 16, 2010 (ML1 0231 0079)
(ML102310079)
Commission) to M. J.
- 4) Letter from J. D. Hughey (U.S. Nuclear Regulatory Commission)
Pacilio (Exelon Generation Company, LLC), "Peach Peach Bottom Atomic Power Station, Units 2 and 3 - Request for Additional Information Regarding License Amendment Request Related to Liquid Nitrogen Storage (TAC (TAG Nos.
ME4131 and ME4132),1I 21, 2010 (ML102861886)
ME4132),° dated October 21,2010 (ML102861886)
(5) Letter from P. B. Cowan (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission - Response to Request for Additional Information for Non-Conservative Technical Specification License Amendment Request for Non-Conservative Associated with the Amount of Liquid Nitrogen Storage, dated December 6, (ML103410398) 2010 (ML103410398)
Commission) to M. J.
(6) Letter from J. D. Hughey (U.S. Nuclear Regulatory Commission)
Pacilio (Exelon Generation Company, LLC), "Peach Peach Bottom Atomic Power Station, Units 2 and 3 - Request for Additional Information Regarding License Amendment Request Related to Liquid Nitrogen Storage (TAC (TAG Nos.
(ML103540505)
ME4132),II dated December 30, 2010 (ML103540505)
ME4131 and ME4132),
u.s.
U.S. Nuclear Regulatory Commission Response to Request for Additional Information License Amendment Request Liquid Nitrogen Storage Docket Nos. 50-277 and 50-278 January 26,2011 26, 2011 Page 2 By letter dated June 25, 2010 (Reference 1), LLC, (Exelon) 1), Exelon Generation Company, LLC, (Exelon) submitted a License Amendment Request (LAR) for the Peach Bottom Atomic Power Station Station (PBAPS), Units 2 and 3, requesting changes to the Technical Specifications (TS) to address address non-conservative TS Surveillance Requirements (SR) associated with the amount of nitrogen nitrogen available in the liquid nitrogen storage tank.
References 2 thru 5 involve requests for additional information and associated responses.
Subsequently, by letter dated December 30, 2010 (Reference 6), the NRC requested that Exelon provide additional information and clarification justifying the newly derived leakage leakage values and existing surveillance methods. The attachment to this letter restates the NRCs NRC's questions followed by Exelon's Exelons response.
Exelon has concluded that the information provided in this response does not impact the conclusions of the: 1) Technical Evaluation, 2) No Significant Hazards Consideration under the standards set forth in 10 CFR 50.92(c), or 3) Environmental Consideration as provided in the original submittal (Reference 1).
There are no regulatory commitments contained in this submittal.
If you have any questions or require additional information, please contact Mr. Richard Gropp at (610) 765-5557.
II declare under penalty of perjury that the foregoing is true and correct. Executed on the 26th day of January 2011.
Respectfully, Respectfully, David P. Helker David Manager - Licensing Manager - Licensing Licensing and Regulatory Affairs Licensing Exelon Generation Exelon Generation Company, LLC
Attachment:
Response to Request for Additional Information - License Amendment Request Response -
Concerning Non-Conservative Technical Specification Associated with the Amount of Amount of Liquid Liquid Nitrogen Nitrogen Storage cc:
cc: Region I,I, Regional Administrator NRC Region NRC NRC Project NRC Manager, NRR - Peach Bottom Project Manager, -
NRC Senior NRC Senior Resident Inspector - Peach Bottom Resident Inspector -
T. Gray, S. T. Gray, S. State of Maryland Maryland R. R.
R. R. Janati, Janati, Bureau Bureau of Radiation Protection, Commonwealth of Pennsylvania
ATTACHMENT PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UNITS2AND3 NRC Docket Nos. 50-277 and 50-278 Renewed Facility Operating License Nos.
DPR-44 and DPR-56 Response to Request for Additional Information License Amendment Request Concerning Non-Conservative Technical Specification Associated with the Amount of Liquid Nitrogen Storage
Attachment Response to RAI Nitrogen Storage LAR for Liquid Nitrogen Storage Docket Nos.
Docket Nos. 50-277 50-277 andand 50-278 50-278 Page 11 of 4 Response to Resonse to Request Request for Additional Additional Information Information License Amendment Request License Request Concerning Concerning Non-Conservative Technical Srecification Non-Conservative Specification Associated with with thethe Amount Amount Liquid Nitrogen of Liquid Nitrogen Storage Storage
Background
By letter dated June 25, 2010, Exelon Generation Generation Company, LLC, LLC, (Exelon) submitted aa License (Exelon) submitted License Amendment Request (LAR) for the Peach Bottom Atomic Power Station (PBAPS), Units Station (PBAPS), Units 22 and and 3, requesting changes to the Technical Specifications (TS) to address non-conservative TS address non-conservative TS Surveillance Requirements (SR) associated with the amount of nitrogen available in nitrogen available the liquid in the liquid nitrogen storage tank. The proposed changes would revise TS SR 3.6.1.3, Primary SR 3.6.1.3, "Primary Containment Isolation Valves (PCIVs), "Reactor BuildThg-to-Suppression (PCI Vs)," and SR 3.6.1.5, Reactor Building-to-Suppression Chamber Vacuum Breakers, Breakers,"to to modify the required level for the liquid nitrogen storage tank.
nitrogen storage Specifically, the proposed changes would revise TS SR 3.6.1.3.1 and SR 3.6.1.5.1 3.6.1.5.1 to require the minimum amount of nitrogen inventory in the liquid nitrogen storage tank be maintained maintained at 2::
22 inches water column, or equivalent volume of> 124,000 standard cubic feet (scf),
of 2:: 124,000 (set), not not the currently stated level of;:::of 16 inches water column (equivalent volume of 2:: 50,000 scf).
set).
Exelon provided supplemental information in support of the proposed License Amendment Request (LAR) by letters dated August 16, 2010 and December 6, 2010.
Subsequently, by letter dated December 30, 2010, the NRC requested additional information in order to complete the review of the LAR. The NRC requested additional information and clarification related to justifying the newly derived leakage values and existing surveillance methods. The specific questions are restated below followed by Exelon's Exelons response.
NRC NRC Question (RAI-02)
Provide a suitable method and justification for determining determThing the required amount of nitrogen in the the storage storage tank that wouldwould account for leakage of the entire SG/G SGIG system while in Th post-LOCA line-up.
lhe-up.
Response
Response The The Safety Safety Grade Instrument Gas Grade Instrument Gas (SGIG) system provides a backup pneumatic source to the Containment Containment Atmospheric Control Control (CAC) purge and vent isolation valves, Reactor Building-to-Chamber vacuum Suppression Chamber Suppression breakers, and the Containment Atmospheric Dilution (CAD) vent vacuum breakers, control valves following control valves coincident with a loss of instrument air (non-safety related DBA-LOCA coincident following aa DBA-LOCA piping).
piping).
The SGIG The SGIG nitrogen supply is nitrogen supply is from the CAD from the nitrogen storage tank. A common supply liquid nitrogen CAD liquid header from the header from the tank is sent tank is to each sent to unit each unit aa to total of 18 end-user pneumatically operated valve of 18 stations per unit.
stations per The majority unit. The majority of of the the SGIG piping is SGIG piping normally filled with gaseous nitrogen from is normally the tank, the from the isolated from tank, isolated instrument air the instrument piping by air piping valve configuration.
check valve by aa check instrument configuration. The instrument piping isis non-safety air piping air with dual related with non-safety related safety-related check dual safety-related providing isolation between check valves providing safety-related SGIG the safety-related the SGIG and and non-safety non-safety related instrument air related instrument air systems. Instrument air nominal systems. Instrument
Attachment Response to RAI LAR for Liquid Nitrogen Storage Docket Nos. 50-277 and 50-278 Page 2 of 4 2of4 pressure is approximately 15 pressure maintains the delta pressure 15 psig greater than SGIG, and this delta the SGIG check valve closed, thus isolating the SGIG nitrogen piping piping from the instrument air piping.
instrument air piping.
Following a DBA-LOCA with loss of instrument air, the instrument air pressure would drop to would drop to less than SGIG pressure, allowing the SGIG check valve to open and distributing nitrogen to distributing nitrogen to the pneumatic stations. The instrument air system would be isolated by the dual SGIG check dual SGIG check valves closed with backpressure from the SGIG system.
The additional piping supplied by the SGIG system following a DBA-LOCA DBA-LOCA with loss loss of instrument air is minimal compared to the entire volume of the SGIG and CAD system system that is is normally filled with nitrogen. Approximately five (5) to ten (10) feet of small diameter instrument instrument piping at each pneumatic operating station will be supplied by SGIG nitrogen in this configuration.
The leak rate calculations to support the LAR submittal were determined during operation with the majority of the SGIG system filled with nitrogen, as well as the CAD system piping which takes a supply off the CAD liquid nitrogen storage tank. The calculation also considers the leakage from portions of SGIG system tubing, leakage at the end-user valve stations, boot seals, and valve stroking. There are multiple factors which provide a high degree of confidence that there is not significant leakage from the additional portion of piping supplied by SGIG during a post-LOCA scenario. Each refuel cycle, a Surveillance Test (ST) of the SGIG system is performed to stroke all of the SGIG valves with instrument air manually isolated by hand valves.
The end-user pneumatically operated valves are stroke-timed and the results are trended to ensure that no adverse trends occur in the ability to stroke the valves. Additionally, whenever the pneumatically operated valve stations are maintained, post-maintenance leak checks of the external piping are performed to ensure that there is no external piping leakage.
The periodic checks performed on the SGIG system piping in conjunction with the proportionally small volume placed in service post-LOCA provides a high degree of confidence that negligible additional nitrogen leakage would be incurred while in the post-LOCA line-up in comparison to the leakage values described in conjunction with this LAR submittal and supporting calculation.
In addition, the end-user pneumatically operated valves are included in the Peach Bottom In Inservice Testing (1ST) program and are tested at a periodicity specified by the 1ST program to lnservice ensure operability of the referenced valves. This test also includes SGIG / instrument air valve manipulations locally at each end-user SGIG supplied valve. These operations would detect manipulations significant leakage from the SGIG piping / valves that would be exposed to SGIG pressure any significant any post-LOCA operations. The results of the 1ST program valve testing is recorded and during post-LOCA during trended and any anomalies are identified and entered into the Correction Action Program (CAP) trended for further evaluation and resolution. The methodology presented in this LAR is suitable to determine the required inventory during normal operation and to accommodate the minor determine increase in increase in system piping during post-LOCA line-up.
system piping NRC Question (RAI-03)
NRC the system leakage represents such a significant amount of the required quantity of Since the Since the NRC nitrogen, the nitrogen, staff requests that the licensee either justify how the existing surveillance NRC staff (Le. tank requirement (i.e.
requirement tank level of 22 inches) will assure that future leakage rates will not increase to level of a point point where where 22 inches willwill no SGIG system for the 7-day period, or propose no longer sustain the SG/G new requirements that surveillance requirements new surveillance 50.36(c) that meet the requirements of 50. 36(c) (3).
Attachment Response to RAI LAR for Liquid Nitrogen Storage Docket Nos. 50-277 and 50-278 Page 3 of 4
Response
25% margin on top of the The margin contained in the original site calculation was selected as 25%
SGIG system required volume (Le., (i.e., approximately 10,000 scf margin for a required 40,000 scf SGIG system required volume). This was not based on extensive empirical data or any proposed system specific criteria. When the non-conservative TS value was originally identified, the new leakage values and administratively controlled level limit to support SGIG system operation were based on extensive empirical data. A past operability evaluation was performed that investigated system usage back to early 2000. An additional investigation was performed in 2010 during preparation of the LAR. Both investigations identified that CAD tank re-fill frequency and tank level changes have been consistent for the past ten (10) years. The current leakage trend is holding steady and the value represented in the LAR is determined to be bounding for this leakage. Furthermore, as previously discussed in response to the question above, the end-user pneumatically operated valves are included in the Peach Bottom lnservice Inservice Testing (1ST) program and are tested at a periodicity specified by the 1ST program to ensure operability of the referenced valves. This test also includes SGIG / instrument air valve manipulations locally at each end-user SGIG supplied valve. These operations would detect any significant leakage from the SGIG piping / valves that would be exposed to SGIG pressure during post-LOCA operations. The results of the 1ST program valve testing are recorded and trended and any anomalies are identified and entered into the Correction Action Program (CAP) for further evaluation and resolution.
Additionally, Peach Bottom has implemented recurring administrative controls to trend SGIG system leakage. Once each refueling cycle for each Peach Bottom unit, a recurring activity has been established for the System Manager to verify leakage using the methodology established in the subject LAR submittal. The leakage check recurring task requires extensive data assembly and calculation. CAD nitrogen liquid storage tank level and pressure data are recorded by Operations during performance of daily ST rounds and the data is uploaded into the plant database for review and evaluation. This data is used to calculate a SGIG system leak rate and compared to the limiting leakage value established in this LAR to ensure that the established value is still bounding.
SurIemental Information Supplemental In addition, Exelon is clarifying information previously provided in the December 6, 2010, 6,2010, response to a request for additional information. Specifically, an equation described in the December 6, 2010, response did not depict the gravitational constant (ge) (gc) value, which should have been referenced for completeness. Therefore, the equation previously depicted in the December 6, 2010, submittal has been modified below to include the (ge) (gc) value.
Solving for hhLL and including a conversion from inches of water column to psi for dP (Note:
3
):
3 Ibm/in density terms are in units of Ibm/in ):
Attachment Response to RAI LAR for Liquid Nitrogen Storage Docket Nos. 50-277 and 50-278 Page 44of of 4
(
IdP*[O.036 1 dP * (0.036. psi )_[-D(.i In.Oh*,.c.
in.ofw.c.
- (JL)D(PVl - PV3)J
() .
)
3 p,
h _
~YV o(
/
L-
- ((:JPI-P",)J
[[(PL Pvi ) -
- gc g - Gravitational Constant
=32.2 lbm*ft
= Ibts2 Ibm*ft / lbf*s 2
alter, change, Modifying the equation to include this value is simply a clarification and does not alter, or modify the methodology or results for the nitrogen storage tank level/volume correlations asas previously described in the December 6, 2010, supplemental response.
Conclusion The information discussed above verifies that the newly derived leakage values are sufficient to account for leakage of the entire SGIG system while in post-LOCA line-up and that the existing surveillance methods are adequate to ensure that the required amount of nitrogen (i.e.,
(Le.,
minimum of 22 inches water column) will be available to support SGIG system post-LOCA operations.}}