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Category:Letter
MONTHYEARML24023A0342024-02-0505 February 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0038 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) ML23341A2102024-01-22022 January 2024 LTR-23-0216-1 - Closure Letter - 2.206 Petition for License Renewal Plant Reactor Pressure Vessel Embrittlement ML23320A3062024-01-22022 January 2024 Issuance of Amendment Nos. 298 and 291 Regarding Revising the Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project 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 ML23340A0332023-12-0101 December 2023 FPL to Fws, Comments Submitted by Florida Power and Light on the Species Status Assessment Accompanying the September 20, 2023 Proposed Threatened Species Status with Section 4(d) Rule for the Miami Cave Crayfish 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, ML23333A0152023-11-27027 November 2023 Attachment G - Arcadis Memo Re FPL Year 4 Raasr Final (June 2, 2023, Appended to Derm letter)-1 ML23333A0102023-11-27027 November 2023 Attachment B - 11/07/2022 - Waterkeeper Scoping Comments-1 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 IR 05000250/20230032023-11-0909 November 2023 Integrated Inspection Report 05000250/2023003 and 05000251/2023003 ML23310A1342023-11-0404 November 2023 10 CFR 2.206 Petition - LTR-23-0216-1 Petition Amendment; Turkey Point Subsequent Renewal with Petitioner 11/04/2023 ML24016A2622023-10-25025 October 2023 Subsequent License Renewal Updated List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected Project 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 ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published IR 05000250/20230102023-09-29029 September 2023 Biennial Problem Identification and Resolution Inspection Report 05000250/2023010 and 05000251/2023010 ML23234A1922023-09-27027 September 2023 Issuance of Amendment Nos. 297 and 290 Regarding Conversion to Improved Standard Technical Specifications ML23265A5492023-09-22022 September 2023 Transmittal of WCAP-18830-P/NP Turkey Point Fuel Storage Criticality Analysis for 24 Month Cycles to Support a License Amendment Request from FPL - License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis ML23243A9522023-09-0808 September 2023 Notice of Availability of the Draft Environmental Impact Statement for the Turkey Point Nuclear Generating Unit Numbers 3 and 4 Subsequent License Renewal Application ML23243A9542023-09-0808 September 2023 Notice of Availability of the Draft Environmental Impact Statement for the Turkey Point Nuclear Generating Unit Numbers 3 and 4 Subsequent License Renewal Application ML23243A9532023-09-0808 September 2023 Notice of Availability of the Draft Environmental Impact Statement for the Turkey Point Nuclear Generating Unit Numbers 3 and 4 Subsequent License Renewal Application ML23243A9552023-09-0808 September 2023 Notice of Availability of the Draft Environmental Impact Statement for the Turkey Point Nuclear Generating Unit Numbers 3 and 4 Subsequent License Renewal Application - Tribe- Section 106 Letters ML23199A2352023-09-0505 September 2023 Letter to EPA-Turkey Point Nuclear Generating Station, Units 3 and 4 - Notice of Availability of Draft Site-Specific Environmental Impact Statement for Subsequent License Renewal ML23199A2482023-09-0505 September 2023 Ltr to Florida Power and Light Co - Turkey Point Nuclear Generating Units 3 and 4 - Notice of Availability of Draft Site-Specific Environmental Impact Statement for Subsequent License Renewal 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 IR 05000250/20230052023-08-21021 August 2023 Updated Inspection Plan for Turkey Point, Units 3 & 4 (Report 05000250/2023005 and 05000251/2023005) 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 IR 05000250/20230022023-08-14014 August 2023 Integrated Inspection Report 05000250/2023002 and 05000251/2023002 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 ML23242A0922023-08-0606 August 2023 Request for Withholding Information from Public Disclosure for Turkey Point Nuclear Generating Unit Nos. 3 and 4 ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment ML23198A2702023-08-0303 August 2023 Issuance of the Site-Specific Environmental Impact Statement Scoping Process Summary Report Associated with the Turkey Point Nuclear Generating Unit Numbers 3 and 4, Subsequent License Renewal Application, Environmental Report Supplement 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 ML23178A1872023-07-25025 July 2023 Review of the Spring 2022 Steam Generator Tube Inspections During Refueling Outage No. 33 ML23188A1242023-07-20020 July 2023 Acknowledgment of Temporary Suspension Request for License Request for License Amendment Request Reactor Protection System, Engineered Safety Features System, and Nuclear Instrumentation System ML23200A0672023-07-18018 July 2023 Tp 2023 RQ Inspection Notification Letter ML23173A0812023-07-17017 July 2023 Supplement to Regulatory Audit Plan in Support of Review of License Amendment Request Supporting Digital Instrumentation & Control Modernization Project (EPID L-2022-LLA-0105) - Non-Proprietary 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) 2024-02-05
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December 1, 2020 Mr. Don Moul Executive Vice President, Nuclear Division and Chief Nuclear Officer Florida Power & Light Company Mail Stop: EX/JB 700 Universe Blvd.
Juno Beach, FL 33408
SUBJECT:
TURKEY POINT NUCLEAR GENERATING UNIT NO. 4 - REVIEW OF THE SPRING 2019 STEAM GENERATOR TUBE INSPECTION REPORT (EPID L-2019-LRO-0103)
Dear Mr. Moul:
By letter dated September 25, 2019, Florida Power & Light Company submitted information summarizing the results of the spring 2019 steam generator inspections performed at Turkey Point Nuclear Generating Unit No. 4. These inspections were performed during refueling outage 31.
The U.S. Nuclear Regulatory Commission staff has completed its review of the information provided and concludes that Florida Power & Light Company provided the information required by the Turkey Point Nuclear Generating Unit No. 4 technical specifications and that no follow-up is needed at this time. The staffs review summary is enclosed.
If you have any questions, please contact me at 301-415-6459 or Eva.Brown@nrc.gov.
Sincerely,
/RA/
Eva A. Brown, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-250
Enclosure:
As stated cc: Listserv
ML20287A368 OFFICE NRR/DORL/LPL2-2/PM NRR/DORL/LPL2-2/LA NRR/DNRL/NCSG/BC NAME EBrown (DMurdock for) BAbeywickrama SBloom (GMakar for)
DATE 10/19/2020 10/14/2020 08/21/2020 OFFICE NRR/DORL/LPL2-2/BC NAME UShoop DATE 12/1/2020 REVIEW OF THE SPRING 2019 STEAM GENERATOR TUBE INSPECTION REPORT FLORIDA POWER & LIGHT COMPANY TURKEY POINT, UNIT NO. 4 DOCKET NO. 50-251 By letter dated September 25, 2019 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML19268B738), Florida Power & Light Company (the licensee) submitted information summarizing the results of the spring 2019 steam generator (SG) inspections performed at Turkey Point Nuclear Generating Unit No. 4 (Turkey Point Unit 4).
These inspections were performed during refueling outage (RFO) 31. The licensee provided additional information concerning the inspections in a letter dated June 24, 2020 (ADAMS Accession No. ML20176A287). The U.S. Nuclear Regulatory Commission (NRC) held a clarification call on the additional information with the licensee on August 20, 2020.
Turkey Point Unit 4 has three Westinghouse Model 44F SGs, which were placed in service in 1983. Each SG contains 3,214 thermally treated Alloy 600 tubes with a nominal outside diameter of 0.875 inches and a nominal wall thickness of 0.050 inches. The tubes are supported by one stainless steel drilled-hole flow distribution baffle, six stainless steel quatrefoil, broached-hole tube support plates, and two sets of anti-vibration bars (AVB) in the U-bends.
The licensee provided the scope, extent, methods, and results of the SG tube inspections in the letters referenced above. In addition, the licensee described corrective actions (e.g., tube plugging) taken in response to the inspection findings.
Based on the review of the information provided, the NRC staff has the following observations:
As part of condition monitoring, the licensee performed a review of historical eddy current inspection data to identify indications that may show wear rates not typical of the inservice tubing population. As a result, the tube in Row 38, Column 58 (R38C58) in SG-B was preventively plugged due to atypical AVB wear growth rates. Specifically, the change in depths at two AVB wear indications in tube R38C58, over the last two operating cycles, were 8 and 10 percent through wall. The licensee reported the growth rates for the two AVB wear indications as 2.9 and 3.7 percent through wall per effective full power year (TW/EFPY), which are both less than the reported 95th percentile AVB wear growth rate of 4.0 percent TW/EFPY. The licensee stated that it is inconclusive to what caused the atypical growth rates based on a historical review of the wear pattern on and around tube R38C58. However, the licensee further stated that no historical possible loose part (PLP) indications have been reported at or around tube R38C58; therefore, it is unlikely that the atypical AVB wear growth rates are due to a foreign object.
During the clarification call on August 20, 2020, the licensee provided clarification on their use of the terms dent and ding. Specifically, the licensee uses the term ding for any signal that was present in the 1993 eddy current inspection data. The term dent is used for all signals that have been identified subsequent to the 1993 eddy current data. The terms dent and ding are not location specific and can be associated with indications in the freespan or at tube support plates.
A newly identified foreign object, shaped like a button-head bolt, was identified in SG-B that could not be removed because it was fixed in place between four adjacent tubes. Adjacent tubes Row 28, Column 34 (R28C34), Row 29, Column 34 (R29C34), and Row 29, Column 35 (R29C35) contained ding signals first reported in 1993; and adjacent tube R28C35 contained a dent signal first reported in 2009. These dent and ding signals were reported to be two to three inches above the top of the tubesheet (TTS). An additional ding signal, less than one inch above the TTS, was first reported in adjacent tube R29C34 in 2009 but was discernable back to 1993. A PLP eddy current analysis code had not been assigned to these tubes prior to RFO 31. During the August 20, 2020, clarification call, the licensee stated that the loose part was found by visual inspection initiated due to the presence of dent and ding signals in a square box pattern (the four adjacent tubes) at the same elevation. Based on a review of historical eddy current inspection data, the licensee reported that the object appears to have been lodged between the four adjacent tubes two to three inches above the TTS and visually confirmed in RFO 31 to have subsequently migrated to the TTS. During the August 20, 2020, clarification call, the licensee stated that it most likely migrated to the TTS prior to 1993 since the ding signals were present in the 1993 eddy current data. The licensee plugged the four tubes surrounding the loose part and will continue to monitor the surrounding tubes during future SG tube inspections.
During RFO 31, ultrasonic testing thickness measurements identified external wall thinning on the feedring in SG-B that appears to have been caused by impingement when feedwater discharges from the neighboring j-tube. The licensee addressed the external wall thinning of the feedring during RFO 31 by adding a weld build-up to the wall of the feedring in the affected area.
Based on a review of the information provided, the NRC staff concludes that the licensee provided the information required by their technical specifications. In addition, the staff concludes that there are no technical issues that warrant additional follow-up action at this time since the inspections appear to be consistent with the objective of detecting potential tube degradation, and the inspection results appear to be consistent with industry operating experience at similarly designed and operated units.