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Category:Inspection Report
MONTHYEARIR 05000250/20240102024-01-0505 January 2024 Focused Engineering Inspection 05000250/2024010 and 05000251/2024010 IR 05000250/20230032023-11-0909 November 2023 Integrated Inspection Report 05000250/2023003 and 05000251/2023003 IR 05000250/20230102023-09-29029 September 2023 Biennial Problem Identification and Resolution Inspection Report 05000250/2023010 and 05000251/2023010 IR 05000250/20230052023-08-21021 August 2023 Updated Inspection Plan for Turkey Point, Units 3 & 4 (Report 05000250/2023005 and 05000251/2023005) IR 05000250/20230022023-08-14014 August 2023 Integrated Inspection Report 05000250/2023002 and 05000251/2023002 IR 05000250/20234022023-06-12012 June 2023 Security Baseline Inspection Report 05000250/2023402 and 05000251/2023402 IR 05000250/20233012023-05-17017 May 2023 NRC Operator License Examination Report 05000250/2023301 and 05000251/2023301 IR 05000250/20230012023-05-12012 May 2023 Integrated Inspection Report 05000250/2023001 and 05000251/2023001 IR 05000250/20220062023-03-0101 March 2023 Annual Assessment Letter for Turkey Point, Units 3 & 4 (Report 05000250/2022006 and 05000251/2022006) IR 05000250/20220042023-01-27027 January 2023 Integrated Inspection Report 05000250/2022004 and 05000251/2022004 IR 05000250/20220112022-12-20020 December 2022 Design Basis Assurance Inspection (Programs) Inspection Report 05000250/2022011 and 05000251/2022011 IR 05000250/20220102022-11-29029 November 2022 Triennial Fire Protection Inspection Report 05000250/2022010 and 05000251/2022010 IR 05000250/20224022022-11-0707 November 2022 Security Baseline Inspection Report 05000250 2022402 and 05000251 2022402 IR 05000250/20220032022-10-31031 October 2022 Integrated Inspection Report 05000250/2022003 and 05000251/2022003 ML22286A1262022-10-28028 October 2022 Review of the Fall 2021 Steam Generator Tube Inspections During Refueling Outage No. 32 IR 05000250/20234012022-10-19019 October 2022 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000250/2023401 and 05000251/2023401 IR 05000250/20220052022-08-26026 August 2022 Updated Inspection Plan for Turkey Point Units 3 & 4 Report 05000250 2022005 and 05000251 2022005-Final ML22229A5332022-08-18018 August 2022 Notification of Target Set Inspection and Request for Information (NRC Inspection Report No. 05000250 2022402 and 05000251 2022402) IR 05000250/20220022022-08-12012 August 2022 Integrated Inspection Report 05000250/2022002 and 05000251/2022002 IR 05000250/20220012022-05-11011 May 2022 Integrated Inspection Report 05000250/2022001 and 05000251/2022001 L-2022-072, Steam Generator Tube Inspection Report2022-05-0606 May 2022 Steam Generator Tube Inspection Report IR 05000250/20224012022-03-0808 March 2022 Security Baseline Inspection Report 05000250/2022401 and 05000251/2022401(U) IR 05000250/20210062022-03-0202 March 2022 Annual Assessment Letter for Turkey Point, Units 3 and 4 (Report No. 05000250/2021006 and 05000251/2021006) IR 05000250/20210042022-02-0202 February 2022 Integrated Inspection Report 05000250/2021004 and 05000251/2021004 IR 05000250/20210032021-11-0303 November 2021 Integrated Inspection Report 05000250/2021003 and 05000251/2021003 IR 05000250/20210072021-11-0303 November 2021 Follow-Up Assessment Letter Report 05000250/2021007 IR 05000250/20210402021-09-30030 September 2021 95001 Supplemental Inspection Report 05000250/2021040 and 05000251/2021040 IR 05000250/20210052021-08-25025 August 2021 Updated Inspection Plan for Turkey Point, Units 3 & 4 (Report 05000250/2021005 and 05000251/2021005) IR 05000250/20210022021-08-0404 August 2021 Integrated Inspection Report 05000250/2021002 and 05000251/2021002 IR 07200062/20210012021-07-21021 July 2021 Operation of an Independent Spent Fuel Storage Installation Report 07200062/2021001 IR 05000250/20214012021-06-11011 June 2021 Security Baseline Inspection Report 05000250/2021401, 05000251/2021401, and 07200062/2021401 IR 05000250/20210012021-05-0707 May 2021 Integrated Inspection Report 05000250/2021001 and 05000251/2021001 and Assessment Follow-Up Letter IR 05000250/20210122021-05-0505 May 2021 Biennial Problem Identification and Resolution Inspection Report 05000250/2021012 and 05000251/2021012 IR 05000250/20214202021-04-29029 April 2021 Security Baseline Inspection Report 05000250/2021420 and 05000251/2021420 Cover Letter IR 05000250/20213012021-04-10010 April 2021 NRC Operator License Examination Report 05000250/2021301 and 05000251/2021301 IR 05000250/20210902021-04-0606 April 2021 Notice of Violation and Proposed Imposition of Civil Penalty $150,000, NRC Inspection Report Nos.05000250/2021090 and 05000251/2021090; Investigation Report Nos. 2-2019-011 and 2-2019-025 Exercise of Enforcement Discretion IR 05000250/20200062021-03-0303 March 2021 Annual Assessment Letter for Turkey Point Nuclear Plant, Unit 3 and Unit 4 Report 05000250/2020006 and 05000251/2020006 IR 05000250/20210102021-02-26026 February 2021 Triennial Inspection of Evaluation of Changes, Tests and Experiments Baseline Inspection Report 05000250/2021010 and 05000251/2021010 IR 05000250/20204022021-02-12012 February 2021 Material Control and Accounting Program Inspection Report 05000250/2020402 and 05000251/2020402 Public Version (Cover Letter Only) IR 05000250/20200042021-02-11011 February 2021 Integrated Inspection Report 05000250/2020004 and 05000251/2020004 and Independent Spent Fuel Storage Installation Inspection (ISFSI) 07200062/2020002 IR 05000250/20210112021-02-0404 February 2021 NRC Inspection Report 05000250/2021011 and 05000251/2021011, and Investigation Report 2-2019-025; and Apparent Violations IR 05000250/20204012020-12-14014 December 2020 Security Baseline Inspection Report 05000250/2020401 and 05000251/2020401 IR 05000250/20200502020-12-0909 December 2020 Special Inspection Report 05000250/2020050 and 05000251/2020050 IR 05000250/20200032020-11-0404 November 2020 Integrated Inspection Report 05000250/2020003 and 05000251/2020003 IR 05000250/20200022020-08-10010 August 2020 Integrated Inspection Report 05000250/2020002, 05000251/2020002, and Independent Spent Fuel Storage Installation Inspection (ISFSI) 07200062/2020001 IR 05000250/20200112020-07-23023 July 2020 NRC Inspection Report 05000250-2020011 and 05000251-2020011 and Investigation Report 2-2019-011; and Apparent Violation Final IR 05000250/20200012020-05-0707 May 2020 Integrated Inspection Report 05000250/2020001 and 05000251/2020001 IR 05000250/20204112020-04-17017 April 2020 Cyber Security Inspection Report 05000250/2020411 and 05000251/2020411 IR 05000250/20200102020-03-30030 March 2020 Design Basis Assurance Inspection (Teams) Inspection Report 05000250/2020010 and 05000251/2020010 IR 05000250/20190042020-01-30030 January 2020 Integrated Inspection Report 05000250/2019004 and 05000251/2019004 and Independent Spent Fuel Storage Installation Inspection (ISFSI) Report 07200062/2019001 2024-01-05
[Table view] Category:Inspection Report Correspondence
MONTHYEARML23178A1872023-07-25025 July 2023 Review of the Spring 2022 Steam Generator Tube Inspections During Refueling Outage No. 33 ML19282C7482019-10-0909 October 2019 Requalification Program Inspection - Turkey Point Nuclear Plant, Units 3 and 4 ML18003A5342018-01-0202 January 2018 RP RFI 2018-01 ML17107A3832017-04-13013 April 2017 Notification of Turkey Point Units 3 & 4 Design Bases Assurance Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000250/2017007 and 05000251/2017007 ML1006003362010-03-0101 March 2010 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection IR 05000250/20084022008-11-21021 November 2008 IR 05000250-08-402, and IR 05000251-08-402, on 10/23/2008, Turkey Point - NRC Security Inspection IR 05000250/20070062007-03-21021 March 2007 IR 05000250-07-006, 05000251-07-006, on 01/22/2007 - 02/09/2007, Turkey Point, Units 3 and 4, Fire Protection IR 05000250/20070012007-03-0101 March 2007 Annual Assessment Letter - Turkey Point Nuclear Plant (NRC Inspection Report 05000250, 251/2007001) IR 05000250/20060112006-11-0909 November 2006 IR 05000250-06-011, 05000251-06-011, on 09/05-15/2006 and 09/25-29/2006, Turkey Point, Units 3 and 4, Component Design Bases Inspection IR 05000250/20064012006-10-11011 October 2006 NRC Inspection Report 05000250-06-401 and 05000251-06-401 (Safeguards Information Removed) IR 05000250/20060142006-08-17017 August 2006 NRC Security Inspection Report 05000250/2006014 and 05000251/2006014 ML0506703402005-02-28028 February 2005 NRC Integrated IR 05000250-04-005,05000251-04-005. Denial of Non-Cited Violation Concerning the Unit 3 Containment Moisture Barrier ML0400902132003-12-22022 December 2003 Undated, Inspector post-inspection Debrief to Region II DRS Managers from R Schin Re Turkey Point Triennial Fire Protection Inspection Summary ML0332505122003-11-20020 November 2003 Notification of Triennial Fire Protection Baseline Inspection Report Nos. IR 05000250-04-007 and IR 05000251-04-007 to Be Conducted in January and February 2004 L-77-357, 11/25/1977 Letter Finding of No Proprietary Information in Inspection Report Nos. 05000250/1977022 and 05000251/19770221977-11-25025 November 1977 11/25/1977 Letter Finding of No Proprietary Information in Inspection Report Nos. 05000250/1977022 and 05000251/1977022 ML18227A5301977-08-16016 August 1977 08/16/1977 Letter Finding No Proprietary Information in Inspection Reports 05000250/1977015 and 05000251/1977015 L-77-252, 08/16/1977 Letter Finding No Proprietary Information in Inspection Reports 05000250/1977014 and 05000251/19770141977-08-15015 August 1977 08/16/1977 Letter Finding No Proprietary Information in Inspection Reports 05000250/1977014 and 05000251/1977014 L-77-237, 07/27/1977 Letter Finding No Proprietary Information in Inspection Reports 05000250/1977011 and 05000251/19770111977-07-27027 July 1977 07/27/1977 Letter Finding No Proprietary Information in Inspection Reports 05000250/1977011 and 05000251/1977011 L-77-238, 07/27/1977 Letter Finding No Proprietary Information in Inspection Reports 05000250/1977012 and 05000251/19770121977-07-27027 July 1977 07/27/1977 Letter Finding No Proprietary Information in Inspection Reports 05000250/1977012 and 05000251/1977012 L-77-220, 07/11/1977 Letter Finding No Proprietary Information in Inspection Reports 05000250/1977013 and 05000251/19770131977-07-11011 July 1977 07/11/1977 Letter Finding No Proprietary Information in Inspection Reports 05000250/1977013 and 05000251/1977013 L-77-210, 08/16/1977 Letter Finding No Proprietary Information in Inspection Reports 05000250/1977008 and 05000251/19770081977-07-0606 July 1977 08/16/1977 Letter Finding No Proprietary Information in Inspection Reports 05000250/1977008 and 05000251/1977008 L-77-153, Response to Inspection Conducted on 03/22-25/1977 & 04/04-08/1977 & Reported in Inspection Report Nos. 05000250/1977004 & 05000251/19770041977-05-20020 May 1977 Response to Inspection Conducted on 03/22-25/1977 & 04/04-08/1977 & Reported in Inspection Report Nos. 05000250/1977004 & 05000251/1977004 2023-07-25
[Table view] 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] |
Text
PAP. 5UX 3iVQ MIAMI, FLQRIDA 33IOI FLORIDA POWER 5 LIGHT COMPANY July 27, 1977 L-77-238 Mr. Norman C. Moseley, Director, Region Office of Inspection and Enforcement II U. S. Nuclear Regulatory Commission 230 Peachtree Street, N.W., Suite 1217 Atlanta, GA 30303
Dear Mr. Moseley:
Re: RII:MVS 50-250/77-12 50-251/77-12 Florida Power 6 Light Company has reviewed the subject inspection report. There is no proprietary information in the report.
Very truly yours, Robert E. Uh ig Vice President REU/MAS:pg Attachment cc: Robert Lowenstein, Esquire
'HELPING BUILD FLORIDA
0 II
gp,R AFGy UNITED STATES
~G< P 0 NUCLEAR REGULATORY COMMISSION Cy ~y %~
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REGION II 230 PEACHTREE STREET, N.W. SUITE 1217
".~ ATLANTA,GEORGIA 30303
+**++ JUL 3 1977 In Reply Refer To:
RII:MVS 50-250/77-12 50-251/77-12 I
Florida Power and Light CDInpany Attn: Dr. R. E. Uhrig, Vice President of Nuclear and General Engineering P. 0. Box 013100 9250 West Flagler Street Miami, Florida 33101 Gentlemen:
I This refers to the inspection conducted by Mr. M. V. Sinkule of this office on June 13-17, 1977; of activities authorized by NRC Operating License Nos. DPR-31 and DPR-41 for. the Turkey Point No. 3 and 4 facilities, and to the discussion of our findings held with Mr. H. E. Yaeger at the conclusion of the inspection.
Areas examined during the inspection and our findings are discussed in the attached inspection report. Within these areas, the inspection consisted of selective examinations of procedures and representative records, interviews with personnel, and observations by the inspector.
Within the scope of this inspection, no items of noncompliance were disclosed.
We have examined actions you have taken with regard to previously identified inspection findings. These are discussed in the attached inspection report.
The results of the inspection pertaining to the postulated fuel handling accident discussed in paragraph 11 of the attached report has been referred to NRC Headquarters for review.
In accordance with Section 2.790 of the NRC's "Rules of Practice,"
Part 2, Title 10, Code of Federal Regulations, a copy of this letter and the attached inspection report will be placed in the NRC's Public Document Room. If this report contains any information that you believe to be proprietary, it's necessary that you submit a written application to this office requesting that such information be withheld from public
SUL 13 )g",7 Florida Power and Light Company disclosure. If no proprietary information is identified, a written statement to that effect should be submitted. If an application is submitted, it must fully identify the bases for which information is claimed to be proprietary. The application should be prepared so that information sought to be withheld is incorporated in a separate paper and referenced in the application since the application will be placed in the Public Document Room. Your application, or written statement, should be submitted to us within 20 days. If we are not contacted as specified, the attached report and this letter may then be placed in the Public Document Room.
Should you have any questions concerning this letter, we will be glad to discuss them with you.
Very truly yours,
(~p g<-. ~ F. J. Long, Chief
/ Reactor Operations and Nuclear Support Branch
Attachment:
RII Inspection Report Nos.
50-250/77-12 50-251/77-12
gp,R REGS UNITED STATES P
0 NUCLEAR REGULATORY COMMISSION Cy O
o REGION II 230 PEACHTREE STREET, N.W. SUITE 1217 ATLANTA,GEORGIA 30303
~+ < o~
Wp*y4 Report Nos.: 50-250/77-12 and 50-251/77-12 Docket Nos.: 50-250 and 50-251 License Nos.: DPR-31 and DPR-41 Category: C/C Licensee: Florida Power and Light Company P. 0. Box 013100 9250 West Flagler Street Miami, Florida 33101 Facility Name: Turkey Point Units 3 and 4 Inspection at: Turkey Point Site, 9 miles east of Florida City, Florida and FP&L General Office in Miami, Florida Inspection conducted: June 13-17, 1977 Inspector: Marvin V. Sinkule Reviewed by: Er C.
R. C. Lewis, Chief Date Reactor Projects Section No. 2 Reactor Operations and Nuclear Support Branch Ins ection Summar Ins ection on June 13-17 1977: Re ort Nos. 50-250/77-12 50-251/77-12 Areas Ins ected: Routine, announced inspection of Unit 4 refueling maintenance; Unit 4 plant operations; Unit 4 pump and valve surveillance program; Unit 3 and Unit 4 reportable occurrences; followup noncompliance items: followup outstanding items; and followup of evaluations of a postulated fuel handling accident analysis. The inspection involved 31 inspector-hours by one NRC inspector.
Results:, Of the seven areas inspected, no items of noncompliance were identified.
RII Rpt. Nos. 50-250/77-12 and 50-251/77-12 DETAILS I Prepared by: / 7 7 M. V. Sinkule, Reactor Inspector ate Reactor Projects Section No. 2 Reactor Operations and Nuclear Support Branch Dates of Inspection: June 13-17, 1977 Reviewed by: E. D.
R. C. Lewis, Chief Date Reactor Projects Section No. 2 Reactor Operations and Nuclear Support Branch
- 1. Persons Contacted J. R. Bensen, Manager, Power Resources, Nuclear, General Office (GO)
- H. E. Yaeger, Plant Manager
- J. K. Hayes, Plant Superintendent, Nuclear
- P. J. White, Plant Superintendent, Maintenance
- D. W. Jones, QC Supervisor
- M. A. Schoppman, Power Resources Specialist, Licensing (GO)
- W. R. Williams, Jr., Assistant Superintendent, Electrical Maintenance
- B. C. Kilpatrick, Assistant Superintendent, Mechanical Maintenance
- H. M. Ainsworth, Assistant Superintendent, Mechanical Maintenance
- J. E. Moore, Superintendent, Nuclear Operations
- G. Gotch, Power Resources Specialist (GO)
- A. E. Siebe, Assistant Manager of QA-Operatons (GO)
- R. J. Spooner, QA Operations Supervisor G. E. Liebler, Power Resources Supervisor, Nuclear (GO)
G. D. Whittier, Senior Licensing Engineer (GO)
D. W. Haase, Technical Department Supervisor A. P. Janelle, Plant Coordinator R. E. Dawson, Reactor Engineer The inspector also talked to and interviewed several other licensee employees, including members of the technical staff.
- Denotes those attending the exit interview on June 16, 1977
- 2. Licensee Action on Previous Ins ection Findin s (Open) (50-250/77-3 and 50-251/77-3; Item I.A.2) The inspector verified that the corrective action to prevent recurrence had been completed as discussed in FP&L letter of April 18, 1977, and that the event was reviewed and evaluated by the licensee by discussions
RII Rpt. Nos. 50-250/77-12 and 50-251/77-12 I-2 with plant personnel and review of records. Specifically the inspector reviewed the following records:
Plant Nuclear Safety Committee (PNSC) meeting minutes dated May 25, 1977 Corporate Nuclear Review Board (CNRB) meeting minutes dated April 26, 1977 Operating Procedure 16002.5 dated May 25, 1977 Operating Procedure 16002.6 dated May 2, 1977 O.P. 16002.6 incorporates a note on step 4.28 to clarify what changes can be made to the refueling procedure without changing the intent of the procedure. The inspector had informed the licensee during the exit interview that the resolution of this item was complete, however, additional consideration indicates that more review is required. This information was transmitted to the licensee by telephone June 17, 1977.
3.
77-12/I:1 'm Unresolved Items lementin Procedures for Valve and Pum Pro ram The licensee's surveillance program does not insure that the requirements of 10 CFR 50.55a(g) will be met. (paragraph 9) 77-12/I:2 Missin E losive Plu from 4B Steam Generator Verification that the entire plug is present in the steam generator tube is not conclusive. (para-graph 10)
Exit Interview A meeting was held on June 16, 1977, with H. E. Yaeger, Plant Manager, and members of his staff (attendees denoted by an asterisk in paragraph 1). Additional discussions were held with H. E. Yaeger by telephone on June 20 and 27, 1977. The scope and results of the inspection concerning the items listed below were discussed.
Missing Steam Generator Tube Plug-paragraph 10 Main Steam Non Return Valve-paragraph 13 Implementation of Pump and Valve Program-paragraph 9
RII Rpt. Nos. 50-250/77-12 and 50-251/77-12 I-3 Reportable Occurrences paragraph 8 Refueling Maintenance paragraph 6 Testing of systems prior to startup paragraph 7 Followup of noncompliance item paragraph 2 Discussions were held with G. E. Liebler, Power Resources Supervisor, concerning the postulated fuel handling accident in the containment on June 17, 1977, at the General Office in Miami and by telephone on June 27 and 30, 1977.
- 5. Other Si nificant Findin s
- a. Plant Status Unit 3 operated at approximately 100 percent during the inspection except for a short outage caused by a problem in the secondary system on June 14, 1977.
Unit 4 was shutdown for refueling during the inspection.
- b. Re ortable Occurrence The licensee reported to the inspector onsite on June 16, 1977, that a pin hole leak was discovered in the "B" emergency diesel cooling system radiator on June 10, 1977, during periodic maintenance of the system. This event will be discussed in a FP&L reportable occurrence which is due to be submitted to the NRC by July 8, 1977.
- 6. Refuelin Maintenance (Unit 4)
The inspector reviewed records of three maintenance activities to verify that the procedures used to control the maintenance work have provisions for administrative approvals for removing the system from service and returning it to service; hold points for inspection and signoffs by other licensee personnel; testing following maintenance; assuring that systems are aligned for normal service; removal of jumpers which may be required for maintenance; and reporting deficiencies to management.
The review included the following records:
Maintenance Procedure (MP) 0707.10, Reactor Trip and Generator Output Breakers, Inspection and Maintenance Administrative Procedure (AP) 103.4, In Plant Equipment Clearance AP 0190.19, Control of Maintenance on Safety Related Systems.
MP 9407.1, 4160 Switchgear, Periodic Maintenance
RII Rpt. Nos. 50-250/77-12 and 50-251/77-12 I-4 MP, 3207.1, Residual Heat Removal Pump-Seal Replacement Plant Work Orders associated with the three maintenance activities Personnel Qualificatibn Records I
In addition to the re'cords review the inspector visited the job site of the Residual Heat Removal (RHR) Pump-Seal Replacement on June 14, 1977. No work was in progress, however, cleanliness controls appeared to be effective. The job site of the periodic maintenance on the 4160 volt breakers was visited on June 16, 1977, and the inspector witnessed a portion of the maintenance and verified that the maintenance was being performed in accordance with ki 9407.1 on the 4C primary coolant pump breaker.
The records review of M.'207.1, indicated that testing was required, however, the exact te'sting requirements were not specified. This item is addressed as unresolved item 76-15/2 in IE Report 50-250/76-15 and 50-251/76-15, Details III, and will be followed at a later date.
MP 9407.1, 4160 Switchgear Procedure, did not have signoff provisions for QC Inspections. Craftsman assigned to the job indicated that QC personnel were periodically monitoring the gob on a random basis. The assistant, maintenance superintendent stated that all electrical maintenance procedures were currently being reviewed to determine the need for additional QC hold points. No items of noncompliance were identified.
7 ~ Review of Plant 0 eration Unit 4 The inspector verifed by review of records and discussions with plant personnel that plans exist to test the following systems prior to startup:
Reactor Coolant System Nuclear Instrumentation System Auxiliary Feedwater System Control Rod System RHR System The following procedures were reviewed:
OP 16001.2, Surveillance Check Lists, page 10 of "Periodic check-off sheets and Technical Specification Surveillance Requirements for Core Refueling."
RII Rpt. Nos. 50-250/77-12 and 50-251/77-12 I-5 OP 0202.1 Steps 5.13 and 8.51 of "Reactor Startup, Cold Conditions to Hot Shutdown Conditions."
In addition, various startup procedures were reviewed to ascertain whether procedures require adherence to the Technical Specifications as they pertain to startup testing and power operation prerequisites.
The following procedures were reviewed:
OP 0202.1, Reactor Startup, Cold Conditions to Hot Shutdown Conditions OP 0202.2, Unit Startup, Hot Shutdown to Power Operations OP 0204.3, Initial Criticality After Refueling OP 0204.5, Startup Sequence after Refueling No items of noncompliance were identified.
- 8. Re ortable Occurrences Three reportable occurrences, two for Unit 3 and one for Unit 4, were reviewed to ascertain that:
(1) reporting requirements delineated in TS 6.9.2 were met; (2) corrective action was taken as required by Criterion XVI of Appendix B to 10 CFR 50; (3) the licensee reviewed and evaluated the event as required by TS 6.5; (4) the review and evaluation of the event included an assessment of generic implications, personnel error and procedural adequacy as required by TS 6.8 and Appendix B to 10 CFR 50.
(a) PO 250-77-5 and 251-77-3 These events actually involve one problem, however, it applies to both unit 3 and unit 4 and pertains to a discrepancy in Technical Specification (TS) Figure 2.1-1, "Reactor Core Thermal and Hydraulic Safety Limits." The PNSC had reviewed the occurrence on May 2, 1977, and the CNRB reviewed the occurrence on April 26, 1977. The discrepancy did not involve the changing of any of the Limiting Safety Settings prescribed in the Technical Specifications. FP&L has prepared a TS change which had been approved by the PNSC on June 13, 1977, however, the change had not yet been submitted to the NRC for approval. No items of noncompl'iance were identified.
(b) RO 250-77-4 This event involved failure of the "B" emergency diesel to come up to the required speed within 15 seconds. This event was reviewed by the PNSC on May 2, 1977. The inspector reviewed the plant work order which was used to repair the system subsequent to evaluation and tests on the fuel system on
RII Rpt. Nos. 50-250/77-12 and 50-251/77-12 I-6 April 8, 1977. The corrective action to prevent recurrence involved replacing a section of the fuel system piping with piping that which utilizes a wedge type fitting instead of the flared fittings. The inspector verified that the licensee had considered the generic applicability within the facility.
This was accomplished by discussion with the maintenance supervisor responsible for implementing a change of all fuel system piping on both diesels.'he licensee also believes that the condition that caused this occurrence is the same condition that caused the occurrence which was discussed in RO 250-77-3. No noncompliance items were identified.
- 9. Unit 4 Valve and Pum Pro ram On November 22, 1976, NRR issued a letter to FP&L outlining guidance to be followed in implementing the requirements of 10 CFR 50.55a (g) which became effective on Unit 4 on January 7, 1977 and will become effective on Unit 3 on August 14, 1979. On February 25, 1977, FP&L submitted the proposed Valve Test, Pump Test, and ISI program for Unit 4 to the NRC including a request for a Technical Specification change. On April 28, 1977, FP&L requested an exemption from the requirements of 10 CFR 50.55a(g) 4(v) and from the Technical Specifications revised in accordance with 10 CFR 50.55a(g)(5)(ii) for 6 months subsequent to the NRC's review of the proposed inservice examination and testing program. On lKy 25, 1977, NRR denied this request and stated that the most conservative aspects of either the Technical Specifications or 10 CFR 50.55a(g) should be implemented.
The inspector reviewed the current valve testing and pump testing program to verify that the conservative aspects of 10 CFR 50.55a(g) and the Technical Specifications have been implemented. The licensee has developed procedures for the testing of pumps. These procedures have been developed to implement the requirements of the program submitted to NRR on February 25, 1977. These procedures are in draft form and are currently being reviewed by the licensee. The licensee is currently reviewing the valve program to determine what code requirements may apply during the current refueling outage.
During the exit interview the licensee was informed that the more conservative aspects of the 10 CFR 50.55a(8) and the current Technical Specifications apply prior to approval of the Technical Specification Revision and that this item is considered unresolved pending esta-blishment of procedures and schedules to insure that the applicable requirements are satisfied. Further review is required to determine if the applicable requirements are currently being met.
RII Rpt. Nos. 50-250/77-12 and 50-251/77-12 I-7
- 10. Steam Generator Tube Plu Unit 4 The licensee had notified RII On May 23, 1977, that a steam generator tube plug was missing from the 4B steam generator, cold leg side.
Subsequently, the licensee had taken video tapes of the inside of the tube to verify that the plug was in the tube. The inspector viewed these tapes which indicate that the plug end is visible, however, the clarity of the video tape was not good. The licensee has taken measurements of the obstruction in the tube and find it approximately 3 inches below the sixth support plate. Neither the measurements or the video tapes establish that the entire plug is in the tube. The inspector informed the licensee during the exit interview that if the entire plug could not be verified a 10 CFR 50.59 evaluation would be required to determine whether or not an unreviewed safety question exists. The licensee informed the inspector by telephone on June 20, 1977, that additional techniques were being employed to verify that the entire plug was in the tube and that an evaluation has been initiated to satisfy the 10 CFR 50.59 requirements. This item is considered unresolved.
Postulated Fuel Handlin Accident Inside Containment Westinghouse (W) notified FP&L by letter dated September 21, 1976, that a postulated fuel handing accident inside the containment may result in site boundary doses in excess of exposure guidelines set forth in 10 CFR 100. A licensee representative acknowledged that the letter was received and that an unofficial evaluation was conducted, however, the records were not retained and were not available to the inspector for review. The licensee representative stated that the decision not to conduct a full scale analysis of the fuel handling accident inside the containment was based on the fact that the accident is addressed in FSAR Section 14.2.1. In addition, the licensee representative felt that information presented to the NRC in a letter dated June 23, 1976, concerning a cask drop accident, could be utilized in analyzing the releases from the fuel handling accident in the containment.
The inspector reviewed the two referenced documents and page 50 of the NRC Safety Evaluation dated March 23, 1972, for Turkey Point 3 and 4 and has no further questions.
On January 18, 1977, NRC issued a letter to FP&L and requested that the licensee provide a detailed evaluation of the potential conse-quences of a fuel assembly drop in the containment. FP&L conducted the analysis and responded to the NRC in a letter dated March 21, 1977, which indicates that the results of the analysis of a postulated
RII Rpt. Nos. 50-250/77-12 and 50-251/77-12 1-8 fuel handling accident in the containment is well below the limits of 10 CFR 100. This submittal is currently being reviewed by NRR.
- 12. Steam Generator Tube Removal Unit 4 The licensee committed to pull a "leaky dented tube," in a letter to the NRC dated April 29, 1977, if possible. If not, an alternative tube will be pulled. The inspector verified by a review of records that two tubes were pulled R42-C53 and R2-C49 from the 4C steam generator. No noncompliance items were identified.
- 13. Steam Line Non Return Valve Unit 4 IE Report 50-250/77-7 and 50-251/77-7 discusses an event relating to the nut and lock wire which secures the disc to the rotating arm which were not in place when the valve was disassembled. The licensee representative stated that the nut was found in the steam bypass line to the condenser. He also stated that records did not indicate whether or not the lock wire had initially been installed and that if it had been it was probably in the main condenser and that the search for it had been abandoned.
The inspector reviewed FP&L Plant Change and Modification Procedure No. 76-14 which was being used for reassembly of the Unit 4 valves.
Step V of that procedure has a QA hold point to verify the cleanliness of the steam lines subsequent to reassembly of the valve. A licensee representative stated that the hold point would be expanded to include correct assembly of the valve. The inspector had no further questions.