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Category:Letter type:L
MONTHYEARL-2024-122, Core Operating Limits Report2024-08-12012 August 2024 Core Operating Limits Report L-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-2024-089, 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 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 L-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update 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-2024-076, 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 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 L-2024-073, Cycle 34 Core Operating Limits Report2024-05-0101 May 2024 Cycle 34 Core Operating Limits Report 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 L-2024-047, Proposed Use of a Subsequent ASME Code Edition and Addenda2024-03-28028 March 2024 Proposed Use of a Subsequent ASME Code Edition and Addenda L-2024-040, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections2024-03-28028 March 2024 Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections L-2024-013, Submittal of Periodic Reports2024-03-28028 March 2024 Submittal of Periodic Reports L-2024-044, Revised Steam Generator Tube Inspection Reports2024-03-19019 March 2024 Revised Steam Generator Tube Inspection Reports L-2024-011, 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 Applications2024-03-13013 March 2024 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-2024-014, Turkey Points, Units 3 and 4 - 2023 Annual Radioactive Effluent Release Report2024-02-29029 February 2024 Turkey Points, Units 3 and 4 - 2023 Annual Radioactive Effluent Release Report L-2024-025, Notification of Improved Standard Technical Specifications (ITS) Implementation2024-02-22022 February 2024 Notification of Improved Standard Technical Specifications (ITS) Implementation L-2024-008, Supplement to 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 Cycles2024-02-0909 February 2024 Supplement to 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-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 2024-08-12
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L-2013-002 10 CFR 50.90 JAN 1 1 2013 FPL.
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 Response to NRC Request for Additional Information Regarding License Amendment Request No. 224 on Technical Specification 3/4.6.2.3 -
Recirculation pH Control System and NaTB Basket Minimum Loading Requirement
References:
(1) M. Kiley (FPL) to U.S. Nuclear Regulatory Commission (L-2012-314), "License Amendment Request No. 224 Regarding Technical Specification 3/4.6.2.3 - Recirculation pH Control System and NaTB Basket Minimum Loading Requirement," Accession No. ML12251A249, September 6, 2012.
(2) Email from Tracy Orf (NRC) to Olga Hanek (FPL), "Draft RAIs re: Sump pH LAR,"
November 30, 2012.
By letter L-2012-314 dated September 6, 2012 [Reference 1], Florida Power & Light Company (FPL) requested to amend Renewed Facility Operating Licenses DPR-31 and DPR-41 and revise the Turkey Point Units 3 and 4 Technical Specifications (TS). The proposed amendment will decrease the minimum required mass of sodium tetraborate decahydrate (NaTB) specified in TS Surveillance Requirement 4.6.2.3 from 11,061 lbms to 7,500 lbms in order to lessen the long term sump pH profile, recover design margin, and facilitate NaTB basket loading and maintenance.
TS 3.6.2.3 addresses the requirements for the Recirculation pH Control System which is a passive safeguard consisting of ten stainless steel wire mesh baskets located in the containment basement and containing a total of at least 11,061 Ibm of NaTB. This passive system assures that there is sufficient NaTB available in the containment to ensure a sump pH greater than 7.0 at the onset of the recirculation phase of a postulated loss-of-coolant accident (LOCA).
By email from the U.S. Nuclear Regulatory Commission (NRC) Project Manager (PM) dated November 30, 2012 [Reference 2], additional information regarding the effects of the proposed reduction in basket loading was requested by the staff in NRC's Steam Generator Tube Integrity and Chemical Engineering Branch (ESGB) to support review of the NaTB License Amendment Request (LAR). The RAI consisted of two (2) questions regarding the projected post-LOCA minimum sump pH profile for 7,500 lbms and the impact of this reduced NaTB loading on post-LOCA chemical precipitate generation. On December 11, 2012, a meeting was held between FPL and NRC representatives to discuss these questions. Based on this discussion, the two RAI questions and the applicable FPL responses are provided in the Attachment to this letter.
This submittal does not alter the significant hazards consideration or environmental assessment previously submitted by FPL letter L-2012-3 14 [Reference 1].
This submittal contains no new commitments and no revisions to existing commitments.
Florida Power & Light Company 9760 SW 344 St., Florida City, FL 33035
Turkey Point Units 3 and 4 L-2013-002 Docket Nos. 50-250 and 50-251 Page 2 of 2 In accordance with 10 CFR 50.91(b)(1), a copy of this letter is being forwarded to the State Designee of Florida.
Should you have any questions regarding this submittal, please contact Mr. Robert J. Tomonto, Licensing Manager, at (305) 246-7327.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on January //, 2013.
Very truly yours, Michael Kiley Site Vice President Turkey Point Nuclear Plant Attachment cc: USNRC Regional Administrator, Region II USNRC Project Manager, Turkey Point Nuclear Plant USNRC Senior Resident Inspector, Turkey Point Nuclear Plant Ms. Cindy Becker, Florida Department of Health Florida Power &Light Company 9760 SW 344 St., Florida City, FL 33035
Turkey Point Units 3 and 4 L-2013-002 Docket Nos. 50-250 and 50-251 Attachment Page 1 of 3 Turkey Point Units 3 and 4 Response to NRC Request for Additional Information Regarding License Amendment Request No. 224 on Technical Specification 3/4.6.2.3 -
Recirculation pH Control System and NaTB Basket Minimum Loading Requirement ATTACHMENT
Turkey Point Units 3 and 4 L-2013-002 Docket Nos. 50-250 and 50-251 Attachment Page 2 of 3 Response to Request for Additional Information The following information is provided by Florida Power & Light Company (FPL) in response to the U. S. Nuclear Regulatory Commission's (NRC) Request for Additional Information (RAI). This information was requested to support License Amendment Request (LAR) No. 224, TS 3/4.6.2.3 -
Recirculation pH Control System and NaTB Basket Minimum Loading Requirement, for Turkey Point Nuclear Plant (PTN) Units 3 and 4 that was submitted to the NRC by FPL letter L-2012-314 on September 6, 2012 [Reference 1].
In an email dated November 30, 2012 [Reference 2], the NRC staff requested additional information regarding FPL's request to implement the proposed reduction in NaTB basket loading under LAR 224. The RAI consisted of two (2) questions from the NRC's Steam Generator Tube Integrity and Chemical Engineering Branch (ESGB) regarding the projected post-LOCA minimum sump pH profile at 7,500 lbms and impact of this reduced NaTB loading on post-LOCA chemical precipitate generation. On December 11, 2012, a telephone call was held between FPL and NRC representatives to discuss these questions. Based on the discussion, the two RAI questions and the applicable FPL responses are documented below.
ESGB-1 License amendment request (LAR) 224 dated September 6, 2012 (ADAMS Accession No. ML12251A249) indicates that a minimum 7500 Ibm sodium tetraborate decahydrate (STB) basket loading will ensure sump pH remains above 7.0 throughout the recirculation phase of a loss of coolant accident. Please provide a plot of sump pH profile as a function of time assuming 75001bm STB and plant conditions that would result in a minimum p11 profile. In addition, either confirm that the methodology used to calculate pH was the same as provided to the NRC in letter dated April 28, 2010 (Accession No. ML101200063) or describe the differences.
9.0 Sump pH for Case 8 8.5 8.0 7.5 7.0- / 2725 seo,7,045 pH 6.5 6.0 5.5 5.0 4.5 4 .0 -.. .. ..
10 100 1000 10000 100000 1000000 10000000 Time (sec)
Figure 1: Minimum Sump pH curve with 75001bs NaTB in sump baskets.
Turkey Point Units 3 and 4 L-2013-002 Docket Nos. 50-250 and 50-251 Attachment Page 3 of 3 The methodology, i.e., Palmer Method, used to calculate the minimum sump pH profile above is the same as that provided to the NRC in FPL letter L-2010-082 dated April 28, 2010 [Reference 3].
ESGB-2 The LAR also indicates that by reducing the STB quantity and therefore peak pH, the post-accident chemical precipitate generation is reduced. Please discuss the quantity of precipitate reduction associated with reducing the peak pH values. For example, providing a quantity of precipitates calculated by the WCAP-16530-NP-A method for a peak pH of 8.01 as compared to a pH of 7.68 would be one way to respond to this question.
As indicated in FPL letter L-2012-3 14 [Reference 1], the proposed reduction in the total TS required mass of NaTB in the baskets from 11,061 lbms to 7,500 lbms will decrease the peak sump pH to approximately 7.680. Preliminary analyses of the post-LOCA chemical precipitate generation using the above WCAP methodology for these two cases will reduce the quantity of chemical precipitate generated by approximately 6.5% for Unit 3 and approximately 5.2% for Unit 4.
References
- 1. M. Kiley (FPL) to U.S. Nuclear Regulatory Commission (L-2012-314), "License Amendment Request No. 224 Regarding Technical Specification 3/4.6.2.3 - Recirculation pH Control System and NaTB Basket Minimum Loading Requirement," Accession No. ML12251A249, September 6, 2012.
- 2. Email from Tracy Orf (NRC) to Olga Hanek (FPL), "Draft RAIs re: Sump pH LAR,"
November 30, 2012.
- 3. M. Kiley (FPL) to U.S. Nuclear Regulatory Commission (L-2010-082), "Supplement to License Amendment Request 196 (ADAMS Accession No. ML092050112) - Revised Summary of Turkey Point Sump pH Calculation Inputs, Assumptions, Methodology, and Results," Accession No. ML101200063, April 28, 2010.