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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 I=PL" March 8, 2012 L-2012-094 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 Steam Generator Tube Integrity and Chemistry 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 RAIs SG Tube Integrity and Chem. Engineering Branch (CSGB)," February 23, 2012.
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 February 23, 2012 [Reference 2],
additional information related to spent fuel pool MetamicTM inserts was requested by the NRC staff in the Steam Generator Tube Integrity and Chemical Engineering Branch (CSGB) to support their review of the St. Lucie Unit 2 EPU License Amendment Request (LAR). The request for additional information (RAI) identified two questions. The response to these RAIs is provided in the attachment to this letter.
This submittal does not alter the significant hazards consideration or environmental assessment previously submitted by FPL letter L-2011-021 [Reference 1].
an FPL Group company
L-2012-094 Page 2 of 2 This submittal contains no new commitments.
In accordance with 10 CFR 50.91(b)(1), a copy of this letter is being forwarded to the designated State of Florida official.
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 -,c/.
Very truly yours, Richard L. Anders Site Vice President St. Lucie Plant Attachment cc: Mr. William Passetti, Florida Department of Health
L-2012,094 Attachment Page 1 of 3 Response to NRC Steam Generator Tube Integrity & Chemical Engineering Branch 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 the review of the Extended Power Uprate (EPU) License Amendment Request (LAR) for St. Lucie 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 February 23, 2012 from T. Off (NRC) to C. Wasik (FPL),
Subject:
St. Lucie 2 EPU - draft RAIs SG Tube Integrity and Chem. Engineering Branch (CSGB), the NRC staff requested additional information regarding FPL's request to implement the St. Lucie Unit 2 EPU.
The RAI consisted of two questions from the NRC's Steam Generator Tube Integrity & Chemical Engineering Branch (CSGB). These two RAI questions and the FPL responses are documented below.
CSGB-10 In the letter dated December 27, 2011, the licensee stated:
A coupon tree will be installedthat holds 10 coupons in the SFP. The coupons are identicalin composition and manufacturingprocess as the MetamicTM inserts. The coupon tree will be placed in a SFP cell in a location that will ensure a representativedose to the coupons. In addition, this location will simulate the flow characteristics,and pool chemistry that the MetamicTMinserts placedin the SFP will experience. The cell location will be in Region 2 of the SFP which typically has highly burned permanently dischargedfuel.
In order to have an effective coupon program the sample coupons should be placed in the SFP in a location where they will receive the maximum dose and flux possible to bound the conditions seen by all the inserts used in the SFP. This allows for reasonable assurance that if the monitoring program were to detect degradation in the coupons, the appropriate corrective actions can be taken to mitigate the degradation of the inserts.
a) Please discuss what is meant by "representative dose" with respect to the placement of the coupon tree in the SFP racks.
b) Please justify the placement of the coupon tree in an alternative location if it is not placed in an environment that bounds SFP conditions for all inserts.
Response
a) Region 1 of the St. Lucie Unit 2 SFP is inappropriate for the placement of a coupon tree as no MetamicTM the inserts are updated Technical credited in the Region 1 configurations analyzed as proposed for Specifications.
Region 2 of the SFP, where most of the MetamicTM inserts will be placed, is used for the storage of permanently discharged fuel assemblies with typical burnups in excess of 35000 MWD/MTU. The assemblies in Region 2, including the assemblies placed in cells with inserts, typically remain in the same location for a period of greater than 5 years, and
L-2012-094 Attachment Page 2 of 3 until removed to dry cask storage. The inserts are thus not exposed to freshly discharged assemblies in an as severe configuration as the coupons as described below.
In deciding on the location of the placement of a coupon tree and the characteristics of fuel assemblies in cells surrounding the cell containing the coupon tree, important factors of consideration are the accumulated dose and the flux. Proximity to higher burned fuel will yield a higher dose, whereas positioning near higher reactivity fuel increases the localized flux.
Achieving a combined effect of a greater accumulated dose and higher flux exposure to the coupons, placed in a specific cell location, requires that fuel assemblies placed in cells adjacent to the coupon tree be a combination of higher reactivity fuel and high burned fuel.
FPL will achieve this combined effect by placing most recent freshly discharged assemblies in at least two of the four cells, face-adjacent to the Region 2 cell containing the coupon tree. Other cells, face-adjacent to the coupon tree, will be loaded with discharged fuel assemblies cooled for no more than 5 years. These assemblies will meet the above stated requirements as they are expected to have burnups in excess of 35,000 MWD/MTU from dose considerations, and will have cooling time of 0 to a maximum of 5 years from reactivity considerations. This configuration of the coupon tree surrounded by recently discharged assemblies, including freshly discharged assemblies in two adjacent cells without a CEA or MetamicTM insert, will create an environment that is expected to bound all inserts.
The environment established around the coupons would provide reasonable assurance that, ifthe monitoring program were to detect degradation in the coupons, proper corrective actions can be taken to mitigate the degradation of the inserts prior to any insert falling below the design requirements.
b) The location of coupon tree in the environment, as discussed in the response to CSGB-11 a, will provide reasonable assurance that any degradation detected by the coupon monitoring program will effectively allow FPL to take appropriate corrective actions to mitigate degradation of the inserts.
L-2012-094 Attachment Page 3 of 3 CSGB-11 Please provide the following:
a) The physical dimensions of the coupons to be used in the SFP. Will some of the coupons have a formed chevron cross-section similar to inserts used in the SFP? If not, please justify how the coupons are representative of the inserts in the SFP.
b) Will there be coupons that simulate potential galvanic coupling that may be seen by the inserts in the SFP? If not, please provide justification for how the coupons are representative of the inserts in the SFP.
Response
a) The MetamicTM coupons are 8 inches tall by 6 inches wide. The coupon thickness is 0.070 inches, which is the same thickness as the MetamicTM inserts. There are a total of 10 MetamicTM coupons installed on the coupon tree.
The MetamicTM coupons do not include a formed chevron cross-section. The coupons are a flat, rectangular panel. As stated in the response to RAI CSGB-7 (reference FPL letter L-2011-524, ML11364A043),-the coupons will be used for the physical measurement inspection (height, width, thickness, and weight) and neutron attenuation testing aspects of the surveillance program. The most important physical measurement parameter is material thickness to monitor the potential for swelling. The thickness of the MetamicTM coupon (0.070 inches) is the same thickness as the MetamicTM inserts. The coupons and inserts are also made from the same material. Therefore, the coupons are representative of the inserts for this critical dimensional check. The remaining coupon measurement parameters (height, width, and weight) serve a supporting role and are utilized to identify early indications of the potential onset of neutron absorber degradation. These parameters will be measured before the coupons are installed in the spent fuel pool, and subsequently checked during future coupon inspections. The relative change in these measured parameters will be evaluated as part of the surveillance program. For these reasons, the coupons do not have to replicate the exact geometry of the inserts.
b) As stated in the response to RAls CSGB-5b and CSGB-7, the visual inspection aspects of the MetamicTM surveillance program will be performed on a representative sample of the actual MetamicTM inserts. These visual inspections of the MetamicTM inserts will be sufficient to detect evidence of galvanic coupling. Visual inspection of the actual inserts rather than the coupons is the preferred method to detect any potential for galvanic coupling as they eliminate the need to simulate area ratio and proximity effects to other dissimilar materials in the spent fuel pool (fuel assemblies, spent fuel pool racks, etc.).
For these reasons, the MetamicTM coupons will not be used as a means to detect galvanic coupling.