Letter Sequence Other |
---|
|
|
MONTHYEARML15040A7202015-03-12012 March 2015 Request for Withholding Information from Public Disclosure for Peach Bottom Atomic Power Station, Unit No. 2 Project stage: Withholding Request Acceptance ML15083A5592015-03-24024 March 2015 Extended Power Uprate: Response to Replacement Steam Dryer Requests for Additional Information Project stage: Other ML15033A4892015-03-27027 March 2015 NRC Staff Review of Replacement Steam Dryer Re-Benchmarking to Support Extended Power Uprate Power Ascension Project stage: Approval ML15086A3332015-03-27027 March 2015 Request for Additional Information Regarding Replacement Steam Dryer Analysis, Exelon Generation Company, Llc. Peach Bottom Atomic Power Station - Unit 2 Project stage: RAI ML15096A0082015-04-0505 April 2015 Extended Power Uprate: Response to Replacement Steam Dryer Requests for Additional Information Project stage: Other ML15084A3422015-04-0606 April 2015 Request for Withholding Information from Public Disclosure for Peach Bottom Atomic Power Station, Unit No. 2 Project stage: Withholding Request Acceptance ML15099A7482015-04-0909 April 2015 Power Ascension Hold at 104% of 3514 Mwt Project stage: Other ML15110A0982015-04-10010 April 2015 E-Mail Peach Bottom Unit 2 - Power Ascension Hold at 104% of 3514 Mwt Project stage: Other ML15091A1342015-04-16016 April 2015 Summary of Closed Meeting Held on March 26, 2015, with Exelon Generation Company, LLC to Discuss Steam Dryer Analysis for Peach Bottom Atomic Power Station, Unit No. 2 Project stage: Meeting ML15125A1682015-04-25025 April 2015 Power Ascension - 108% Hold Point Decision Project stage: Other ML15127A5182015-05-0505 May 2015 Draft Request for Additional Information (Tac No. MF4792) Project stage: Draft RAI ML15127A5262015-05-0505 May 2015 Draft Request for Additional Information (Attachment 2) Project stage: Draft RAI ML15110A0852015-05-12012 May 2015 Request for Withholding Information from Public Disclosure for Peach Bottom Atomic Power Station, Unit No. 2 Project stage: Withholding Request Acceptance ML15135A4372015-05-15015 May 2015 Approval of Steam Dryer Methodology and Resumption of EPU Power Ascension Project stage: Other ML15135A4022015-05-15015 May 2015 Extended Power Uprate: Response to Replacement Steam Dryer Request for Additional Information Project stage: Request ML15127A2082015-05-19019 May 2015 Approval of Revision to Methodology for Establishing Replacement Steam Dryer Strain Limits Project stage: Other 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) Project stage: Response to RAI 2015-04-05
[Table View] |
|
---|
Category:Legal-Affidavit
MONTHYEARML23317A1192023-11-10010 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 2023-11-10
[Table view] 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
[Table view] |
Text
PROPRIETARY INFORMATION - WITHHOLD UNDER 10 CFR 2.390 10 CFR 50.4 10 CFR 2.390 April 5, 2015 U.S. Nuclear Regulatory Commission ATTN: 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
Subject:
Extended Power Uprate: Response to Replacement Steam Dryer Requests for Additional Information
Reference:
- 1. NRC Letter to Exelon, Peach Bottom Atomic Power Station, Units 2 and 3 - Issuance of Amendments Re: Extended Power Uprate (TAC Nos.
ME9631 and ME9632), dated August 25, 2014 (ADAMS Accession No. ML14133A046)
- 2. Exelon letter to the NRC, Extended Power Uprate: Request for NRC Approval of Revision to Methodology for Establishing Replacement Steam Dryer Strain Limits, dated February 3, 2015 (ADAMS Accession No. ML15034A573)
- 3. Exelon letter to the NRC, Extended Power Uprate: Response to Replacement Steam Dryer Requests for Additional Information, dated March 24, 2015 (ADAMS Accession No. ML15083A559)
- 4. NRC Letter to Exelon, NRC Staff Review of Request for Approval of Revision to Methodology for Establishing Replacement Steam Dryer Strain Limits (TAC NO. MF4792), dated March 27, 2015 (ADAMS Accession No. ML15033A489).
In accordance with 10 CFR 50.92, the NRC issued Reference 1, License Amendment Nos.
293 and 296 to the Peach Bottom Atomic Power Station (PBAPS) Renewed Facility Operating Licenses (FOLs) to increase the authorized maximum power level from 3514 megawatts thermal (MWt) to 3951 MWt. This change to power level is considered an extended power uprate (EPU).
The amended FOLs contain specific license conditions that control the monitoring, evaluating, and taking prompt action in response to potential adverse flow effects as a result of the EPU on plant structures, systems, and components (including verifying the Attachment 1 contains Proprietary Information.
When separated from Attachment 1, this document is decontrolled.
U.S. Nuclear Regulatory Commission Response to Replacement Steam Dryer RAI April5,2015 Page2 continued structural integrity of the replacement steam dryer (RSD)) during initial EPU power ascension.
As described in Exelon Generation Company, LLC (EGC) letter dated February 3, 2015 (Reference 2), data collected at near the previously licensed thermal power level identified low frequency loads on the RSD that were not previously predicted. The NRC staff reviewed the information regarding the revised methodology and provided a request for additional information (RAI). The EGC response to that request was submitted on March 24, 2015 (Reference 3). The NRC determined the response provided reasonable assurance of RSD structural integrity and approved power ascension up to 104% of 3514 MWt (Reference 4). The NRC Staff also requested additional information to support further review of the RSD methodology. This letter provides the response to that RAI.
Westinghouse Electric Company (WEC) considers portions of the information provided in the Attachment 1 response proprietary and, therefore, exempt from public disclosure pursuant to 10 CFR 2.390. In accordance with 10 CFR 2.390 and in support of this request for withholding, an affidavit executed by WEC is provided in Attachment 3.
There are no regulatory commitments contained in this letter.
Should you have any questions concerning this letter, please contact Mr. Ken Ainger at (630) 657-3330.
Respectfully, David P. Helker Manager, Licensing and Regulatory Affairs Exelon Generation Company, LLC Attachments:
- 1. Response to Request for Additional Information - Proprietary, Westinghouse Electric Company LLC LTR-BWR-ENG-15-032-P
- 2. Response to Request for Additional Information - Non-Proprietary, Westinghouse Electric Company LLC LTR-BWR-ENG-15-032-NP
- 3. Affidavit cc: USNRC Region I, Regional Administrator w/attachments USNRC Senior Resident Inspector, PBAPS w/attachments USNRC Project Manager, PBAPS w/attachments R. R. Janati, Commonwealth of Pennsylvania w/o proprietary attachment S. T. Gray, State of Maryland w/o proprietary attachment
Attachment 2 Peach Bottom Atomic Power Station Unit 2 NRC Docket No. 50-277 Response to Request for Additional Information - Non-Proprietary Westinghouse Electric Company LLC LTR-BWR-ENG-15-032-NP The Nuclear Regulatory Commission (NRC) issued Amendment Nos. 293 and 296 to Renewed Facility Operating License Nos. DPR-44 and DPR-56 for Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3 (ADAMS Accession No. ML14133A046).
These amendments authorized an increase in the maximum licensed thermal power level for PBAPS, Units 2 and 3, from 3514 megawatts thermal (MWt) to 3951 MWt, which is an increase of approximately 12.4 percent.
In accordance with PBAPS Unit 2 License Condition 2.C(15)(d)3, EGC requested NRC approval for a revision to the methodology for establishing the RSD strain limits and provided additional information in letters dated February 3, 2015 (ADAMS Accession No. ML15034A573) and March 24, 2015 (ADAMS Accession No. ML15083A559). The NRC staff has reviewed that information, approved further power ascension, and requested additional information on March 27, 2015. The response to that request is provided in this attachment.
Westinghouse Non-Proprietary Class 3 LTR-BWR-ENG-15-032-NP Response to the U.S. NRC Requests for Additional Information Relative to the Peach Bottom Replacement Steam Dryer Acoustic/Structural Analyses Set April 5, 2015 Westinghouse Electric Company LLC 1000 Westinghouse Drive Cranberry Township, PA 16066 USA
© 2015 Westinghouse Electric Company LLC All Rights Reserved
Westinghouse Non-Proprietary Class 3 LTR-BWR-ENG-15-032-NP
RAI-10
Acceptance criteria for non-main steam line (MSL) acoustic methodology The following comments and RAIs address the remaining unresolved issues associated with the licensees proposed non-MSL acoustic methodology. Satisfactory response to these comments and RAIs will provide reasonable assurance of the methodology conservatism and support a decision to allow power ascension to proceed.
Observations on the information submitted so far:
Using (( )) to infer the alternating stress state in a steam dryer is, in principle, acceptable.
Statistical studies of the peak measured strains on the dryer hood and skirt by the licensee appear to show that ((
)) with guidelines in NUREG 0484. The licensee indicated that cumulative distribution function (CDF) curves were developed, ((
))
To further validate the licensees findings from its analysis, the NRC staff requests that the CDF curves for SG4 and SG20 be provided for review.
The ((
)) does not have a sound technical basis. Therefore, this raises concerns regarding the stress analysis of the PBAPS Unit 2 steam dryer. All ((
)) do not seem to be included in the current analysis, raising the concern that the
(( )) may not be an appropriate upper bound. Also, the ((
)) These problems with the approach used to date lead to
((
)) adding further uncertainty to the accuracy of the current calculations.
The general methodology as submitted by the licensee is reasonable, but the ((
)) must be complete and representative of low frequency (less than 50 Hz) strains and stresses in all major dryer components (outer hoods, inner and middle hoods, and skirt), and the approach used to determine the (( )) in the analysis must be revised as follows:
a) Due to possible inaccuracies in the ((
)) a frequency shift of at least +/-10% must be considered to ensure that all (( )) are included in the analyses.
b) (( )) used in the analysis should be submitted, and demonstrated to be reasonable for use on the outer hood, middle/inner hood, and skirt, regardless of whether the (( ))
1
Westinghouse Non-Proprietary Class 3 LTR-BWR-ENG-15-032-NP c) The (( )) should be based on attempting to match as closely as possible ((
))1 d) The simulated (( )) should bound the measured ones.
e) Simulated (( )) should be reasonably consistent with those measured.
f) The (( )) must be used to estimate the top 5 maximum stresses and their locations on the upper and lower dryer.
In addition, the following information is requested, prior to the meeting on March 26, 2015:
g) For each of the (( )) please provide ((
)) at each of the strain gage locations on the hood.
h) Please confirm whether the outer hood, middle hood and inner hood are dynamically coupled.
1
((
))
2
Westinghouse Non-Proprietary Class 3 LTR-BWR-ENG-15-032-NP
Response
RAI-10a)
In the original non-main steam line acoustic (NMSLA) stress calculation (RAI 1a describes the method, and RAI-1d provides the results), [
]a,c The [
]a,c The results are provided in Table RAI-10a-1.
Table RAI-10a-2 [
]a,c All results [ ]a,c Table RAI-10a-1: Maximum NMSLA Stress, Upper Dryer a,c Table RAI-10a-2: Maximum NMSLA Stress, Lower Dryer a,c 3
Westinghouse Non-Proprietary Class 3 LTR-BWR-ENG-15-032-NP RAI-10b)
[
]a,c As discussed [
]a,c Additionally,
[
]a,c As part of the evaluation [
]a,c A comparison of [
]a,c For the hoods, [
]a,c The results [
]a,c Thus the [
]a,c In addition, [
]a,c As shown [
]a,c Based on the above, [
]a,c 4
Westinghouse Non-Proprietary Class 3 LTR-BWR-ENG-15-032-NP RAI-10c)
RAI-10c), RAI-10d), RAI-10e), RAI-10f)
RAI-10, parts c through f [
]a,c 5
Westinghouse Non-Proprietary Class 3 LTR-BWR-ENG-15-032-NP a,c Figure RAI-10c-1: [ ]a,c 6
Westinghouse Non-Proprietary Class 3 LTR-BWR-ENG-15-032-NP a,c Figure RAI-10c-2: [ ]a,c
[
]a,c 7
Westinghouse Non-Proprietary Class 3 LTR-BWR-ENG-15-032-NP a,c Figure RAI-10c-3: [ ]a,c a,c Figure RAI-10c-4: [ ]a,c 8
Westinghouse Non-Proprietary Class 3 LTR-BWR-ENG-15-032-NP
[
]a,c Table RAI-10c-1: [ ]a,c a,c Table RAI-10c-2 [
]a,c 9
Westinghouse Non-Proprietary Class 3 LTR-BWR-ENG-15-032-NP Table RAI-10c-2: [ ]a,c a,c
[
]a,c 10
Westinghouse Non-Proprietary Class 3 LTR-BWR-ENG-15-032-NP Table RAI-10c-3: [ ]a,c a,c
[
]a,c Additional NRC request:
[
]a,c 11
Westinghouse Non-Proprietary Class 3 LTR-BWR-ENG-15-032-NP a,c Figure RAI-10c-5: [ ]a,c a,c Figure RAI-10c-6: [ ]a,c 12
Westinghouse Non-Proprietary Class 3 LTR-BWR-ENG-15-032-NP RAI-10g)
[
]a,c Tables RAI-10g-1 through RAI-10g-3 [
]a,c Table RAI-10g-1: Peach Bottom Unit 2 Replacement Steam Dryer Modal Displacements a,c 13
Westinghouse Non-Proprietary Class 3 LTR-BWR-ENG-15-032-NP a,c 14
Westinghouse Non-Proprietary Class 3 LTR-BWR-ENG-15-032-NP a,c 15
Westinghouse Non-Proprietary Class 3 LTR-BWR-ENG-15-032-NP a,c 16
Westinghouse Non-Proprietary Class 3 LTR-BWR-ENG-15-032-NP Table RAI-10g-2: Peach Bottom Unit 2 Replacement Steam Dryer Modal Strains at Top Surface a,c 17
Westinghouse Non-Proprietary Class 3 LTR-BWR-ENG-15-032-NP a,c 18
Westinghouse Non-Proprietary Class 3 LTR-BWR-ENG-15-032-NP a,c 19
Westinghouse Non-Proprietary Class 3 LTR-BWR-ENG-15-032-NP a,c 20
Westinghouse Non-Proprietary Class 3 LTR-BWR-ENG-15-032-NP Table RAI-10g-3: Peach Bottom Unit 2 Replacement Steam Dryer Modal Strains at Bottom Surface a,c 21
Westinghouse Non-Proprietary Class 3 LTR-BWR-ENG-15-032-NP a,c 22
Westinghouse Non-Proprietary Class 3 LTR-BWR-ENG-15-032-NP a,c 23
Westinghouse Non-Proprietary Class 3 LTR-BWR-ENG-15-032-NP a,c 24
Westinghouse Non-Proprietary Class 3 LTR-BWR-ENG-15-032-NP RAI-10h)
[
]a,c 25
Attachment 3 Peach Bottom Atomic Power Station Unit 2 NRC Docket No. 50-277 AFFIDAVIT Note contains proprietary information as defined by 10 CFR 2.390.
WEC, as the owner of the proprietary information, has executed the enclosed affidavit, which identifies that the proprietary information has been handled and classified as proprietary, is customarily held in confidence, and has been withheld from public disclosure. The proprietary information has been faithfully reproduced in the attachment such that the affidavit remains applicable.
inghouse Westinghouse Electric Company Engineering, Equipment and Major Projects 1000 Westinghouse Drive, Building 3 Cranberry Township, Pennsylvania 16066 USA U.S. Nuclear Regulatory Commission Direct tel: (412) 374-4643 Document Control Desk Direct fax: (724) 940-8560 11555 Rockville Pike e-mail: greshaja@westinghouse.com Rockville, MD 20852 Proj. ltr: WEC-PCH-RSD-15-061 CAW-15-4155 April 2, 2015 APPLICATION FOR WITHHOLDING PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE
Subject:
LTR-BWR-ENG-15-032-P, "Response to the U.S. NRC Requests for Information Relative to the Peach Bottom Replacement Stearn Dryer Acoustic/Structural Analyses Set" The proprietary information for which withholding is being requested in the above-referenced report is further identified in Affidavit CAW-15-4155 signed by the owner of the proprietary information, Westinghouse Electric Company LLC. The Affidavit, which accompanies this letter, sets forth the basis on which the information may be withheld from public disclosure by the Commission and addresses with specificity the considerations listed in paragraph (b)(4) of 10 CFR Section 2.390 of the Commission's regulations.
- Accordingly, this letter authorizes the utilization of the accompanying Affidavit by Exelon Generation.
Correspondence with respect to the proprietary aspects of the Application for Withholding or the Westinghouse Affidavit should reference CAW-15-4155, and should be addressed to James A. Gresham, Manager, Regulatory Compliance, Westinghouse Electric Company, 1000 Westinghouse Drive, Building 3 Suite 310, Cranberry Township, Pennsylvania 16066.
Very truly yours, i~ger Regulatory Compliance Enclosures
CAW-15-4155 April 2, 2015 AFFIDAVIT COMMONWEALTH OF PENNSYLVANIA:
SS COUNTY OF BUTLER:
I, James A Gresham, am authorized to execute this Affidavit on behalf of Westinghouse Electric Company LLC (Westinghouse), and that the averments of fact set forth in this Affidavit are true and correct to the best of my knowledge, information, and belief.
4:mes A Gresham, Manager Regulatory Compliance
2 CAW-15-4155 (1) I am Manager, Regulatory Compliance, Westinghouse Electric Company LLC (Westinghouse),
and as such, I have been specifically delegated the function of reviewing the proprietary information sought to be withheld from public disclosure in connection with nuclear power plant licensing and rule making proceedings, and am authorized to apply for its withholding on behalf of Westinghouse.
(2) I am making this Affidavit in conformance with the provisions of 10 CFR Section 2.390 of the Commission's regulations and in conjunction with the Westinghouse Application for Withholding Proprietary Information from Public Disclosure accompanying this Affidavit.
(3) I have personal knowledge of the criteria and procedures utilized by Westinghouse in designating information as a trade secret, privileged or as confidential commercial or financial information.
(4) Pursuant to the provisions of paragraph (b)(4) of Section 2.390 of the Commission's regulations, the following is furnished for consideration by the Commission in determining whether the information sought to be withheld from public disclosure should be withheld.
(i) The information sought to be withheld from public disclosure is owned and has been held in confidence by Westinghouse.
(ii) The information is of a type customarily held in confidence by Westinghouse and not customarily disclosed to the public. Westinghouse has a rational basis for determining the types of information customarily held in confidence by it and, in that connection, utilizes a system to determine when and whether to hold certain types of information in confidence. The application of that system and the substance of that system constitute Westinghouse policy and provide the rational basis required.
Under that system, information is held in confidence if it falls in one or more of several types, the release of which might result in the loss of an existing or potential competitive advantage, as follows:
(a) The information reveals the distinguishing aspects of a process (or component, structure, tool, method, etc.) where prevention of its use by any of Westinghouse's competitors without license from Westinghouse constitutes a competitive economic advantage over other companies.
3 CAW-15-4155 (b) It consists of supporting data, including test data, relative to a process (or component, structure, tool, method, etc.), the application of which data secures a competitive economic advantage, e.g., by optimization or improved marketability.
(c) Its use 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 a similar product.
(d) It reveals cost or price information, production capacities, budget levels, or commercial strategies of Westinghouse, its customers or suppliers.
(e) It reveals aspects of past, present, or future Westinghouse or customer funded development plans and programs of potential commercial value to Westinghouse.
(f) It contains patentable ideas, for which patent protection may be desirable.
(iii) There are sound policy reasons behind the Westinghouse system which include the following:
(a) The use of such information by Westinghouse gives Westinghouse a competitive advantage over its competitors. It is, therefore, withheld from disclosure to protect the Westinghouse competitive position.
(b) It is information that is marketable in many ways. The extent to which such information is available to competitors diminishes the Westinghouse ability to sell products and services involving the use of the information.
(c) Use by our competitor would put Westinghouse at a competitive disadvantage by reducing his expenditure of resources at our expense.
(d) Each component of proprietary information pertinent to a particular competitive advantage is potentially as valuable as the total competitive advantage. If competitors acquire components of proprietary information, any one component
4 CAW-15-4155 may be the key to the entire puzzle, thereby depriving Westinghouse of a competitive advantage.
(e) Unrestricted disclosure would jeopardize the position of prominence of Westinghouse in the world market, and thereby give a market advantage to the competition of those countries.
(f) The Westinghouse capacity to invest corporate assets in research and development depends upon the success in obtaining and maintaining a competitive advantage.
(iv) The information is being transmitted to the Commission in confidence and, under the provisions of 10 CFR Section 2.390; it is to be received in confidence by the Commission.
(v) The information sought to be protected is not available in public sources or available information has not been previously employed in the same original manner or method to the best of our knowledge and belief.
(vi) Th~ proprietary information sought to be withheld in this submittal is that which is appropriately marked in LTR-BWR-ENG-15-032-P, "Response to the U.S. NRC Requests for Information Relative to the Peach Bottom Replacement Steam Dryer Acoustic/Structural Analyses Set" for submittal to the Commission, being transmitted by Exelon Generation letter and Application for Withholding Proprietary Information from Public Disclosure, to the Document Control Desk. The proprietary information as submitted by Westinghouse is that associated with the NRC's review of a revised methodology for determining RSD strain limits for PBAPS Unit 2, and may be used only for that purpose.
(a) This information is part of that which will enable Westinghouse to:
(i) Assist Exelon Generation in obtaining NRC review and approval of a revised methodology for determining RSD strain limits for PBAPS Unit 2.
5 CAW-15-4155 (b) Further this information has substantial commercial value as follows:
(i) Westinghouse plans to sell the use of this information to its customers for purposes of plant specific replacement steam dryer analysis for licensing basis applications.
(ii) Its use by a competitor would improve their competitive position in the design and licensing of a similar product for BWR steam dryer analysis methodology.
(iii) The information requested to be withheld reveals the distinguishing aspects of a methodology which was developed by Westinghouse.
Public disclosure of this proprietary information is likely to cause substantial harm to the competitive position of Westinghouse because it would enhance the ability of competitors to provide similar technical evaluation and licensing defense services for commercial power reactors without commensurate expenses. Also, public disclosure of the information would enable others to use the information to meet NRC requirements for licensing documentation without purchasing the right to use the information.
The development of the technology described in part by the information is the result of applying the results of many years of experience in an intensive Westinghouse effort and the expenditure of a considerable sum of money.
In order for competitors of Westinghouse to duplicate this information, similar technical programs would have to be performed and a significant manpower effort, having the requisite talent and experience, would have to be expended.
Further the deponent sayeth not.
PROPRIETARY INFORMATION NOTICE Transmitted herewith are proprietary and non-proprietary versions of documents furnished to the NRC associated with the NRC' s review of a revised methodology for determining RSD strain limits with regard to RSD analysis benchmarking for PBAPS Unit 2, and may be used only for that purpose.
In order to conform to the requirements of 10 CFR 2.390 of the Commission's regulations concerning the protection of proprietary information so submitted to the NRC, the information which is proprietary in the proprietary versions is contained within brackets, and where the proprietary information has been deleted in the non-proprietary versions, only the brackets remain (the information that was contained within the brackets in the proprietary versions having been deleted). The justification for claiming the information so designated as proprietary is indicated in both versions by means of lower case letters (a) through (f) located as a superscript immediately following the brackets enclosing each item of information being identified as proprietary or in the margin opposite such information. These lower case letters refer to the types of information Westinghouse customarily holds in confidence identified in Sections (4)(ii)(a) through (4 )(ii)(f) of the Affidavit accompanying this transmittal pursuant to 10 CFR 2.390(b)(1 ).
COPYRIGHT NOTICE The reports transmitted herewith each bear a Westinghouse copyright notice. The NRC is permitted to make the number of copies of the information contained in these reports which are necessary for its internal use in connection with generic and plant-specific reviews and approvals as well as the issuance, denial, amendment, transfer, renewal, modification, suspension, revocation, or violation of a license, permit, order, or regulation subject to the requirements of 10 CFR 2.390 regarding restrictions on public disclosure to the extent such information has been identified as proprietary by Westinghouse, copyright protection notwithstanding. With respect to the non-proprietary versions of these reports, the NRC is permitted to make the number of copies beyond those necessary for its internal use which are necessary in order to have one copy available for public viewing in the appropriate docket files in the public document room in Washington, DC and in local public document rooms as may be required by NRC regulations if the number of copies submitted is insufficient for this purpose. Copies made by the NRC must include the copyright notice in all instances and the proprietary notice if the original was identified as proprietary.