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Category:Letter
MONTHYEARIR 05000335/20230102024-01-26026 January 2024 NRC Quadrennial Focused Engineering Inspection (FEI) Commercial Grade Dedication Report 05000335/2023010 and 05000389/2023010 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) IR 05000335/20230042024-01-24024 January 2024 Integrated Inspection Report 05000335/2023004 and 05000389/2023004 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, ML23332A1772023-11-28028 November 2023 Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-162, Response to 50.69 2nd Round of Rals2023-11-21021 November 2023 Response to 50.69 2nd Round of Rals IR 05000335/20230032023-11-0606 November 2023 Integrated Inspection Report 05000335/2023003 and 05000389/2023003 ML23270B8882023-10-23023 October 2023 Regulatory Audit Summary Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structure, Systems, and Components for Nuclear Power Reactors EPID L-2022-LLA-0182 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 ML23275A1102023-10-0202 October 2023 License Amendment Request Revision 2 for the Technical Specifications Conversion to NUREG-1432, Revision 5 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 IR 05000335/20233012023-09-20020 September 2023 NRC Operator License Examination Report 05000335/2023301 and 05000389/2023301 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-2023-108, Report of 10 CFR 50.59 Plant Changes2023-09-11011 September 2023 Report of 10 CFR 50.59 Plant Changes 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-2023-112, 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 ML23219A0042023-09-0101 September 2023 Transmittal Letter - Safety Evaluation Related to the SLRA of St. Lucie Plant, Units 1and 2, Revision 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 IR 05000335/20230022023-08-0707 August 2023 Integrated Inspection Report 05000335/2023002 and 05000389/2023002 L-2023-105, Preparation and Scheduling of Operator Licensing Examinations2023-08-0303 August 2023 Preparation and Scheduling of Operator Licensing Examinations ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment ML23212B2652023-07-27027 July 2023 Operator Licensing Written Examination Approval 05000335/2023301 and 05000389/2023301 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 ML23200A1232023-07-21021 July 2023 Transmittal Letter for the St. Lucie SLRA Review 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) ML23184A0352023-06-30030 June 2023 Notification of St. Lucie Units 1 & 2 Focused Engineering Inspection (FEI) 05000335/2023010 and 05000389/2023010 and Initial Information Request 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) IR 05000335/20234032023-06-29029 June 2023 Security Inspection Report 05000335/2023403 and 05000389/2023403 IR 05000335/20234022023-06-20020 June 2023 Security Baseline Inspection Report 05000335/2023402 and 05000389/2023402 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 IR 05000335/20234012023-05-16016 May 2023 Cyber Security Inspection Report 05000335/2023401 and 05000389/2023401 (Cover Letter) IR 05000335/20230012023-05-0909 May 2023 Integrated Inspection Report 05000335/2023001 and 05000389/2023001 ML23109A1132023-04-30030 April 2023 SLRA Change Schedule Letter 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 ML23097A1642023-04-17017 April 2023 Summary of March 23, 2023, Meeting with Florida Power and Light on St. Lucie and Turkey Point Improved Technical Specifications Conversion License Amendment Requests L-2023-055, 2022 Annual Environmental Operating Report2023-04-12012 April 2023 2022 Annual Environmental Operating Report 2024-01-08
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October 4, 2006 Mr. J. A. Stall Senior Vice President, Nuclear and Chief Nuclear Officer Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420
SUBJECT:
ST. LUCIE NUCLEAR PLANT, UNITS 1 AND 2 - NRC RECEIPT OF RESPONSE TO GENERIC LETTER 2003-01, CONTROL ROOM HABITABILITY (TAC NOS. MB9849 AND MB9850)
Dear Mr. Stall:
The Nuclear Regulatory Commission (NRC) acknowledges the receipt of your response to Generic Letter (GL) 2003-01, Control Room Habitability, in letters dated August 11, 2003 (Agencywide Documents Access and Management System Accession No. ML032250375),
December 9, 2003 (ML033450304), and October 29, 2004 (ML043070441). This letter provides a status of your response and describes any additional information that may be necessary to consider your response to GL 2003-01 complete.
The GL requested that you confirm that the St. Lucie Unit 1 and 2 control rooms meet their design bases (e.g., General Design Criteria [GDC] 1, 3, 4, 5 and 19, draft GDC, or principal design criteria), with special attention to: (1) Determination of the most limiting unfiltered and/or filtered inleakage into the control room and comparison to values used in your design bases for meeting control room operator dose limits from accidents (GL 2003-01, Item 1a),
(2) Determination that the most limiting unfiltered inleakage is incorporated into your hazardous chemical assessments (GL 2003-01, Item 1b), and (3) Determination that reactor control capability is maintained in the control room or at the alternate shutdown location in the event of smoke (GL 2003-01, Item 1b). The GL further requested information on any compensatory measures in use to demonstrate control room habitability (CRH) and plans to retire them (GL 2003-01, Item 2).
You reported the results of tracer gas tests for the St. Lucie Unit 1 and 2 control rooms, which are separate control rooms that are pressurized for accident mitigation, using American Society for Testing and Materials standard ASTM E741, Standard Test Method for Determining Air Change in a Single Zone by Means of a Tracer Gas Dilution.
For Unit 1, you determined that the maximum tested value for inleakage into the Control Room Envelope (CRE) was 423 cubic feet per minute (cfm), which is less than the value of 500 cfm assumed in your operability determination using the current methodology in the Updated Final Safety Analysis Report (UFSAR).
For Unit 2, you determined that the maximum tested value for inleakage into the CRE was 229 cfm, which is less than the value of 430 cfm assumed in your operability determination using the current UFSAR methodology.
Mr. J. A. Stall You stated your plan to revise each units design basis radiological dose analysis for CRH using Alternate Source Term (AST) methodology, which will add some margin by increasing the allowable leakage value.
You indicated that, based on your evaluation, you have concluded that no hazards exist to the control room personnel from postulated chemical releases in and around the plant. You also indicated that reactor control capability is maintained from either the control room or the alternate shutdown panel in the event of smoke.
The GL further requested that you assess your Technical Specifications (TSs) to determine if they verify the integrity of the CRE, including ongoing verification of the inleakage assumed in the design basis analyses for CRH, in light of the demonstrated inadequacy of a delta () P measurement as the only method to provide such verification (GL 2003-01, Item 1c). As permitted by the GL, you provided a schedule for revising the surveillance requirements (SRs) in the TSs to reference an acceptable surveillance methodology. In your October 29, 2004, response, you indicated that you will submit a license amendment request (LAR) to adopt TS SRs that verify CRH per TS Task Force (TSTF) traveler TSTF-448 within 6 months following NRC approval of TSTF-448.
The information you provided indicated that there are no interim compensatory measures currently required to demonstrate CRH. The NRC staff notes that you rely on an operability determination to demonstrate CRH, which needs to be retired by changing the design basis information in the UFSAR. However, the NRC staff also notes that you have committed to revise your UFSAR design basis radiological dose analyses for CRH using AST methodology.
The information you provided supported the NRC staff conclusion that your are committed to meet the draft GDC for Unit 1 and the GDC for Unit 2 regarding CRH.
Your commitment to revise your design basis radiological dose analyses for CRH using AST methodology and to adopt industry standard TSs based on TSTF-448 is acceptable for purposes of closing out your response to GL 2003-01. The NRC staff will monitor submission of the LARs and interact with you, as necessary, during the amendment process.
If you have any questions regarding this correspondence, please contact me at (301) 415-3974.
Sincerely,
/RA Brendan T. Moroney, Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-335 and 50-389 cc: See next page
ML062510064 NRR-106 OFFICE LPL2-2/PM LPL2-2/LA SCVB/BC PGCB/BC LPL2-2/BC(A)
NAME BMoroney BClayton RDennig CJackson LRaghavan DATE 09/14 /06 09/14/06 09/18/06 09/18/06 10/04/06 Mr. J. A. Stall ST. LUCIE PLANT Florida Power and Light Company cc:
Mr. William E. Webster Mr. Christopher R. Costanzo Vice President, Nuclear Operations Plant General Manager Florida Power & Light Company St. Lucie Nuclear Plant P.O. Box 14000 6351 South Ocean Drive Juno Beach, FL 33408-0420 Jensen Beach, Florida 34957 Senior Resident Inspector Mr. Terry Patterson St. Lucie Plant Licensing Manager U.S. Nuclear Regulatory Commission St. Lucie Nuclear Plant P.O. Box 6090 6351 South Ocean Drive Jensen Beach, Florida 34957 Jensen Beach, Florida 34957 Craig Fugate, Director Mark Warner, Vice President Division of Emergency Preparedness Nuclear Operations Support Department of Community Affairs Florida Power & Light Company 2740 Centerview Drive P.O. Box 14000 Tallahassee, Florida 32399-2100 Juno Beach, FL 33408-0420 M. S. Ross, Managing Attorney Mr. Rajiv S. Kundalkar Florida Power & Light Company Vice President - Nuclear Engineering P.O. Box 14000 Florida Power & Light Company Juno Beach, FL 33408-0420 P.O. Box 14000 Juno Beach, FL 33408-0420 Marjan Mashhadi, Senior Attorney Florida Power & Light Company Mr. J. Kammel 801 Pennsylvania Avenue, NW. Radiological Emergency Suite 220 Planning Administrator Washington, DC 20004 Department of Public Safety 6000 Southeast Tower Drive Mr. Douglas Anderson Stuart, Florida 34997 County Administrator St. Lucie County Mr. Bill Parks 2300 Virginia Avenue Operations Manager Fort Pierce, Florida 34982 St. Lucie Nuclear Plant 6351 South Ocean Drive Mr. William A. Passetti, Chief Jensen Beach, Florida 34957-2000 Department of Health Bureau of Radiation Control Mr. Seth B. Duston 2020 Capital Circle, SE, Bin #C21 Training Manager Tallahassee, Florida 32399-1741 St. Lucie Nuclear Plant 6351 South Ocean Drive Mr. Gordon L. Johnston Jensen Beach, Florida 34957-2000 Site Vice President St. Lucie Nuclear Plant 6351 South Ocean Drive Jensen Beach, Florida 34957-2000