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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-2024-004, Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years2024-01-18018 January 2024 Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years L-2024-002, Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2024-01-0808 January 2024 Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump 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-2023-179, Unusual or Important Environmental Event - Turtle Mortality2023-12-14014 December 2023 Unusual or Important Environmental Event - Turtle Mortality L-2023-168, License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 52023-12-12012 December 2023 License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 5 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-2023-162, Response to 50.69 2nd Round of Rals2023-11-21021 November 2023 Response to 50.69 2nd Round of Rals L-2023-131, Subsequent License Renewal Application - Second Annual Update2023-09-28028 September 2023 Subsequent License Renewal Application - Second Annual Update L-2023-136, Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-26026 September 2023 Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-122, Corrections to the 2022 Annual Radiological Environmental Operating Report2023-09-20020 September 2023 Corrections to the 2022 Annual Radiological Environmental Operating Report L-2023-127, Correction to the 2022 Annual Radioactive Effluent Release Report2023-09-18018 September 2023 Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-113, Correction to the 2020 Annual Radiological Environmental Operating Report2023-09-14014 September 2023 Correction to the 2020 Annual Radiological Environmental Operating Report L-2023-118, Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-11011 September 2023 Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-108, Report of 10 CFR 50.59 Plant Changes2023-09-11011 September 2023 Report of 10 CFR 50.59 Plant Changes L-2023-112, Corrections to the 2021 Annual Radioactive Effluent Release Report2023-09-0606 September 2023 Corrections to the 2021 Annual Radioactive Effluent Release Report L-2023-107, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.42023-09-0606 September 2023 Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4 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-2023-105, Preparation and Scheduling of Operator Licensing Examinations2023-08-0303 August 2023 Preparation and Scheduling of Operator Licensing Examinations L-2023-099, Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2023-07-26026 July 2023 Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump L-2023-102, Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches2023-07-26026 July 2023 Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches L-2023-097, Subsequent License Renewal Application Revision 1 - Supplement 62023-07-13013 July 2023 Subsequent License Renewal Application Revision 1 - Supplement 6 L-2023-076, In-Service Inspection Program Owner'S Activity Report (OAR-1)2023-07-11011 July 2023 In-Service Inspection Program Owner'S Activity Report (OAR-1) 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-2023-082, Subsequent License Renewal Application Revision 1, Supplement 52023-06-14014 June 2023 Subsequent License Renewal Application Revision 1, Supplement 5 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-2023-071, 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-2023-059, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response2023-04-21021 April 2023 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response L-2023-055, 2022 Annual Environmental Operating Report2023-04-12012 April 2023 2022 Annual Environmental Operating Report L-2023-041, Annual Radiological Environmental Operating Report for Calendar Year 20222023-04-0404 April 2023 Annual Radiological Environmental Operating Report for Calendar Year 2022 L-2023-051, Report of 10 CFR 50.59 Plant Changes2023-04-0404 April 2023 Report of 10 CFR 50.59 Plant Changes 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-2023-042, Periodic Update of Population Data within 10 and 50 Miles of the Plant2023-03-27027 March 2023 Periodic Update of Population Data within 10 and 50 Miles of the Plant L-2023-026, Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 42023-03-27027 March 2023 Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 4 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-2023-039, Cycle 27 Core Operating Limits Report2023-03-0707 March 2023 Cycle 27 Core Operating Limits Report L-2023-032, 2022 Annual Radioactive Effluent Release Report2023-02-28028 February 2023 2022 Annual Radioactive Effluent Release Report L-2023-038, 2022 Annual Operating Report2023-02-28028 February 2023 2022 Annual Operating Report L-2023-016, Radiological Emergency Plan - Revision 74 Report of Changes to Emergency Plan2023-02-15015 February 2023 Radiological Emergency Plan - Revision 74 Report of Changes to Emergency Plan L-2023-019, Annual Summary of Commitment Changes Implemented Without Prior NRC Notification for Calendar Year 20222023-02-15015 February 2023 Annual Summary of Commitment Changes Implemented Without Prior NRC Notification for Calendar Year 2022 L-2023-009, Owner'S Activity Report2023-01-31031 January 2023 Owner'S Activity Report L-2022-188, Unusual or Important Environmental Event - Turtle Mortality2022-12-19019 December 2022 Unusual or Important Environmental Event - Turtle Mortality 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-2022-175, Application to Adopt 10 CPR 50.69, 'Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2022-12-0202 December 2022 Application to Adopt 10 CPR 50.69, 'Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors 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-2022-165, Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) 4.3.1-1a(second Round) - Class 1 Fatigue Response2022-10-26026 October 2022 Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) 4.3.1-1a(second Round) - Class 1 Fatigue Response 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 2024-01-08
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0 FPL Florida Power &Light Company, 6501 S. Ocean Drive, Jensen Beach, FL 34957 February 29, 2012 L-2012-084 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Re: St. Lucie Plant Unit 1 Docket No. 50-335 Renewed Facility Operating License No. DPR-67 Supplemental Information for the Extended Power Uprate License Amendment Request Related to the Post-Loss of Coolant Accident (LOCA) Boric Acid Precipitation Analysis
References:
(1) R. L. Anderson (FPL) to U.S. Nuclear Regulatory Commission (L-2010-259), "License Amendment Request (LAR) for Extended Power Uprate," November 22, 2010, Accession No. ML103560419.
(2) R. L. Anderson (FPL) to U.S. Nuclear Regulatory Commission (L-2010-442), "Response to NRC Nuclear Performance and Code Review Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request,"
October 20, 2011, Accession No. ML11297A198.
By letter L-2010-259 dated November 22, 2010 [Reference 1], Florida Power & Light Company (FPL) requested to amend Renewed Facility Operating License No. DPR-67 and revise the St. Lucie Unit 1 Technical Specifications (TS). The proposed amendment will increase the unit's licensed core thermal power level from 2700 megawatts thermal (MWt) to 3020 MWt and revise the Renewed Facility Operating License and TS to support operation at this increased core thermal power level. This represents an approximate increase of 11.85% and is therefore considered an Extended Power Uprate (EPU).
By letter L-2011-442 [Reference 2], FPL provided response to the NRC staff Nuclear Performance and Code Review Branch (SNPB) request for additional information (RAI) related to post-LOCA boric acid precipitation. The boric acid precipitation analysis was updated to reflect revised hot leg injection requirements. The attachment to this letter transmits supplemental information for the EPU License Amendment Request (LAR) Attachment 5 Section 2.8.5.6.3.5, Technical Evaluation - Post-LOCA Boric Acid Precipitation and the RAI responses provided in Reference 2.
an FPL Group company &_? jj
L-2012-084 Page 2 of 2 This submittal contains no new commitments and no revisions to existing commitments.
This submittal does not alter the significant hazards consideration or environmental assessment previously submitted by FPL letter L-2010-259 [Reference 1].
In accordance with 10 CFR 50.91 (b)(1), a copy of this letter is being forwarded to the designated State of Florida official.
Should you have any questions regarding this submittal, please contact Mr. Christopher Wasik, St. Lucie Extended Power Uprate LAR Project Manager, at 772-467-7138.
I declare under penalty of perjury that the foregoing is true and correct to the best of my knowledge.
Executed on A'Y- F ,
Very truly yours, Site Vice President St. Lucie Plant Attachment cc: Mr. William Passetti, Florida Department of Health
L-2012-084 Attachment Page 1 of 4 SUPPLEMENTAL INFORMATION FOR THE EXTENDED POWER UPRATE LICENSE AMENDMENT REQUEST By letter L-2010-259, dated November 22, 2010, Accession Number ML103560419, Florida Power & Light (FPL) requested to amend the St. Lucie Unit 1 Renewed Facility Operating License to increase the licensed core thermal power level from 2700 megawatts thermal (MWt) to 3020 MWt, which constitutes an extended power uprate (EPU).
By letter L-2011-442, dated October 20, 2011, Accession No. ML11297A198, FPL provided a response to the NRC staff Nuclear Performance and Code Review Branch (SNPB) request for additional information (RAI) related to the EPU post-LOCA boric acid precipitation analysis. The EPU boric acid precipitation analysis has since been updated to reflect revised hot leg injection requirements. The following is provided as supplemental information to the EPU License Amendment Request and the referenced response to SNPB RAIs.
Supplemental Information for LAR Attachment 5 Section 2.8.5.6.3.5, Technical Evaluation - Post LOCA Boric Acid Precipitation.
- 1. Summary of Change During the winter 2012 EPU implementation outage, FPL performed testing of the hot leg injection (HLI) flow paths. Following that testing, FPL updated the boric acid precipitation analysis to reflect a minimum required HLI flow rate of 229 gpm. This value revises the value identified in the EPU LAR and is supported by the analysis updates described below. The methodology used for the revised analysis remains unchanged from the previously submitted EPU analysis.
- 2. Input Consideration Certain plant specific input values used in the analysis are changed to support the new minimum HLI flow rate requirement. A comparison of the values used for these parameters in the previously submitted boric acid precipitation analysis and those in the revised analysis is provided below:
Parameter Previous Value New Value (Current EPU Analysis) (EPU Re-analysis)
HLI flow rate (gpm) 250 229 Maximum refueling water tank (RWT) 2600 2300 boric acid concentration (ppm)
Maximum safety injection tank (SIT) 2600 2300 boric acid concentration (ppm)
Maximum RWI volume (gallons) 705,000 580,000 Boric Acid Solubility Limit (wt%) 27.6 29.27
L-2012-084 Attachment Page 2 of 4 The previous EPU boric acid precipitation analysis value for maximum RWT volume is greater than the actual maximum volume. A higher RWT volume is conservative, as it introduces more boric acid into the reactor coolant system (RCS). A solubility limit of 29.27 wt% has been credited. This is the solubility limit of boric acid in water at atmospheric pressure and at the boiling point temperature of the boric acid solution in water (218 0 F). The maximum RWT and SIT boric acid concentrations are plant specific inputs that are administratively maintained.
- 3. Summary of Results The boric acid precipitation analysis was revised to address the revised input conditions documented above and the revised results were evaluated against the previous EPU evaluations. The re-analysis determined that beginning simultaneous hot and cold leg injection at 6.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> post-LOCA, with a HLI flow rate of 229 gpm provides acceptable results. At 6.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> post-LOCA, the HLI (229 gpm) is less than the boil-off rate of approximately 250 gpm.
The analysis credits flushing only after HLI exceeds boil-off, which begins at approximately 8.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> post-LOCA for the re-analysis. Flushing is equal to HLI minus boil-off rate. The case of 229 gpm of HLI begun at 6.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> post-LOCA resulted in a maximum boric acid concentration of 29.1 wt% at 9.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />, which is less than the solubility limit of 29.27 wt%.
Based on the results of the re-analysis, seen in Table 1, the maximum core boric acid concentration remains less than the solubility limit. Therefore, the proposed EPU remains acceptable with the revised EPU boric acid precipitation analysis.
Figure 1 shows the results of the post-LOCA boric acid precipitation analysis by comparing the boric acid concentration as a-function of time for HLI flow rate of 229 gpm and a flushing flow of 20 gpm.
Figure 2 shows the reactor vessel flow rate comparison. The required minimum simultaneous hot and cold leg flow rate for EPU increased as follows: (1) from 190 gpm for the current condition to 229 gpm to the hot leg for EPU, and (3).from 235 gpm for the current condition to 275 gpm to the cold leg for EPU. It has been confirmed that a minimum hot-and cold leg injection flow rate of 229 gpm to the hot leg and 275 gpm to-he cold leg will be available within the four to six hour window post-LOCA for EPU.
Table I Summary of Results for the Updated Boric Acid Precipitation Analysis EPU Analysis -
CENPD-254-P-A Methodology Modified by the Waterford Approach Parameter EPU Result Boric acid solubility limit 29.27 wt%
Time boric acid concentration reaches solubility limit with no HLI 9.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> Minimum simultaneous hot and cold leg injection flow rates Hot leg 229 gpm Cold leg 275 gpm Initiation time for simultaneous hot and cold leg injection 4 to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> post-LOCA Minimum core boric acid concentration with 229 gpm HLI started 29.1 wt% at 9.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> post-LOCA at 6.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> Maximum core boric acid concentration with 20 gpm flushing flow 21.9 wt% at 6.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> post-LOCA initiated at 6.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />
L-2012-084 Attachment Page 3 of 4 Figure 1 Updated Boric Acid Precipitation Analysis Boric Acid Concentration in the Core versus Time 40 30 z2f-N.*
0 20 'N, z
0 U
0M 10 NO HLI
Solubility t imit (29.27 wt%
- 229gpm LI I-t at 6 hrs
............ 20agpm R shing Ffowat 6 its I I I I I I I I II I 0
0 4 8 12 16 20 TIME AFTER LOCA, HOURS
L-2012-084 Attachment Page 4 of 4 Figure 2 Updated Boric Acid Precipitation Analysis Core Boil-off and Simultaneous Hot/Cold Leg Injection versus Time 600
- I I II I i I I I I I I I I I I I i I I I 500 400 0~
C9 300 U_
200 100 BOIL OFF CURVE
HLI=2M9GP V1At 6hrs 0
0 5 10 15 20 25 TIME AFTER LOCA, HOURS