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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
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0 FPL. August 17, 2012 L-2012-330 POWERING TODAY.
EMPOWERING TOMORROW.0 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555-0001 Re: Turkey Point Unit 4 Docket No. 50-251 Relief Request No. 7 Response to Request for Additional Information Questions
References:
- 1) FPL letter L-2012-193 to the USNRC, dated June 5, 2012, Concrete Containment Inservice Inspection Program Exempt Tendon Inspection Relief Request 7
- 2) Email from Farideh E. Saba (NRC) to R. J. Tomonto (FPL), "Draft RAIs: Turkey Point - Unit 4 RR No. 7 Exempt tendon inspection)," dated July 17, 2012 On June 5, 2012 Florida Power and Light Company (FPL) submitted letter L-2012-193, (Reference 1), requesting relief from the requirement to perform examinations at the inaccessible end of the designated exempt tendons during the Turkey Point Unit 4 2012 refueling outage.
By electronic mail from the Nuclear Regulatory Commission (NRC) Project Manager (PM) dated July 17, 2012, the NRC requested Florida Power & Light Company (FPL) to discuss the draft request for additional information (RAI) questions (Reference 2).
On July 26, 2012 FPL and NRC Staff during a teleconference discussed the draft RAIs to determine need for further clarification. Following the discussion, NRC requested FPL to reply to the RAI questions as provided in Reference 2.
Attachment 1 contains both the NRC RAI questions, and the FPL responses to RAI questions.
The information provided herein does not change the conclusions stated in Reference 1 and, does not create any new commitments.
an FPL Group company
L-2012-330 Page 2 Should there be any questions, please contact Mr. Robert J. Tomonto, Licensing Manager at 305 246-7327.
Very truly yours, Michael Kiley Vice President Turkey Point Nuclear Plant Attachment Enclosure cc: Regional Administrator, USNRC Region II USNRC Senior Resident Inspector - Turkey Point Plant
L-2012-330, Attachment 1 Page 1 of 3 NRC RAI Ouestions and FPL Responses RAI Ouestion 1:
Provide details on any anomalies that have been detected/observed during the previous inspections with respect to corrosion of the tendon wires FPL Response to RAI Ouestion 1:
The following anomalies described herein are equal to or greater than Level 3 corrosion (pitting between 0.000" and 0.003"):
During the 20th Year inspections Level 3 corrosion was identified on the edges of the bearing plate at both ends of Tendon 42H83. These defects were caused either by incomplete coating touch-up after the original stressing operations, or incomplete coating coverage on the plate edges. These areas of light corrosion did not indicate progressive degradation. At that time, action was taken to clean and touch-up the defects with coating material.
During the 3 0 th year inspection rust scale and pitting of Level 5 corrosion (0.006" <
Pitting _< 0.010") was found on the cap and outside of the gasket area on a bearing plate.
The Turkey Point Unit 4, Tendon 51H01 is a horizontal tendon and located in the tendon inspection pit at buttress #5. The tendon is the lowest tendon in the pit and the pit might have been flooded and cap might have been exposed to standing water in the past. As expected, the inspection showed that the cap and the outside area of the tendon assembly were corroded. At that time, action was taken to replace the cap and replace any grease lost due to corroded tendon cap.
During the 3 5th year inspection Level 5 corrosion (0.006" < Pitting < 0.0 10") was found on a bearing plate on an area that is outside of the gasket seating area. The corroded area is not a load transfer area and is located outside of the grease protected area of the tendon assembly. It was determined that based on the location of the detected corrosion, the condition did not have an effect on the design function of tendon 51 HO 1. New gasket, tendon cap hardware and grease were installed at that time.
The preliminary inspection results of the 4 0 th year for Turkey Point Unit 4 tendon surveillance have no conditions with corrosion greater than or equal to Level 3 corrosion.
RAI Ouestion 2:
Provide list of the tendons that were found:
- a. The lift-off forced was below the acceptance criteria?
- b. The lift- off forced was above the acceptance criteria?
- c. Failed with any other reason?
L-2012-330, Attachment 1 Page 2 of 3 FPL Response to Question 2:
- a. The lift-off force was below the acceptance criteria?
During the 15th year inspection, Turkey Point Unit 4 hoop tendon 13H51 was reported ( in FPL letter L-88-336 ) to have a measured lift-off force of 0.3 percent variance below the lower bound predicted value. Re-evaluation of the 15 th year surveillance results utilizing the proper normalizing factors for calculating the predicted upper and lower limits for lift-off force measurements concluded that the 15th year surveillance results were found acceptable. Due to low tendon lift-off forces observed during the 20th year surveillance, a containment re-analysis was performed (and approved by the NRC) in 1994, resulting in revised tendon lift-off requirements for future surveillances. Subsequently, the results of the 25th, 30th, and 35th Year Tendon inspections were found acceptable regarding the lift-off forces.
Preliminary results of the 40th Tendon surveillance are within acceptable lift-off force criteria.
- b. The lift-off force was above the acceptance criteria?
None.
- c. Failed with any other reason?
None.
RAI Question 3:
When was the last time that tendon number: 1D20, 1D23, 2D20, and 51H40 inspected or tested? What are your plans for inspecting them in future?
FPL Response to RAI Question 3:
The Unit 4 Tendons 1D20, 1D23, 2D20, and 51H40 were part of a general inspection performed during the 40th year surveillance. Additionally, for the dome tendons 1D20, ID23 a visual inspection was performed on the accessible South East end only. For dome tendon 2D20, a visual inspection was performed on the accessible East end only.
For hoop tendon 51 H40, a visual was performed on the accessible Buttress #1 only.
Visual tendon surveillance consists of sheathing filler inspection and testing, inspection for water, anchorage inspection, concrete inspection around tendons, and replacement of grease after completion of all inspections. The preliminary results of the 4 0 th year inspection found no abnormalities related to the visual inspections performed at the accessible ends of these tendons The tendon selection for each inspection is on a random basis. At this time, there are no definitive plans to inspect these tendons in subsequent tendon inspections.
I L-2012-330, Attachment I Page 3 of 3 RAI Question 4:
Please justify for your "request due to hardship" to perform the required examinations of end of the tendon anchorages during the plant outage.
FPL Response to RAI Ouestion 4:
Relief Request 7, Reference 1 was submitted pursuant to 10 CFR 50.55a (a)(3)i, as an alternative to the Code requirements of IWL-252 1.1 (c) for the exempt tendons. As described in Reference 1, the proposed alternate examinations provide more stringent requirements than IWL requirements by providing examination of additional tendon anchorages exposed to a similar environment in close proximity to the randomly selected tendons that are considered exempted due to safety concerns.