Letter Sequence Request |
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EPID:L-2020-SLR-0002, Enclosure 4, Non-proprietary Reference Documents and Redacted Versions of Proprietary Reference Documents (Public Version) (Approved, Closed) |
Results
Other: L-2021-129, Ssubsequent License Renewal Application: Aging Management Requests for Confirmation Of/Additional Information (Rci/Rai) Set 1 Responses, L-2021-144, Subsequent License Renewal Application-Aging Management Requests for Additional Information (RAI) Set 2 Responses, L-2021-157, L-2021-157 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 6 Responses, L-2021-172, Subsequent License Renewal Application - Aging Management Requirement for Additional Information Set 7, Response, L-2021-190, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 2 Responses Revision 1, L-2021-199, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 10 Responses, L-2021-200, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 11 Response, L-2021-223, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 12 Response, L-2021-224, Subsequent License Renewal Application - First Annual Update, L-2021-248, Subsequent License Renewal Application Aging Management Requests for Additional Information (RAI) Set 14 Response, ML21005A058, ML21015A214, ML21036A217, ML21208A447, ML21214A035, ML21302A019
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MONTHYEARML20329A2642020-11-16016 November 2020 Enclosure 4, Non-proprietary Reference Documents and Redacted Versions of Proprietary Reference Documents (Public Version) Project stage: Request ML21006A4172021-01-15015 January 2021 Subsequent License Renewal Acceptance Letter Project stage: Acceptance Review ML21015A2142021-01-15015 January 2021 Subsequent License Renewal Application Acceptance Federal Register Notice FRN Project stage: Other ML21005A0582021-01-15015 January 2021 Subsequent License Renewal Application - Portal Letter Project stage: Other ML21036A2172021-03-0101 March 2021 SLRA - Proprietary Determination Letter Project stage: Other L-2021-081, Subsequent License Renewal Application - Aging Management Supplement 12021-04-21021 April 2021 Subsequent License Renewal Application - Aging Management Supplement 1 Project stage: Supplement ML21161A1192021-06-10010 June 2021 RAIs Set 1 Final Aging Management of Irradiated Concrete and Steel Reactor Vessel Supports Final Project stage: Request L-2021-129, Ssubsequent License Renewal Application: Aging Management Requests for Confirmation Of/Additional Information (Rci/Rai) Set 1 Responses2021-07-0808 July 2021 Ssubsequent License Renewal Application: Aging Management Requests for Confirmation Of/Additional Information (Rci/Rai) Set 1 Responses Project stage: Other L-2021-147, Subsequent License Renewal Application - Aging Management Supplement 3 Revision 12021-07-26026 July 2021 Subsequent License Renewal Application - Aging Management Supplement 3 Revision 1 Project stage: Supplement ML21214A0432021-08-0202 August 2021 SLRA June 30, 2021, Public Meeting Discussion Questions Project stage: Request L-2021-144, Subsequent License Renewal Application-Aging Management Requests for Additional Information (RAI) Set 2 Responses2021-08-11011 August 2021 Subsequent License Renewal Application-Aging Management Requests for Additional Information (RAI) Set 2 Responses Project stage: Other ML21214A0352021-08-16016 August 2021 Subsequent License Renewal Application (SLRA) Compiled Aging Management Audit Breakout Questions Project stage: Other ML21208A4472021-08-16016 August 2021 Subsequent License Renewal Application Aging Management Audit Report Project stage: Other L-2021-155, Subsequent License Renewal Application on Aging Management - Request for Additional Information (Rai), Set 4 Response2021-08-30030 August 2021 Subsequent License Renewal Application on Aging Management - Request for Additional Information (Rai), Set 4 Response Project stage: Request L-2021-157, L-2021-157 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 6 Responses2021-09-10010 September 2021 L-2021-157 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 6 Responses Project stage: Other L-2021-172, Subsequent License Renewal Application - Aging Management Requirement for Additional Information Set 7, Response2021-09-20020 September 2021 Subsequent License Renewal Application - Aging Management Requirement for Additional Information Set 7, Response Project stage: Other L-2021-174, NextEra Energy Point Beach, LLC - Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) Set 9 Response2021-10-0101 October 2021 NextEra Energy Point Beach, LLC - Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) Set 9 Response Project stage: Request ML21286A6042021-10-0505 October 2021 SLRA Safety RAIs Set 10 Final Project stage: Request L-2021-200, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 11 Response2021-10-25025 October 2021 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 11 Response Project stage: Other L-2021-190, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 2 Responses Revision 12021-11-0303 November 2021 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 2 Responses Revision 1 Project stage: Other ML21292A1852021-11-0303 November 2021 Letter to Applicant Point Beach Nuclear Plant, Units 1 and 2 Notice of Availability of the Draft Plant-Specific Supplement 23, Second Renewal Project stage: Draft Other L-2021-199, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 10 Responses2021-11-0404 November 2021 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 10 Responses Project stage: Other ML21302A0192021-11-10010 November 2021 Maintenance of Reference Material at the Lester Public Library Associated with the Staff'S Review Project stage: Other ML21312A5202021-11-10010 November 2021 Proprietary Determination Letter SLRA Safety RAIs Set 1 Response Project stage: RAI L-2021-221, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 10 Responses Supplement 12021-11-19019 November 2021 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 10 Responses Supplement 1 Project stage: Supplement L-2021-224, Subsequent License Renewal Application - First Annual Update2021-11-30030 November 2021 Subsequent License Renewal Application - First Annual Update Project stage: Other L-2021-223, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 12 Response2021-12-0909 December 2021 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 12 Response Project stage: Other L-2021-248, Subsequent License Renewal Application Aging Management Requests for Additional Information (RAI) Set 14 Response2022-01-0606 January 2022 Subsequent License Renewal Application Aging Management Requests for Additional Information (RAI) Set 14 Response Project stage: Other ML22041A3342022-02-23023 February 2022 Transmittal Letter for Point Beach Final SE for SLRA Review to AA La 2-9 (3) Project stage: Approval ML22054A1082022-02-23023 February 2022 Subsequent License Renewal Application Safety Evaluation Public Project stage: Approval ML22054A1062022-02-23023 February 2022 Srla Safety Evaluation Documents and Transmittal Letter Project stage: Request ML22139A2292022-05-25025 May 2022 Transmittal Letter for Point Beach Final SE for SLRA Review Rev1 Project stage: Approval ML22139A2282022-05-25025 May 2022 Srla Safety Evaluation Revision 1 Documents and Transmittal Letter Project stage: Request 2021-04-21
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Category:Letter type:L
MONTHYEARL-2024-001, Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements2024-01-26026 January 2024 Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-174, Subsequent License Renewal Application - Third Annual Update2023-12-13013 December 2023 Subsequent License Renewal Application - Third Annual Update L-2023-176, Supplement to Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-2023-159, Part 3 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 3 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks and Security Event Notifications Final Rule L-2023-128, License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program2023-09-19019 September 2023 License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2023-089, Refueling Outage Owner'S Activity Report (OAR-1) Unit 2 for Inservice Inspections2023-07-24024 July 2023 Refueling Outage Owner'S Activity Report (OAR-1) Unit 2 for Inservice Inspections L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023 Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452) L-2023-088, 10 CFR 50.55a Requests, Relief Requests I6-RR-1, I6-RR-2, and I6-RR-3 Sixth Ten-Year Inservice Inspection Program Interval2023-06-27027 June 2023 10 CFR 50.55a Requests, Relief Requests I6-RR-1, I6-RR-2, and I6-RR-3 Sixth Ten-Year Inservice Inspection Program Interval L-2023-075, Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-022023-06-0909 June 2023 Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-02 L-2023-073, Subsequent License Renewal Application, Second Annual Update Request for Additional Information Set 1 Response2023-06-0101 June 2023 Subsequent License Renewal Application, Second Annual Update Request for Additional Information Set 1 Response L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal L-2023-058, 2022 Annual Monitoring Report2023-04-10010 April 2023 2022 Annual Monitoring Report L-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023 Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update L-2023-028, and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2023-03-27027 March 2023 and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications L-2023-048, Core Operating Limits Report (COLR) Cycle 40 (U2C40)2023-03-18018 March 2023 Core Operating Limits Report (COLR) Cycle 40 (U2C40) L-2023-025, Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-12023-03-15015 March 2023 Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-1 L-2023-029, and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3)2023-03-10010 March 2023 and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2023-036, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections2023-02-24024 February 2023 Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections L-2023-011, Response to Requests for Additional Information (Rais) Regarding License Amendment Request 297, Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk Informed2023-02-21021 February 2023 Response to Requests for Additional Information (Rais) Regarding License Amendment Request 297, Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk Informed L-2022-185, Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-12-0909 December 2022 Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2022-177, Subsequent License Renewal Application - Second Annual Update2022-11-28028 November 2022 Subsequent License Renewal Application - Second Annual Update L-2022-180, CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2022-11-0909 November 2022 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums L-2022-168, and Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report2022-10-26026 October 2022 and Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report L-2022-161, U1R40 Steam Generator Tube Inspection Report2022-10-13013 October 2022 U1R40 Steam Generator Tube Inspection Report L-2020-159, 10 CFR 50.59 Evaluation and Commitment Change Summary Report2022-10-0404 October 2022 10 CFR 50.59 Evaluation and Commitment Change Summary Report L-2022-160, Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-10-0404 October 2022 Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2022-164, Technical Specification Bases and Technical Requirements Manual Change Summary2022-10-0404 October 2022 Technical Specification Bases and Technical Requirements Manual Change Summary L-2022-148, Florida Power & Light Company, Comments on NRC Inspection Procedure (IP) 71111.21 N.03, Commercial Grade Dedication2022-09-16016 September 2022 Florida Power & Light Company, Comments on NRC Inspection Procedure (IP) 71111.21 N.03, Commercial Grade Dedication L-2022-150, 10 CFR 50 Appendix E Evacuation Time Estimate Study for Point Beach Nuclear Plant2022-09-13013 September 2022 10 CFR 50 Appendix E Evacuation Time Estimate Study for Point Beach Nuclear Plant L-2022-121, Exemption Request, License Amendment Request and Revised Response in Support of a Risk-informed Resolution of Generic Letter 2004-022022-07-29029 July 2022 Exemption Request, License Amendment Request and Revised Response in Support of a Risk-informed Resolution of Generic Letter 2004-02 L-2022-124, Refueling Outage U1R40 Owner'S Activity Report (OAR-1) for Inservice Inspections2022-07-20020 July 2022 Refueling Outage U1R40 Owner'S Activity Report (OAR-1) for Inservice Inspections L-2022-065, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations; Request for Comment2022-04-20020 April 2022 Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations; Request for Comment L-2022-039, and Point Beach, Units 1 & 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2022-04-14014 April 2022 and Point Beach, Units 1 & 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications L-2022-012, Florida Power & Light Company Nuclear Property Insurance - 10 CFR 50.54(w)(3)2022-03-16016 March 2022 Florida Power & Light Company Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2022-013, Subsequent License Renewal Application - Environmental Report Review Review Request for Additional Information (RAI) No. HCR-1 Supplemental Response2022-01-25025 January 2022 Subsequent License Renewal Application - Environmental Report Review Review Request for Additional Information (RAI) No. HCR-1 Supplemental Response L-2021-248, Subsequent License Renewal Application Aging Management Requests for Additional Information (RAI) Set 14 Response2022-01-0606 January 2022 Subsequent License Renewal Application Aging Management Requests for Additional Information (RAI) Set 14 Response L-2021-240, Subsequent License Renewal Application - Aging Management Request for Additional Information Set 13 Response2022-01-0606 January 2022 Subsequent License Renewal Application - Aging Management Request for Additional Information Set 13 Response L-2021-223, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 12 Response2021-12-0909 December 2021 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 12 Response L-2021-224, Subsequent License Renewal Application - First Annual Update2021-11-30030 November 2021 Subsequent License Renewal Application - First Annual Update L-2021-222, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 11 Response Revision 12021-11-23023 November 2021 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 11 Response Revision 1 L-2021-221, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 10 Responses Supplement 12021-11-19019 November 2021 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 10 Responses Supplement 1 L-2021-208, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 9 Response Supplement 12021-11-0404 November 2021 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 9 Response Supplement 1 L-2021-199, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 10 Responses2021-11-0404 November 2021 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 10 Responses L-2021-190, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 2 Responses Revision 12021-11-0303 November 2021 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 2 Responses Revision 1 L-2021-200, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 11 Response2021-10-25025 October 2021 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 11 Response 2024-01-26
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARL-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2023-075, Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-022023-06-0909 June 2023 Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-02 L-2023-073, Subsequent License Renewal Application, Second Annual Update Request for Additional Information Set 1 Response2023-06-0101 June 2023 Subsequent License Renewal Application, Second Annual Update Request for Additional Information Set 1 Response L-2023-011, Response to Requests for Additional Information (Rais) Regarding License Amendment Request 297, Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk Informed2023-02-21021 February 2023 Response to Requests for Additional Information (Rais) Regarding License Amendment Request 297, Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk Informed ML23011A2802023-01-11011 January 2023 Units 1 and 2 - Response to Requests for Additional Information (Rals) Regarding License Amendment Request 297, Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk Informed . ML22229A1052022-08-17017 August 2022 Response to Questions Regarding Point Beach Nuclear Power Plant with Attachment NRC 2022-0022, Response to Request for Supplemental Information (Rsi) Regarding License Amendment Request (LAR) 297, Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2,2022-07-11011 July 2022 Response to Request for Supplemental Information (Rsi) Regarding License Amendment Request (LAR) 297, Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, L-2022-013, Subsequent License Renewal Application - Environmental Report Review Review Request for Additional Information (RAI) No. HCR-1 Supplemental Response2022-01-25025 January 2022 Subsequent License Renewal Application - Environmental Report Review Review Request for Additional Information (RAI) No. HCR-1 Supplemental Response L-2021-240, Subsequent License Renewal Application - Aging Management Request for Additional Information Set 13 Response2022-01-0606 January 2022 Subsequent License Renewal Application - Aging Management Request for Additional Information Set 13 Response L-2021-248, Subsequent License Renewal Application Aging Management Requests for Additional Information (RAI) Set 14 Response2022-01-0606 January 2022 Subsequent License Renewal Application Aging Management Requests for Additional Information (RAI) Set 14 Response L-2021-223, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 12 Response2021-12-0909 December 2021 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 12 Response L-2021-222, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 11 Response Revision 12021-11-23023 November 2021 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 11 Response Revision 1 L-2021-199, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 10 Responses2021-11-0404 November 2021 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 10 Responses L-2021-208, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 9 Response Supplement 12021-11-0404 November 2021 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 9 Response Supplement 1 L-2021-190, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 2 Responses Revision 12021-11-0303 November 2021 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 2 Responses Revision 1 L-2021-200, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 11 Response2021-10-25025 October 2021 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 11 Response L-2021-174, NextEra Energy Point Beach, LLC - Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) Set 9 Response2021-10-0101 October 2021 NextEra Energy Point Beach, LLC - Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) Set 9 Response L-2021-172, Subsequent License Renewal Application - Aging Management Requirement for Additional Information Set 7, Response2021-09-20020 September 2021 Subsequent License Renewal Application - Aging Management Requirement for Additional Information Set 7, Response L-2021-173, Subsequent License Renewal Application-Aging Management Request for Additional Information (RAI) Set 8 Response2021-09-16016 September 2021 Subsequent License Renewal Application-Aging Management Request for Additional Information (RAI) Set 8 Response L-2021-157, L-2021-157 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 6 Responses2021-09-10010 September 2021 L-2021-157 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 6 Responses L-2021-165, Submittal of Subsequent License Renewal Application - Aging Management Requests for Confirmation Of/Additional Information (Rci/Rai) Set 1 Responses Supplement 12021-09-10010 September 2021 Submittal of Subsequent License Renewal Application - Aging Management Requests for Confirmation Of/Additional Information (Rci/Rai) Set 1 Responses Supplement 1 L-2021-155, Subsequent License Renewal Application on Aging Management - Request for Additional Information (Rai), Set 4 Response2021-08-30030 August 2021 Subsequent License Renewal Application on Aging Management - Request for Additional Information (Rai), Set 4 Response L-2021-154, Subsequent License Renewal Application -Aging Management Requests for Confirmation Of/Additional Information (Rci/Rai) Set 3 Responses2021-08-25025 August 2021 Subsequent License Renewal Application -Aging Management Requests for Confirmation Of/Additional Information (Rci/Rai) Set 3 Responses L-2021-144, Subsequent License Renewal Application-Aging Management Requests for Additional Information (RAI) Set 2 Responses2021-08-11011 August 2021 Subsequent License Renewal Application-Aging Management Requests for Additional Information (RAI) Set 2 Responses L-2021-116, Subsequent License Renewal Application Environmental Report Review Requests for Confirmation Of/Additional Information (Rci/Ral) Set Response2021-06-10010 June 2021 Subsequent License Renewal Application Environmental Report Review Requests for Confirmation Of/Additional Information (Rci/Ral) Set Response NRC 2020-0044, Response to Request for Additional Information Request for Exemption from 10 CFR 73, Appendix B, Section VI Regarding Annual Force-On-Force Exercise2020-12-0808 December 2020 Response to Request for Additional Information Request for Exemption from 10 CFR 73, Appendix B, Section VI Regarding Annual Force-On-Force Exercise NRC 2020-0024, Response to Request for Additional Information Request for Exemption from Certain Operator Requalification Requirements2020-08-17017 August 2020 Response to Request for Additional Information Request for Exemption from Certain Operator Requalification Requirements NRC 2019-0042, NextEra Energy Point Beach, LLC, Relief Request 1-RR-13 and 2-RR-13, Response to Request for Additional Information2019-10-17017 October 2019 NextEra Energy Point Beach, LLC, Relief Request 1-RR-13 and 2-RR-13, Response to Request for Additional Information NRC-2018-0050, Response to Request for Additional Information Regarding License Amendment Request 288, Request to Extend Containment Leakages Rate Test Frequency2018-11-16016 November 2018 Response to Request for Additional Information Regarding License Amendment Request 288, Request to Extend Containment Leakages Rate Test Frequency NRC 2018-0044, Supplement to Response to Request for Additional Information Regarding License Amendment Request 287, Application to Adopt 10 CFR 50.69, Risk Informed Categorization and Treatment of Structures, ...2018-09-28028 September 2018 Supplement to Response to Request for Additional Information Regarding License Amendment Request 287, Application to Adopt 10 CFR 50.69, Risk Informed Categorization and Treatment of Structures, ... NRC 2018-0038, Response to Request for Additional Information Regarding License Amendment Request 287, Application to Adopt 10 CFR 50.69, Risk Informed Categorization and Treatment of Structures, System, and Components (Sscs) for Nuclear2018-08-10010 August 2018 Response to Request for Additional Information Regarding License Amendment Request 287, Application to Adopt 10 CFR 50.69, Risk Informed Categorization and Treatment of Structures, System, and Components (Sscs) for Nuclear NRC 2018-0014, NextEra Energy Point Beach, LLC, Construction Truss License Amendment Request 278, Response to Request for Additional Information2018-04-12012 April 2018 NextEra Energy Point Beach, LLC, Construction Truss License Amendment Request 278, Response to Request for Additional Information L-2018-068, Florida Power and Light Co. - Response to Request for Additional Information Re Decommissioning Funding Plan Updates for Independent Spent Fuel Storage Installations2018-04-0303 April 2018 Florida Power and Light Co. - Response to Request for Additional Information Re Decommissioning Funding Plan Updates for Independent Spent Fuel Storage Installations ML17363A1452017-12-21021 December 2017 Response to Request for Additional Information Regarding License Amendment Request 286, Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactor NRC 2017-0052, Supplement to LAR 287, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Plants2017-10-26026 October 2017 Supplement to LAR 287, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Plants NRC 2017-0041, to License Amendment Request 286, Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors2017-08-21021 August 2017 to License Amendment Request 286, Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors NRC 2017-0010, Response to Final Request for Additional Information Steam Generator License Amendment Request for H* Alternate Repair Criteria for Steam Generator Tube Sheet Expansion Region2017-04-20020 April 2017 Response to Final Request for Additional Information Steam Generator License Amendment Request for H* Alternate Repair Criteria for Steam Generator Tube Sheet Expansion Region NRC 2017-0008, Response to Final Request for Additional Information on Steam Generator Tube Inspection Report2017-02-23023 February 2017 Response to Final Request for Additional Information on Steam Generator Tube Inspection Report L-2016-137, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage...2016-12-15015 December 2016 Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage... NRC 2016-0048, Response to Request for Additional Information Regarding LAR 280 - Removal of Completed License Conditions and Change to the Ventilation Filter Testing Program2016-11-0404 November 2016 Response to Request for Additional Information Regarding LAR 280 - Removal of Completed License Conditions and Change to the Ventilation Filter Testing Program L-2016-188, Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools, Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f)2016-11-0303 November 2016 Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools, Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) NRC-2016-0033, Response to Request for Additional Information, License Amendment Request 279, Elimination of Technical Specification Section 3.7.14, Primary Auxiliary Building Ventilation2016-07-27027 July 2016 Response to Request for Additional Information, License Amendment Request 279, Elimination of Technical Specification Section 3.7.14, Primary Auxiliary Building Ventilation NRC 2016-0029, Response to Request for Additional Information Regarding License Amendment Request 280 - Removal of Completed License Conditions and Change to the Ventilation Filter Testing Program2016-07-11011 July 2016 Response to Request for Additional Information Regarding License Amendment Request 280 - Removal of Completed License Conditions and Change to the Ventilation Filter Testing Program NRC 2016-0012, Response to Request for Additional Information, License Amendment Request 271 Associated with NFPA 8052016-04-0707 April 2016 Response to Request for Additional Information, License Amendment Request 271 Associated with NFPA 805 NRC 2016-0008, Response to Request for Additional Information on NFPA 805 License Amendment Request 2712016-02-22022 February 2016 Response to Request for Additional Information on NFPA 805 License Amendment Request 271 NRC 2016-0006, License Amendment Request 277. Revision to Staff Augmentation Times in the Emergency Plan, Supplemental Response to Request for Additional Information No. 5 -Correction to Table 5.12016-02-0909 February 2016 License Amendment Request 277. Revision to Staff Augmentation Times in the Emergency Plan, Supplemental Response to Request for Additional Information No. 5 -Correction to Table 5.1 NRC 2016-0003, License Amendment Request 277, Revision to Staff Augmentation Times in the Plant Emergency Plan, Supplemental Response to Request for Additional Information No. 52016-01-26026 January 2016 License Amendment Request 277, Revision to Staff Augmentation Times in the Plant Emergency Plan, Supplemental Response to Request for Additional Information No. 5 NRC 2015-0068, Request for Additional Information for Relief Request 2-RR-11 - MF66152015-11-19019 November 2015 Request for Additional Information for Relief Request 2-RR-11 - MF6615 NRC-2015-0069, Response to Request for Information Supporting Flooding Hazards Reevaluation Report Audit2015-11-0606 November 2015 Response to Request for Information Supporting Flooding Hazards Reevaluation Report Audit 2023-08-07
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October 1, 2021 L-2021-174 10 CFR 54.17 U.S. Nuclear Regulatory Commission Attention: Document Control Desk 11545 Rockville Pike One White Flint North Rockville, MD 20852-2746 Point Beach Nuclear Plant Units 1 and 2 Dockets 50-266 and 50-301 Renewed License Nos. DPR-24 and DPR-27 SUBSEQUENT LICENSE RENEWAL APPLICATION - AGING MANAGEMENT REQUEST FOR ADDITIONAL INFORMATION (RAI) SET 9 RESPONSE
References:
- 1. NextEra Energy Point Beach, LLC (NEPB) Letter NRC 2020-0032 dated November 16, 2020, Application for Subsequent Renewed Facility Operating Licenses (ADAMS Package Accession No. ML20329A292)
- 2. U.S. Nuclear Regulatory Commission (NRC) Letter dated January 15, 2021, Point Beach Nuclear Plant, Units 1 and 2 - Determination of Acceptability and Sufficiency for Docketing, Proposed Review Schedule, and Notice of Opportunity to Request a Hearing Regarding the NextEra Energy Point Beach, LLC Application for Subsequent License Renewal (EPID No. L-2020-SLR-0002)
(ADAMS Accession No. ML21006A417)
- 3. NRC Letter dated January 15, 2021, Point Beach Nuclear Plant, Units 1 and 2 - Aging Management Audit Plan Regarding the Subsequent License Renewal Application Review (ADAMS Accession No. ML21007A260)
- 4. U.S. Nuclear Regulatory Commission Meeting with NextEra Energy Concerning the Point Beach Subsequent License Renewal Application Review - June 3, 2021 Public Meeting (ADAMS Accession No. ML21148A116)
- 5. NEPB Letter L-2021-144 dated August 11, 2021, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 2 Responses (ADAMS Accession No. ML21223A308)
- 6. NRC Email and Attachment dated September 2, 2021, Point Beach SLRA Safety RAI Set 9 Final (ADAMS Accession Nos. ML21273A023, ML21273A022)
NEPB, owner and licensee for Point Beach Nuclear Plant (PBN) Units 1 and 2, has submitted a subsequent license renewal application (SLRA) for the Facility Operating Licenses for PBN Units 1 and 2 (Reference 1).
On January 15, 2021, the NRC determined that NEPBs SLRA was acceptable and sufficient for docketing (Reference 2), and on January 15, 2021 issued the regulatory audit plan for the aging management portion of the SLRA review (Reference 3). Based on the information exchanged and discussions held during the public meeting held on June 3, 2021 (Reference 4), and NEPBs responses to RAIs B.2.3.27-1 and B.2.3.27-4 (Reference 5 Attachments 13 and 16), the NRC issued its Set 9 RAI to NEPB (Reference 6). The attachment to this letter provides the response to this follow-up information request.
NextEra Energy Point Beach, LLC 6610 Nuclear Road, Two Rivers, WI 54241
Document Control Desk L-2021-174 Page 2 For ease of reference, the index of attached information is provided on page 3 of this letter.
Should you have any questions regarding this submittal, please contact me at (561) 304-6256 or William.Maher@fpl.com.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on the 1st day of October 2021.
Sincerely, William Digitally signed by William Maher DN: cn=William Maher, o=Nuclear, ou=Nuclear Licensing Projects, Maher email=william.maher@fpl.com, c=US Date: 2021.10.01 08:14:08 -04'00' William D. Maher Licensing Director - Nuclear Licensing Projects Cc: Administrator, Region III, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC Public Service Commission Wisconsin
Document Control Desk L-2021-174 Page 3 Attachment Index Attachment RAI No. Subject No.
1 B.2.3.27-1a Cathodic Protection for Buried Steel Piping/Preventive Action Category E
Point Beach Nuclear Plant Units 1 and 2 Dockets 50-266 and 50-301 NEPB Response to NRC RAI No. B.2.3.27-1a L-2021-174 Attachment 1 Page 1 of 10
- 1. SLRA Section B.2.3.27, Buried and Underground Piping and Tanks Note: This is a follow-up RAI to address the applicants responses to RAIs B.2.3.27-1 and B.2.3.27-4, dated August 11, 2021 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML21223A308).
Regulatory Basis:
Section 54.21(a)(3) of Title 10 of the Code of Federal Regulations (10 CFR) requires an applicant to demonstrate that the effects of aging for structures and components will be adequately managed so that the intended function(s) will be maintained consistent with the current licensing basis for the period of extended operation. One of the findings that the U.S. Nuclear Regulatory Commission (NRC) staff must make to issue a renewed license (10 CFR 54.29(a)) is that actions have been identified and have been or will be taken with respect to managing the effects of aging during the period of extended operation on the functionality of structures and components that have been identified to require review under 10 CFR 54.21, such that there is reasonable assurance that the activities authorized by the renewed license will continue to be conducted in accordance with the current licensing basis. In order to complete its review and enable it to make a finding under 10 CFR 54.29(a), the staff requires additional information in regard to the matters described below.
RAI B.2.3.27-1a [Cathodic Protection for Buried Steel Piping/Preventive Action Category E]
Background:
SLRA Section B.2.3.27, Buried and Underground Piping and Tanks, states, in part, that [t]he PBN Buried and Underground Piping and Tanks AMP [aging management program], with enhancements, will be consistent with exception [not related to the subject RAI] with the 10 elements of NUREG-2191 [Generic Aging Lessons Learned for Subsequent License Renewal (GALL-SLR) Report],Section XI.M41, Buried and Underground Piping and Tanks.
The applicants responses to RAIs B.2.3.27-1 and B.2.3.27-4 state, in part, the following:
- (RAI B.2.3.27-1 response) [t]he 2015 cathodic protection survey for PBN states that the following buried piping systems have cathodic protection: circulating water supply and return, service water supply and return, fire protection water, fuel oil, and propane system lines. However, not all of these buried piping systems are completely cathodically protected. No activities are currently planned to increase the coverage of cathodic protection system to 100 percent of the buried SLR [subsequent license renewal]-scope piping.
- (RAI B.2.3.27-4 response) [s]ince not all of the buried piping within the scope of SLR is cathodically protected and no activities are planned to increase the cathodic protection coverage to 100 percent, a clarification is added to state that buried SLR-scope piping will be classified as Category E, unless a reevaluation
Point Beach Nuclear Plant Units 1 and 2 Dockets 50-266 and 50-301 NEPB Response to NRC RAI No. B.2.3.27-1a L-2021-174 Attachment 1 Page 2 of 10 based on future OE [operating experience] and soil conditions, as defined in NUREG 2191, Table XI.M41-2, [Inspection of Buried and Underground Piping and Tanks,] determines that another Preventive Action Category, such as Category F, is more applicable. Preventive Action Category C will not be used.
- (RAI B.2.3.27-1 response) [a] 1992 analysis of soil samples was obtained during the installation of 4 groundwater monitoring wells in the Unit 1 and Unit 2 facades, near the containment structures. The soil samples were extracted every 5 feet during the well borings and the samples were analyzed for pH, resistivity, and chlorides. The samples had an average resistivity of 16,740 ohm-cm, which was considered mildly corrosive per the sampling manual used, Corrosion Control, Air Force Manual (AFM), No. 88-9. The average pH was 9.52, which was considered to be within the optimum range of 8.5 to 11.0. The average amount of chlorides was approximately 59 ppm, which was well below the 500 ppm minimum for an aggressive chloride environment.
- (RAI B.2.3.27-1 response) [a] 2009 analysis of soil samples in the immediate vicinity of the buried fire protection system piping was performed after the piping had been excavated for 10-year inspections. The sample results indicated that resistivity was within the 13,800-16,600 Ohm-cm range, redox potential had a range of 81.9-172 mV [millivolts], the soil pH was 7.9, chlorides were measured at 31.8 mg/kg, sulfides were within a range of 11.6-13.4 mg/kg, and moisture content was at 19.1 percent. The associated action request (AR) stated that the soil sample results proved that the soil was nonaggressive.
- (RAI B.2.3.27-1 response) [a] review of PBN plant-specific operating experience (OE) spanning the 10-year operating period prior to January 1, 2020, was performed and was documented in SLRA Section B.2.3.27. The OE review was inclusive of all buried components, including components outside the scope of SLR. No aging-related failures were identified for buried piping or tank components. The OE review indicated that when excavations were performed in 2009 and 2016, no evidence of wall loss was identified.
GALL-SLR Report Table XI.M41-2 states that Preventive Action Category E applies when a cathodic protection system has been installed but all or portions of the piping covered by that system fail to meet any of the criteria of Preventive Action Category C piping, provided (a) coatings and backfill are provided in accordance with the preventive actions program element of this AMP; (b) plant-specific OE is acceptable (i.e., no leaks in buried piping due to external corrosion, no significant coating degradation or metal loss in more than 10 percent of inspections conducted); and (c) soil has been determined to not be corrosive.
GALL-SLR Report Table XI.M41-2 references American Water Works Association (AWWA) C105, Polyethylene Encasement for Ductile-Iron Pipe Systems, Table A.1, Soil-Test Evaluation, with respect to determining soil corrosivity. AWWA C105, Table A.1 uses the soil parameters of soil resistivity, pH, redox potential, sulfides, and moisture to determine the overall soil corrosivity index.
Point Beach Nuclear Plant Units 1 and 2 Dockets 50-266 and 50-301 NEPB Response to NRC RAI No. B.2.3.27-1a L-2021-174 Attachment 1 Page 3 of 10 Issue:
The responses to the RAIs B.2.3.27-1 and B.2.3.27-4 did not quantify the coverage of the cathodic protection system with respect to in-scope buried steel piping. Without this information, the NRC staff cannot make a reasonable assurance finding with respect to whether Preventive Action Category E is appropriate for in-scope buried steel piping.
The staff notes that Preventive Action Category E applies when a cathodic protection system has been installed but fails to meet any of the criteria of Preventive Action Category C piping. It was not the staffs intent that Preventive Action Category E would be used where cathodic protection was not installed.
The staff also notes the following: (a) the 1992 soil analysis does not provide results related to redox potential, sulfides, or moisture; and (b) these soil parameters are cited in AWWA C105, Table A.1 to determine the overall soil corrosivity index for steel components.
Request:
Provide additional information quantifying the coverage of the cathodic protection system with respect to in-scope buried steel piping. If cathodic protection will not be provided for a significant majority of in-scope buried steel piping, provide additional technical justification for why cathodic protection is not necessary (e.g., the number of inspections performed on buried steel piping between 2009 and 2016, whether these inspections were performed on cathodically protected or non-cathodically protecting piping, number of soil analyses performed in 1992 and 2009, location of the soil samples with respect to in-scope buried steel piping, discussion of external surface loss of material rates for buried steel piping).
NEPB Response:
The buried steel piping in the scope of the PBN Buried and Underground Piping and Tanks AMP includes service water, fire protection and fuel oil. Based on the potentials measured with the portable reference cell (PRC) (Cu/CuSO4 cell) as part of the PBN cathodic protection (CP) survey performed in 2015, a conclusion can be drawn that the buried piping located in the area between the intake structure and the turbine building on the east side of the plant has adequate CP coverage. The buried steel piping located at all other areas of the plant have minimal to no coverage. Accordingly, based on the total linear feet of in-scope buried steel piping for the plant site, approximately 20% of the piping has CP coverage. However, the piping on the east side of the plant could be considered to have at least 80% coverage.
Table 1 provides a summary of both in-scope and non-in-scope buried steel (including cast iron and ductile iron) piping inspections that have been performed at PBN to date, a majority of which, as noted in column four, can be considered to have no CP coverage.
Point Beach Nuclear Plant Units 1 and 2 Dockets 50-266 and 50-301 NEPB Response to NRC RAI No. B.2.3.27-1a L-2021-174 Attachment 1 Page 4 of 10 Table 1 - Buried Steel Piping Inspections Date of Components Type of CP Coverage Results Inspection Inspected Inspection The excavated piping was coated with coal-tar epoxy. Coating was intact on about 80% of the pipe, hard and tightly adhering.
Numerous rocks and stones from backfill were embedded in the coating. The bottom 20% of the piping did not appear to be coated. Exposed surfaces (uncoated) were visually inspected. A dark magnetite oxide layer was on the exposed Fire piping, which is consistent with a Protection Visual low-oxygen, low-corrosive No (West side of environment. No pitting was 8/2009 Ring Header Hardness plant) identified nor was there any Section 3B Soil (SLR scope) significant external wall degradation. Soil samples demonstrated a low-corrosivity environment (13,800 - 16,600 ohm-cm Resistivity, 7.9 pH, 31.8 mg/kg Chlorides). The excavation exposed less than 10 feet of the piping due to the proximity to the road and the short length of this piping segment. Hardness testing was performed indicating no presence of selective leaching.
Conventional UT was performed near the GW collars and did not reveal any internal wall loss. GW identified one section 2 feet 11 inches beyond the curve north where there was a coating anomaly. The approximate Service Ultrasonic location of the anomaly was Water Return (UT) Yes(1) (East side of where there is a sleeve/support 11/2011 for the piping where it travels Header Guided plant)
(SLR scope) Wave (GW) through the Unit 2 Turbine Hall foundation. A total of 18 feet of the piping was inspected with GW representing 11.5% of the entire return header.
Point Beach Nuclear Plant Units 1 and 2 Dockets 50-266 and 50-301 NEPB Response to NRC RAI No. B.2.3.27-1a L-2021-174 Attachment 1 Page 5 of 10 Date of Components Type of CP Coverage Results Inspection Inspected Inspection 15 feet of piping (10 feet for section 2 and 5 feet for section 2A) were visually inspected and supplemented with radiography and hardness testing. The results indicated that the internal cement liner was adhered to the piping and there was no external Fire pitting/general corrosion. Based Visual Protection on the visual inspection, the Radiography No (South side of 6/2012 Ring Header coating on piping was in excellent (RT) plant)
Section 2A, 2 condition. Hardness testing was Hardness (SLR scope) performed on the top of an uncoated mechanical flange which indicated no presence of selective leaching. Other exposed systems were visually inspected during this excavation and were found to be in good condition.
10 feet of 6-inch diameter coated Drainage and cast iron piping was visually Sanitary inspected with supplemental RT Waste - performed. The external coating Abandoned was degraded with tape edges Turbine Hall Visual No (South side of peeled back, metal exposed, and 6/2012 had poor adhesion. The piping to Old Sewer RT plant)
Treatment / had surface rust and exterior Segment 2 pitting and mill scale present.
(Non-SLR Since this piping is abandoned, scope) no remaining life projection was made.
10 feet of 6-inch diameter uncoated cast iron piping was visually inspected with supplemental RT performed. The Drainage and external portion of the pipe Sanitary appeared to be in relatively good Waste - shape which included some Water general surface rust with minor Visual No (South side of exterior pitting. This piping was 6/2012 Treatment RT plant) estimated to have a general Filter Backwash corrosion rate of 0.00162 in/year (Non-SLR and is expected to function well scope) beyond the period of extended operation (PEO) end date.
Point Beach Nuclear Plant Units 1 and 2 Dockets 50-266 and 50-301 NEPB Response to NRC RAI No. B.2.3.27-1a L-2021-174 Attachment 1 Page 6 of 10 Date of Components Type of CP Coverage Results Inspection Inspected Inspection 10 feet of 1-inch diameter uncoated carbon steel piping was Service Air - visually inspected with Fuel Oil supplemental RT performed. No Pumphouse measurable external corrosion Visual No (South side of was identified. The rate of 6/2012 to Turbine RT plant) corrosion was determined to be Hall (Non-SLR very small and the remaining life scope) of the common-Unit pipe would function well beyond the PEO end date.
A 6-foot horizontal section and a 4-foot vertical section of 6-inch diameter cement lined cast iron fire piping were inspected.
Original installation of this piping included a heavy plastic liner around the piping, thus the piping was not in direct contact with the Fire Header surrounding soil. There was a No (North side of thin black coating (most likely 4/2015 6-KC-1 Visual plant) bituminous or asphaltic) on the (SLR scope) piping that was in very good condition. There were no obvious holidays in the coating and there was no evidence of external wall loss. The internal surface was also inspected and the cement lining was fully intact throughout the length of the piping.
The valve and piping were in very Fire good condition. The paint was Protection still fully adhered both inside and Diesel out on the valve. The external tar Generator coating was still intact, with no No (North side of discernible wall loss. Internally, 11/2016 Bldg. West Visual plant) the cement lining was intact with Header Cross uniform wall thickness and no Connect signs of degradation. The soil (SLR scope) conditions were uniform from top to bottom.
Point Beach Nuclear Plant Units 1 and 2 Dockets 50-266 and 50-301 NEPB Response to NRC RAI No. B.2.3.27-1a L-2021-174 Attachment 1 Page 7 of 10 Date of Components Type of CP Coverage Results Inspection Inspected Inspection The emergency fuel oil storage tank, T-072, was internally cleaned and visually inspected within the tank interior and the UT non-buried portion of the tank T-072, Visual (tank exterior. UT wall thickness Emergency interior and measurements were obtained for 11/2020 Fuel Oil No exterior of the tank from the interior. The Storage Tank non-buried corrosion rate was determined to (SLR scope) portion) be 0.31 mils/yr and the calculated remaining life was determined to be well beyond the PEO end date.
Notes:
- 1. Two of the test points near the service water piping were less than -850 mV but still greater than -800 mV. Consistent with Element 6, Item m.ii, of GALL-SLR XI.M41, this polarized potential was considered acceptable based on the generally high resistivity of the soil.
Since CP coverage is not provided for all of the in-scope buried steel piping, the following discussion provides justification for why additional CP coverage is not necessary:
Fire Protection Piping Installed per NFPA 24 As mentioned in the response to Set 2 RAI B.2.3.27-2 (Reference 3), since the fire protection piping was installed per the requirements of NFPA 24 and the piping will be subject to periodic flow testing in accordance with NFPA 25, section 7.3.1, per NUREG-2191,Section XI.M41, Element 2 Item g.iii, preventive actions beyond those in NFPA 24 need not be provided. Therefore, a CP system is unnecessary for the buried fire main piping. Additionally, the external surface of this piping will be periodically inspected as part of the PBN Buried and Underground Piping and Tanks AMP.
Soil Analyses The results of the soil sample analyses performed in 1991 (note the soil sample was obtained in 1991 but the results were published in 1992), 2009, and 2012 are discussed in the response to Set 6 RAI B.2.3.21-2 (Reference 4). Additionally, per NUREG-2191,Section XI.M41, Element 2 Item g.ii backfill quality was described by plant records as stated in the response to Set 2 RAI B.2.3.27-4 (Reference 3) and excavations inspections have examined the backfill. Each of these soil sample analyses described the soil as having low aggressiveness. The soil sample aggressiveness is confirmed by comparing soil parameters to AWWA C105, Table A.1 (Reference 5). The location of these soil samples with respect to in-scope buried steel piping is as follows:
Point Beach Nuclear Plant Units 1 and 2 Dockets 50-266 and 50-301 NEPB Response to NRC RAI No. B.2.3.27-1a L-2021-174 Attachment 1 Page 8 of 10
- The 1991 soil samples were obtained during the installation of 4 groundwater monitoring wells in the Unit 1 and Unit 2 facades, near the containment structures. Although not adjacent to any specific buried piping, these samples were in the vicinity of buried fire protection piping. The soil sample parameters can be scored as follows with respect to AWWA C105:
o Resistivity: 16,740 ohm-cm average; (>3,000 ohm-cm; 0 points) o pH: 9.52 average; (>8.5; 3 points) o Redox potential: 0.13 standard hydrogen electrode (SHE); (Selected 50 to +100 mV based on 2009 results; 3.5 points) o Sulfides: Sulfides were not measured, but the sulfate level was 360 ppm.
(Assumed Trace; 2 points) o Moisture: 21.6% average (Assumed Fair drainage, generally moist; 1 point)
Based on assumptions made for redox potential, sulfides, and moisture content, the soil sample would have an approximate score of 9.5 points with respect to AWWA C105. Therefore, there is reasonable assurance that the soil from these samples can be treated as mildly corrosive and note that the samples were not adjacent to any specific pipe.
- The 2009 soil sample analysis was adjacent to the buried fire protection piping section 3B (just outside the required backfill). This piping is on the west side of the plant and is considered to have minimal or no CP coverage.
The soil sample parameters are listed below with the respective AWWA C105 category and points within parentheses:
o Resistivity: 13,800-16,600 ohm-cm; (>3,000 ohm-cm; 0 points) o pH: 7.9; (7.5-8.5; 0 points) o Redox potential: 81.9-172 mV; (50 to +100 mV; 3.5 points) o Sulfides: 11.6-13.4 mg/kg, but the AR noted that sample data was taken outside of the EPA recommended hold times. Trace was used in the BP Works V1.0A simulation. (Selected Positive for conservatism; 3.5 points) o Moisture: 19.1% (Assumed Fair drainage, generally moist; 1 point)
The soil sample would score 8.0 points with respect to AWWA C105. Per AWWA C105, Section A.2, since the total is not equal to 10 points or higher, the soil is not considered corrosive to ductile-iron pipe.
- The 2012 soil sample analysis was adjacent to the buried fire protection piping sections 2 and 2A (just outside the required backfill). This piping is on the south side of the plant and is considered to have minimal or no CP coverage. The soil sample parameters can be scored as follows with respect to AWWA C105:
o Resistivity: 6,740 ohm-cm; (>3,000 ohm-cm; 0 points) o pH: 8.6; (>8.5; 3 points)
Point Beach Nuclear Plant Units 1 and 2 Dockets 50-266 and 50-301 NEPB Response to NRC RAI No. B.2.3.27-1a L-2021-174 Attachment 1 Page 9 of 10 o Redox potential: 107 mV; (>100 mV; 0 points) o Sulfides: 1.2 mg/kg dry weight which was below the reporting limit of 3.5 mg/kg. (Trace; 2 points) o Moisture: 7.9% (Assumed Fair drainage, generally moist; 1 point)
The soil sample would score 6.0 points with respect to AWWA C105. Per AWWA C105, Section A.2, since the total is not equal to 10 points or higher, the soil is not considered corrosive to ductile-iron pipe.
In summary, the soil near the buried piping considered to have minimal or no CP coverage is of low aggressiveness. Additionally, the in-scope buried steel piping is installed substantially above ground water level minimizing exposure to moisture.
Inspections on Buried Piping As previously stated in the response to Set 2 RAI B.2.3.27-4 (Reference 3), per NUREG-2191,Section XI.M41, Element 2 Item g.iv, a review of PBN plant-specific operating experience (OE) spanning the 10-year operating period prior to January 1, 2020 was performed and documented in SLRA Section B.2.3.27. The OE review was inclusive of all buried components, including components outside the scope of SLR. No aging-related failures were identified for buried piping or tank components.
As shown in Table 1, of the 9 buried steel piping and tank inspections documented between 2009 and 2020, 8 of these inspections were performed on components with minimal or no CP coverage. For the one inspection performed on the service water piping considered to have CP coverage, no discernible wall loss was identified. For the cast iron drainage and sanitary waste piping between the turbine hall and the old sewer treatment facility, external pitting was identified but no corrosion rate was required to be calculated, since it had been abandoned. The external corrosion for the non-abandoned uncoated drainage and sanitary and waste piping was low. In addition, T-072, the emergency fuel oil storage tank, was found to have minor internal/external corrosion. This piping and structure are considered to have minimal or no CP coverage. For the service air piping and fire protection piping, no discernible wall loss was identified, and therefore, no corrosion rate was calculated.
Since the projected remaining life of inspected piping and tank goes well beyond the PEO end date, the risk of component failure or failing to meet wall thickness criteria prior to the respective pre-SPEO inspections and component life re-evaluations remains low.
The AMP basis document did not take any exception to NUREG-2191,Section XI.M41, Element 4; therefore, piping inspection locations are selected based on risk (i.e., susceptibility to degradation and consequences of failure), and characteristics such as coating type (i.e., material type), coating condition, CP system efficacy, backfill characteristics, soil resistivity, pipe contents, and pipe function are considered. CP system efficacy, as determined by historical and the most recent CP survey reports, will be a factor in selection of pre-SPEO and SPEO inspection locations.
Point Beach Nuclear Plant Units 1 and 2 Dockets 50-266 and 50-301 NEPB Response to NRC RAI No. B.2.3.27-1a L-2021-174 Attachment 1 Page 10 of 10 In conclusion, none of the piping within the scope of SLR showed discernible wall loss on the piping exterior, and the only measurable wall loss was on the emergency fuel oil storage tank, T-072, and the non-SLR scope drainage and sanitary piping which was minimal. Therefore, there is reasonable assurance that performing the number of inspections recommended by NUREG-2191, Table XI.M41-2 Preventive Action Category E will be adequate for identifying and managing aging of such piping. No additional CP installation nor supplementary inspections in addition to those committed to in the previous RAI responses need to be performed for the buried steel (including cast iron/ductile iron) piping. The SLRA commitments include provisions to inspect more frequently or expand inspection samples if the inspected piping fails to meet acceptance criteria or is projected to not meet acceptance criteria.
References:
- 1. Point Beach Nuclear Plant Units 1 and 2 Subsequent License Renewal Application (Public Version), Enclosure 3, Attachment 1, dated November 2020 (ADAMS Accession No. ML20329A247)
- 2. NextEra Energy Point Beach, LLC (NEPB) Letter to NRC L-2021-081 dated April 21, 2021, Subsequent License Renewal Application - Aging Management Supplement 1 (ADAMS Accession No. ML21111A155)
- 3. NextEra Energy Point Beach, LLC (NEPB) Letter to NRC L-2021-144 dated August 11, 2021, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 2 Responses (ADAMS Accession No. ML21223A308)
- 4. NextEra Energy Point Beach, LLC (NEPB) Letter to NRC L-2021-157 dated September 10, 2021, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 6 Responses (ADAMS Accession No. ML21253A140)
- 5. ANSI/AWWA C105/A21.5-18, AWWA Standard for Polyethylene Encasement for Ductile-Iron Pipe Systems, American Water Works Association, Denver Colorado, September 2018.
Associated SLRA Revisions:
None.