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Category:Letter type:L
MONTHYEARL-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-2024-007, Inservice Inspection Program Owner'S Activity Report (OAR-1)2024-01-18018 January 2024 Inservice Inspection Program Owner'S Activity Report (OAR-1) 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-2023-166, Turkey Points Units 3 and 4, Correction to the 2022 Annual Radioactive Effluent Release Report2023-12-0606 December 2023 Turkey Points Units 3 and 4, Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-172, 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-2023-146, Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-078, License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles2023-11-15015 November 2023 License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles L-2023-077, License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis2023-10-11011 October 2023 License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis L-2023-110, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-08-25025 August 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2023-115, Inservice Inspection Program Owner'S Activity Report (OAR-1)2023-08-21021 August 2023 Inservice Inspection Program Owner'S Activity Report (OAR-1) 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-2023-094, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-07-27027 July 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project 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-2023-086, Request Temporary Suspension of Turkey Point License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation.2023-06-28028 June 2023 Request Temporary Suspension of Turkey Point License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation. L-2023-074, Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update2023-06-0202 June 2023 Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update L-2023-069, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-05-31031 May 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2023-072, Preparation and Scheduling of Operator Licensing Examinations2023-05-22022 May 2023 Preparation and Scheduling of Operator Licensing Examinations 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-2023-061, 2022 Annual Radiological Environmental Operating Report2023-05-12012 May 2023 2022 Annual Radiological Environmental Operating Report L-2023-062, Cycle 33 Core Operating Limits Report2023-04-27027 April 2023 Cycle 33 Core Operating Limits Report L-2023-060, Radiological Emergency Plan, Revision 752023-04-26026 April 2023 Radiological Emergency Plan, Revision 75 L-2023-054, Submittal of Periodic Reports2023-04-12012 April 2023 Submittal of Periodic Reports L-2023-049, Correction to U4R33 Steam Generator Tube Inspection Report2023-03-30030 March 2023 Correction to U4R33 Steam Generator Tube Inspection 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-2023-025, 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-2023-040, Response to Requests for Additional Information (Rals) and Requests for Confirmation of Information (Rc Ls) Following Regulatory Audit of Subsequent License Renewal Application2023-03-0303 March 2023 Response to Requests for Additional Information (Rals) and Requests for Confirmation of Information (Rc Ls) Following Regulatory Audit of Subsequent License Renewal Application L-2023-037, Annual Radioactive Effluent Release Report2023-03-0101 March 2023 Annual Radioactive Effluent Release Report L-2023-017, Radiological Emergency Plan Revision 73 and Revision 7 42023-02-17017 February 2023 Radiological Emergency Plan Revision 73 and Revision 7 4 L-2023-010, Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of RPS / ESFAS / Nis2023-02-10010 February 2023 Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of RPS / ESFAS / Nis L-2023-004, Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of Huma Factors Results2023-01-17017 January 2023 Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of Huma Factors Results 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-2022-181, Response to Request for Additional Information Regarding License Amendment Request for the Technical Specifications Conversion to NUREG-1431, Revision 52022-12-0101 December 2022 Response to Request for Additional Information Regarding License Amendment Request for the Technical Specifications Conversion to NUREG-1431, Revision 5 L-2022-182, Emergency Response Data System (Eros) Changes2022-11-17017 November 2022 Emergency Response Data System (Eros) Changes 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-2022-171, 10 CFR 50.59(d)(2) Summary Report2022-10-20020 October 2022 10 CFR 50.59(d)(2) Summary Report L-2022-167, Submittal of Periodic Reports2022-10-13013 October 2022 Submittal of Periodic Reports L-2022-166, Response to Request for Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement2022-10-0505 October 2022 Response to Request for Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement L-2022-149, U4R33 Steam Generator Tube Inspection Report2022-10-0404 October 2022 U4R33 Steam Generator Tube Inspection 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-2022-148, 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-2022-151, Evacuation Time Estimate Study2022-09-15015 September 2022 Evacuation Time Estimate Study L-2022-142, Revised Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-0042022-08-19019 August 2022 Revised Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-004 L-2022-136, Response to Request for Additional Information Regarding Turkey Point Unit 3 Cycle 32 Steam Generator Tube Inspection Report2022-08-12012 August 2022 Response to Request for Additional Information Regarding Turkey Point Unit 3 Cycle 32 Steam Generator Tube Inspection Report L-2022-109, Inservice Inspection Program - Owner'S Activity Report (OAR-1)2022-06-27027 June 2022 Inservice Inspection Program - Owner'S Activity Report (OAR-1) L-2022-076, Subsequent License Renewal Application - Appendix E Environmental Report Supplement 22022-06-0909 June 2022 Subsequent License Renewal Application - Appendix E Environmental Report Supplement 2 2024-01-25
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARL-2023-078, License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles2023-11-15015 November 2023 License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles L-2023-077, License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis2023-10-11011 October 2023 License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis L-2023-086, Request Temporary Suspension of Turkey Point License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation.2023-06-28028 June 2023 Request Temporary Suspension of Turkey Point License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation. ML23095A0072023-04-0404 April 2023 License Amendment Request Revision 2 for the Technical Specifications Conversion to NUREG-1431 Revision 5 L-2023-010, Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of RPS / ESFAS / Nis2023-02-10010 February 2023 Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of RPS / ESFAS / Nis L-2023-004, Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of Huma Factors Results2023-01-17017 January 2023 Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of Huma Factors Results 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-2022-110, License Amendment Request 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project (Non-Proprietary)2022-08-26026 August 2022 License Amendment Request 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project (Non-Proprietary) ML22243A1622022-08-26026 August 2022 Submittal of License Amendment Request 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project ML21265A3722021-09-23023 September 2021 Improved Technical Specifications Conversion, Volume 1, Revision 0, Application of Selection Criteria to the Turkey Point Nuclear Generating Station Unit 3 and Unit 4 Technical Specifications L-2021-158, Contents of the Turkey Point Nuclear Plant, Units 3 and 4 Improved Technical Specifications (Its) Submittal2021-09-22022 September 2021 Contents of the Turkey Point Nuclear Plant, Units 3 and 4 Improved Technical Specifications (Its) Submittal ML21265A3772021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 6, Revision 0, Section 3.1, Reactivity Control Systems ML21265A3852021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 14, Revision 0, Section 3.9, Refueling Operations ML21265A3812021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 9, Revision 0, Section 3.5, Emergency Core Cooling Systems (ECCS) ML21265A3872021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 16, Revision 0, Section 5.0, Administrative Controls ML21265A3792021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 8, Revision 0, Section 3.3, Instrumentation ML21265A3802021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 9, Revision 0, Section 3.4, Reactor Coolant Systems (RCS) ML21265A3842021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 13, Revision 0, Section 3.8, Electrical Power Systems ML21265A3862021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 15, Revision 0, Section 4.0, Design Features ML21265A3782021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 7, Revision 0, Section 3.2, Power Distribution Limits ML21265A3832021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 12, Revision 0, Section 3.7, Plant Systems ML21265A3752021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 4, Revision 0, Chapter 2.0, Safety Limits (Sls) ML21265A3762021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 5, Revision 0, Section 3.0, LCO and SR Applicability ML21265A3732021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 2, Revision 0, Determination of No Significant Hazards Considerations Generic Changes ML21265A3822021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 11, Revision 0, Section 3.6, Containment Systems ML21265A3742021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 3, Revision 0, Chapter 1.0, Use and Application L-2021-071, License Amendment Request 273, Update Listing of Approved LOCA Methodologies to Adopt Full Spectrum Tm LOCA Methodology2021-04-15015 April 2021 License Amendment Request 273, Update Listing of Approved LOCA Methodologies to Adopt Full Spectrum Tm LOCA Methodology L-2020-157, Supplement to License Amendment Request 264, Adopt Emergency Action Level (EAL) Scheme Described in NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors2020-11-0505 November 2020 Supplement to License Amendment Request 264, Adopt Emergency Action Level (EAL) Scheme Described in NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors L-2020-053, Exigent License Amendment Request 272, One-Time Extension of TS 6.8.4 Steam Generator Inspection Program2020-04-0404 April 2020 Exigent License Amendment Request 272, One-Time Extension of TS 6.8.4 Steam Generator Inspection Program L-2020-003, License Amendment Request 268, Request to Extend Containment Leakage Rate Test Frequency2020-01-27027 January 2020 License Amendment Request 268, Request to Extend Containment Leakage Rate Test Frequency L-2019-203, License Amendment Request 264, Adopt Emergency Action Level (EAL) Scheme Described in NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors.2019-12-0606 December 2019 License Amendment Request 264, Adopt Emergency Action Level (EAL) Scheme Described in NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors. L-2019-192, License Amendment Request 270, Modify Containment Atmosphere Radioactivity Monitoring, Containment Ventilation Isolation and RCS Leakage Detection System Requirements2019-11-0404 November 2019 License Amendment Request 270, Modify Containment Atmosphere Radioactivity Monitoring, Containment Ventilation Isolation and RCS Leakage Detection System Requirements L-2019-005, License Amendment Request 266, Clarify Requirements When One Unit Is Outside the Applicability of Certain Technical Specifications2019-02-14014 February 2019 License Amendment Request 266, Clarify Requirements When One Unit Is Outside the Applicability of Certain Technical Specifications L-2018-219, Supplement to License Amendment Request 265, Revise NFPA 805 License Condition for Reactor Coolant Pump Seals2018-12-0303 December 2018 Supplement to License Amendment Request 265, Revise NFPA 805 License Condition for Reactor Coolant Pump Seals L-2018-203, Supplement to License Amendment Request 257, Modify Emergency Diesel Generator Partial-Load Rejection Surveillance Requirement2018-11-20020 November 2018 Supplement to License Amendment Request 257, Modify Emergency Diesel Generator Partial-Load Rejection Surveillance Requirement L-2018-175, Subsequent License Renewal Application, Safety Review Requests for Additional Information (RAI) Set 5 Responses2018-10-17017 October 2018 Subsequent License Renewal Application, Safety Review Requests for Additional Information (RAI) Set 5 Responses L-2018-170, License Amendment Request 265, Revise NFPA 805 License Condition for Reactor Coolant Pump Seals2018-10-17017 October 2018 License Amendment Request 265, Revise NFPA 805 License Condition for Reactor Coolant Pump Seals L-2018-176, Subsequent License Renewal Application, Responses to the August 2018 NRC On-Site Regulatory Audit Follow-Up Items2018-10-17017 October 2018 Subsequent License Renewal Application, Responses to the August 2018 NRC On-Site Regulatory Audit Follow-Up Items L-2018-177, Subsequent License Renewal Application Safety Review Requests for Confirmation of Information (Rci) Responses2018-10-0909 October 2018 Subsequent License Renewal Application Safety Review Requests for Confirmation of Information (Rci) Responses L-2018-187, Subsequent License Renewal Application Revision to SLRA Section 3.5.2.2.2.6, Reduction of Strength and Mechanical, Properties of Concrete Due to Irradiation2018-10-0505 October 2018 Subsequent License Renewal Application Revision to SLRA Section 3.5.2.2.2.6, Reduction of Strength and Mechanical, Properties of Concrete Due to Irradiation ML18130A4662018-06-12012 June 2018 Amendments Regarding Technical Specifications Pertaining to IST Program and ISI Program Requirements and Surveillance Frequency Control Program Applicability L-2018-049, Application to Add Limiting Condition for Operation (LCO) 3.0.6 to the Technical Specifications2018-05-29029 May 2018 Application to Add Limiting Condition for Operation (LCO) 3.0.6 to the Technical Specifications L-2018-044, License Amendment Request 257, Modify Emergency Diesel Generator Partial-Load Rejection Surveillance Requirement2018-05-14014 May 2018 License Amendment Request 257, Modify Emergency Diesel Generator Partial-Load Rejection Surveillance Requirement L-2018-065, License Amendment Request 258, Revise Reactor Core Safety Limit to Reflect WCAP-17642-PA, Revision 12018-05-0303 May 2018 License Amendment Request 258, Revise Reactor Core Safety Limit to Reflect WCAP-17642-PA, Revision 1 L-2018-082, Turkey Point, Units 3 and 4 - Enclosure 2 to L-2018-082, Applications for Withholding Proprietary Information from Public Disclosure Per 10 CFR 2.390 (Public Version)2018-04-10010 April 2018 Turkey Point, Units 3 and 4 - Enclosure 2 to L-2018-082, Applications for Withholding Proprietary Information from Public Disclosure Per 10 CFR 2.390 (Public Version) L-2018-082, Enclosure 4 to L-2018-082 - Non-Proprietary Reference Documents and Redacted Versions of Proprietary Documents (Public Version)2018-04-10010 April 2018 Enclosure 4 to L-2018-082 - Non-Proprietary Reference Documents and Redacted Versions of Proprietary Documents (Public Version) ML18113A1422018-04-10010 April 2018 Enclosure 2 to L-2018-082, Applications for Withholding Proprietary Information from Public Disclosure Per 10 CFR 2.390 (Public Version) ML18113A1412018-04-10010 April 2018 Enclosure 1 to L-2018-082, Subsequent License Renewal Application, Enclosure Summary ML18113A1342018-04-10010 April 2018 Transmittal of Subsequent License Renewal Application Revision 1 L-2018-086, Subsequent License Renewal Application Appendix E Environmental Report Supplemental Information2018-04-10010 April 2018 Subsequent License Renewal Application Appendix E Environmental Report Supplemental Information 2023-06-28
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Text
FPL 10 CFR §50.55a L-2005-168 SEP 2 3 2005 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555
Subject:
Turkey Point Nuclear Plant Unit 3 Docket No. 50-250 10 CFR 50.55a Request for Temporary Non-Code Repair Spent Fuel Pool Cooling Line (Request No. 6)
Title 10 of the Code of Federal Regulations (10 CFR), Section 50.55a(g) requires that nuclear power facility components must meet the requirements contained in specific editions of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code or Code),Section XI, for Inservice Inspection, and Repair and Replacement Programs.
Specifically, the ASME Code,Section XI, Article IWA-4000 applies to flaws requiring repair.
Pursuant to 10 CFR 50.55a(a)(3)(ii) Florida Power & Light (FPL) requests approval to deviate from the requirements of Article IWA-4000.
On April 19, 2005, a through-wall flaw was detected in a Unit 3 spent fuel pool (SFP) cooling system line. FPL is preparing to perform a permanent ASME Code repair. Until the permanent repair is made, FPL would like to install a temporary non-Code repair to limit leakage from the line. In addition, since the SFP cooling system is not redundant, FPL would like to employ the same temporary non-Code repair, if the permanent repair could not be completed within the projected time at the time the permanent repair is implemented. The continued use of the non-Code repair would allow restoration of the SFP cooling system so that pool temperatures do not rise excessively.
The non-Code repair of the SFP cooling line will be temporary. FPL considers the continued use of the non-Code repair in the event the permanent repair cannot be completed in time to be a prudent contingency measure. The housekeeping burden until the permanent repair is implemented is a hardship and the inability to continue use of the non-Code repair would create a hardship in that the SFP water temperature would increase to the point of boiling without cooling. FPL requests approval of a deviation from the provisions of the ASME Code,Section XI, Article IWA-4000 in that compliance would result in hardship without a compensating increase in the level of quality or safety. The basis for the acceptability of the deviation is contained in Enclosure 1. Enclosure 2 contains additional information regarding repair plans, and flaw examination and evaluation.
an FPL Group company
Florida Power & Light letter L-2005-168 10 CFR 50.55a Request for Temporary Non-Code Repair Spent Fuel Pool Cooling Line Page 2 of 2 FPL is requesting approval for the deviation such that the temporary non-Code repair can be expeditiously implemented and be utilized until the permanent repair is complete. While the permanent repair is currently scheduled for December 2005, it will be completed no later than the next Unit 3 refueling outage currently scheduled for March 2006.
If there are any questions regarding the information contained in this submission, please contact Mr. Walter Parker at 305-246-6632.
Very truly yours, Terry 0. Jones Vice President Turkey Point Nuclear Plant
Enclosures:
- 1) 10 CFR 50.55a Request
- 2) Additional Information cc: Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Nuclear Plant
Florida Power & Light Letter No. L-2005-168 10 CFR 50.55a Request for Temporary Non-Code Repair Spent Fuel Pool Cooling Line (Request No. 6)
Enclosure 1 1.0 Introduction Pursuant to 10 CFR 50.55a(a)(3)(ii), Florida Power & Light (FPL) requests approval to deviate from the requirements of Article IWA-4000 of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code or Code).
On April 19, 2005, a through-wall flaw was detected in a Unit 3 spent fuel pool (SFP) cooling system line. FPL is preparing to perform a permanent ASME Code repair. Until the repair is made, FPL would like to install a temporary non-Code repair to limit leakage from the line. In addition, since the SFP cooling system is not redundant, FPL would employ the same temporary non-Code repair if the permanent repair cannot be completed within the projected time at the time the permanent repair is implemented. The non-Code repair will reduce the housekeeping burden due to leakage and then, if necessary, allow restoration of the SFP cooling system in order that pool temperatures do not rise excessively if the permanent repair cannot be completed during the initial repair attempt.
2.0 ASME Code Component Affected The affected pipe section is at the discharge of the SFP cooling system heat exchanger to the Unit 3 SFP.
The pipe is 8 inch seamless fabricated from ASTM A 312, Type 304 Stainless Steel, Schedule 10S. Design code of record: USAS ANSI B31.1. Code Class 3.
Design temp and pressure: 212TF and 150 psig.
3.0 Applicable Code Edition and Addenda ASME Code,Section XI, 1998 through 2000 Addenda for the repair/replacement program.
4.0 Applicable Code Requirement for Which a Deviation is Requested ASME Code,Section XI, Article IWA-4000 Section XI of the ASME Code specifies Code-acceptable repair methods for flaws that exceed Code-acceptable limits in piping that is in service. A Code repair is required to restore the
Florida Power & Light letter L-2005-168 10 CFR 50.55a Request for Temporary Non-Code Repair Spent Fuel Pool Cooling Line Page 2 of 5 structural integrity of the flawed piping, independent of the operational mode of the plant when the flaw is detected.
5.0 Reason for Request 5.1 Flaw Detection and Hardship Determination On April 19, 2005, a through-wall flaw was detected in a Unit 3 SFP cooling system line.
Leakage from the flaw was approximately 6 cubic centimeters per minute (cc/min) at the time of discovery. The leak rate is gradually increasing. FPL employed ASME Code Case N-513, as approved by the NRC in Regulatory Guide 1.147 and cited in 10 CFR 50.55a(b)(2)(xiii)(A), to evaluate the acceptability of the flaw for continued service until a repair could be made.
FPL intends to perform a permanent Code repair to the affected section of the leaking SFP cooling system line. FPL intends to employ the temporary non-Code repair to minimize leakage until the permanent repair is made. During the implementation of the permanent repair, in the event the repair cannot be completed in the time available, FPL would continue to employ the temporary non-Code repair so that the SFP cooling system could be returned to operation.
The Unit 3 SFP cooling system is not redundant. It must be removed from service in order to drain the leaking portion of the discharge line to perform a permanent repair.
The limited amount of time available to complete the repair is judged to be adequate; however, FPL considers the continued use of the temporary non-Code repair, as a contingency, to be a prudent compensatory measure to ensure continued cooling of the Unit 3 SFP. The non-Code repair consists of a mechanical gasketed clamp that is designed for the service conditions of the piping system. The evaluation of a bounding flaw with the clamp in place assures the structural integrity of the pipe until the permanent repair is complete. Since this type of repair is not allowed by the ASME Code, FPL requests permission to deviate from the Code. The temporary non-Code repair will be employed until the permanent repair is made and will continue to be used in the event the permanent repair cannot be completed in time at the time of the initial repair attempt.
FPL will continue daily visual inspections to monitor any leakage from the temporary repair until the permanent repair is completed.
Florida Power & Light letter L-2005-168 10 CFR 50.55a Request for Temporary Non-Code Repair Spent Fuel Pool Cooling Line Page 3 of 5 Until the permanent repair is made, the temporary non-Code repair will minimize leakage and reduce the housekeeping burden. The inability to employ the temporary non-Code repair creates a hardship without a compensating increase in the level of quality or safety in that additional worker dose is necessary to address housekeeping needs due to leakage.
In addition, the continued use of the non-Code repair will allow restoration of the SFP cooling system in order that pool temperatures do not rise excessively. If the permanent repair could not be completed in time to avoid excessive pool temperature, then compliance with the Code would create a hardship without a compensating increase in the level of quality or safety in that the SFP water temperature could increase to the point of boiling without cooling. The estimated time for the SFP water to reach boiling is 67 hours7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> in December 2005. The estimated time for the pool water to reach the administrative limit of 170TF is 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />. The estimates of the time to perform the various Code repairs vary from 20 to 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />. Additional information on repair options is contained in Section 1.0 of Enclosure 2.
5.2 Root Cause Determination and Flaw Characterization Pinhole Leak Requiring Repair
- The Unit 3 Spent Fuel Pit heat exchanger room is located at elevation 18' and the main entrance door for this room is made of grating steel that exposes the piping within the room to moisture and salt-laden corrosive outdoor environment.
- The flaw in the stainless steel 8-inch pipe is pinhole size (approximately 1/64-inch diameter) and located at the bottom side of the pipe.
- The flaw is local in extent (i.e., not circumferential) and is OD-initiated.
- The flaw is located /2 inch downstream from the flange butt weld for valve 3-820, the SFP heat exchanger outlet valve.
- Leakage volume was minimal at discovery (approximately 6 cc/min).
Based on the above, the cause of pipe wall degradation is judged to be chloride-induced outside diameter (OD)-initiated stress corrosion cracking (SCC). The flaw initiated from the base of the pit that formed on the OD surface of the pipe (pitting is commonly associated with the SCC phenomena).
FPL has performed non-destructive examinations (NDE) in accordance with ASME Code Case N-513 and is monitoring leak rate daily. Visual inspection and dye-penetrant examination in the area of the flaw did not detect additional flaws or general wastage.
The flaw remains bounded by the flaw evaluation discussed in Section 5.3 for a pinhole leak.
Florida Power & Light letter L-2005-168 10 CFR 50.55a Request for Temporary Non-Code Repair Spent Fuel Pool Cooling Line Page 4 of 5 Potential Repair-Induced Flaw FPL's repair process is designed to ensure a reliable permanent Code repair is achieved.
However, there is a remote possibility that performing the branch connection repair method (see Repair Option 1 in Section 1.1 of Enclosure 2) might result in bum-through of the thin-wall Schedule 10S pipe during the welding process.
In order to provide a contingency should this occur with the need to restore operation of the SFP cooling system, FPL has evaluated a bounding case for a potential bum-through.
Since guidance for evaluation of non-planar through-wall flaws is not provided in Code Case N-513, an alternate wall thinning criteria was developed using the "Limits of Reinforcement" rules in Paragraph NB-3640 of the ASME Code, 1989 Edition.
5.3 Flaw Evaluation Pinhole Leak A flaw evaluation was performed in accordance with ASME Code Case N-513. The evaluation used the "through-wall flaw" approach and assumed the pinhole leak to have a planar flaw length of 0.25 inch in the axial or circumferential direction. The analysis yielded an allowable flaw size of 4.93 inches in the axial direction and 14.86 inches in the circumferential direction. Flaw growth to the next refueling outage in March 2006 is predicted as negligible in both the axial and circumferential directions. Therefore, there is adequate margin to the allowable flaw size.
Bum-Through During Repair An approach using "Limits of Reinforcement" described in the ASME Code Section III was used to approximate an allowable through-wall hole diameter. Through-wall pit sizes up to approximately 3.65 inches in diameter can be tolerated for a nominal pipe thickness of 0.148 inch without exceeding ASME Code margins. This is much greater than the assumed pinhole flaw size and bounds the flaw size of a potential bum-through for the installation of a 2-inch diameter branch connection. Flaw growth to the next refueling outage in March 2006 with a larger initial flaw size of 3.65 inches is predicted as negligible in both the axial and circumferential directions. Section 4.0 in Enclosure 2 provides additional detail regarding this approach.
Florida Power & Light letter L-2005-168 10 CFR 50.55a Request for Temporary Non-Code Repair Spent Fuel Pool Cooling Line Page 5 of 5 The area around the bum-through hole will be examined to verify adequate wall thickness and be properly prepared prior to installation of the temporary non-Code repair.
6.0 Duration of Proposed Alternative The permanent repair will be completed no later than the next Unit 3 refueling outage currently scheduled for March 2006.
Florida Power & Light letter L-2005-168 Enclosure 2 Additional Information 1.0 Permanent Repair Options The following three Code repair options are planned. Option 1 below is the primary repair option however, the final recommendation will be based on conclusions of NDE inspections performed along with the actual spent fuel pool heatup rate at the time of the repair.
1.1 Option 1 (Figure 1) is to add a 2-inch diameter welded branch connection at the through-wall pinhole leak. The branch connection with a welded plug will act as the new pressure boundary at the attachment profile. All selected materials are compatible with SFP cooling system class and service. The time estimate for completion of this repair option is 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />.
1.2 Option 2 (Figure 2) is the installation of a pipe spool piece to replace the affected portion of the 8-inch diameter piping. The spool piece will be shop prepared.
This replacement section of pipe will be pre-sized and will be designed to minimize required field welding (one slip-on flange). All selected materials are designed to be compatible with SFP cooling system class and service. The time estimate for completion of this repair option is 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />.
1.3 Option 3 is a gas tungsten arc (GTAW) open root weld repair at through-wall holes on thin wall pipe. The GTAW process uses an open root technique with a maximum root opening of 5/32 inch for an open root butt joint with no limitation on the length of the grind-out. This repair method is also appropriate, if conditions warrant, to be performed on the existing through-wall pinhole location with proper pipe prep-work, or may be performed following a pipe wall burn-through created during welding. The time estimate for completion of this repair option is 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />.
NDE, as specified by the ASME Code, will be performed during any of the repairs described above.
2.0 Temporary Non-Code Repair Method The selected design for the temporary non-Code repair contingency employs commercial grade materials able to withstand expected operating pressure and temperature conditions should a bum-through be created on the Schedule 10S 8-inch diameter stainless steel pipe during welding for the Code repair activity. The non-Code component is a simplified pipe clamp (Figure 3) designed to fit over a through-wall hole. The clamp and bolting material is robust and able to withstand any anticipated operating condition.
Florida Power & Light letter L-2005-168 Additional Information Page 2 of 3 3.0 Pre-Repair Non-Destructive Examination A pre-repair visual assessment and PT, has characterized the flaw as a pinhole size, rounded 1
indication less than 1/32 inch in diameter, that is located approximately /2 inch from the weld toe in the weld's heat affected zone. This indication is located at the bottom of the horizontal run pipe. Unlike a developed crack, propagation of the discovered pinhole on the 8-inch pipe is highly unlikely based on the following four considerations:
- 1. Pipe wall degradation due to boric acid corrosion is not a concern since pipe material is austenitic stainless steel (ASTM A 312 Type 304) that is highly resistant to this failure mode.
- 2. Flow-induced pipe wall degradation is not a concern since hydraulic shear load near the pipe wall is at its minimal value (i.e., low fluid velocity).
- 3. Flaw propagation for a pinhole flaw is unlike crack flaws. A pinhole flaw is well defined and finite.
- 4. The piping at the flaw location is not subject to fatigue-type or vibratory loading as it is remote from rotating equipment.
Augmented inspection in accordance with ASME Code Case N-513 was performed. No additional flaws were found.
Additional NDE will be performed at the flaw area after the piping is removed from service immediately prior to repair.
4.0 Alternate Approach for Non-Planar Through-wall Flaws Guidance for evaluation of non-planar through-wall flaws is not provided in Code Case N-513.
An alternate wall thinning criteria was developed using the "Limits of Reinforcement" rules in Paragraph NB-3640 of the ASME Code. The model used is illustrated in Figure 4.
Referring to Figure 4, Area Al (which is between the thinned area and the limits of reinforcement) should be balanced by Area A2 (which is within the thinned area) in which case the following equation can be written:
1.5F -/. (tnom -tmin) = L, (tni. - tp (1) or rearranging:
Florida Power & Light letter L-2005-168 Additional Information Page 3 of 3 Lm = 1.5R/jjtno m- tpi) (2)
(t mintP where:
Lm = diameter of defect, in Rm = mean pipe radius, in tnom = nominal pipe wall thickness, in tmin = minimum allowable thickness, in tp = remaining thickness under pit, in.
This model conservatively assumes that all areas within the region less than tnom in thickness are at the "pit" remaining thickness tp. The minimum required wall thickness, tmin, is calculated from:
tr pD. (3) 2(S +0.4p) where:
p = maximum operating pressure (150 psig)
Do = outside diameter (8.625 in)
S = allowable stress (17,800 psi).
Thus, tmln = 0.0362 inch.
By setting tp = 0 in Equation 2 (through-wall pit), the allowable hole diameter may be determined for a range of nominal pipe wall thicknesses (see Figure 5). It can be seen that through-wall pit sizes up to approximately 3.65 inches in diameter can be tolerated for a nominal pipe thickness of 0.148 inch without exceeding ASME Code margins. This is much greater than the assumed flaw size.
Flaw growth with a larger initial flaw size of 3.65 inches is predicted as negligible in both the axial and circumferential directions.
CODE REPAIR - WELDED BRANCH CONNECTION HALF COUPLING 2
(EXIST. THRU WALL)
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0.00 -IIIII 0.00 1.00 2.00 3.00 4.00 5.00 6.00 7.00 8.00 9.00 10.00 Defect Diameter, L. (in)
Figure 5: Allowable Non-Planar Flaws for Various Nominal Wall Thicknesses