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Category:Letter
MONTHYEARIR 05000335/20250102024-10-21021 October 2024 Notification of St. Lucie Plant Units 1 & 2 Comprehensive Engineering Team Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000335/2025010 and 05000389/2025010 ML24227A9702024-10-18018 October 2024 Letter to Kenneth Mack Dir, License and Reg Compliance, NextEra Energy, Inc Response to Request Re Engagement Re Sub License Renewal Environmental Review - St Lucie Nuclear Plant 1 and 2 L-2024-085, Refueling Outage SL1-32 Low Pressure Turbine Rotor Inspection Results2024-10-15015 October 2024 Refueling Outage SL1-32 Low Pressure Turbine Rotor Inspection Results L-2024-165, Report of 10 CFR 50.59 Plant Changes, Tests and Experiments Made2024-10-14014 October 2024 Report of 10 CFR 50.59 Plant Changes, Tests and Experiments Made L-2024-118, Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1)2024-10-0808 October 2024 Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1) ML24255A3092024-09-30030 September 2024 SLRA - Revised SE Letter L-2024-155, Subsequent License Renewal Application, Third Annual Update2024-09-27027 September 2024 Subsequent License Renewal Application, Third Annual Update L-2024-158, Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-25025 September 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes 05000335/LER-2024-001, Unplanned Reactor Scram2024-09-25025 September 2024 Unplanned Reactor Scram IR 05000335/20240112024-09-18018 September 2024 Biennial Problem Identification and Resolution Inspection Report 05000335/2024011 and 05000389/2024011 L-2024-136, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-16016 September 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-138, License Amendment Request L-2024-138, Fuel Methodology Changes in Support of St. Lucie, Unit 2 Transition to 24-Month Fuel Cycles2024-09-11011 September 2024 License Amendment Request L-2024-138, Fuel Methodology Changes in Support of St. Lucie, Unit 2 Transition to 24-Month Fuel Cycles L-2024-148, Submittal of Offsite Dose Calculation Manual (Odcm), Revision 552024-09-0909 September 2024 Submittal of Offsite Dose Calculation Manual (Odcm), Revision 55 IR 05000335/20240052024-08-22022 August 2024 Updated Inspection Plan for St. Lucie, Units 1 & 2 - Report 05000335/2024005 and 05000389/2024005 L-2024-140, Cycle 28 Core Operating Limits Report2024-08-14014 August 2024 Cycle 28 Core Operating Limits Report L-2024-133, Snubber Program Plan Submittal2024-08-14014 August 2024 Snubber Program Plan Submittal L-2024-132, 2024 Population Update Analysis2024-08-13013 August 2024 2024 Population Update Analysis IR 05000335/20240022024-08-13013 August 2024 Integrated Inspection Report 05000335-2024002 and 05000389-2024002 L-2024-129, Relief Request (RR) 14. Limited Coverage Exams Due to Impractical Inservice Inspection Requirements - Fourth Ten-Year Inservice Inspection Program Interval2024-08-0707 August 2024 Relief Request (RR) 14. Limited Coverage Exams Due to Impractical Inservice Inspection Requirements - Fourth Ten-Year Inservice Inspection Program Interval 05000389/LER-2024-003, Unplanned Reactor Scram2024-08-0505 August 2024 Unplanned Reactor Scram ML24163A0012024-08-0505 August 2024 LTR-24-0119-1-1 Response to Nh Letter Regarding Review of NextEras Emergency Preparedness Amendment Review L-2024-121, Subsequent License Renewal Commitment 30 Revision2024-07-30030 July 2024 Subsequent License Renewal Commitment 30 Revision L-2024-123, Submittal of In-Service Inspection Program Owners Activity Report (OAR-1)2024-07-29029 July 2024 Submittal of In-Service Inspection Program Owners Activity Report (OAR-1) L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024 Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes ML24184B2822024-07-16016 July 2024 – Request to Use a Later Code Edition and Addenda of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML24193A2432024-07-12012 July 2024 – Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan 05000389/LER-2024-002-01, Safety Injection Tank Vent Through Wall Leakage2024-07-11011 July 2024 Safety Injection Tank Vent Through Wall Leakage L-2024-110, Environmental Protection Plan Report, Unusual or Important Environmental Event - Manatee in Intake2024-07-10010 July 2024 Environmental Protection Plan Report, Unusual or Important Environmental Event - Manatee in Intake L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024 Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal L-2024-109, Schedule for Subsequent License Renewal Environmental Review2024-07-0303 July 2024 Schedule for Subsequent License Renewal Environmental Review ML24172A1562024-06-27027 June 2024 Relief Request - PSL2-I5-RR-01 Proposed Alternative to Amse Code XI Code Examination Requirements - System Leakage Test of Reactor Pressure Vessel Bottom Head and Class 1 and 2 Piping in Covered Trenches L-2024-104, Response to Request for Additional Information, St. Luce 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 102024-06-26026 June 2024 Response to Request for Additional Information, St. Luce 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 L-2024-097, Technical Specification Special Report2024-06-20020 June 2024 Technical Specification Special Report L-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update ML24149A2862024-06-12012 June 2024 NextEra Fleet - Proposed Alternative Frr 23-01 to Use ASME Code Case N-752-1, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section X1, Division 1 (EPID L-2023-LLR-0009) - Letter L-2024-090, Revised Steam Generator Tube Inspection Reports2024-06-0404 June 2024 Revised Steam Generator Tube Inspection Reports IR 05000335/20244012024-06-0303 June 2024 Security Baseline Inspection Report 05000335/2024401 and 05000389/2024401 ML24135A0642024-05-17017 May 2024 Correction Letter - Amendment Nos. 253 and 208 Regarding Conversion to Improved Standard Technical Specifications L-2024-075, Notification of Improved Standard Technical Specifications (ITS) Implementation2024-05-13013 May 2024 Notification of Improved Standard Technical Specifications (ITS) Implementation IR 05000335/20240012024-05-10010 May 2024 Integrated Inspection Report 05000335/2024001 and 05000389/2024001 ML24127A0632024-05-0606 May 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-053, License Amendment Request L-2024-053, Updated Spent Fuel Pool Criticality Analysis2024-04-30030 April 2024 License Amendment Request L-2024-053, Updated Spent Fuel Pool Criticality Analysis L-2024-070, Cycle 32 Core Operating Limits Report2024-04-29029 April 2024 Cycle 32 Core Operating Limits Report L-2024-071, Cycle 27 Core Operating Limits Report2024-04-29029 April 2024 Cycle 27 Core Operating Limits Report ML24108A0632024-04-18018 April 2024 – Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection L-2024-056, Annual Radiological Environmental Operating Report for Calendar Year 20232024-04-17017 April 2024 Annual Radiological Environmental Operating Report for Calendar Year 2023 L-2024-064, Florida Power & Light Company - 10 CFR 50.46 - Emergency Core Cooling System SBLOCA 30-Day Report2024-04-17017 April 2024 Florida Power & Light Company - 10 CFR 50.46 - Emergency Core Cooling System SBLOCA 30-Day Report L-2024-054, 2023 Annual Environmental Operating Report2024-04-0909 April 2024 2023 Annual Environmental Operating Report ML24093A2612024-04-0202 April 2024 – Investigation Summary, Office of Investigations Case Number 2-2023-005 L-2024-047, Proposed Use of a Subsequent ASME Code Edition and Addenda2024-03-28028 March 2024 Proposed Use of a Subsequent ASME Code Edition and Addenda 2024-09-09
[Table view] Category:Safety Evaluation
MONTHYEARML24255A3092024-09-30030 September 2024 SLRA - Revised SE Letter ML24184B2822024-07-16016 July 2024 – Request to Use a Later Code Edition and Addenda of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML24172A1562024-06-27027 June 2024 Relief Request - PSL2-I5-RR-01 Proposed Alternative to Amse Code XI Code Examination Requirements - System Leakage Test of Reactor Pressure Vessel Bottom Head and Class 1 and 2 Piping in Covered Trenches ML24149A2862024-06-12012 June 2024 NextEra Fleet - Proposed Alternative Frr 23-01 to Use ASME Code Case N-752-1, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section X1, Division 1 (EPID L-2023-LLR-0009) - Letter ML24078A2622024-03-26026 March 2024 Revision to the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule ML24017A2092024-03-12012 March 2024 – Issuance of Amendment Nos. 254 and 209 to Adopt 10 CFR 50.69, Risk Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML24005A2772024-02-20020 February 2024 Issuance of Amendment Nos. 253 and 208 Regarding Conversion to Improved Standard Technical Specifications ML23219A0032023-09-0101 September 2023 SLRA SER Rev 1 ML23200A1462023-07-21021 July 2023 Safety Evaluation Related to the SLRA of St. Lucie Plant, Units 1 and 2 ML22255A1022022-09-21021 September 2022 Authorization and Safety Evaluation for Alternative Relief Request No. 10 - Hardship or Unusual Difficulty Without Compensating Increase in Level of Quality or Safety ML22038A1872022-02-0909 February 2022 Authorization and Safety Evaluation for Relief Request No. 19 (RR19) - the Use of an Alternative to ASME Code Case N-729-6 for Replacement Reactor Vessel Closure Head Penetration Nozzle 85 ML21342A2092022-01-14014 January 2022 Issuance of Amendment Nos. 252 and 207 to Allow Risk-Informed Completion Times (RICT) for the 120-Volt Alternating Current (AC) Instrument Bus Requirements ML21236A1312021-09-30030 September 2021 Authorization of RR 15 Regarding Extension of ASME Requirements Related to Reactor Pressure Vessel Weld Examinations from 10 to 20 Years ML21022A2192021-02-26026 February 2021 Issuance of Amendment No. 206 to Replace the Current Time-Limited Reactor Coolant System Pressure/Temperature Limit Curves and LTOP Setpoints with Curves and Setpoints That Will Remain Effective for 55 Effective Full Power Years ML21027A2262021-02-17017 February 2021 Approval of Alternative to ASME Code, Section XI to Use an Alternative Inservice Inspection Schedule for the Reaction Vessel Closure Head Bolting ML20329A4022021-02-0303 February 2021 Approval of Alternative to Use ASME Code Case N-513-4 for Alternative Repair of Intake Cooling Water System ML20259A2982020-11-18018 November 2020 Issuance of Amendment No. 205 Regarding Modification of the Reactor Coolant Pump Flywheel Inspection Program ML20237F2572020-10-30030 October 2020 Issuance of Amendment Nos. 251 and 204 Regarding Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6 Development of Emergency Action Levels for Non-Passive Reactors ML20099A3482020-06-25025 June 2020 Safety Evaluation for Relief Request for Fifth Ten-Year Inservice Inspection (ISI) Interval - Alternative Risk-Informed Inservice Inspection Program for Class 1 and 2 Piping Welds ML20023B3782020-02-19019 February 2020 Safety Evaluation for Relief Request RR-16, Alternate Repair of 2B Boric Acid Makeup Pump Revision for the Fourth 10-Year Inservice Inspection Interval ML20015A1232020-02-0606 February 2020 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML19266A0722020-01-27027 January 2020 Issuance of Amendment Nos. 250 and 202 Regarding Technical Specification Changes to Allow the Performance of Selected Emergency Diesel Generator Surveillance Requirements During Power Operation ML19254B5332019-09-30030 September 2019 Safety Evaluation for Relief Request RR#15, Revision 0, Regarding Limited Piping Examinations ML19148A7442019-07-31031 July 2019 Issuance of Amendment Nos. 161, 249, 200, 287, and 281 to Add Technical Specification Limiting Condition for Operation 3.0.6 ML19203A1662019-07-26026 July 2019 Issuance of Exigent Amendment No. 248 Technical Specification 3/4.8.1 Change to Allow for a One-Time Extension of the Allowed Outage Time for One Emergency Diesel Generator ML19115A2812019-05-31031 May 2019 Safety Evaluation for Relief Request No. 6 for the Fifth 10 Year Inservice Inspection Interval ML19058A4922019-04-23023 April 2019 Issuance of Amendment 198 Regarding Technical Specification Changes to Reduce the Number of Control Element Assemblies ML18274A2242018-11-0202 November 2018 Issuance of Amendment Nos. 246 and 197 Regarding Technical Specifications Site Area Map ML18256A0982018-10-30030 October 2018 Safety Evaluation for Relief Request No.5 for the Fifth 10-Year Inservice Inspection Interval ML18129A1492018-07-0909 July 2018 Issuance of Amendments Regarding Technical Specification Changes Related to the Auxiliary Feedwater System (CAC Nos. MG0237 and MG0238; EPID L-2017-LLA-0296) ML18106B1212018-04-25025 April 2018 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML18046A7122018-03-26026 March 2018 Issuance of Amendments Regarding the Unusual Event Fire Related Emergency Action Level Scheme ML18018A0332018-01-26026 January 2018 Safety Evaluation of Relief Requests for the Fifth 10-Year Inservice Testing Program (EPID L-2017-LLR-0113; L-2017-LLR-0017, L-2017-LLR-0018, L-2017-LLR-0119, L-2017-LLR-0120, L-2017-LLR-0121, and L-2017-LLR-0122) ML17334A9362018-01-0404 January 2018 Relief from the Requirements of the ASME Code Regarding Relief Request No. 17, Revision 0, for the Fourth 10-Year Inservice Inspection Interval (CAC No. MF9826; EPID L-2017-LLR-0043) ML17341A4422018-01-0404 January 2018 Relief from the Requirements of the ASME Code Relief Request No. 3 for the Fifth 10-Year Inservice Inspection Interval (CAC No. MF9288; EPID L-2017-LLR-0003) ML17257A0152017-10-31031 October 2017 Issuance of Amendments Regarding Technical Specification Changes Related to the Reactor Protection System and Limiting Condition for Operation 3.0.5 ML17263A1202017-10-27027 October 2017 Inservice Inspection Plan Fourth 10-Year Interval Relief Request No. 16 (CAC No. MF9827; EPID L-2017-LLR-0044) ML17248A3792017-10-23023 October 2017 Issuance of Amendments to Revise the Renewed Facility Operating Licenses Fire Protection License Conditions (CAC Nos. MF9681 and MF9682; EPID L-2017-LLA-0230) ML17235A5652017-10-0505 October 2017 Issuance of Amendments Regarding Technical Specification Changes Related to Component Cyclic or Transient Limits ML17219A1742017-08-31031 August 2017 Relief from the Requirements of the ASME Code Regarding Relief Request 12 for the Fourth 10-Year Inservice Inspection Interval ML17195A2912017-08-14014 August 2017 Issuance of Amendments Regarding Relocation of Radiation Monitor Requirements from Technical Specifications to Licensee-Controlled Documents ML17132A1672017-07-10010 July 2017 Inservice Inspection Plan Fourth 10 Year Interval Relief Request No. 13 ML17110A2702017-05-10010 May 2017 Inservice Inspection Plan Fourth 10-year Interval Relief Request No. 14 Rev 0 - ML17027A0782017-04-0707 April 2017 Issuance of Amendments Regarding Technical Specifications for Inservice Testing Programs (CAC Nos. MF8202 Through MF8209) ML17038A2252017-03-29029 March 2017 Issuance of Amendment No. 188 Regarding Emergency Diesel Generator Day Tank Volume ML16330A1182016-12-15015 December 2016 NextEra Fleet - Safety Evaluation for Proposed Alternative to the American Society of Mechanical Engineers Operation and Maintenance Code by Adoption of Approved Code Case OMN-20, Inservice Test Frequency (CAC Nos. MF8195 Through MF8201) ML16251A1282016-12-0505 December 2016 Issuance of Amendments to Update Appendix B to the Renewed Facility Operating License to Incorporate the 2016 Biological Opinion ML16292A7612016-11-0202 November 2016 Inservice Inspection Plan Fourth 10 Year Interval Relief Request No. 11 ML16166A4242016-10-0505 October 2016 St. Lucie Plant, Unit Nos. 1 and 2 - Issuance of Amendments Regarding the Use of a New Computer Code to Model the Containment Vacuum Analyses ML16183A1382016-09-19019 September 2016 Issuance of Amendments Regarding Technical Specification Change to Eliminate the Moderator Temperature Coefficient Surveillance Test at the End of Cycle 2024-09-30
[Table view] |
Text
Mr. Robert Coffey Vice President, Nuclear &
Chief Nuclear Officer Florida Power & Light Company 700 Universe Boulevard Mail Stop: EX/JB Juno Beach, FL 33408
SUBJECT:
ST. LUCIE PLANT, UNIT NOS. 1 AND 2 - SUPPLEMENT TO REVISION 1 OF THE SAFETY EVALUATION FOR THE SUBSEQUENT LICENSE RENEWAL APPLICATION REVIEW RESULTING FROM A COMMITMENT CHANGE
Dear Mr. Coffey:
By letter dated August 3, 2021 (Agencywide Documents Access and Management System Package Accession No. ML21215A314), as revised by letter dated October 12, 2021 (ML21285A107) and supplemented by letters dated April 7, 2022 (ML22097A202), April 13, 2022 (ML22103A014), May 19, 2022 (ML22139A083), June 13, 2022 (ML22164A802), July 11, 2022 (ML22192A078), August 9, 2022 (ML22221A134), September 8, 2022 (ML22251A202),
September 19, 2022 (ML22262A149), September 22, 2022 (ML22265A134), September 28, 2022 (ML22271A399), October 26, 2022 (ML22299A037), March 27, 2023 (ML23086B990),
April 21, 2023 (ML23111A129), April 30, 2023 (ML23109A113),June 14, 2023 (ML23165A114) and July 13, 2023 (ML23194A211), Florida Power & Light Company (FPL or the applicant) submitted an application for the subsequent license renewal (SLR) of Renewed Facility Operating License Nos. DPR-67 and NPF-16 for the St. Lucie Plant, Unit Nos. 1 and 2 (St.
Lucie), to the U.S. Nuclear Regulatory Commission (NRC). FPL submitted the application pursuant to Title 10 of the Code of Federal Regulations, part 54, Requirements for Renewal of Operating Licenses for Nuclear Power Plants, for SLR.
The NRC staff determined that the application was complete and acceptable for docketing as communicated by letter dated September 24, 2021 (ML21246A091) and noticed in the Federal Register on August 16, 2021 (86 FR 45768). The staff completed its review of the St. Lucie Subsequent License Renewal Application (SLRA) and issued the safety evaluation (SE) report on September 1, 2023 (ML23219A003).
On July 30, 2024, FPL submitted a letter (ML24212A194) notifying the NRC of a commitment change for St. Lucie, Unit 1. For Commitment Number 30 regarding the Buried and Underground Piping and Tanks, the schedule to install cathodic protection systems no later than 10 years prior to the subsequent period of operation (SPEO) is changed to 6 years prior to the SPEO. Section 3.0.3.3.23 and Table A.1 - Commitment 30, of the SE is hereby revised to reflect the schedule change, as shown in the enclosure. The Staff understands that this modification will be reflected in the next revised UFSAR Supplement for St. Lucie SLR.September 30, 2024 If you have any questions regarding this matter, please contact the SLR project manager, Mr.
Vaughn Thomas, by email at Vaughn.Thomas@nrc.gov.
Sincerely, Michele Sampson, Director Division of New and Renewed Licenses Office of Nuclear Reactor Regulation Docket Nos. 50-335 and 50-389 Enclosure Section 3.0.3.3.23 and Table A.1 cc w/encl: Listserv Signed by Sampson, Michele on 09/30/24
SUBJECT:
ST. LUCIE PLANT, UNIT NOS. 1 AND 2 - SUPPLEMENT TO REVISION 1 OF THE SAFETY EVALUATION FOR THE SUBSEQUENT LICENSE RENEWAL APPLICATION REVIEW RESULTING FROM A COMMITMENT CHANGE DATED:
SEPTEMBER 30, 2024 DISTRIBUTION:
E-MAIL:
PUBLIC RidsNrrDnrl Resource RidsNrrPMSt.Lucie Resource RidsACRS_MailCTR Resource RidsRgn2MailCenter Resource RidsRgn2Dnms Resource RidsRgn2Drp Resource RidsRgn2Drs Resource RidsRgn2Ora Resource RidsRgn2Opa Resource RidsNrrOd Resource VThomas, NRR/DNRL LGibson, NRR/DNRLLRakovan, NMSS/REFS TSmith, NMSS/REFS MSampson, NRR/DNRL SLee, NRR/DNRL NJordan, NRR/DORL DWrona, NRR/DORL ANaber, OGC MWoods, OGC RSkokowski, OEDO TKeene, OEDO SBurnell, HQ/OPADMcIntyre, HQ/OPA LWilkins, OCA DGasperson, RII/OPA JPelchat, RII/FCO DScrenci, RI/OPA JHickman, RII/DRP DDumbacher, RII/DRP Kenneth.Mack2@fpl.com ADAMS ML24255A309 OFFICE DNRL/NLRP:PM DNRL/NLRP:LA OGC DNLR/NLRP:BC NAME VThomas KBratcher STurk LGibson DATE 9/11/2024 9/11/2024 9/24/2024 9/27/2024 OFFICE DNRL:D NAME MSampson DATE OFFICIAL RECORD COPY9/30/24 3.0.3.3.23 Buried and Underground Piping and Tanks
SLRA section B.2.3.27 describes the new buried and underground piping and tanks program as consistent with GALL-SLR Report AMPXI.M41, Buried and Underground Piping and Tanks, except for the exception identified in the SLRA (the exception was added by letter dated September8,2022 (ML22251A202) in response to RAI B.2.3.27-1a). The applicant amended this SLRA section by letters dated April7,2022 (ML22097A202) and September8,2022 (ML22251A202).
Staff Evaluation. During the audit (ML22188A086), the staff reviewed the applicants claim of consistency with the GALL-SLR Report. The staff compared the scope of program, preventive actions, parameters monitored or inspected, detection of aging effects, monitoring and trending, acceptance criteria, and corrective actions program elements of the SLRA to the corresponding program elements of GALL-SLR Report AMPXI.M41.
The staff finds that the preventive actions program element, as modified by response to RAIB.2.3.27-1 (ML22164A802), is acceptable because it is consistent with GALL-SLR Report AMPXI.M41 recommendations: (a) buried metallic piping (excluding a portion of buried stainless steel (SS) piping, which the staff addresses in the exception below) is either concrete encased or externally coated with epoxy, coal tar epoxy, or fusion bonded epoxy; (b) portions of buried fire protection system piping (not covered by [a] above) are externally coated in accordance with NFPA 24, Standard for the Installation of Private Fire Service Mains and Their Appurtenances; and (c) underground steel piping is externally coated with zinc or coal tar epoxy.
The staff also reviewed the portions of the preventive actions program element associated with the exception to determine whether the program will be adequate to manage the aging effects for which it is credited. The staffs evaluation of this exception follows.
Exception 1. As amended by letter dated September8,2022 (ML22251A202), SLRA section B.2.3.27 includes an exception to the preventive actions program element related to buried SS piping buried beneath the Unit 1 turbine building, which could not be confirmed as externally coated. The staff reviewed this exception against the corresponding program element in GALL-SLR Report AMPXI.M41 and finds it acceptable as follows. In its response to RAI B.2.3.212 (ML22164A802), the applicant provided results from soil corrosivity testing conducted between 2011 and 2014. The applicant clarified (in its response to RAI B.2.3.27-1a) that the soil sample in which detectable levels of chlorides and sulfates were measured was near the intake cooling water piping on the intake side of the plant where saltwater intrusion had occurred and was not located near the subject uncoated SS piping. Based on the review of the soil corrosivity testing data (excluding the outlier soil sample noted above), the staff noted that soil can be considered moderately corrosive (the second least aggressive out of four categories) to SS when scoring in accordance with Table 9-4, Soil Corrosivity Index from BPWORKS, of Electric Power Research Institute (EPRI) Report 3002005294, Soil Sampling and Testing Methods to Evaluate the Corrosivity of the Environment for Buried Piping and Tanks at Nuclear Power Plants.
Enclosure In addition, as noted in the third supplement to NUREG-1930, Safety Evaluation Report Related to the License Renewal of Indian Point Nuclear Generating Unit Nos. 2 and 3, soil is considered aggressive for uncoated SS when soil resistivity is less than 1,000 ohm-cm, pH is less than 4.5, and chlorides are more than 500 parts per million. The staff noted the measured values of soil resistivity, pH, and chlorides were within these limits, confirming that the soil is nonaggressive for uncoated SS. Furthermore, the staff did not identify instances of age-related degradation in buried SS piping during the audit. Based on the nonaggressive environment and acceptable OE, the staff finds that two inspections of buried SS piping in each 10-year period (consistent with GALL-SLR Report Table XI.M412, Inspection of Buried and Underground Piping and Tanks) provides reasonable assurance that the effects of aging will be adequately managed during the SPEO.
The staff conducted an audit to verify the applicants claim of consistency with the GALL-SLR Report. Based on a review of the SLRA (as amended), and the applicants responses to RAIs B.2.3.27-1, B.2.3.27-2, and B.2.3.21-2, the staff finds that the scope of program, preventive actions, parameters monitored or inspected, detection of aging effects, monitoring and trending, acceptance criteria, and corrective actions program elements for which the applicant claimed consistency with the GALL-SLR Report are consistent with the corresponding program elements of GALL-SLR Report AMP XI.M41.
The staff also reviewed the exception between the applicants program and GALL-SLR Report XI.M41 associated with the preventive actions program element, and its justification, and finds that the AMP, with the exception, is adequate to manage the applicable aging effects.
Operating Experience. SLRA section B.2.3.27 summarizes OE related to the buried and underground piping and tanks program. The staff reviewed OE information in the lapplication and during the audit. As discussed in the audit report (ML22188A086), the staff reviewed plant OE information provided by the applicant to: (a) identify examples of age-related degradation, as documented in the applicants corrective action program database; and (b) provide a basis for the staffs conclusions on the ability of the applicants proposed AMPs to manage the effects of aging in the subsequent period of extended operation.
The staff did not identify any OE indicating that the applicant should modify its proposed program. Based on the audit and review of the application, the staff finds that the conditions and OE at the plant are bounded by those for which the buried and underground piping and tanks program was evaluated.
UFSAR Supplement. SLRA appendix A1, section 19.2.2.27 and appendix A2, section 19.2.2.27 provide the UFSAR supplement for the buried and underground piping and tanks program. The staff reviewed this UFSAR supplement description of the program and noted that it is consistent with the recommended description in GALL-SLR Report Table XI-01. As amended by letter dated July 30, 2024 (ML24212A194), the staff also noted the applicant committed to the following: (a) implement the new buried and underground piping and tanks program no later than six months prior to the subsequent period of extended operation for managing the effects of aging for applicable components; (b) install cathodic protection systems at least 6 years (for Unit 1) or 10years (for Unit 2) before the subsequent period of extended operation; (c) begin program inspections 6 years (for Unit 1) or 10years (for Unit 2) before the subsequent period of extended operation; and (d) complete the first 10-year interval inspections six months prior to the SPEO or no later than the last refueling outage prior to the subsequent period of extended operation. The staff finds that the information in the UFSAR supplement is an adequate summary description of the program.
Conclusion. Based on the review of the applicants buried and underground piping and tanks program, the staff concludes that those program elements for which the applicant claimed consistency with the GALL-SLR Report are consistent. The staff also reviewed the exception, and finds that with the exception implemented, the AMP will be adequate to manage the applicable aging effects. The staff concludes that the applicant has demonstrated that the effects of aging will be adequately managed so that the intended function(s) will be maintained consistent with the CLB for the subsequent period of extended operation, as required by 10CFR54.21(a)(3). The staff also reviewed the UFSAR supplement for this AMP and concludes that it provides an adequate summary description of the program, as required by 10CFR54.21(d).
Table A.1 - Commitment 30
NUREG Item -2192 Implementation No. Program/Topic Section Commitment Schedule Source 30 Buried and XI.M41 Implement the new PSL Buried and Underground Piping Program inspections SLRA Rev. 1 Underground Piping and Tanks AMP. begin 6 years before ML21285A110 and Tanks a) Install cathodic protection systems and perform the SPEO. SLRA Supplement 1 (19.2.2.27) effectiveness reviews in accordance with Table Inspections that are ML22097A202 XI.M41-2 in NUREG-2191,Section XI.M41. to be completed prior Letter to the SPEO are ML24212A194 b) If after five years of operation the cathodic completed 6 months protection system does not meet the prior to the SPEO or effectiveness acceptance criteria defined by no later than the last NUREG-2191, Tables XI.M41-2 and -3 (-850 mV refueling outage prior relative to a CSE, instant off, for at least 80% of to the SPEO.
the time, and in operation for at least 85% of the Install cathodic time), FPL commits to performing two additional protection systems at buried steel piping inspections beyond the least 6 years before number required by Preventive Action Category the SPEO.
F resulting in a total of 13 inspections being Program and SLR completed 6 months prior to the SPEO. The enhancements are cathodic protection criterion listed above will implemented 6 continue to be used after five years through the months prior to the end of the SPEO. SPEO, i.e.:
c) Perform periodic pressure testing and blow-out PSL1: 09/01/2035
testing (purging) with air or nitrogen of the annular volume between the underground stainless steel fuel oil piping and its respective guard piping to verify no leakage of guard pipe and no leakage from the fuel oil piping. This testing will be performed for at least 25 percent of the stainless steel fuel oil piping housed within guard piping at an interval not to exceed 5 years with the first occurrence prior to the SPEO. The annular volume between the fuel oil piping and guard piping will be pressurized to 110 percent of the design pressure of any component within the boundary (not to exceed the maximum allowable test pressure of any non-isolated components) with test pressure being held for a continuous eight hour interval.