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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
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARL-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 ML23275A1142023-10-0202 October 2023 Improved Technical Specifications Conversion, Chapter 2.0, Safety Limits, Revision 1 - Volume 4 L-2023-126, Enclosure 1: Contents of Improved Technical Specifications (ITS) Submittal2023-10-0202 October 2023 Enclosure 1: Contents of Improved Technical Specifications (ITS) Submittal ML23275A1262023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 5.0, Administrative Controls, Revision 2 - Volume 16 ML23275A1252023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 4.0, Design Features, Revision 2 - Volume 15 ML23275A1242023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.9, Refueling Operations, Revision 2 - Volume 14 ML23275A1232023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.8, Electrical Systems, Revision 2 - Volume 13 ML23275A1222023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.7, Plant Systems, Revision 2 - Volume 12 ML23275A1212023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.6, Containment Systems, Revision 2 - Volume 11 ML23275A1192023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.4, Reactor Coolant System, Revision 2 - Volume 9 ML23275A1202023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.5, Emergency Core Cooling Systems, Revision 2 - Volume 10 ML23275A1182023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.3, Instrumentation, Revision 2 - Volume 8 ML23275A1162023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.1, Reactivity Control Systems, Revision 2 - Volume 6 ML23275A1172023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.2, Power Distribution Limits, Revision 2 - Volume 7 ML23275A1152023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.0, LCO and SR Applicability, Revision 2 - Volume 5 ML23275A1102023-10-0202 October 2023 License Amendment Request Revision 2 for the Technical Specifications Conversion to NUREG-1432, Revision 5 ML23275A1112023-10-0202 October 2023 Improved Technical Specifications (ITS) Revision 2 Submittal Volumes 1 Through 16 ML23275A1122023-10-0202 October 2023 Improved Technical Specifications Conversion License Amendment Request Self-Identified Administrative Changes - Volume 2 L-2023-082, Subsequent License Renewal Application Revision 1, Supplement 52023-06-14014 June 2023 Subsequent License Renewal Application Revision 1, Supplement 5 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-2022-160, 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 L-2022-154, Subsequent License Renewal Application Revision 1, Supplement 42022-09-22022 September 2022 Subsequent License Renewal Application Revision 1, Supplement 4 L-2022-046, Subsequent License Renewal Application Revision - Documents WCAP-18623-P/NP Revision 1 Submittal2022-04-13013 April 2022 Subsequent License Renewal Application Revision - Documents WCAP-18623-P/NP Revision 1 Submittal L-2022-043, Subsequent License Renewal Application Revision 1 - Supplement 12022-04-0707 April 2022 Subsequent License Renewal Application Revision 1 - Supplement 1 ML22010A0962022-01-0505 January 2022 Trp 010 St Lucie SLRA - Boricacidcorrbreakoutq - Makar ML21285A1072021-10-12012 October 2021 Subsequent Licensee Renewal Application, Revision 1 ML21285A1082021-10-12012 October 2021 Enclosure 1: St. Lucie Nuclear Plant, Units 1 and 2, Subsequent Licensee Renewal Application, Revision 1 ML21285A1112021-10-12012 October 2021 Subsequent Licensee Renewal Application, Revision 1, Appendix E, Applicant'S Environmental Report L-2021-192, Subsequent Licensee Renewal Application, Revision 1, Appendix E, Applicant'S Environmental Report2021-10-12012 October 2021 Subsequent Licensee Renewal Application, Revision 1, Appendix E, Applicant'S Environmental Report L-2021-142, Westinghouse Report LTR-REA-21-1-NP, Revision 1, St. Lucie Nuclear Plant, Units 1 and 2, Subsequent License Renewal: Unit 1 Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data, May 26, 20212021-08-0303 August 2021 Westinghouse Report LTR-REA-21-1-NP, Revision 1, St. Lucie Nuclear Plant, Units 1 and 2, Subsequent License Renewal: Unit 1 Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data, May 26, 2021 ML21215A3152021-08-0303 August 2021 Application for Subsequent Renewed Facility Operating Licenses ML21215A3162021-08-0303 August 2021 Enclosure 1: Subsequent License Renewal Application Enclosures Summary ML21215A3192021-08-0303 August 2021 Appendix E - Applicant'S Environmental Report for St. Lucie L-2021-192, Westinghouse, Report LTR-REA-21-1-NP, Revision 1, St. Lucie Units 1 & 2 Subsequent License Renewal: Unit 1 Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data, May 26, 20212021-05-26026 May 2021 Westinghouse, Report LTR-REA-21-1-NP, Revision 1, St. Lucie Units 1 & 2 Subsequent License Renewal: Unit 1 Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data, May 26, 2021 L-2020-164, License Amendment to Allow Risk Informed Completion Times (RICT) for the 120-Volt AC Instrument Bus Requirements2020-12-21021 December 2020 License Amendment to Allow Risk Informed Completion Times (RICT) for the 120-Volt AC Instrument Bus Requirements L-2020-020, License Amendment Request for RCS Pressure/ Temperature Limits and LTOP Applicable for 55 Effective Full Power Years2020-02-18018 February 2020 License Amendment Request for RCS Pressure/ Temperature Limits and LTOP Applicable for 55 Effective Full Power Years L-2019-091, License Amendment Request to Modify the Reactor Coolant Pump (RCP) Flywheel Inspection Program Requirements2019-10-0909 October 2019 License Amendment Request to Modify the Reactor Coolant Pump (RCP) Flywheel Inspection Program Requirements L-2019-147, Exigent Technical Specification Amendment Request One-Time Allowed Outage Time Extension for Inoperable EDG2019-07-19019 July 2019 Exigent Technical Specification Amendment Request One-Time Allowed Outage Time Extension for Inoperable EDG L-2018-161, License Amendment Request to Allow Performance of Selected Emergency Diesel Generator (EDG) Surveillance Requirements (Srs) During Power Operation2018-12-20020 December 2018 License Amendment Request to Allow Performance of Selected Emergency Diesel Generator (EDG) Surveillance Requirements (Srs) During Power Operation L-2018-182, License Amendment Request Iodine Removal System Elimination2018-11-0909 November 2018 License Amendment Request Iodine Removal System Elimination L-2018-201, Fourth Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2018-11-0909 November 2018 Fourth Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b L-2018-147, Submittal of License Amendment Request to Remove the Site Area Map from Technical Specifications2018-08-0202 August 2018 Submittal of License Amendment Request to Remove the Site Area Map from Technical Specifications L-2018-121, License Amendment Request to Reduce the Number of Control Element Assemblies2018-06-29029 June 2018 License Amendment Request to Reduce the Number of Control Element Assemblies L-2018-120, License Amendment Request to Remove the Site Area Map from the Technical Specifications2018-06-25025 June 2018 License Amendment Request to Remove the Site Area Map from the Technical Specifications L-2018-111, Second Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2018-06-0707 June 2018 Second Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b L-2018-049, Application to Add Limiting Condition for Operation (LCO) 3.0.6 to the Technical Specifications2018-05-29029 May 2018 Application to Add Limiting Condition for Operation (LCO) 3.0.6 to the Technical Specifications L-2018-031, License Amendment Request Focused Adoption of NEI 99-01. Revision 6 Unusual Event Fire-Related Emergency Action Level Scheme2018-01-31031 January 2018 License Amendment Request Focused Adoption of NEI 99-01. Revision 6 Unusual Event Fire-Related Emergency Action Level Scheme L-2017-155, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2017-12-19019 December 2017 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors L-2017-139, License Amendment Request to Add New Required Actions for an Inoperable Auxiliary Feedwater Pump Steam Supply2017-09-14014 September 2017 License Amendment Request to Add New Required Actions for an Inoperable Auxiliary Feedwater Pump Steam Supply 2023-06-14
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0January FPL. 21, 2016 L-2016-012 10 CFR 50.90 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Re: St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Application for Technical Specification Change to Remove the 10 Year Sediment Cleaning of the Fuel Oil Storage Tank and Relocate to Licensee-Controlled Documents
References:
- 1. FPL Letter L-2015-170 dated July14, 2015, "Application for Technical Specification Change to Remove the 10 Year Sediment Cleaning of the Fuel Oil Storage Tank and Relocate to Licensee-Controlled Documents," Adams Accession No. ML15198A032.
- 2. NRC Email dated December 4, 2015, "Draft St. Lucie RAI (Fuel Oil Storage Tank Sediment Cleaning)."
In Reference 1, Florida Power & Light Company (FPL) submitted a proposed license amendment that would relocate the Technical Specification (TS) Surveillance Requirements of (SR) 4.8.1.1 .2.g to the Updated Final Safety Analysis Report (UFSAR) for St. Lucie Unit 1 and the UFSAR for St. Lucie Unit 2. In reference 2, the NRC provided a request for additional information (RAI) needed for the Staff to complete its review of the application. The Enclosure to this letter provides FPL's response to the RAI and contains new TS markups consistent with the RAI response. The original no significant hazards evaluation provided in the Reference 1 bounds this response.
Please contact Mr. Ken Frehafer at 772-467-7748 if there are any questions about this submittal.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on January 2."1. ,2016 Sincerely, Christopher R. Costanzo Site Vice President St. Lucie Plant Enclosure cc: USNRC Regional Administrator, Region II */
USNRC Senior Resident Inspector, St. Lucie Nuclear Plant
- Fiorida Power & Light Company 6501 S. Ocean Drive, Jensen Beach, FL 34957
L-2016-012 Enclosure Page 1 of 6 FPL Response to Request for Additional Information St. Lucie, Unit 1 and 2 (Dockets 50-335 and 50-389)
License Amendment Request for Technical Specification Change to Remove the 10 Year Sediment Cleaning of the Fuel Oil Storage Tank and Relocate to Licensee-Controlled Documents (M1F6488 & M1F6489)
NRC RAT MF6488/MF6489-SBPB-01 BACKGROUN1D:
As required by 10 CFR 5 0.3 6 (c)(3), Surveillance Requirement (SR) are the requirements related to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the Limiting Condition for Operations (LCOs) will be met.
In the subject St. Lucie License Amendment Request (LAR), the current Technical Specification (TS) SR 4.8.1.1 .2.g for Unit 2 reads as follows:
- g. At least once per ten years by:
- 1. Draining each fuel oil storage tank, removing the accumulated sediment and cleaning the tank using a sodium hypochlorite solution, and,
- 2. Performing a pressure test of those portions of the diesel fuel oil system designed to Section III, subsection ND of the American Society of Mechanical Engineers (ASME) Code in accordance with the Inservice Inspection Program.
It should be noted that this LAR also proposed changes to the Unit 1 SR requirements, but the current Unit 1 SRs differ slightly from the current Unit 2 SRs.
ISSUE:
Although the LAR includes discussion of the cleaning requirement portion of SR, the SR 4.8.1.1 .2.g.2 contains pressure testing requirement for portions of the fuel oil system, which was not addressed in Technical Specification Task Force-2, nor included in the other precedent plants TSs referenced in LAR. The staff is unable to locate any discussion or basis for removal/relocation of this fuel oil system pressure testing SR.
RAJ:
Please explain the rationale behind the removal of the pressure tests of those portions of the diesel fuel oil system designed to Section III, subsection ND of the ASME Code for each unit. Include the following in your explanation:
- 1. Describe how the diesel fuel oil system is classified as an ASME Code Class 3 system, as specified in current TSs.
- 2. Verify, that TS 4.0.5 contains the equivalent SR for inservice inspection and testing of ASME Code Class 1, 2, and 3 components and is applicable to the pressure testing of the diesel fuel oil system.
- 3. Explain how the regulations at 10 CFR 50.36 (c)(2) and 10 CFR 50.36 (c)(3) will continue to be met for LCO 3.8.1 after the removal of the pressure tests
- 4. Provide a description of the location where a commitment to a 10-year surveillance frequency for pressure testing of the fuel oil system will be maintained.
L-2016-012 Enclosure Page 2 of 6 FPL Response FPL proposes to reinstate the pressure test portions of the applicable TSSRs. The following TS markups and corresponding word-processed TSs supersede those provided in the original application.
L-2016-012 Enclosure Page 3 of 6 ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (continued) ' ,/
Inservice Inspection Program.
4.8.1.1.3 Repoors- (Not Used) 4.8.1.1.4 The Class 1 E underground cable system shall be demonstrated OPERABLE within 30 days after the movement of any loads in excess of 80% of the ground surface design basis load over the cable ducts by pulling a mandrel with a diameter of at least 80% of the duct's inside diameter through a duct exposed to the maximum loading (duct nearest the ground's surface) and verifying that the duct has not been damaged.
ST. LUCIE - UNIT 1 3/4 8-6b Amendment No. 403,442.
448, 42,8, 484-, 223
L-2016-012 Enclosure Page 4 of 6 ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued')
- 12. Verifying that the automatic load sequence timers are operable with the interval between each load block within +1 second of its design interval.
- 13. Performing Surveillance Requirement 4.8.1.1.2a.4 within 5 minutes of shutting down the diesel generator after it has operated within a load band of 3450 kW to 3685 kV# for at least 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or until operating temperatures have stabilized.
- f. In accordance with the Surveillance Frequency Control Program or after any modifications which could affect diesel generator interdependence by starting*....
the diesel generators simuttaneously, during shutdovwn, and verifying that the diesel generators accelerate to approximately 900 rpm in less than or equal to 10 seconds.
2" rfrigapesr eto hs otoso h iesel fuel oil system esigned to Section III, subsection ND of the ASME Code in accordance with the !nservice Inspection Program.
4.8.1.1.3 Reports - (Not Used).
4.8.1.1.4 The Class IE underground cable system shall be demonstrated OPERABLE within 30 days after the movement of any loads in excess of 80% of the ground surface design basis load over the cable ducts by pulling a mandrel with a diameter of at least 80% of the duct's inside diameter through a duct exposed to the maximum loading (duct nearest the ground's surface) and verifying that the duct has not been damaged.
- This band is meant as guidance to avoid routine overloading of the engine. Variations in load in excess of this band due to changing bus loads shall not invalidate this test.
... This test may be conducted in accordance with the manufacturer's recommendations concerning engine prelube period.
ST. LUCIE - UNIT 2 3/4 8-7a ST.
UCIE-UIT23/4
-7aAmendment No. ,3, . 424. .
L-2016-012 Enclosure Page 5 of 6 ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (continued)
- g. In accordance with the Surveillance Frequency Control Program by performing a pressure test of those portions of the diesel fuel oil system designed to USAS B31 .7 Class 3 requirements in accordance with the Inservice inspection Program.
4.8.1.1.3 Repots - (Not Used) 4.8.1.1.4 The Class 1E underground cable system shall be demonstrated OPERABLE within 30 days after the movement of any loads in excess of 80% of the ground surface design basis load over the cable ducts by pulling a mandrel with a diameter of at least 80% of the duct's inside diameter through a duct exposed to the maximum loading (duct nearest the ground's surface) and verifying that the duct has not been damaged.
ST. LUCIE - UNIT 1 3486 3/4 8-6b Amendment No. 4-03, 44-2, 448, 438,484,-22-3
L-2016-012 Enclosure Page 6 of 6 ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued't
- 12. Verifying that the automatic load sequence timers are operable with the interval between each load block within +1 second of its design interval.
- 13. Performing Surveillance Requirement 4.8.1.1.2a.4 within 5 minutes of shutting down the diesel generator after it has operated within a load band of 3450 kW to 3685 kVV# for at least 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or until operating temperatures have stabilized.
- f. In accordance with the Surveillance Frequency Control Program or after any modifications which could affect diesel generator interdependence by starting***
the diesel generators simultaneously, during shutdown, and verifying that the diesel generators accelerate to approximately 900 rpm in less than or equal to 10 seconds.
- g. In accordance with the Surveillance Frequency Control Program by performing a pressure test of those portions of the diesel fuel oil system designed to Section Ill, subsection ND of the ASME Code in accordance with the Inservice Inspection Program.
4.8.1.1.3 Reports- (Not Used).
4.8.1.1.4 The Class lE underground cable system shall be demonstrated OPERABLE within 30 days after the movement of any loads in excess of 80% of the ground surface design basis load over the cable ducts by pulling a mandrel with a diameter of at least 80% of the duct's inside diameter through a duct exposed to the maximum loading (duct nearest the ground's surface) and verifying that the duct has not been damaged.
- This band is meant as guidance to avoid routine overloading of the engine. Variations in load in excess of this band due to changing bus loads shall not invalidate this test.
- This test may be conducted in accordance with the manufacturer's recommendations concerning engine prelube period.
ST. LUCIE - UNIT 2 3/4 8-7a ST.UCIE- -7aAmendment UIT23/4No. 89, *8, -124, 4
0January FPL. 21, 2016 L-2016-012 10 CFR 50.90 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Re: St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Application for Technical Specification Change to Remove the 10 Year Sediment Cleaning of the Fuel Oil Storage Tank and Relocate to Licensee-Controlled Documents
References:
- 1. FPL Letter L-2015-170 dated July14, 2015, "Application for Technical Specification Change to Remove the 10 Year Sediment Cleaning of the Fuel Oil Storage Tank and Relocate to Licensee-Controlled Documents," Adams Accession No. ML15198A032.
- 2. NRC Email dated December 4, 2015, "Draft St. Lucie RAI (Fuel Oil Storage Tank Sediment Cleaning)."
In Reference 1, Florida Power & Light Company (FPL) submitted a proposed license amendment that would relocate the Technical Specification (TS) Surveillance Requirements of (SR) 4.8.1.1 .2.g to the Updated Final Safety Analysis Report (UFSAR) for St. Lucie Unit 1 and the UFSAR for St. Lucie Unit 2. In reference 2, the NRC provided a request for additional information (RAI) needed for the Staff to complete its review of the application. The Enclosure to this letter provides FPL's response to the RAI and contains new TS markups consistent with the RAI response. The original no significant hazards evaluation provided in the Reference 1 bounds this response.
Please contact Mr. Ken Frehafer at 772-467-7748 if there are any questions about this submittal.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on January 2."1. ,2016 Sincerely, Christopher R. Costanzo Site Vice President St. Lucie Plant Enclosure cc: USNRC Regional Administrator, Region II */
USNRC Senior Resident Inspector, St. Lucie Nuclear Plant
- Fiorida Power & Light Company 6501 S. Ocean Drive, Jensen Beach, FL 34957
L-2016-012 Enclosure Page 1 of 6 FPL Response to Request for Additional Information St. Lucie, Unit 1 and 2 (Dockets 50-335 and 50-389)
License Amendment Request for Technical Specification Change to Remove the 10 Year Sediment Cleaning of the Fuel Oil Storage Tank and Relocate to Licensee-Controlled Documents (M1F6488 & M1F6489)
NRC RAT MF6488/MF6489-SBPB-01 BACKGROUN1D:
As required by 10 CFR 5 0.3 6 (c)(3), Surveillance Requirement (SR) are the requirements related to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the Limiting Condition for Operations (LCOs) will be met.
In the subject St. Lucie License Amendment Request (LAR), the current Technical Specification (TS) SR 4.8.1.1 .2.g for Unit 2 reads as follows:
- g. At least once per ten years by:
- 1. Draining each fuel oil storage tank, removing the accumulated sediment and cleaning the tank using a sodium hypochlorite solution, and,
- 2. Performing a pressure test of those portions of the diesel fuel oil system designed to Section III, subsection ND of the American Society of Mechanical Engineers (ASME) Code in accordance with the Inservice Inspection Program.
It should be noted that this LAR also proposed changes to the Unit 1 SR requirements, but the current Unit 1 SRs differ slightly from the current Unit 2 SRs.
ISSUE:
Although the LAR includes discussion of the cleaning requirement portion of SR, the SR 4.8.1.1 .2.g.2 contains pressure testing requirement for portions of the fuel oil system, which was not addressed in Technical Specification Task Force-2, nor included in the other precedent plants TSs referenced in LAR. The staff is unable to locate any discussion or basis for removal/relocation of this fuel oil system pressure testing SR.
RAJ:
Please explain the rationale behind the removal of the pressure tests of those portions of the diesel fuel oil system designed to Section III, subsection ND of the ASME Code for each unit. Include the following in your explanation:
- 1. Describe how the diesel fuel oil system is classified as an ASME Code Class 3 system, as specified in current TSs.
- 2. Verify, that TS 4.0.5 contains the equivalent SR for inservice inspection and testing of ASME Code Class 1, 2, and 3 components and is applicable to the pressure testing of the diesel fuel oil system.
- 3. Explain how the regulations at 10 CFR 50.36 (c)(2) and 10 CFR 50.36 (c)(3) will continue to be met for LCO 3.8.1 after the removal of the pressure tests
- 4. Provide a description of the location where a commitment to a 10-year surveillance frequency for pressure testing of the fuel oil system will be maintained.
L-2016-012 Enclosure Page 2 of 6 FPL Response FPL proposes to reinstate the pressure test portions of the applicable TSSRs. The following TS markups and corresponding word-processed TSs supersede those provided in the original application.
L-2016-012 Enclosure Page 3 of 6 ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (continued) ' ,/
Inservice Inspection Program.
4.8.1.1.3 Repoors- (Not Used) 4.8.1.1.4 The Class 1 E underground cable system shall be demonstrated OPERABLE within 30 days after the movement of any loads in excess of 80% of the ground surface design basis load over the cable ducts by pulling a mandrel with a diameter of at least 80% of the duct's inside diameter through a duct exposed to the maximum loading (duct nearest the ground's surface) and verifying that the duct has not been damaged.
ST. LUCIE - UNIT 1 3/4 8-6b Amendment No. 403,442.
448, 42,8, 484-, 223
L-2016-012 Enclosure Page 4 of 6 ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued')
- 12. Verifying that the automatic load sequence timers are operable with the interval between each load block within +1 second of its design interval.
- 13. Performing Surveillance Requirement 4.8.1.1.2a.4 within 5 minutes of shutting down the diesel generator after it has operated within a load band of 3450 kW to 3685 kV# for at least 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or until operating temperatures have stabilized.
- f. In accordance with the Surveillance Frequency Control Program or after any modifications which could affect diesel generator interdependence by starting*....
the diesel generators simuttaneously, during shutdovwn, and verifying that the diesel generators accelerate to approximately 900 rpm in less than or equal to 10 seconds.
2" rfrigapesr eto hs otoso h iesel fuel oil system esigned to Section III, subsection ND of the ASME Code in accordance with the !nservice Inspection Program.
4.8.1.1.3 Reports - (Not Used).
4.8.1.1.4 The Class IE underground cable system shall be demonstrated OPERABLE within 30 days after the movement of any loads in excess of 80% of the ground surface design basis load over the cable ducts by pulling a mandrel with a diameter of at least 80% of the duct's inside diameter through a duct exposed to the maximum loading (duct nearest the ground's surface) and verifying that the duct has not been damaged.
- This band is meant as guidance to avoid routine overloading of the engine. Variations in load in excess of this band due to changing bus loads shall not invalidate this test.
... This test may be conducted in accordance with the manufacturer's recommendations concerning engine prelube period.
ST. LUCIE - UNIT 2 3/4 8-7a ST.
UCIE-UIT23/4
-7aAmendment No. ,3, . 424. .
L-2016-012 Enclosure Page 5 of 6 ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (continued)
- g. In accordance with the Surveillance Frequency Control Program by performing a pressure test of those portions of the diesel fuel oil system designed to USAS B31 .7 Class 3 requirements in accordance with the Inservice inspection Program.
4.8.1.1.3 Repots - (Not Used) 4.8.1.1.4 The Class 1E underground cable system shall be demonstrated OPERABLE within 30 days after the movement of any loads in excess of 80% of the ground surface design basis load over the cable ducts by pulling a mandrel with a diameter of at least 80% of the duct's inside diameter through a duct exposed to the maximum loading (duct nearest the ground's surface) and verifying that the duct has not been damaged.
ST. LUCIE - UNIT 1 3486 3/4 8-6b Amendment No. 4-03, 44-2, 448, 438,484,-22-3
L-2016-012 Enclosure Page 6 of 6 ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued't
- 12. Verifying that the automatic load sequence timers are operable with the interval between each load block within +1 second of its design interval.
- 13. Performing Surveillance Requirement 4.8.1.1.2a.4 within 5 minutes of shutting down the diesel generator after it has operated within a load band of 3450 kW to 3685 kVV# for at least 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or until operating temperatures have stabilized.
- f. In accordance with the Surveillance Frequency Control Program or after any modifications which could affect diesel generator interdependence by starting***
the diesel generators simultaneously, during shutdown, and verifying that the diesel generators accelerate to approximately 900 rpm in less than or equal to 10 seconds.
- g. In accordance with the Surveillance Frequency Control Program by performing a pressure test of those portions of the diesel fuel oil system designed to Section Ill, subsection ND of the ASME Code in accordance with the Inservice Inspection Program.
4.8.1.1.3 Reports- (Not Used).
4.8.1.1.4 The Class lE underground cable system shall be demonstrated OPERABLE within 30 days after the movement of any loads in excess of 80% of the ground surface design basis load over the cable ducts by pulling a mandrel with a diameter of at least 80% of the duct's inside diameter through a duct exposed to the maximum loading (duct nearest the ground's surface) and verifying that the duct has not been damaged.
- This band is meant as guidance to avoid routine overloading of the engine. Variations in load in excess of this band due to changing bus loads shall not invalidate this test.
- This test may be conducted in accordance with the manufacturer's recommendations concerning engine prelube period.
ST. LUCIE - UNIT 2 3/4 8-7a ST.UCIE- -7aAmendment UIT23/4No. 89, *8, -124, 4