|
---|
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) 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) 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 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. 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. RS-14-001, Enclosure 1, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Updated Transmittal 1 (Annex a) for the Peach Bottom, Unit 3. Report No. RS-14-0012014-03-25025 March 2014 Enclosure 1, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Updated Transmittal #1 (Annex a) for the Peach Bottom, Unit 3. Report No. RS-14-001 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 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 2024-06-24
[Table view] Category:Legal-Affidavit
MONTHYEARML24121A1852024-04-25025 April 2024 Attachment 2: Curtiss-Wrights Affidavit Withholding Portions of Material Presented to the NRC on May 14, 2024 ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums ML22320A5592022-11-16016 November 2022 2022 Annual Report - Guarantees of Payment of Deferred Premiums ML22301A1742022-10-28028 October 2022 Global Nuclear Fuel Americas, LLC (GNF) - Part 21 60-Day Interim Report Notification: GNF3 Raised Water Rod (SC-22-04 Rt) ML22145A0852022-05-25025 May 2022 Response to Request for Additional Information - Proposed Relief Request Associated with Reactor Pressure Vessel N-16A Nozzle Repair ML22003A0022021-12-20020 December 2021 Proposed Relief Request Associated with Reactor Pressure Vessel N-16A Nozzle Repair ML21307A0542021-11-0202 November 2021 Annual Report - Guarantees of Payment of Deferred Premiums ML21272A2772021-09-29029 September 2021 Update to Application for Order Approving License Transfers and Proposed Conforming License Amendments ML21057A2732021-02-25025 February 2021 Application for Order Approving License Transfers and Proposed Conforming License Amendments NMP1L3371, Summary of Changes, Quality Assurance Topical Report, NO-AA-10 & Decommissioning Quality Assurance Program, NO-DC-102021-02-10010 February 2021 Summary of Changes, Quality Assurance Topical Report, NO-AA-10 & Decommissioning Quality Assurance Program, NO-DC-10 ML20329A3452020-11-24024 November 2020 Relief Request Associated with N-16A Reactor Pressure Vessel Instrument Nozzle Repairs - Submittal of Analyses ML20310A1152020-11-0404 November 2020 Annual Report - Guarantees of Payment of Deferred Premiums ML19318G1702019-11-14014 November 2019 2019 Annual Report - Guarantees of Payment of Deferred Premiums ML18316A0032018-11-0707 November 2018 Submittal of 2018 Annual Report - Guarantees of Payment of Deferred Premiums ML18205A3112018-07-24024 July 2018 Application for Subsequent Renewed Operating Licenses - Update Per 10 CFR 2.390 ML18150A3872018-05-30030 May 2018 License Amendment Request - Revised Technical Specifications to Allow Two Safety Relief Valves / Safety Values to Be Out-of-Service with Increased Reactor Pressure Safety Limit ML17243A0112017-08-30030 August 2017 Measurement Uncertainty Recapture License Amendment Request - Supplement 4 Response to Request for Additional Information ML16048A4412016-02-17017 February 2016 Transmittal of Extended Power Uprate: Results of Replacement Steam Dryer Power Ascension Testing ML16049A2582016-02-11011 February 2016 Transmittal of Exelon Nuclear Radiological Emergency Plan Revision ML16028A1712016-01-14014 January 2016 Transmittal of Exelon Nuclear Radiological Emergency Plan Revision ML15274A4672015-10-0101 October 2015 MELLLA License Amendment Request - Supplement 6 Response to Request for Additional Information ML15247A0882015-09-0404 September 2015 Attachment 2, EPU and Mellla+ Combined Rsd Masrs (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 ML15196A6372015-07-15015 July 2015 Error Identified in Letter from Exelon to NRC Re Predicted Strain Ratios Provided in Response to Request for Additional Information (RAI-11) ML15187A3912015-07-0606 July 2015 Supplement 4 - Response to Request for Additional Information on Mellla+ License Amendment Request, Attachments; 2, 3 and 4 ML15096A0082015-04-0505 April 2015 Extended Power Uprate: Response to Replacement Steam Dryer Requests for Additional Information ML14321A7052014-11-14014 November 2014 2014 Annual Report - Guarantees of Payment of Deferred Premiums ML14247A5032014-09-0404 September 2014 License Amendment Request - Maximum Extended Load Line Limit Analysis Plus ML14204A7092014-07-23023 July 2014 Enclosure 3, Affidavit of Peter M. Yandow RS-14-160, Co. - Submission of Standard Practice Procedure Plans and Foreign Ownership Control or Influence Package2014-07-0202 July 2014 Co. - Submission of Standard Practice Procedure Plans and Foreign Ownership Control or Influence Package ML14105A3842014-04-11011 April 2014 Extended Power Uprate License Amendment Request - Supplement 24 Response to Request for Additional Information ML14035A1582014-01-31031 January 2014 Extended Power Uprate License Amendment Request - Supplement 19 Response to Request for Additional Information ML13240A0022013-08-22022 August 2013 Extended Power Uprate License Amendment Request - Supplement 9 Response to Request for Additional Information 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 RS-12-227, Exelongeneration, Submission of Standard Practice Procedure Plans and Updated Foreign Ownership Control or Influence Package2012-12-19019 December 2012 Exelongeneration, Submission of Standard Practice Procedure Plans and Updated Foreign Ownership Control or Influence Package ML11325A3882011-11-18018 November 2011 Issuance of the Core Operating Limits Report for Reload 18, Cycle 19, Revision 7 ML1127000682011-09-26026 September 2011 Enclosure 3, Mfn 10-245 R4, Affidavit ML1031904262010-11-0808 November 2010 Corp. - 2010 Annual Report - Guarantees of Payment of Deferred Premiums ML1008301582010-03-23023 March 2010 Enclosure 2 to Mfn 10-124, Affidavit of James F. Harrison Response to NRC Request for Information Regarding Appeal of Denial of Request for Withholding Certain Information: Reference 1 Letter from J. Hughey (NRC) to J. Head (GEH) February 2 ML0520003282005-07-14014 July 2005 Surveillance Program for Channel-Control Blade Interference ML0508101932005-03-18018 March 2005 Renewed Facility Operating License No. DPR-56, Incorporation of Lead Use Assemblies 2024-04-25
[Table view] |
Text
ATTACHMENT 3 GNF Response to RAI 44 - Non-Proprietary Version and Affidavit GNF Letter CFL-EXN-HE0-13-036 R1
ENCLOSURE 2 CFL-EXN-HE0-13-036 R1 Revised GNF Response to NRC RAI 44 for License Amendment Request for Use of Neutron Absorbing Spent Fuel Pool Rack Inserts for Peach Bottom Atomic Power Station Units 2 and 3 Non-Proprietary Information- Class I (Public)
INFORMATION NOTICE This is a non-proprietary version of CFL-EXN-HE0-13-036 R1 Enclosure 1, which has the proprietary information removed. Portions of the document that have been removed are indicated by white space inside an open and closed bracket as shown here [[ ]].
CFL-EXN-HE0-13-036 R 1 Non-Proprietary Information Class I (Public) Page 1 of 5
RAI-44
PBAPS has proposed a two tier approach for crediting degraded Boraf1ex until the NETCO-SNAP-INJ{) rack inserts are installed. The second tier, i.e., the 'Restricted' tier, credits Boraflex with more than 50o/o degradation. To account for the potential relocation of Boraflex during a seistnic event, PBAPS has proposed an additional bumup requirement past the point of peak reactivity for the 'Restricted' tier. The NRC staff requires additional information regarding the 'Restricted' tier. Please provide the following information:
a) Provide the keff of the Restricted storage cells both with and without the additional bumup requirement and with the Boraflex being credited.
b) Provide the keff of the Restricted storage cells both with and without the additional bumup requirement but without the Boraflex being credited.
c) Provide a description of the Monte Carlo models that are being used to provide those estimations of ketf* The description can be in reference to the model that was used for the
'Unrestricted' tier.
GNF RESPONSE TO RAI-44:
I terns a. and b.
The responses to RAI-44.a and RAI-44.b are provided in Table 44-1 and Table 44-2. Table 44-1 provides the nominal, in-rack reactivities for the system with and without credit for bumup past the point of peak reactivity and Boraflex. Table 44-2 provides the same information but includes biases, tolerances, and uncertainties, as appropriate, from NED0-33686 (Reference 44-1 ).
Note that the "Without Boraflex, Without Bumup" numbers are for illustrative purposes only, as Tier-2 cells are restricted from storage of bundles without bumup being credited.
Table 44-1-Nominal System Reactivities (Keft)
Nominal In-Rack Keff With Boraflex Without Boraflex With Burnup [[
Without Bumup ]]
Table 44 System Reactivities Including Biases, Tolerances, and Uncertainties (KMax)
Max In-Rack Keff With Boraflex Without Boraflex With Bumup [[
Without Bumup ]]
The application of the NED0-33686 adders to the nominal values in Table 44-1 was done in two ways. For the "With Boraflex" cases, the final bias, tolerance, and uncertainty values were taken directly from Table 14 of NED0-33686 and applied without modification. For the "Without Boraflex" cases, the same source of information was used to assess total bias, tolerance and
CFL-EXN-HE0-13-036 Rl Non-Proprietary Information Class I (Public) Page 2 of5 uncertainty adders, but the following Borat1ex related terms were removed as they are not
.
appropriate for application in the cases where Boraflex is not credited:
[[
]]
When assessing the appropriateness of the remaining bias, tolerance, and uncertainty terms for application to these cases, justification is most clearly provided by discussing the impact of the changes to the system being modeled on each category of adders, as is done in the following sections.
[[
CFL-EXN-HE0-13-036 Rl Non-Proprietary Information Class I (Public) Page 3 of5
]]
Item c.
In response to RAI-44.c, it is noted that the Monte Carlo models utilized to calculate these numbers were identical to those described in Sections 4.2 and 5.2 of NED0-33686, with the following exceptions:
Monte Carlo Storage Rack Models With Borat1ex:
Borat1ex panels are modeled with thinning beyond that described in Section 5.2 to represent a uniform B-10 areal density of 0.01113 B-10/cm2
- This is consistent with the description provided in Appendix C ofNED0-33686.
Without Borat1ex:
All Borat1ex materials are modeled as water.
Monte Carlo Bundle Models With Bumup:
The analysis used to credit bumup for this BWR analysis can be divided into two steps which contain elements which are distinct from those described in NED0-33686. The first step involves the selection of a limiting bundle, and the second involves the modeling of that bundle in the rack system.
CFL-EXN-HE0-13-036 Rl Non-Proprietary Information Class I (Public) Page 4 of5 a Limiting Bundle The limiting bundle to model in the rack system is selected by performing the following steps:
[[
]]
Modeling the Bundle in the Storage System The same limiting bundle is assumed to exist in every allowable storage location, consistent with the methodology outlined in NED0-33686. As opposed to the single peak reactivity lattice assumption, however, the bundle in the bumup credit analysis is [[
]]
CFL-EXN-HE0-13-036 Rl Non-Proprietary Information Class I (Public) Page 5 of5 The bundles are modeled with one axial zone representing the entire fuel assembly consistent with the bundle modeling assumptions described in Section 4.2 of NEDO 33686. The lattice selected to represent this axial zone has an in-core reactivity of 1.2170, as described in Appendix C of the same report.
REFERENCE:
44-1. Global Nuclear Fuel, "Peach Bottom Atomic Power Station: Fuel Storage Criticality Safety Analysis of Spent Fuel Storage Racks with Boraflex," NED0-33686, Revision 1, June 2012.
ENCLOSURE 3 CFL-EXN-HE0-13-036 R1 Affidavit
Global Nuclear Fuel- Americas AFFIDAVIT I, Atul A. Karve, state as follows:
(1) I am Engineering Manager, Methods, Global Nuclear Fuel- Americas, LLC (GNF-A), and have been delegated the function of reviewing the information described in paragraph (2) which is sought to be withheld, and have been authorized to apply for its withholding.
(2) The information sought to be withheld is contained in Enclosure 1 of GNF's letter, CFL-EXN-HE0-13-036 R1, C. Lamb (GNF-A) to T. Loomis (Exelon Nuclear), entitled "Revised GNF Response to NRC RAI 44 for the License Amendment Request for Use of Neutron Absorbing Spent Fuel Pool Rack Inserts for Peach Bottom Atomic Power Station Units 2 and 3," dated April 16,2013. GNF-A proprietary information in Enclosure 1, which is entitled Revised GNF Response to NRC RAI 44 for License Amendment Request for Use of Neutron Absorbing Spent Fuel Pool Rack Inserts for Peach Bottom Atomic Power Station Units 2 and 3," is identified by a dotted underline inside double square brackets. [[Ihi.~--~~nt~_IJ.~~j_~JHL~~~~TIP.l~---~:~!.]] In all cases, the superscript notation {3 } refers to Paragraph (3) of this affidavit, which provides the basis for the proprietary determination.
(3) In making this application for withholding of proprietary information of which it is the owner or licensee, GNF-A relies upon the exemption from disclosure set forth in the Freedom of Information Act ("FOIA"), 5 USC Sec. 552(b)( 4), and the Trade Secrets Act, 18 USC Sec. 1905, and NRC regulations 10 CFR 9.17(a)(4), and 2.390(a)(4) for "trade secrets" (Exemption 4). The material for which exemption from disclosure is here sought also qualify under the narrower definition of "trade secret", within the meanings assigned to those terms for purposes of FOIA Exemption 4 in, respectively, Critical Mass Energy Project v. Nuclear Regulatory Commission, 975 F2d 871 (DC Cir. 1992), and Public Citizen Health Research Group v. FDA, 704 F2d 1280 (DC Cir. 1983).
(4) Some examples of categories of information which fit into the definition of proprietary information are:
- a. Information that discloses a process, method, or apparatus, including supporting data and analyses, where prevention of its use by GNF-A's competitors without license from GNF -A constitutes a competitive economic advantage over other companies;
- b. Information which, if used by a competitor, would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing of a similar product;
- c. Information which reveals aspects of past, present, or future GNF-A customer-funded development plans and programs, resulting in potential products to GNF-A;
- d. Information which discloses patentable subject matter for which it may be desirable to obtain patent protection.
The information sought to be withheld is considered to be proprietary for the reasons set forth in paragraphs (4)a. and (4) b. above.
CFL-EXN-HE0-13-036 Rl Enclosure 1 Affidavit Page 1 of 3
(5) To address 10 CFR 2.390 (b) (4), the information sought to be withheld is being submitted to NRC in confidence. The information is of a sort customarily held in confidence by GNF-A, and is in fact so held. The information sought to be withheld has, to the best of my knowledge and belief, consistently been held in confidence by GNF-A, no public disclosure has been made, and it is not available in public sources. All disclosures to third parties including any required transmittals to NRC, have been made, or must be made, pursuant to regulatory provisions or proprietary agreements which provide for maintenance of the information in confidence. Its initial designation as proprietary information, and the subsequent steps taken to prevent its unauthorized disclosure, are as set forth in paragraphs (6) and (7) following.
(6) Initial approval of proprietary treatment of a document is made by the manager of the originating component, the person most likely to be acquainted with the value and sensitivity of the information in relation to industry knowledge, or subject to the terms under which it was licensed to GNF-A. Access to such documents within GNF-A is limited on a "need to know" basis.
(7) The procedure for approval of external release of such a document typically requires review by the staff manager, project manager, principal scientist or other equivalent authority, by the manager of the cognizant marketing function (or his delegate), and by the Legal Operation, for technical content, competitive effect, and determination of the accuracy of the proprietary designation. Disclosures outside GNF-A are limited to regulatory bodies, customers, and potential customers, and their agents, suppliers, and licensees, and others with a legitimate need for the information, and then only in accordance with appropriate regulatory provisions or proprietary agreements.
(8) The information identified in paragraph (2), above, is classified as proprietary because it contains details of the nuclear fuel criticality licensing methodology for the GEH Boiling Water Reactor (BWR). Development of these methods, techniques, and information and their application for the design, modification, and analyses methodologies and processes was achieved at a significant cost GNF-A.
The development of the evaluation processes along with the interpretation and application of the analytical results is derived from the extensive experience database that constitutes a major GNF-A asset.
(9) Public disclosure of the information sought to be withheld is likely to cause substantial harm to GNF-A's competitive position and foreclose or reduce the availability of profit-making opportunities. The information is part of GNF-A's comprehensive BWR safety and technology base, and its commercial value extends beyond the original development cost.
The value of the technology base goes beyond the extensive physical database and analytical methodology and includes development of the expertise to determine and apply the appropriate evaluation process. In addition, the technology base includes the value derived from providing analyses done with NRC-approved methods.
The research, development, engineering, analytical, and NRC review costs compnse a substantial investment of time and money by GNF -A.
CFL-EXN-HE0-13-036 Rl Enclosure 1 Affidavit Page 2 of 3
The precise value of the to devise an evaluation process and apply the correct analytical methodology is difficult to quantify, but it clearly is substantial.
GNF-A's competitive advantage will be lost if its competitors are able to use the results of the GNF-A experience to normalize or verify their own process or if they are able to claim an equivalent understanding by demonstrating that they can arrive at the same or similar conclusions.
The value of this information to GNF-A would be lost if the information were disclosed to the public. Making such information available to competitors without their having been required to undertake a similar expenditure of resources would unfairly provide competitors with a windfall, and deprive GNF-A of the opportunity to exercise its competitive advantage to an adequate return on its large investment in developing and obtaining these very valuable analytical tools.
I declare under penalty of perjury that the foregoing affidavit and the matters stated therein are true and correct to the best of my knowledge, information, and belief.
Executed on this 16th day of April 2013.
Atul A. Karve Engineering Manager, Methods Global Nuclear Fuel- Americas, LLC CFL-EXN-HE0-13-036 R1 Enclosure 1 Affidavit Page 3 of 3
ATTACHMENT 4 Updated Markup of Technical Specification Page 4.0-2 (Units 2 and 3)
Design Features 4.0 4.0 DESIGN FEATURES (continued) 4.3 Fuel Storage 4.3.1 Cr1t1calitY 4.3.1.1 The spent fuel storage racks are designed and shall be maintained with:
- a. Fuel assemblies having a maximum k-inf1nity of
~ 1.383 in the normal reactor core configuration at cold conditions;
- b. k,f1 s 0.95 if fully flooded with unborated water,
- d. rhe installed neutron wn1ch includes an allowance for uncertaJ.n._~ as absorbing rac.:k inserts having a described in Section 10.3 of the UFSAR;~
Boron-1 0 areal density 0. 0 l 02 A nominal 6.280 inch center to center distance between fuel assemblies placed in the storage rackf) ( I ; and I 4.3.1.2 The new fuel storage racks shall not be used for fuel storage. The new fuel shall be stored in the spent fuel storage racks.
() 4.3.2 Drainage The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below plant elevation 219 ft.
4.3.3 Caoac1tv The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 3819 fuel assemblies.
- )
PBAPS UNIT 2 4.0-2 Amendment No. 210
Design Features 4.0
( 4.0 DESIGN FEATURES (continued) 4.3 Fuel Storage 4.3.1 Cr1t1cal1tv 4.3.1.1 The spent fuel storage racks are designed and shall be maintained wtth:
~*, Fuel assemblies having a maximum k-infinity of
~ 1.362 in the normal reactor core configuration at cold conditions;
- b. k, 11 ~ 0.95 if fully flooded with unborated water, wn1ch includes an allowance for uncert~ as
- d. rhe installed neutron described in Section 10.3 of the UFSAR~
absorbing rack inserts having a Boron- I0 areal density 2: 0.0 l 02 A no*inal 6.280 inch center to center distance betw~ fuel assemblies placed in the storage g/cml.
rack~( I; and I 4.3.1.2 The new fuel storage racks shall not be used for fuel storage. The new fuel shall be stored in the spent fuel storage racks.
( 4.3.2 Drainage The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below plant elevation 219 ft.
4.3.3 Capacjtv The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 3819 fuel assemblies.
PBAPS UNIT 3 4.0-2 Amendment No. 214