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Category:Legal-Affidavit
MONTHYEARL-23-065, Annual Financial Report2023-05-22022 May 2023 Annual Financial Report CP-202300181, ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI, Corrected Affidavit for Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-04-20020 April 2023 ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI, Corrected Affidavit for Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-22-200, Response to Request for Additional Information Regarding a 180-Day Steam Generator Tube Inspection Report Fall 2021 Refueling Outage2022-10-21021 October 2022 Response to Request for Additional Information Regarding a 180-Day Steam Generator Tube Inspection Report Fall 2021 Refueling Outage L-22-057, Annual Financial Report - Affidavit2022-05-25025 May 2022 Annual Financial Report - Affidavit L-21-041, Annual Financial Report - Affidavit2021-12-14014 December 2021 Annual Financial Report - Affidavit ML21132A2422021-05-12012 May 2021 Response to Request for Additional Information Regarding Steam Generator Tube Sleeve License Amendment Request L-20-161, Response to Request for Additional Information Regarding License Amendment Request to Modify Technical Specifications 3.4.16, RCS Specific Activity, 3.7.13 Secondary Specific Activity, 5.5.7, Ventilation Filter .2020-06-0909 June 2020 Response to Request for Additional Information Regarding License Amendment Request to Modify Technical Specifications 3.4.16, RCS Specific Activity, 3.7.13 Secondary Specific Activity, 5.5.7, Ventilation Filter . L-20-126, Request for Threshold Determination - Corporate Organization and Ownership2020-05-0404 May 2020 Request for Threshold Determination - Corporate Organization and Ownership L-20-067, Retrospective Premium Guarantee - 2020 Internal Cash Flow Projection2020-03-0404 March 2020 Retrospective Premium Guarantee - 2020 Internal Cash Flow Projection L-19-200, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI - Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2019-08-29029 August 2019 ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI - Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments ML16237A0552016-08-22022 August 2016 Submittal of After Action Report/Improvement Plan for Exercise on 06/14/2016 L-16-028, Retrospective Premium Guarantee2016-03-0202 March 2016 Retrospective Premium Guarantee ML0926704712009-09-22022 September 2009 G20090544/EDATS: OEDO-2009-0574 - Edwin M. Hackett Memo, Letter from Citizen Power (Theodore S. Robinson) Concerning the License Renewal for the Beaver Valley Power Station ML0920405122009-07-21021 July 2009 G20090418/EDATS: OEDO-2009-0458 - Edwin M. Hackett Memo, Letter from Citizen Power and Beyond Nuclear Concerning the License Renewal for the Beaver Valley Power Station L-07-106, License Amendment Request No. 07-007 Alloy 800 Steam Generator Tube Sleeving2007-09-19019 September 2007 License Amendment Request No. 07-007 Alloy 800 Steam Generator Tube Sleeving L-07-103, Supplemental Information for License Amendment Request Nos. 333 & 204 (Rev. 2 of WCAP-16518)2007-07-26026 July 2007 Supplemental Information for License Amendment Request Nos. 333 & 204 (Rev. 2 of WCAP-16518) 2023-05-22
[Table view] Category:Letter type:L
MONTHYEARL-23-267, Submittal of Discharge Monitoring Report (Npdes), Permit No. PA00256152023-12-18018 December 2023 Submittal of Discharge Monitoring Report (Npdes), Permit No. PA0025615 L-23-229, Request for Additional Information Regarding the Spring 2023 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F-Star Reports2023-11-29029 November 2023 Request for Additional Information Regarding the Spring 2023 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F-Star Reports L-23-247, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-11-17017 November 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-23-227, Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Third Quarter 20232023-10-20020 October 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Third Quarter 2023 L-23-208, Submittal of Discharge Monitoring Report Cnpdes), Permit No. PA00256152023-09-14014 September 2023 Submittal of Discharge Monitoring Report Cnpdes), Permit No. PA0025615 L-23-167, Twenty-Third Refueling Outage Inservice Inspection Summary Report2023-09-13013 September 2023 Twenty-Third Refueling Outage Inservice Inspection Summary Report L-23-205, Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-09-12012 September 2023 Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-23-172, Quality Assurance Program Manual2023-08-31031 August 2023 Quality Assurance Program Manual L-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023 Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-23-179, Submittal of Discharge Monitoring Report, (NPDES) Permit No. PA00256152023-07-18018 July 2023 Submittal of Discharge Monitoring Report, (NPDES) Permit No. PA0025615 L-23-165, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-06-26026 June 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-23-139, Response to Request for Additional Information Regarding Fall 2022 180-Day Steam Generator Tube Inspection Report2023-06-13013 June 2023 Response to Request for Additional Information Regarding Fall 2022 180-Day Steam Generator Tube Inspection Report L-23-055, Submittal of the Updated Final Safety Analysis Report, Revision 342023-05-23023 May 2023 Submittal of the Updated Final Safety Analysis Report, Revision 34 L-23-065, Annual Financial Report2023-05-22022 May 2023 Annual Financial Report L-23-137, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-05-18018 May 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-23-125, Cycle 24 Core Operating Limits Report2023-05-17017 May 2023 Cycle 24 Core Operating Limits Report L-23-132, Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations2023-05-10010 May 2023 Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations L-23-129, Response to Request for Additional Information for 10 CFR 50.55a Request 2-TYP-4-RV-06 for Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations2023-05-0505 May 2023 Response to Request for Additional Information for 10 CFR 50.55a Request 2-TYP-4-RV-06 for Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations L-23-115, Submittal of 2022 Annual Radioactive Effluent Release Report, 2022 Annual Radiological Environmental Operating Report, and 2022 Annual Environmental Operating Report (Non-Radiological2023-04-27027 April 2023 Submittal of 2022 Annual Radioactive Effluent Release Report, 2022 Annual Radiological Environmental Operating Report, and 2022 Annual Environmental Operating Report (Non-Radiological L-23-126, Discharge Monitoring Report (Npdes), Permit No. PA00256152023-04-22022 April 2023 Discharge Monitoring Report (Npdes), Permit No. PA0025615 L-23-053, 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2023-04-14014 April 2023 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-23-061, Submittal of the Decommissioning Funding Status Reports2023-03-31031 March 2023 Submittal of the Decommissioning Funding Status Reports L-23-058, 180-Day Steam Generator Tube Inspection Report2023-03-27027 March 2023 180-Day Steam Generator Tube Inspection Report L-23-066, Annual Notification of Property Insurance Coverage2023-03-21021 March 2023 Annual Notification of Property Insurance Coverage L-23-036, Report of Facility Changes, Tests and Experiments2023-03-13013 March 2023 Report of Facility Changes, Tests and Experiments L-23-086, Response to Request for Additional Information for Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair2023-03-0404 March 2023 Response to Request for Additional Information for Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair L-23-087, Supplement to Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair (L-2023-LLA-0027)2023-03-0404 March 2023 Supplement to Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair (L-2023-LLA-0027) L-23-073, Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair2023-03-0101 March 2023 Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair L-23-016, Twenty-Eighth Refueling Outage Inservice Inspection Summary Report2023-02-21021 February 2023 Twenty-Eighth Refueling Outage Inservice Inspection Summary Report L-23-064, Discharge Monitoring Report, (NPDES) Permit No. PA00256152023-02-21021 February 2023 Discharge Monitoring Report, (NPDES) Permit No. PA0025615 L-23-057, Energy Harbor Nuclear Corp Retrospective Premium Guarantee2023-02-20020 February 2023 Energy Harbor Nuclear Corp Retrospective Premium Guarantee L-22-193, Request for Exemption from Specific Provisions in 10 CFR 50 Appendix H2023-02-14014 February 2023 Request for Exemption from Specific Provisions in 10 CFR 50 Appendix H L-22-286, Supplement to Request for an Amendment to Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time2023-02-14014 February 2023 Supplement to Request for an Amendment to Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time L-23-032, Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Second Half of 20222023-01-23023 January 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Second Half of 2022 L-22-281, Discharge Monitoring Report (NPDES) Permit No. PA00256152022-12-16016 December 2022 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-22-246, Response to Request for Additional Information Regarding a Request to Consolidate Fuel Decay Time Technical Specifications to New LCO2022-12-0707 December 2022 Response to Request for Additional Information Regarding a Request to Consolidate Fuel Decay Time Technical Specifications to New LCO L-22-217, Submittal of Discharge Monitoring Report (NPDES) Permit No. PA00256152022-11-21021 November 2022 Submittal of Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-22-226, Emergency Preparedness Plan2022-11-0404 November 2022 Emergency Preparedness Plan L-22-222, Cycle 29-1 Core Operating Limits Report2022-10-31031 October 2022 Cycle 29-1 Core Operating Limits Report L-22-228, Independent Spent Fuel Storage Installation Changes, Tests, and Experiments2022-10-26026 October 2022 Independent Spent Fuel Storage Installation Changes, Tests, and Experiments L-22-200, Response to Request for Additional Information Regarding a 180-Day Steam Generator Tube Inspection Report Fall 2021 Refueling Outage2022-10-21021 October 2022 Response to Request for Additional Information Regarding a 180-Day Steam Generator Tube Inspection Report Fall 2021 Refueling Outage L-22-232, Withdrawal of a License Amendment Request Associated with Fire Protection Program Changes2022-10-21021 October 2022 Withdrawal of a License Amendment Request Associated with Fire Protection Program Changes L-22-238, Submittal of Discharge Monitoring Report (NPDES) Permit No. PA00256152022-10-20020 October 2022 Submittal of Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-22-227, Revised August 2022 Outfall 003 & 004 NPDES Discharge Monitoring Report (Dmr), Revised Daily Effluent Monitoring Report Forms for Outfalls 003 & 004 and Corrective Action Letter from Eurofins2022-10-0303 October 2022 Revised August 2022 Outfall 003 & 004 NPDES Discharge Monitoring Report (Dmr), Revised Daily Effluent Monitoring Report Forms for Outfalls 003 & 004 and Corrective Action Letter from Eurofins L-22-219, Submittal of Discharge Monitoring Report (NPDES) Permit No. PA00256152022-09-26026 September 2022 Submittal of Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-22-204, Submittal of Evacuation Time Estimates2022-09-0707 September 2022 Submittal of Evacuation Time Estimates L-22-137, Request for Fire Protection Program Changes2022-09-0606 September 2022 Request for Fire Protection Program Changes L-21-238, License Amendment Request for Addition of Analytical Methodology to the Core Operating Limits Report for a Full Spectrum Loss of Coolant Accident2022-08-31031 August 2022 License Amendment Request for Addition of Analytical Methodology to the Core Operating Limits Report for a Full Spectrum Loss of Coolant Accident L-22-188, Response to Request for Additional Information Regarding Steam Generator Inspection Report- Fall 2021 Refueling Outage2022-08-22022 August 2022 Response to Request for Additional Information Regarding Steam Generator Inspection Report- Fall 2021 Refueling Outage L-22-191, Spent Fuel Storage Cask Registration2022-08-17017 August 2022 Spent Fuel Storage Cask Registration 2023-09-14
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARL-23-229, Request for Additional Information Regarding the Spring 2023 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F-Star Reports2023-11-29029 November 2023 Request for Additional Information Regarding the Spring 2023 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F-Star Reports L-23-139, Response to Request for Additional Information Regarding Fall 2022 180-Day Steam Generator Tube Inspection Report2023-06-13013 June 2023 Response to Request for Additional Information Regarding Fall 2022 180-Day Steam Generator Tube Inspection Report L-23-129, Response to Request for Additional Information for 10 CFR 50.55a Request 2-TYP-4-RV-06 for Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations2023-05-0505 May 2023 Response to Request for Additional Information for 10 CFR 50.55a Request 2-TYP-4-RV-06 for Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations L-23-086, Response to Request for Additional Information for Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair2023-03-0404 March 2023 Response to Request for Additional Information for Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair L-22-246, Response to Request for Additional Information Regarding a Request to Consolidate Fuel Decay Time Technical Specifications to New LCO2022-12-0707 December 2022 Response to Request for Additional Information Regarding a Request to Consolidate Fuel Decay Time Technical Specifications to New LCO L-22-200, Response to Request for Additional Information Regarding a 180-Day Steam Generator Tube Inspection Report Fall 2021 Refueling Outage2022-10-21021 October 2022 Response to Request for Additional Information Regarding a 180-Day Steam Generator Tube Inspection Report Fall 2021 Refueling Outage L-22-188, Response to Request for Additional Information Regarding Steam Generator Inspection Report- Fall 2021 Refueling Outage2022-08-22022 August 2022 Response to Request for Additional Information Regarding Steam Generator Inspection Report- Fall 2021 Refueling Outage ML22094A1152022-04-0404 April 2022 Response to a Request for Additional Information Regarding a Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start and Bus Separation Instrumentation (EPID No. L-202 L-22-079, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations2022-03-16016 March 2022 Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations ML21147A1462021-05-27027 May 2021 Response to Request for Additional Information Regarding Generic Letter 2004-02 ML21132A2422021-05-12012 May 2021 Response to Request for Additional Information Regarding Steam Generator Tube Sleeve License Amendment Request L-21-106, Response to Request for Additional Information Regarding Amendment Request to Update Analytical Methods Used to Develop Reactor Coolant System Pressure and Temperature Limits2021-04-22022 April 2021 Response to Request for Additional Information Regarding Amendment Request to Update Analytical Methods Used to Develop Reactor Coolant System Pressure and Temperature Limits ML21055A8862021-02-24024 February 2021 Response to Request for Additional Information Regarding Steam Generator Inspection 180-Day Report ML21048A0822021-02-16016 February 2021 Response to Request for Additional Information Regarding Steam Generator Tube Sleeve License Amendment Request L-21-030, Response to Request for Additional Information Regarding an Amendment to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff, Into the Facility Technical Specifications (EPID L-20202021-01-27027 January 2021 Response to Request for Additional Information Regarding an Amendment to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff, Into the Facility Technical Specifications (EPID L-2020 L-20-277, Response to Request for Additional Information Regarding Steam Generator Tube Sleeve License Amendment Request2021-01-22022 January 2021 Response to Request for Additional Information Regarding Steam Generator Tube Sleeve License Amendment Request L-20-293, Response Correction to a Request for Additional Information Regarding License Amendment Request to Modify Technical Specifications 3.4.162020-11-30030 November 2020 Response Correction to a Request for Additional Information Regarding License Amendment Request to Modify Technical Specifications 3.4.16 L-20-162, Supplemental Response to NRC Generic Letter 2004-022020-11-30030 November 2020 Supplemental Response to NRC Generic Letter 2004-02 L-20-276, Response to Request for Additional Information Regarding Steam Generator Inspection Report2020-10-30030 October 2020 Response to Request for Additional Information Regarding Steam Generator Inspection Report L-20-161, Response to Request for Additional Information Regarding License Amendment Request to Modify Technical Specifications 3.4.16, RCS Specific Activity, 3.7.13 Secondary Specific Activity, 5.5.7, Ventilation Filter .2020-06-0909 June 2020 Response to Request for Additional Information Regarding License Amendment Request to Modify Technical Specifications 3.4.16, RCS Specific Activity, 3.7.13 Secondary Specific Activity, 5.5.7, Ventilation Filter . L-20-155, Response to Request for Additional Information Regarding Request for Exemptions to Certain Periodic Training Requirements for Security Personnel (Epids L-2020-LLE-0026 to -0040)2020-05-0606 May 2020 Response to Request for Additional Information Regarding Request for Exemptions to Certain Periodic Training Requirements for Security Personnel (Epids L-2020-LLE-0026 to -0040) L-20-097, Response to Request for Additional Information and Supplemental Information Regarding License Amendment Request to Modify Technical Specifications 3.4.16, RCS Specific Activity, 3.7.13 Secondary Specific Activity,.2020-04-14014 April 2020 Response to Request for Additional Information and Supplemental Information Regarding License Amendment Request to Modify Technical Specifications 3.4.16, RCS Specific Activity, 3.7.13 Secondary Specific Activity,. L-20-125, Response to Request for Additional Information Regarding 10 CFR 50.55a Request Number SRR-1, Rev. 0, Snubber Testing2020-04-0303 April 2020 Response to Request for Additional Information Regarding 10 CFR 50.55a Request Number SRR-1, Rev. 0, Snubber Testing L-19-182, Response to RAI Regarding an Application for Order Consenting to Transfer of License2019-08-0202 August 2019 Response to RAI Regarding an Application for Order Consenting to Transfer of License L-18-209, Response to Request for Additional Information Regarding Steam Generator Technical Specification License Amendment Request2018-10-28028 October 2018 Response to Request for Additional Information Regarding Steam Generator Technical Specification License Amendment Request L-18-121, Response to Request for Supplemental Information Regarding Generic Letter 2016-01 Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools.2018-05-25025 May 2018 Response to Request for Supplemental Information Regarding Generic Letter 2016-01 Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools. L-18-125, Response to Follow-up Request for Additional Information Regarding Exemption Request for a Physical Barrier Requirement IEPID-L-2017-l-LE-0019 (CAC Nos.000976/05000334/-L-2017-LLE-0019 MG0010, 000976/05000334/L-2017-LLE-0019 MG0011,000976/02018-05-0202 May 2018 Response to Follow-up Request for Additional Information Regarding Exemption Request for a Physical Barrier Requirement IEPID-L-2017-l-LE-0019 (CAC Nos.000976/05000334/-L-2017-LLE-0019 MG0010, 000976/05000334/L-2017-LLE-0019 MG0011,000976/0 ML18099A1232018-04-0606 April 2018 Response to Request for Additional Information Regarding Request to Modify Rtpts Values L-18-061, Units. 1 & 2, Davis-Besse, and Perry, Response to Request for Additional Information Regarding Exemption Request for a Physical Barrier Requirement2018-03-16016 March 2018 Units. 1 & 2, Davis-Besse, and Perry, Response to Request for Additional Information Regarding Exemption Request for a Physical Barrier Requirement L-17-375, Response to Request for Additional Information Regarding Request 1-TYP-4-BA-01 to Extend the Inservice Inspection Interval for Certain Reactor Vessel Welds2018-01-0505 January 2018 Response to Request for Additional Information Regarding Request 1-TYP-4-BA-01 to Extend the Inservice Inspection Interval for Certain Reactor Vessel Welds L-17-372, Response to Request for Additional Information Regarding Request to Use ASME Code Case N-513-4 (EPID 000976/05000334/L-2017-LLR-0088,000976/05000346/L-2017-LLR-0088, 000976/05000412/L-2017-LLR-0088, and 000976/05000440/L-2017-LLR-0088)2017-12-23023 December 2017 Response to Request for Additional Information Regarding Request to Use ASME Code Case N-513-4 (EPID 000976/05000334/L-2017-LLR-0088,000976/05000346/L-2017-LLR-0088, 000976/05000412/L-2017-LLR-0088, and 000976/05000440/L-2017-LLR-0088) L-17-296, Response to Request for Additional Information Re Request to Revise the Emergency Plan2017-09-20020 September 2017 Response to Request for Additional Information Re Request to Revise the Emergency Plan L-17-197, Response to Request for Additional Information and Supplemental Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 8052017-06-23023 June 2017 Response to Request for Additional Information and Supplemental Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 L-17-104, Response to Request for Additional Information Regarding a Request to Revise the Emergency Plan2017-05-20020 May 2017 Response to Request for Additional Information Regarding a Request to Revise the Emergency Plan ML17213A0172017-05-11011 May 2017 Enclosure B: Beaver Valley, Unit 2, Seismic Probabilistic Risk Assessment in Response to 50.54(0 Letter with Regard to NTTF 2.1 ML17213A0162017-05-11011 May 2017 Enclosure a: Beaver Valley, Units 1, Seismic Probabilistic Risk Assessment in Response to 50.54(f) Letter with Regard to NTTF 2.1 L-17-053, Response to Request for Additional Information Regarding 10 CFR 50.55a Request Numbers PR6 and PR72017-02-22022 February 2017 Response to Request for Additional Information Regarding 10 CFR 50.55a Request Numbers PR6 and PR7 L-17-024, Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 8052017-01-30030 January 2017 Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 L-16-299, Response to Generic Letter 2016-01. Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools2016-10-31031 October 2016 Response to Generic Letter 2016-01. Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools L-16-212, Response to Request for Additional Information Regarding 2015 Steam Generator Inspection Reports2016-07-14014 July 2016 Response to Request for Additional Information Regarding 2015 Steam Generator Inspection Reports L-16-162, Response to Requests for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805, and Request to Change Implementation Schedule2016-05-12012 May 2016 Response to Requests for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805, and Request to Change Implementation Schedule L-16-085, Request for Additional Information Response Related to Modification of Technical Specification 5.3.1, Unit Staff Qualifications.2016-03-22022 March 2016 Request for Additional Information Response Related to Modification of Technical Specification 5.3.1, Unit Staff Qualifications. ML16063A2882016-03-0202 March 2016 Response to NRC Request for Additional Information, Per 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force (NTTF) Review of Insights from the Fukushima Dai-ichi Accident L-16-058, Supplemental Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 8052016-02-24024 February 2016 Supplemental Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 L-15-371, Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 8052015-12-21021 December 2015 Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 L-15-303, Response to Request for Additional Information Regarding Submittal of Reactor Vessel Internals Aging Management Program2015-11-0606 November 2015 Response to Request for Additional Information Regarding Submittal of Reactor Vessel Internals Aging Management Program L-15-325, Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 8052015-11-0606 November 2015 Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 L-15-261, Response to Request for Additional Information Regarding Submittal of Reactor Vessel Internals Aging Management Program2015-08-26026 August 2015 Response to Request for Additional Information Regarding Submittal of Reactor Vessel Internals Aging Management Program L-15-202, Response to Request for Additional Information on Expedited Seismic Evaluation Process (ESEP) Reports and Seismic Hazard and Screening Reports Submitted, Per 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term..2015-06-29029 June 2015 Response to Request for Additional Information on Expedited Seismic Evaluation Process (ESEP) Reports and Seismic Hazard and Screening Reports Submitted, Per 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term.. L-15-188, Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 8052015-06-26026 June 2015 Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 2023-06-13
[Table view] |
Text
WITHHOLD FROM PUBLIC DISCLOSURE UNDER 10 CFR 2.390 WHEN SEPARATED FROM ENCLOSURE B, THIS DOCUMENT CAN BE DECONTROLLED Energy Harbor Nuclear Corp.
Beaver Valley Power Station P.O. Box 4 Shippingport, PA 15077 John J. Grabnar 724-682-5234 Site Vice President, Beaver Valley Nuclear October 21 , 2022 L-22-200 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Subject:
Beaver Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 Response to Request for Additional Information Regarding a 180-Day Steam Generator Tube Inspection Report Fall 2021 Refueling Outage (EPID No. L-2022-LRO-0064)
By correspondence dated May 5, 2022 (Accession No. ML22126A089), Energy Harbor Nuclear Corp. submitted to the Nuclear Regulatory Commission (NRC) a steam generator tube inspection report. The report provided information required by the technical specifications that was obtained during the Fall 2021 refueling outage inspections. By email dated August 25, 2022 (Accession No. ML22238A281), the NRC staff requested additional information regarding the report.
The response to the request for additional information is provided in enclosures A and B that present non-proprietary and proprietary versions, respectively, of the attachments to document number EH-22-022, Transmittal of Responses to Requests for Additional Information on the Beaver Valley 2R22 Steam Generator 180-Day Report.
Enclosure C contains Affidavit CAW-22-046 signed by Westinghouse Electric Company LLC (Westinghouse). The affidavit sets forth the basis on which proprietary information owned by Westinghouse that is contained in Enclosure B may be withheld from public disclosure by the Nuclear Regulatory Commission (Commission) and addresses with specificity the considerations listed in paragraph (b)(4) of Section 2.390 of the Commissions regulations.
Accordingly, it is respectively requested that the information that is proprietary to Westinghouse be withheld from public disclosure in accordance with 10 CFR Section 2.390 of the Commissions regulations.
Beaver Valley Power Station, Unit No. 2 L-22-200 Page 2 Correspondence with respect to the copyright or proprietary aspects of the items listed above or the supporting Westinghouse Affidavit should reference CAW-22-046 and should be addressed to Camille T. Zozula, Manager, Regulatory Compliance and Corporate Licensing.
There are no regulatory commitments contained in this submittal. If there are any questions or if additional information is required, please contact Mr. Phil H. Lashley, Manager - Fleet Licensing, at (330) 696-7208.
Sincerely, John J Digitally signed by John J Grabnar Gra b na r Date: 2022.10.21 14:24:3s -04*00*
John J. Grabnar
Enclosures:
A. Response to Request for Additional Information (Non-proprietary)
B. Response to Request for Additional Information (Proprietary)
C. Affidavit for Withholding Proprietary Information cc: NRC Region I Administrator NRC Resident Inspector NRR Project Manager Director BRP/DEP Site BRP/DEP Representative
Enclosure A L-22-200 Response to Request for Additional Information (Non-proprietary)
(9 pages follow)
Westinghouse Non-Proprietary Class 3 Westinghouse Electric Company DMW-NRCD-RF-LR-000002 NP-Attachment Revision 0 Beaver Valley Power Station, Unit 2 - Responses to Request For Additional Information -
Refueling Outage 22 Steam Generator 180 Day Report September 2022 Author:
Jay R. Smith*
Component Design and Management Programs Author:
Jeffrey M. Raschiatore*
Inspection Services Verifier:
Bradley T. Carpenter*
Component Design and Management Programs Reviewer:
Gary W. Whiteman*
Licensing Engineering Approved:
Robert S. Chappo, Jr.*, Manager Component Design and Management Programs
©2022 Westinghouse Electric Company LLC All Rights Reserved
- Electronically approved records are authenticated in the Electronic Document Management System.
DMW-NRCD-RF-LR-000002 NP-Attachment Page 1 of 9 Rev. 0
- This record was final approved on 9/23/2022, 3:25:08 PM. (This statement was added by the PRIME system upon its validation)
Westinghouse Non-Proprietary Class 3 Beaver Valley Power Station, Unit 2 - Responses to Request For Additional Information -
Refueling Outage 22 Steam Generator 180 Day Report
Background
By letter dated May 5, 2022 (ML22126A089), Energy Harbor Nuclear Corp. submitted the Unit #2 2R22 Steam Generator 180 Day Report summarizing the results of the fall 2021 steam generator (SG) inspections performed at Beaver Valley Power Station, Unit 2 (BVPS-2). The inspections were performed during refueling outage 22 (2R22). Technical Specification (TS) Section 5.6.6.2 requires that a report be submitted within 180 days after the initial entry into hot shutdown (MODE 4) following completion of an inspection of the SGs performed in accordance with TS Section 5.5.5.2.
Responses to Request for Additional Information To complete its review of the inspection, the U.S. Nuclear Regulatory Commission (NRC) staff requests the following additional information:
RAI 1
Table 2R22 Examination Techniques Used for Degradation Detection/Sizing states that an Internal Westinghouse Technique Qualification was used for axial primary water stress corrosion cracking (PWSCC) at dented tube support plates (TSPs) less than 2 volts. It was noted that Electric Power Research Institute Examination Technique Specification Sheet 96012.1 was used in 2R21 (2020) for axial PWSCC at dented TSPs less than 2 volts (ML20287A373). Please provide additional information regarding why a different examination technique was used in 2R22 for axial PWSCC at dented TSPs less than 2 volts.
Response
EPRI Examination Technique Specification Sheet (ETSS) 96012.1 provides a qualified technique for detection of axial PWSCC at TSP intersections with dents less than 2 volts; however, application of this technique had produced a significant number of overcalls as experienced throughout the industry.
To reduce the number of overcalls, a supplemental data screening criterion had been developed by Westinghouse in 2005. Since 2005, BVPS-2 has used ETSS 96012.1 in conjunction with the Westinghouse supplemental screening criterion for the detection of axial PWSCC at dented TSPs with dents less than 2 volts. The supplemental screening criterion establishes the phase angle and voltage amplitude signal responses for when diagnostic +POINTTM(1) probe inspections are required. The performance of the +POINT probe screening criteria was benchmarked to the data set contained in EPRI ETSS 96012.1 and was demonstrated to result in consistent performance statistics provided in ETSS 96012.1. During the inspections since 2005, the EPRI ETSS 96012.1 technique essential variables, calibration, and normalization procedures were used. The development of the bobbin coil probe supplemental screening technique was referred to as an Internal Westinghouse Technique Qualification within the 2R22 180-Day report (Reference 1) rather than ETSS 96012.1.
1
+POINT is a trademark of Zetec, its affiliates and/or its subsidiaries in the United States of America and may be registered in other countries throughout the world. All rights reserved. Unauthorized use is strictly prohibited. Other names may be trademarks of their respective owners.
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- This record was final approved on 9/23/2022, 3:25:08 PM. (This statement was added by the PRIME system upon its validation)
Westinghouse Non-Proprietary Class 3 The supplemental screening criterion requires that all TSP intersections [
]a,c,e Application of this screening criterion to the ETSS 96012.1 data set produced consistent detection performance statistics provided in the ETSS, thereby demonstrating acceptability of the criterion.
RAI 2
During 2R22, the +Point probe observed circumferential indications in four Alloy 800 nickel banded mechanical tubesheet sleeves (three installed in 2R20 (2018) and one installed in 2R21 (2020)) located at the lower tubesheet hard roll joint at the lower expansion transition below the nickel band region. It was noted that one of the sleeves installed in 2R20 (2018) had a circumferential signal after sleeve installation and prior to being placed in service. While preliminary assessments suggested the signals could be circumferential outside diameter stress corrosion cracking (ODSCC) on the outer surface of the parent tube, it was determined that the circumferential signals may be fabrication related and not flaws because (1) flaws at this location are not likely due to the full-depth hard roll condition of the parent tube, (2) one circumferential signal had a precursor after sleeve installation and prior to being placed in service, and (3) the Ghent Version 2 probe did not observe signals like those observed by the +Point probe and did not detect any flaw-like signals. The affected tubes were proactively plugged during 2R22. Please discuss the following:
- a. A comparison of the precursor eddy current signal in the one sleeve installed in 2R20 (2018) compared to the circumferential signal observed during 2R22.
Response
The nickel banded mechanical tubesheet sleeve in SG B Tube R18C24 was installed in 2R20 (2018). The baseline sleeve inspection was performed with the +POINT probe only, as the Ghent Version 2 probe had not been developed at the time of the inspection. A circumferential signal was present below the nickel band region from historical data review of the baseline +POINT probe inspection as shown in Figure 1.
During the subsequent in-service inspections (ISI) of this sleeve performed in 2R21 (2020) and 2R22 (2021), the combination Ghent Version 2 probe was used for the inspection of sleeves.
The combination Ghent Version 2 probe contained both magnetically biased Ghent coils and +POINT coils.
The +POINT coil response of the circumferential signal changed from 2R20 to 2R21 as shown by comparing the probe responses in Figure 1 and Figure 2. The change in the +POINT probe signal response from the 2R20 baseline inspection is attributed to the strong magnet contained in the Ghent portion of the probe. The strong magnet in the Ghent V2 probe magnetizes the sleeve/parent tube which is detected by the +Point coil prior to the test piece magnetization dissipating. This magnetic saturation decreases permeability variations within the sleeve/parent tube which in turn improves eddy current flow through the test piece, ultimately providing improved detection capability for the +Point coil. The +POINT response did not change from 2R21 to 2R22 as shown in Figure 2 and Figure 3 when both inspections used the combination Ghent Version 2 probe.
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- This record was final approved on 9/23/2022, 3:25:08 PM. (This statement was added by the PRIME system upon its validation)
Westinghouse Non-Proprietary Class 3 Ghent coil inspections of the lower sleeve joint were performed in 2R21 and 2R22 and showed a circumferential response in both inspections. There was no change in the circumferential responses from 2R21 to 2R22 as shown in Figure 4 and Figure 5.
.... . SG BR18C24 2R20,2018
+POINT Baseline
Circumferential
Response
Figure 1: 2R20 Baseline +POINT Probe Examination of SG B R18C24 Lower Sleeve Joint Circumferential
Response
Figure 2: 2R21 +POINT Probe 1st ISI Examination of SG B R18C24 Lower Sleeve Joint DMW-NRCD-RF-LR-000002 NP-Attachment Page 4 of 9 Rev. 0
- This record was final approved on 9/23/2022, 3:25:08 PM. (This statement was added by the PRIME system upon its validation)
Westinghouse Non-Proprietary Class 3 I
Circumferential
Response
Figure 3: 2R22 +POINT Probe 2nd ISI Examination of SG B R18C24 Lower Sleeve Joint Circumferential
Response
Figure 4: 2R21 Ghent Probe 1st Examination of SG B R18C24 Lower Sleeve Joint DMW-NRCD-RF-LR-000002 NP-Attachment Page 5 of 9 Rev. 0
- This record was final approved on 9/23/2022, 3:25:08 PM. (This statement was added by the PRIME system upon its validation)
Westinghouse Non-Proprietary Class 3 Circumferential
Response
Figure 5: 2R22 Ghent Probe 2nd Examination of SG B R18C24 Lower Sleeve Joint
- b. Why the preliminary assessment suggested ODSCC on the outer surface of the parent tube.
Response
During 2R22, all alloy 800 nickel banded mechanical tubesheet sleeves were inspected with the Ghent Version 2 probe. This probe contains both +POINT and Ghent coils. The Ghent portion of the probe contains strong magnets adjacent to the Ghent coils to minimize the response of the nickel band material. An eddy current Independent Qualified Data Analyst (IQDA) determined that four signals found with the +Point coil, just below the bottom of the nickel band, were flaw-like. The four were reported as single circumferential indications (SCIs), with the tubes being proactively plugged.
To assess where in the sleeve/parent tube joint these occurred, the IQDA performed a comparison of the phase and voltage amplitude between these four signals and known flaws from the calibration standard. Three calibration standard electrical discharge machining (EDM) notches were used and were located on the outer diameter (OD) of the sleeve, inner diameter (ID) of the parent tube, and OD of the parent tube. The phase and voltage amplitude results of the comparison are provided in Table 1 below. Responses from all test frequencies were used in the comparison, but only the results from the qualified reporting frequency of 70kHz are provided.
It was observed that the phase response of the four signals reported in 2R22 are similar to the response of an OD circumferential EDM notch on the parent tube. This comparison of phase responses led the IQDA to initially report the signals appear to be initiated on the outer surface of the parent tube during the inspection.
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- This record was final approved on 9/23/2022, 3:25:08 PM. (This statement was added by the PRIME system upon its validation)
Westinghouse Non-Proprietary Class 3 Table 1:
Ghent Probe Response Comparison of Calibration Standard and 2R22 Signals Voltage, Phase, Sample/Tube Amplitude, degrees Vpp Calibration Standard Ghent Probe Responses Parent Tube 71% Through Wall (TW) OD 113 1.63 Circ. EDM Notch Parent Tube 66%TW ID Circ. EDM Notch 96 1.72 Sleeve 43%TW OD Circ. EDM Notch 50 2.84 2R22 Sleeve Signal Ghent Probe Responses SGB R18 C24 112 4.56 SGB R18 C14 115 6.77 SGB R12 C59 105 2.44 SGA R13 C56 112 3.01
- c. Any insights on why the circumferential signals in the three tubes installed during 2R20 (2018) were not observed during the inspections performed during 2R21 (2020). The staff notes that the Ghent Version 2 probe was also used during 2R21 and that two sleeved tubes were plugged due to axial scratches located in the lower tubesheet sleeve joint (ML20287A373).
Response
The Ghent Version 2 probe eddy current signals for the 4 circumferential signals reported are similar in their appearance, voltage amplitude and phase between 2R21 and 2R22. The eddy current data analysis guidelines and ETSS were the same for both inspections. While not reported in 2R21, the IQDA in 2R22 took a conservative approach to report these signals as single circumferential indications as opposed to reporting as sleeve anomalies.
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- This record was final approved on 9/23/2022, 3:25:08 PM. (This statement was added by the PRIME system upon its validation)
Westinghouse Non-Proprietary Class 3
- d. It is the staffs understanding that the use of a high-speed buffing tool for mechanically conditioning the tube prior to sleeving may have been eliminated prior to 2R20 (2018) (ML18348B206). If so, could the lack of tube buffing prior to sleeve installation in these tubes be related to the eddy current indications? In addition, are any changes to the sleeve installation process being considered?
Response
Alloy 800 mechanical nickel banded tubesheet sleeves were installed in the BVPS-2 SGs during 2R16 (2012) and during each refueling outage from 2R19 (2017) through 2R22 (2021). High speed buffing (tube conditioning) of the parent tube was not performed prior to sleeve installation in any of the sleeving campaigns at BVPS-2. The mechanical sleeve qualification report (Reference 2) specified that based on current testing and evaluation this process step may be eliminated in the future when sufficient confidence level is developed. An evaluation of field experience involving visual examination of over 600 conditioned tubes, in four different plants, indicated that process control, in the form of normal in-process instructions and quality assurance surveillance is sufficient to ensure acceptable condition of the tube ID. Therefore, at BVPS-2 there has been no changes related to tube conditioning from when first implemented through the most recent 2R22 outage. Even when tube conditioning has been performed, the operation focuses on the hydraulic expansion regions in the upper sleeve joint as discussed in the mechanical sleeve qualification report (Reference 2). The lower sleeve joint in the nickel band region only received cursory buffing as the buffing tool is being quickly inserted and withdrawn from the upper sleeve joint.
The EPRI SG Examination Guidelines Appendix H qualification (Reference 3) used the Ghent Version 2 combination probe that included Ghent coils and +POINT coils. This is the same designed probe used in the 2R21 inspection and in 2R20 as a prototype probe. The Ghent probe qualification was performed with laboratory samples that replicated the lower tubesheet sleeve joint containing the nickel band and microlok regions. The samples consisted of an Alloy 600 parent tube hard rolled into a carbon steel tubesheet collar simulant and an Alloy 800 tubesheet sleeve hard rolled into the parent tube/collar as described in Reference
- 3. EDM notches were placed into the parent tubes prior to installation into the test assembly. The qualification testing samples were clean materials that had not been in operation.
During the investigation into the origin of the sleeve signals in the four sleeves from 2R22 (2021), eddy current data from the Ghent Version 2 probe used for the EPRI Appendix H Ghent probe qualification (Reference 3) were reviewed. In this review, it was noted that the same type of signals or responses were present below the nickel band region in some of the laboratory samples that simulated the sleeve to parent tube lower joints. In the Appendix H qualification of the Ghent V2 probe, nine sleeve/parent tube samples were used. Five of these samples had circumferential signals detected by the +POINT coils and were similar to those found in the four sleeves during 2R22. The signals were also detected by the Ghent probe but had smaller voltage amplitudes than the +POINT probe response. Since the qualification testing had signals in clean samples and similar signals found in the field where buffing or tube conditioning were not performed, it is concluded that the signals were not related to the lack of conditioning prior to sleeve installation.
Currently, there are no changes to the sleeving process being considered.
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- This record was final approved on 9/23/2022, 3:25:08 PM. (This statement was added by the PRIME system upon its validation)
Westinghouse Non-Proprietary Class 3
References:
- 1. Energy Harbor Nuclear Corporation Letter L-22-100, Beaver Valley Power Station, Unit No. 2, Docket No. 50-412, License No. NPF-73, 180-Day Steam Generator Tube Inspection Report, May 5, 2022.
- 2. Westinghouse Report WCAP-15919-P, Revision 2, Steam Generator Tube Repair for Westinghouse Designed Plants with 7/8 Inch Inconel 600 Tubes Using Leak Limiting Alloy 800 Sleeves, January 2006.
- 3. Westinghouse Report SG-CDMP-19-17-P, Revision 1, Qualification of an Examination Technique to Inspect Parent Tube Flaws Adjacent to the Nickel Band of an Alloy 800 Sleeve at Beaver Valley Unit 2, April 2020.
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- This record was final approved on 9/23/2022, 3:25:08 PM. (This statement was added by the PRIME system upon its validation)
Enclosure C L-22-200 Affidavit for Withholding Proprietary Information (3 pages follow)
Westinghouse Non-Proprietary Class 3 AFFIDAVIT CAW-22-046 Page 1 of 3 COMMONWEALTH OF PENNSYLVANIA:
COUNTY OF BUTLER:
(1) I, Zachary S. Harper, have been specifically delegated and authorized to apply for withholding and execute this Affidavit on behalf of Westinghouse Electric Company LLC (Westinghouse).
(2) I am requesting the proprietary portions of DMW-NRCD-RF-LR-000002 P-Attachment, Revision 0, Beaver Valley Power Station, Unit 2 - Responses to Request for Additional Information - Refueling Outage 22 Steam Generator 180 Day Report, be withheld from public disclosure under 10 CFR 2.390.
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(i) The information sought to be withheld from public disclosure is owned and has been held in confidence by Westinghouse and is not customarily disclosed to the public.
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(iii) Westinghouse notes that a showing of substantial harm is no longer an applicable criterion for analyzing whether a document should be withheld from public disclosure. Nevertheless, 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 justifications and licensing defense services for commercial power reactors without commensurate expenses. Also, public disclosure of the information would enable
- This record was final approved on 9/23/2022, 2:55:38 PM. (This statement was added by the PRIME system upon its validation)
Westinghouse Non-Proprietary Class 3 AFFIDAVIT CAW-22-046 Page 2 of 3 others to use the information to meet NRC requirements for licensing documentation without purchasing the right to use the information.
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(6) The attached documents are bracketed and marked to indicate the bases for withholding. The justification for withholding 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
- This record was final approved on 9/23/2022, 2:55:38 PM. (This statement was added by the PRIME system upon its validation)
Westinghouse Non-Proprietary Class 3 AFFIDAVIT CAW-22-046 Page 3 of 3 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 (5)(a) through (f) of this Affidavit.
I declare that the averments of fact set forth in this Affidavit are true and correct to the best of my knowledge, information, and belief.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on: 09/23/2022 ________________________
Zachary S. Harper, Manager Licensing Engineering