Letter Sequence Supplement |
|---|
EPID:L-2018-LLA-0181, License Amendment Request to Reduce the Number of Control Element Assemblies (Approved, Closed) |
|
|
|
|---|
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] |
Text
FEB 2 2 2019 L-2019-041 10 CFR 50.90 U. S. Nuclear Regulatoq Commission Attn: Document Control Desk Washington D C 20555-0001 RE: St. Lucie Unit 2 Docket No. 50-389 Renewed Facility Operating Licenses NPF-16 Supplemental Information for License Amendment Request to Reduce the Number of Control Element Assemblies
References:
- 1. Florida Power & Light Company letter L-2018-121, License Amendtnent Request to Reduce the Number of Control Element Assemblies, June 29, 2018 (ADAMS Accession No.
l'v1L18180A094)
- 2. Florida Power & Light Company letter L-2018-153, Supplemental Information for License Amendment Request to Reduce the Number of Control Element Assemblies, August 17, 2018 (ADAMS Accession No. ML18229A050)
- 3. Florida Power & Light Company letter L-2018-205, Response to Request for Additional Information Regarding License Amendment Request to Reduce the Number of Control Element Assemblies, November 15,2018 (ADAMS Accession No. ML18319A043 In Reference 1, as supplemented by References 2 and 3, Florida Power & Light Company (FPL) requested an amendment to Renewed Facility Operating License NPF-16 for St. Lucie Unit 2. The proposed license amendment modifies the St. Lucie Unit 2 Technical Specifications (TS) by reducing the number of control element assemblies (CEAs) specified in the TS, from 91 to 87, to support permanent removal of four 4-element (mini-dual) CEAs from the reactor core. The proposed license amendment relatedly deletes a reference to the 4-element CEAs in an existing TS definition.
Subsequent to the above submittals, FPL was made aware of changes to a proposed St. Lucie Unit 2 TS page that are warranted, though editorial in nature. Accordingly, the enclosure to this letter provides the existing St. Lucie Unit 2 TS page marked up to show the latest proposed changes. The TS marked up page supersedes the corresponding page provided in Reference 1. No changes are proposed to the St. Lucie Unit 2 TS Bases.
The enclosure to this letter does not alter the conclusion in Reference 1 that the proposed amendment does not involve a significant hazards consideration pursuant to 10 CFR 50.92, and that there are no significant environmental impacts associated with this proposed change. In accordance with 10 CFR 50.91(b)(1), a copy of the proposed change is being forwarded to the designee for the State of Florida.
Florida Power & Light Company 6501 S. Ocean Drive, Jensen Beach, FL 34957
St. Lucie Nuclear Plant L-2019-041 Docket No. 50-389 Page 2 of2 This letter contains no new regulatory commitments.
If you have any questions or require additional information, please contact Mr. 1\1ichael Snyder, St.
Lucie Licensing Manager, at (772) 467-7036.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on Februaryll., 2019.
Sincerely, odo~
Daniel DeBoer Site Director- St. Lucie Nuclear Plant, Units 1 and 2 Florida Power & Light Company Enclosure cc: USNRC Regional Administrator, Region II USNRC Project Manager, St. Lucie Nuclear Plant, Units 1 and 2 USNRC Senior Resident Inspector, St. Lucie Nuclear Plant, Units 1 and 2 Ms. Cindy Becl$:er, Florida Department of Health
St. Lucie Nuclear Plant Unit 2 L-2019-041 Docket No. 50-389 Enclosure Page 1 of2 ST. LUCIE UNIT 2 PROPOSED TECHNICAL SPECIFICATIONS PAGE (MARKUP)
(1 page follows)
St. Lucie Nuclear Plant Unit 2 L-2019-041 Docket No. 50-389 Enclosure Page 2 of2 ST. LUCIE UNIT 2 PROPOSED TECHNICAL SPECIFICATIONS PAGE (MARKUP)
DEFINITIONS CHANNEL FUNCTIONAL TEST 1.6 A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated signal into the channel as close to the primary sensor as practicable to verify OPERABILITY including alarm and/or trip functions.
CONTAINMENT VESSEL INTEGRITY 1.7 CONTAINMENT VESSEL INTEGRITY shall exist when:
- a. All containment vessel penetrations required to be closed during accident conditions are either:
- 1. Capable of being closed by an OPERABLE containment automatic isolation valve system, or
- 2. Closed by manual valves, blind flanges, or deactivated automatic valves secured in their closed positions, except for valves that are open on an intermittent basis under administrative control.
- b. All containment vessel equipment hatches are closed and sealed,
- c. Each containment vessel air lock is in compliance with the requirements of Specification 3.6.1.3,
- d. The containment leakage rates are within the limits of Specification 3.6.1.2, and
- e. The sealing mechanism associated with each penetration (e.g., welds, bellows or 0-rings) is OPERABLE.
CONTROLLED LEAKAGE 1.8 CONTROLLED LEAKAGE shall be the seal water flow supplied from the reactor coolant pump seals.
CORE ALTERATION 1.9 CORE ALTERATION shall be the movement or manipulation of any fuel, sources, rea*ctivity control components, or other components affecting reactivity within the reactor vessel with the vessel head removed and fuel in the vessel. Exceptions to the above include sl1aree (4 fiR!JCfel'l)
CQRII:gl $IEIR'l$1'11 :il~~e~bli$ii (C~,A ii) wjtl~olrav*l'l iRie IRe ~f'lflOF §lolielo otF1;:!8llolFe (UGS) OF evolutions performed with the in place su.ch as -GEA latching/unlatching or verification of latching/unlatching h do not constitute CORE ALTERATION. Suspension of CORE ALTERATIONS shall ot preclude completi n of movement of a component to a safe position.
CORE OPERATING LIMITS 1.9a THE COLR is the unit specific document th t provides cycle specific parameter limits for the current operating relo d cycle. These cycle specific parameter limits shall be determined for each reload cycle in a cordance with Speci cation 6.9.1 .11. Plant operation within these limits is addressed in individu I Specifications. control element a ssem bly (C EA)
ST. LUCIE- UNIT 2 1-2 Amendment No. 85, 88, *
