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Category:Letter type:L
MONTHYEARL-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024
Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)
L-2024-004, Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years2024-01-18018 January 2024
Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years
L-2024-002, Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2024-01-0808 January 2024
Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump
L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023
Quality Assurance Topical Report (FPL-1) Revision 30 Update
L-2023-179, Unusual or Important Environmental Event - Turtle Mortality2023-12-14014 December 2023
Unusual or Important Environmental Event - Turtle Mortality
L-2023-168, License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 52023-12-12012 December 2023
License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 5
L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023
Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654,
L-2023-162, Response to 50.69 2nd Round of Rals2023-11-21021 November 2023
Response to 50.69 2nd Round of Rals
L-2023-131, Subsequent License Renewal Application - Second Annual Update2023-09-28028 September 2023
Subsequent License Renewal Application - Second Annual Update
L-2023-136, Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-26026 September 2023
Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
L-2023-122, Corrections to the 2022 Annual Radiological Environmental Operating Report2023-09-20020 September 2023
Corrections to the 2022 Annual Radiological Environmental Operating Report
L-2023-127, Correction to the 2022 Annual Radioactive Effluent Release Report2023-09-18018 September 2023
Correction to the 2022 Annual Radioactive Effluent Release Report
L-2023-113, Correction to the 2020 Annual Radiological Environmental Operating Report2023-09-14014 September 2023
Correction to the 2020 Annual Radiological Environmental Operating Report
L-2023-118, Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-11011 September 2023
Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
L-2023-108, Report of 10 CFR 50.59 Plant Changes2023-09-11011 September 2023
Report of 10 CFR 50.59 Plant Changes
L-2023-112, Corrections to the 2021 Annual Radioactive Effluent Release Report2023-09-0606 September 2023
Corrections to the 2021 Annual Radioactive Effluent Release Report
L-2023-107, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.42023-09-0606 September 2023
Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4
L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023
Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update
L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023
and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2
L-2023-105, Preparation and Scheduling of Operator Licensing Examinations2023-08-0303 August 2023
Preparation and Scheduling of Operator Licensing Examinations
L-2023-099, Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2023-07-26026 July 2023
Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump
L-2023-102, Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches2023-07-26026 July 2023
Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches
L-2023-097, Subsequent License Renewal Application Revision 1 - Supplement 62023-07-13013 July 2023
Subsequent License Renewal Application Revision 1 - Supplement 6
L-2023-076, In-Service Inspection Program Owner'S Activity Report (OAR-1)2023-07-11011 July 2023
In-Service Inspection Program Owner'S Activity Report (OAR-1)
L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023
Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)
L-2023-082, Subsequent License Renewal Application Revision 1, Supplement 52023-06-14014 June 2023
Subsequent License Renewal Application Revision 1, Supplement 5
L-2023-074, Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update2023-06-0202 June 2023
Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update
L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023
NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal
L-2023-059, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response2023-04-21021 April 2023
Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response
L-2023-055, 2022 Annual Environmental Operating Report2023-04-12012 April 2023
2022 Annual Environmental Operating Report
L-2023-041, Annual Radiological Environmental Operating Report for Calendar Year 20222023-04-0404 April 2023
Annual Radiological Environmental Operating Report for Calendar Year 2022
L-2023-051, Report of 10 CFR 50.59 Plant Changes2023-04-0404 April 2023
Report of 10 CFR 50.59 Plant Changes
L-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023
Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update
L-2023-042, Periodic Update of Population Data within 10 and 50 Miles of the Plant2023-03-27027 March 2023
Periodic Update of Population Data within 10 and 50 Miles of the Plant
L-2023-026, Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 42023-03-27027 March 2023
Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 4
L-2023-028, and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2023-03-27027 March 2023
and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications
L-2023-025, Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-12023-03-15015 March 2023
Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-1
L-2023-029, and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3)2023-03-10010 March 2023
and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3)
L-2023-039, Cycle 27 Core Operating Limits Report2023-03-0707 March 2023
Cycle 27 Core Operating Limits Report
L-2023-032, 2022 Annual Radioactive Effluent Release Report2023-02-28028 February 2023
2022 Annual Radioactive Effluent Release Report
L-2023-038, 2022 Annual Operating Report2023-02-28028 February 2023
2022 Annual Operating Report
L-2023-016, Radiological Emergency Plan - Revision 74 Report of Changes to Emergency Plan2023-02-15015 February 2023
Radiological Emergency Plan - Revision 74 Report of Changes to Emergency Plan
L-2023-019, Annual Summary of Commitment Changes Implemented Without Prior NRC Notification for Calendar Year 20222023-02-15015 February 2023
Annual Summary of Commitment Changes Implemented Without Prior NRC Notification for Calendar Year 2022
L-2023-009, Owner'S Activity Report2023-01-31031 January 2023
Owner'S Activity Report
L-2022-188, Unusual or Important Environmental Event - Turtle Mortality2022-12-19019 December 2022
Unusual or Important Environmental Event - Turtle Mortality
L-2022-185, Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-12-0909 December 2022
Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2
L-2022-175, Application to Adopt 10 CPR 50.69, 'Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2022-12-0202 December 2022
Application to Adopt 10 CPR 50.69, 'Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
L-2022-180, CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2022-11-0909 November 2022
CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums
L-2022-165, Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) 4.3.1-1a(second Round) - Class 1 Fatigue Response2022-10-26026 October 2022
Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) 4.3.1-1a(second Round) - Class 1 Fatigue Response
L-2022-160, Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-10-0404 October 2022
Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2
2024-01-08
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0 Florida Power &Light Company, 6501 S. Ocean Drive, Jensen Beach, FL 34957 FPL December 20, 2011 L-2011-556 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Re: St. Lucie Plant Unit 2 Docket No. 50-389 Renewed Facility Operating License No. NPF-16 Response to NRC Vessels & Internals Integrity Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request
References:
(1) R. L. Anderson (FPL) to U.S. Nuclear Regulatory Commission (L-2011-021),
"License Amendment Request for Extended Power Uprate," February 25, 2011, Accession No. ML110730116.
(2) Email from T. Orf (NRC) to C. Wasik (FPL), "St. Lucie 2 EPU draft RAI - Reactor Vessel & Internals Branch (CVIB)," December 6, 2011.
(3) U.S. Nuclear Regulatory Commission (R.A. Nelson) letter to Electric Power Research Institute (N. Wilmshurst), "Final Safety Evaluation of EPRI Report, Materials Reliability Program Report 1016596 (MRP-227), Revision 0,
'Pressurized Water Reactor (PWR) Internals Inspection and Evaluation Guidelines' (TAC No. ME0680)," June 22, 2011, Accession No. ML111600498.
(4) R. L. Anderson (FPL) to U.S. Nuclear Regulatory Commission (L-2011-255), St.
Lucie Plant Unit 1, "Response to NRC Vessels & Internals Integrity Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request," July 8, 2011, Accession No. ML 1 194A01 6.
By letter L-2011-021 dated February 25, 2011 [Reference 1], Florida Power & Light Company (FPL) requested to amend Renewed Facility Operating License No. NPF-16 and revise the St. Lucie Unit 2 Technical Specifications (TS). The proposed amendment will increase the unit's licensed core thermal power level from 2700 megawatts thermal (MWt) to 3020 MWt and revise the Renewed Facility Operating License and TS to support operation at this increased core thermal power level. This represents an approximate increase of 11.85% and is therefore considered an extended power uprate (EPU).
By email from the NRC Project Manager dated December 6, 2011 [Reference 2],
additional information related to the proposed EPU was requested by the NRC staff in the Vessels and Internals Integrity Branch (CVIB) to support their review of the EPU an FPL Group company
St. Lucie Unit 2 L72011-556 Docket No. 50-389 Page 2 of 2 LAR. The request for additional information (RAI) identified two questions. The response to these RAIs is provided in the attachment to this letter.
This RAI response includes a revision to current commitments associated with the aging management of the RVI components during the period of extended operation. The Reactor Vessel Internals Inspection Program (currently listed in Section 18.1.3 of the St.
Lucie Unit 2 Updated Final Safety Analysis Report) was based on industry knowledge available at the time the license for St. Lucie Unit 2 was renewed. Since that time, industry-led efforts have been in progress by the Electric Power Research Institute (EPRI) Materials Reliability Program (MRP) Reactor Internals Issues Task Group (RI-ITG) and later by the MRP Reactor Internals Focus Group (RI-FG). The EPRI MRP RI-FG developed MRP-227, "Pressurized Water Reactor (PWR) Internals Inspection and Evaluation Guidelines," (Revision 0). MRP-227, Revision 0 was approved by the NRC staff on June 22, 2011 (ML111600498) [Reference 3].
In Reference 3, the NRC requested that EPRI publish an accepted version of MRP-227 to include a "-A" (designating accepted). FPL commits to adopting MRP-227-A in place of the existing RVI Inspection program. This commitment applies to St. Lucie Unit 2 and is independent of the EPU LAR currently under staff review.
Note that a similar commitment to adopt MRP-227-A was made for St. Lucie Unit 1 in FPL letter L-2011-255 [Reference 4].
In accordance with 10 CFR 50.91 (b)(1), a copy of this letter is being forwarded to the designated State of Florida official.
This submittal does not alter the significant hazards consideration or environmental assessment previously submitted by FPL letter L-2011-021 [Reference 1].
Should you have any questions regarding this submittal, please contact Mr. Christopher Wasik, St. Lucie Extended Power Uprate LAR Project Manager, at 772-467-7138.
I declare under penalty of perjury that the foregoing is true and correct to the best of my knowledge.
Executed on vto - "LO%..Wr- 2 tI Very truly yours, Richard L. Anderso Site Vice President St. Lucie Plant Attachment cc: Mr. William Passetti, Florida Department of Health
St. Lucie Unit 2 L-2011-556 Docket No. 50-389 Attachment Page 1 of 2 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 Extended Power Uprate (EPU) License Amendment Request (LAR) for St: Lucie Nuclear Plant Unit 2 that was submitted to the NRC by FPL via letter (L-2011-021) dated February 25, 2011, Accession Number ML110730116.
In an email dated December 6, 2011 from NRC (Tracy Orf) to FPL (Chris Wasik),
Subject:
"St.
Lucie 2 EPU draft RAI - Reactor Vessel & Internals Branch (CVIB)," the NRC requested additional information regarding FPL's request to implement the EPU. The RAI consisted of two (2) questions from the NRC's Vessels and Internals Integrity Branch (CVIB). The RAI questions and the FPL responses are documented below.
CVIB-1 Although Florida Power & Light Company (FPL) committed to submit an RVI component inspection program for St. Lucie, Units 1 and 2 prior to the period of extended operation, FPL did not specifically commit to submit an RVI component inspection program conforming to the industry's standard program. The staff requests that the licensee discuss its plans to implement the industry's recommended inspection and evaluation guidelines for RVI components as documented in topical report MRP-227, Rev. 0 guidelines, as modified by the staff's final SE, for the implementation of all aging effects including stress relaxation for Saint Lucie, Unit 2.
Response
Florida Power & Light Company (FPL) hereby revises its current commitments associated with the aging management of the St. Lucie Unit 2 reactor vessel internals (RVI) components during the period of extended operation to adopt MRP-227 in place of the existing Reactor Vessel Internals Inspection Program. This RAI response includes a revision to current commitments associated with the aging management of the RVI components during the period of extended operation. The Reactor Vessel Internals Inspection Program (currently listed in Section 18.1.3 of the St. Lucie Unit 2 Updated Final Safety Analysis Report) was based on industry knowledge available at the time the license for St. Lucie Unit 2 was renewed. Since that time, industry-led efforts have been in progress by the Electric Power Research Institute (EPRI) Materials Reliability Program (MRP) Reactor Internals Issues Task Group (RI-ITG) and later by the MRP Reactor Internals Focus Group (RI-FG). The EPRI MRP RI-FG developed MRP-227, "Pressurized Water Reactor (PWR) Internals Inspection and Evaluation Guidelines," (Revision 0). MRP-227, Revision 0 was approved by the NRC staff on June 22, 2011 (MLI 11600498)
[Reference 1]. As indicated in the Reference 1 Safety Evaluation, MRP-227 includes inspection requirements for RVI components that are subject to stress relaxation.
In Reference 1, the NRC requested that EPRI publish an accepted version of MRP-227 to include a "-A" (designating accepted). FPL commits to adopting MRP-227-A in place of the existing RVI Inspection program. This commitment applies to St. Lucie Unit 2 and is independent of the EPU LAR currently under staff review.
St. Lucie Unit 2 L-2011-556 Docket No. 50-389 Attachment Page 2 of 2 Note that a similar commitment to adopt MRP-227-A was made for St. Lucie Unit 1 in accordance with FPL letter L-2011-255 [Reference 2]
CVIB-2 Please.provide the peak reactor vessel fluence at 47 Effective Full Power Years.
Response
The St. Lucie Unit 2 Extended Power Uprate (EPU) 47 Effective Full Power Year (EFPY) peak 2 reactor vessel fluence at the inside diameter (ID) clad to base metal interface is 3.67E+19 n/cm (E > 1 Mev).
References:
- 1. U.S. Nuclear Regulatory Commission (R.A. Nelson) letter to Electric Power Research Institute (N. Wilmshurst), "Final Safety Evaluation of EPRI Report, Materials Reliability Program Report 1016596 (MRP-227), Revision 0, 'Pressurized Water Reactor (PWR)
Internals Inspection and Evaluation Guidelines' (TAC No. ME0680)," June 22, 2011, Accession No. ML111600498.
- 2. R. L. Anderson (FPL) to U.S. Nuclear Regulatory Commission (L-2011-255), St. Lucie Plant Unit 1, "Response to NRC Vessels & Internals Integrity Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request,"
July 8, 2011, Accession No. ML11194A016.
