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Category:Letter
MONTHYEARL-2024-106, Fifth and Sixth 10-Year Inservice Testing Interval Relief Request No. VR-022024-08-12012 August 2024 Fifth and Sixth 10-Year Inservice Testing Interval Relief Request No. VR-02 L-2024-122, Core Operating Limits Report2024-08-12012 August 2024 Core Operating Limits Report IR 05000250/20240112024-08-0606 August 2024 Comprehensive Engineering Team Inspection (CETI) Inspection Report 05000250/2024011 and 05000251/2024011 ML24163A0012024-08-0505 August 2024 LTR-24-0119-1-1 Response to Nh Letter Regarding Review of NextEras Emergency Preparedness Amendment Review L-2024-089, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP- 17 451-P. Revision 1. Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections2024-07-25025 July 2024 Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP- 17 451-P. Revision 1. Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024 Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes ML24184B2822024-07-16016 July 2024 – Request to Use a Later Code Edition and Addenda of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML24193A2432024-07-12012 July 2024 – Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024 Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal ML24173A1902024-06-28028 June 2024 Withdrawal of an Amendment Request ML24159A2652024-06-26026 June 2024 Correction of Safety Evaluation for Issuance of Amendment Nos. 298 & 291 Regarding Revising the Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2024-100, Withdrawal of License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project2024-06-19019 June 2024 Withdrawal of License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project L-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update ML24149A2862024-06-12012 June 2024 NextEra Fleet - Proposed Alternative Frr 23-01 to Use ASME Code Case N-752-1, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section X1, Division 1 (EPID L-2023-LLR-0009) - Letter IR 05000250/20244012024-06-0505 June 2024 – Security Baseline Inspection Report 05000250-2024401, 05000251-2024401 and 07200062-2024401 L-2024-076, Reply to Notice of Violation; NOV 05000250, 05000251/2024010-052024-05-29029 May 2024 Reply to Notice of Violation; NOV 05000250, 05000251/2024010-05 L-2024-082, 2023 Annual Radiological Environmental Operating Report2024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report IR 05000250/20240012024-05-10010 May 2024 Integrated Inspection Report 05000250/2024001 and 05000251/2024001 L-2024-060, 10 CFR 50.59(d)(2) Evaluation and 10 CFR 50.71(e)(2) Technical Specification Bases Summaries Report2024-05-0909 May 2024 10 CFR 50.59(d)(2) Evaluation and 10 CFR 50.71(e)(2) Technical Specification Bases Summaries Report ML24127A1862024-05-0909 May 2024 Request for Withholding Information from Public Disclosure ML24135A0942024-05-0909 May 2024 Periodic Update to the Updated Final Safety Analysis Report ML24127A0632024-05-0606 May 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-073, Cycle 34 Core Operating Limits Report2024-05-0101 May 2024 Cycle 34 Core Operating Limits Report IR 05000250/20240102024-05-0101 May 2024 Design Basis Assurance Inspection Programs Inspection Report 05000250/2024010 and 05000251/2024010 and Notice of Violation L-2024-072, Cycle 33 Core Operating Limits Report2024-05-0101 May 2024 Cycle 33 Core Operating Limits Report L-2024-048, Divider Plate Assemblies Bounding Analysis Evaluation for Subsequent License Renewal Commitment Revision2024-04-30030 April 2024 Divider Plate Assemblies Bounding Analysis Evaluation for Subsequent License Renewal Commitment Revision L-2024-069, Radiological Emergency Plan Revision 762024-04-22022 April 2024 Radiological Emergency Plan Revision 76 L-2024-066, Sixth 10-Year Inservice Testing Interval Relief Request No. PR-022024-04-17017 April 2024 Sixth 10-Year Inservice Testing Interval Relief Request No. PR-02 ML24023A0342024-02-0505 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) 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 ML23341A2102024-01-22022 January 2024 LTR-23-0216-1 - Closure Letter - 2.206 Petition for License Renewal Plant Reactor Pressure Vessel Embrittlement 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 2024-08-06
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April 28, 2015 L-2015-113 FPL. 10 CFR 50.46 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555-0001 Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 10 CFR 50.46, "Acceptance Criteria for Emergency Core Cooling Systems in Light Water Nuclear Power Reactors" - 2014 Annual Report
References:
- 1. FPL letter from Michael Kiley to U.S. NRC Document Control Desk, "Turkey Point Units 3 and 4, Docket Nos. 50-250 and 50-251, 10 CFR 50.46, 'Acceptance Criteria for Emergency Core Cooling Systems in Light Water Nuclear Power Reactors' - 2013 Annual Report and 30-Day Special Report," L-2014-084, April 6, 2014.
- 2. FPL Letter, M. Kiley to U. S. Nuclear Regulatory Commission, "Turkey Point Units 3 and 4, Dockets Nos. 50-250 and 50-251, 10 CFR 50.46, 'Acceptance Criteria for Emergency Core Cooling Systems in Light Water Nuclear Power Reactors' - 30 Day Special Report," L-2014-037, Accession No. ML14069A082, February 18, 2014.
- 3. FPL letter, M. Kiley to U. S. Nuclear Regulatory Commission, "Turkey Point Unit 3, Dockets No. 50-250, 10 CFR 50.46, 'Acceptance Criteria for Emergency Core Cooling Systems in Light Water Nuclear Power Reactors'- 30 Day Special Report," L-2014-077, Accession No.
ML14098A469, March 24, 2014.
- 4. FPL letter, M. Kiley to U. S. Nuclear Regulatory Commission, "Turkey Point Units 4, Dockets No. 50-251, 10 CFR 50.46, 'Acceptance Criteria for Emergency Core Cooling Systems in Light Water Nuclear Power Reactors' - 30 Day Special Report," L-2014-302, Accession No.
ML14310A292, October 15, 2014
- 5. FPL letter, M. Kiley to U. S. Nuclear Regulatory Commission, "Turkey Point Units 3 and 4, Dockets Nos. 50-250 and 50-251, 10 CFR 50.46, 'Acceptance Criteria for Emergency Core Cooling Systems in Light Water Nuclear Power Reactors'- 30 Day Special Report," L-2014-359, Accession No. ML14351A073, December 3, 2014.
- 6. Westinghouse Letter, M. W. James to R. Klein, "Florida Power and Light Company Turkey Point Units 3 & 4- 10 CFR 50.46 Annual Notification and Reporting for 2014," NF-NEXT-1 5-46, March 9, 2015.
10 CFR 50.46 2013 Annual Report 10 CFR 50.46(a)(3)(ii) requires that licensees report to the Commission at least annually the nature of changes to, or errors discovered in, the Emergency Core Cooling System (ECCS) evaluation models (EM), or in the application of such models that affect the peak clad temperature calculation and their effect on the limiting ECCS analysis. Table 1 provides the Florida Power & Light Company (FPL) 10 CFR 50.46 Peak Cladding Temperature (PCT) 2014 report for Turkey Point Units 3 and 4.
Florida Power &Light Company ODD-9760 SW 344 St Homestead, FL 33035 P"(
L-2015-113 Page 2 of 4 FPL letter L-2014-084 (Reference 1), submitted the 2013 10 CFR 50.46 Annual Report and a 30-Day Special Report. The 2013 annual report documented the Extended Power Uprate (EPU)
Large Break Loss of Cooling Accident (LBLOCA) PCT of 2115'F and EPU Small Break LOCA (SBLOCA) PCT of 1231'F for Turkey Point Units 3 and 4.
FPL letter L-2014-037 (Reference 2), submitted a 30-Day Special Report documenting an error in the LBLOCA EM in the calculation of the burst strain performed by the HOTSPOT code (Reference 2). The impact of this error resulted in an estimated PCT impact of +18 °F. The revised LBLOCA PCT for Turkey Point Units 3 and 4 was 2133 OF with a cumulative change of 89 0 F due to the EM error. The SBLOCA EM is not affected by the identified error.
FPL letter L-2014-084 (Reference 1), submitted a 30-Day Special Report documenting several LBLOCA EM errors. One issue was related to the grid heat transfer enhancement calculation which potentially affected the heat transfer at gridded elevations. Another error was introduced due to a change in the methodology used to calculate grid blockage ratio and porosity. The methodology change resulted in a change to the grid inputs which affected the heat transfer in the core during a LBLOCA. In addition, deficiencies were identified in the vessel Section 7 Mid-Level Elevation modeling documentation. The LBLOCA EM errors and documentation deficiencies had a negligible effect on LBLOCA analysis results, leading to an estimated PCT impact of 0°F. The 30-Day Special Report also reported the estimated PCT impact of +18 OF due to an error in the LBLOCA EM previously reported by FPL letter L-2014-037. The revised LBLOCA PCT for Turkey Point Units 3 and 4 was 2133 OF with a cumulative change of 89°F due to the EM error.
FPL letters L-2014-077 (Reference 3) and L-2014-302 (Reference 4) submitted a 30-Day Special Report for Units 3 and 4 respectively. The LBLOCA PCT reported in the 30 -Day special report removed the 120 F mixed core penalty no longer applicable for Unit 3 Cycle 27 and Unit 4 Cycle 28 and future cycles with only 15x1 5 Upgraded fuel assemblies. The SBLOCA PCT was not affected by the mixed core penalty.
FPL letter L-2014-359 (Reference 5) submitted a 30-Day Special Report for Turkey Point Units 3 and 4 documenting an error in the LBLOCA EM in the calculation of decay heat in the WCOBRA/TRAC code. The correction of this error resulted in an estimated impact of +3 °F on LBLOCA PCT for Turkey Point Units 3 and 4. The SBLOCA EM was not affected by the identified errors.
By letter dated March 9, 2015, Westinghouse identified several errors in the SBLOCA EM not previously discussed. Two errors were associated with the NOTRUMP computer code (reactor coolant system response model). One error was related to the fuel rod gap conductance model.
Another error was identified in the calculation of the radiation heat transfer coefficient within the fuel rod model. Other errors were identified in the pre-departure from nucleate boiling (pre-DNB) cladding surface heat transfer coefficient calculation in the SBLOCTA code (cladding heat-up calculations). The SBLOCA EM errors had a negligible effect on small break LOCA analysis results, leading to an estimated PCT impact of 0°F. The magnitude of these SBLOCA errors and the resultant cumulative changes and errors for the SBLOCA EM remain below the 50 OF 30-day reporting threshold of 10 CFR 50.46(a)(3)(i) and (ii).
Table 1 provides the Turkey Point Units 3 and 4 2014 Annual Summary listing all the changes and errors identified by Westinghouse in 2014 in the LBLOCA and SBLOCA EMs. The 2014 Turkey Point Units 3 and 4 LBLOCA and SBLOCA PCTs are 2124°F and 1231 'F, respectively.
The PCT cumulative changes are 80'F for LBLOCA and 0 °F for SBLOCA, respectively.
L-2015-113 Page 3 of 4 10 CFR 50.46(a)(3)(ii) also requires that a schedule for reanalysis be provided or compliance with the requirements of the regulation be shown ifthe error is significant. Compliance with 10 CFR 50.46 requirements is demonstrated by total estimated LBLOCA and SBLOCA PCTs of 2124°F and 1231'F, respectively, both remaining below the limit of 2200 0 F.
Should there be any questions, please contact Mitch Guth, Licensing Manager, at 305-246-6698.
Very truly yours, Michael Kiley Vice President Turkey Point Nuclear Plant cc: Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant
L-2015-113 Page 4 of 4 TABLE 1 Turkey Point Units 3 and 4 LBLOCA and SBLOCA PCT 2014 Annual Report Peak Clad Cumulative LBLOCA Temperature Change 2013 10 CFR 50.46 Annual Report (Ref. 1) 2115 OF 71 OF Errors in 2014 0
- Error in Burst Strain Application (Re. 1)+18 F +18 OF 0
- Grid Heat Transfer Enhancement Calculation (Ref. 1) 0 F 0 °F
- Changes to Grid Blockage Ratio and Porosity (Ref. 1) 0 OF 0 OF
- Vessel Section 7 Mid-Level Elevation Modeling (Ref. 1) 0 OF 0 OF
- Decay Group Uncertainty Factors Errors (Ref. 5) +3 OF +3 OF
- Temporary Mixed Core Penalty Removed (Ref. 3)(Ref. 4) -12 OF -12 OF 2014 10 CFR 50.46 Annual Report 2124 OF 80 OF SBLOCA 2013 10 CFR 50.46 Annual Report (Ref, 1) 1231 OF 0 OF Errors in 2014
- Fuel Rod Gap Conductance (Ref. 6) 0 OF 0 OF
- Radiation Heat Transfer Model (Ref. 6) 0 OF 0 OF
- SBLOCTA Pre-DNB Cladding Surface Area Heat Transfer Coefficient (Ref. 6) 0 OF 0 OF 2014 10 CFR 50.46 Annual Report 1231 OF 0 OF