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| {{#Wiki_filter:0October 6, 2015FPLi L-2015-25810 CFR 50.4U. S. Nuclear Regulatory CommissionAttn: Document Control DeskWashington, DC 20555Re: St. Lucie Unit 1Docket No. 50-335RAI REPLY FOR LICENSE RENEWAL CONDENSATE STORAGE TANKCROSS-CONNECT BURIED PIPING INSPECTION COMMITMENTReferences:1. FPL Letter L-2015-135 dated April 29, 2014, "License Renewal Condensate Storage Tank Cross-Connect Buried Piping Inspection (Unit 1 only) Revised Commitment", ADAMS Accession No.ML15 146A055.2. Request for Additional Information License Renewal Condensate Storage Tank Cross-ConnectBuried Piping Inspection Commitment Florida Power and Light Company St. Lucie Unit No. 1(M1F65 18), ADAMS Accession No. ML1 523 7A4 18.Florida Power & Light (FPL) submitted FPL Letter L-20 15-135 dated May 12, 2015, "License RenewalCondensate Storage Tank Cross-Connect Buried Piping Inspection (Unit 1 only) Revised Commitment"in Reference 1. Reference 2 forwarded a NRC request for additional information (RAI) on the submittal.FPL's response to the RAIs is attached to this correspondence.Please contact Lyle Berry at (772) 467-7680 should you have any questions regarding this submittal.VeryEric S. KatzmnanLicensing ManagerSt. Lucie PlantESK/lrbAttachmentcc: USNRC Regional Administrator, Region IIUSNRC Project Manager, St. Lucie Nuclear PlantUSNIRC Senior Resident Inspector, St. Lucie Nuclear PlantFlorida Power & Light Company6501 S. Ocean Drive, Jensen Beach, FL 34957 L-2015-258AttachmentPage 1 of 3REQUEST FOR ADDITIONAL INFORMATIONLICENSE RENEWAL CONDENSATE STORAGE TANKCROSS-CONNECT BURIED PWPNG INSPECTION COMMITMENTFLORIDA POWER AND LIGHT COMPANYST. LUCIE UNIT NO. 1DOCKET NO. 50-335TAG NO. MF6518By letter dated May 12, 2015 (Agency wide Documents Access and Management System Accession No.ML 15 146A055), Florida Power and Light Company provided information regarding the license renewalcommitment for St. Lucie Plant, Unit No. 1 (St. Lucie) to perform a one-time inspection of theCondensate Storage Tank (CST) cross-connect buried piping, prior to the end of the initial operatinglicense term.The U.S. Nuclear Regulatory Commission (NRC) staff has determined that additional information isrequired to complete its review.RAT 1 For the concrete that encases the CST piping, state the extent (i.e., length and depth) of concretethat was exposed and the condition of the concrete.RAI 2 State the basis for why water intrusion is not expected through the concrete to the surface of thestainless steel CST cross-connect piping, or if the potential for water intrusion exists, why lossof material or cracking of the stainless steel piping is not expected. | | {{#Wiki_filter:0October 6, 2015FPLi L-2015-25810 CFR 50.4U. S. Nuclear Regulatory CommissionAttn: Document Control DeskWashington, DC 20555Re: St. Lucie Unit 1Docket No. 50-335RAI REPLY FOR LICENSE RENEWAL CONDENSATE STORAGE TANKCROSS-CONNECT BURIED PIPING INSPECTION COMMITMENT |
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| | ==References:== |
| | : 1. FPL Letter L-2015-135 dated April 29, 2014, "License Renewal Condensate Storage Tank Cross-Connect Buried Piping Inspection (Unit 1 only) Revised Commitment", ADAMS Accession No.ML15 146A055.2. Request for Additional Information License Renewal Condensate Storage Tank Cross-ConnectBuried Piping Inspection Commitment Florida Power and Light Company St. Lucie Unit No. 1(M1F65 18), ADAMS Accession No. ML1 523 7A4 18.Florida Power & Light (FPL) submitted FPL Letter L-20 15-135 dated May 12, 2015, "License RenewalCondensate Storage Tank Cross-Connect Buried Piping Inspection (Unit 1 only) Revised Commitment"in Reference 1. Reference 2 forwarded a NRC request for additional information (RAI) on the submittal.FPL's response to the RAIs is attached to this correspondence.Please contact Lyle Berry at (772) 467-7680 should you have any questions regarding this submittal.VeryEric S. KatzmnanLicensing ManagerSt. Lucie PlantESK/lrbAttachmentcc: USNRC Regional Administrator, Region IIUSNRC Project Manager, St. Lucie Nuclear PlantUSNIRC Senior Resident Inspector, St. Lucie Nuclear PlantFlorida Power & Light Company6501 S. Ocean Drive, Jensen Beach, FL 34957 L-2015-258AttachmentPage 1 of 3REQUEST FOR ADDITIONAL INFORMATIONLICENSE RENEWAL CONDENSATE STORAGE TANKCROSS-CONNECT BURIED PWPNG INSPECTION COMMITMENTFLORIDA POWER AND LIGHT COMPANYST. LUCIE UNIT NO. 1DOCKET NO. 50-335TAG NO. MF6518By letter dated May 12, 2015 (Agency wide Documents Access and Management System Accession No.ML 15 146A055), Florida Power and Light Company provided information regarding the license renewalcommitment for St. Lucie Plant, Unit No. 1 (St. Lucie) to perform a one-time inspection of theCondensate Storage Tank (CST) cross-connect buried piping, prior to the end of the initial operatinglicense term.The U.S. Nuclear Regulatory Commission (NRC) staff has determined that additional information isrequired to complete its review.RAT 1 For the concrete that encases the CST piping, state the extent (i.e., length and depth) of concretethat was exposed and the condition of the concrete.RAI 2 State the basis for why water intrusion is not expected through the concrete to the surface of thestainless steel CST cross-connect piping, or if the potential for water intrusion exists, why lossof material or cracking of the stainless steel piping is not expected. |
| L-201 5-25 8AttachmentPage 2 of 3NRC RAI# 1For the concrete that encases the CST piping, state the extent (i.e., length and depth) of concrete that was"_- exposed and the condition of the concrete.FPL Response to RAI # 1On March 29, 2015 excavation activities uncovered a concrete structure at the design location ofthe pipe (8-C-95 Condensate Storage Tank cross-connect). A section of concrete was exposedapproximately 11 feet long. The width was 18 inches and the depth of the concrete was determined to be18 inches by partial (semi-circle) excavation at two locations approximately 6 feet apart on the East side.The West side was not disturbed because design drawings indicated a fire protection pipe was in closeproximity on the West side. The drawings identify the lowest section of the pipe run is at elevation13 feet (the nominal site grade elevation is elevation 18 feet) and this is the approximate location wherethe concrete was exposed.There were no indications of any degradation of the concrete such as cracking, spalling, scaling, pitting,leaching, erosion, settlement, cavitation or abrasion areas, voids, pop outs or exposed reinforcing steel.Debris observed on the concrete duct is from excavated soil and gravel. The concrete duct has roughedges and surface. It can be concluded that this roughness is due to concrete formwork removal during theoriginal construction activities and the condition is in accordance with the original constructionspecification for concrete which states, "for surfaces against which backfill or concrete is to be placed notreatment is required except for repair of defective areas."NRC RAI# 2State the basis for why water intrusion is not expected through the concrete to the surface of the stainlesssteel CST cross-connect piping, or if the potential for water intrusion exists, why loss of material orcracking of the stainless steel piping is not expected.FPL Response to RAI # 2The As-Built isometric drawing for the pipe is dated August 7, 1973. Specific records associated with theconcrete placement for the pipe were not located. Plant operating experience obtained from the buriedpiping program and the observed condition of the concrete which was exposed during the inspection willbe used to support the conclusion that water intrusion does not exist and loss of material or cracking ofthe stainless steel piping is not expected.The excavation site was dry which is consistent with the design. Unit 1 FSAR Figure 3-8.41 "Water Tableat EL + 3 'Loading" and Unit 2 FSAR Section 2.4.13.5 "Design Basis for Subsurface HydrostaticLoading" identify "The water table is at elevation plus 3 feet MVLW [sic] for normal conditions...". Withthe design location being approximately 10 feet above the normal water table, the concrete encased pipeis not likely to be submerged for extended periods of time.Summary_ of Inspection Results from excavation of the pipe / concreteAs stated above, on March 29 2015 excavation activities uncovered a concrete structure at the designlocation of the pipe. This supported the conclusion that the pipe is encased in concrete and not directlyburied. | | L-201 5-25 8AttachmentPage 2 of 3NRC RAI# 1For the concrete that encases the CST piping, state the extent (i.e., length and depth) of concrete that was"_- exposed and the condition of the concrete.FPL Response to RAI # 1On March 29, 2015 excavation activities uncovered a concrete structure at the design location ofthe pipe (8-C-95 Condensate Storage Tank cross-connect). A section of concrete was exposedapproximately 11 feet long. The width was 18 inches and the depth of the concrete was determined to be18 inches by partial (semi-circle) excavation at two locations approximately 6 feet apart on the East side.The West side was not disturbed because design drawings indicated a fire protection pipe was in closeproximity on the West side. The drawings identify the lowest section of the pipe run is at elevation13 feet (the nominal site grade elevation is elevation 18 feet) and this is the approximate location wherethe concrete was exposed.There were no indications of any degradation of the concrete such as cracking, spalling, scaling, pitting,leaching, erosion, settlement, cavitation or abrasion areas, voids, pop outs or exposed reinforcing steel.Debris observed on the concrete duct is from excavated soil and gravel. The concrete duct has roughedges and surface. It can be concluded that this roughness is due to concrete formwork removal during theoriginal construction activities and the condition is in accordance with the original constructionspecification for concrete which states, "for surfaces against which backfill or concrete is to be placed notreatment is required except for repair of defective areas."NRC RAI# 2State the basis for why water intrusion is not expected through the concrete to the surface of the stainlesssteel CST cross-connect piping, or if the potential for water intrusion exists, why loss of material orcracking of the stainless steel piping is not expected.FPL Response to RAI # 2The As-Built isometric drawing for the pipe is dated August 7, 1973. Specific records associated with theconcrete placement for the pipe were not located. Plant operating experience obtained from the buriedpiping program and the observed condition of the concrete which was exposed during the inspection willbe used to support the conclusion that water intrusion does not exist and loss of material or cracking ofthe stainless steel piping is not expected.The excavation site was dry which is consistent with the design. Unit 1 FSAR Figure 3-8.41 "Water Tableat EL + 3 'Loading" and Unit 2 FSAR Section 2.4.13.5 "Design Basis for Subsurface HydrostaticLoading" identify "The water table is at elevation plus 3 feet MVLW [sic] for normal conditions...". Withthe design location being approximately 10 feet above the normal water table, the concrete encased pipeis not likely to be submerged for extended periods of time.Summary_ of Inspection Results from excavation of the pipe / concreteAs stated above, on March 29 2015 excavation activities uncovered a concrete structure at the designlocation of the pipe. This supported the conclusion that the pipe is encased in concrete and not directlyburied. |
| L-2015-258AttachmentPage 3 of 3No degradation of the concrete such as cracking, spalling, scaling, pitting, leaching, erosion, settlement,cavitation, abrasion, areas, voids, pop outs or exposed reinforcing steel were identified during theinspection. Debris observed on the concrete duct was from excavated soil and gravel. The concrete ducthas rough edges and surface. It can be concluded that this roughness is due to concrete fornwork removalduring the original construction activities.Based on the observed condition of the concrete, water intrusion is not expected through the concrete tothe surface of the stainless steel crosstie piping.Results of the inspection are located in the Corrective Action program under Action Request (AR)02036344.Buried Piping ProgramSt. Lucie has implemented a buried piping inspection program in accordance with NEI 09-14, "Guidelinefor the Management of Underground Piping and Tank Tntegrity"', Rev. 3. Program review determined thatSt. Lucie Unit 2 design documents are very specific and require concrete encasement of buried piping thatis stainless steel or contains licensed material. Since the Unit 1 design documents did not specificallyrequire this encasement, exploratory digs were conducted. In each of the inspections, the piping wasfound to be encased in concrete and the concrete was solid with no delamination. This piping was thenexempt from piping surface inspection as part of the buried piping inspection program, since it wasdetermined to be encased in concrete.In accordance with NEI 09-14 Rev. 3, the St. Lucie buried piping program scope includes safety- related,licensed material, or environmentally hazardous lines. The 8-C-95 line does not fall into this scopingcondition, but was included and credited in the buried piping program due to the St. Lucie one-timelicense renewal conmmitment. St. Lucie's Buried Piping Asset Management Plan is a living document andis periodically updated with inspection results, risk ranking, and future inspection scope.St. Lucie conducted soil sampling as part of the buried piping inspection program. In general, the soil pHwas approximately 9.0, indicating the soil was alkaline. Based on the EPRI presentation, "WhatConstitutes Corrosive Soil", by Doug Munson, dated July 2013, a pH > 8.5 indicates dissolved salts, lowresistivity, and corrosive to cast iron. The CST crosstie piping at St. Lucie is stainless steel and loss ofmaterial or cracking are not expected to occur with the tested soil condition, due to any migration of waterthrough the concrete to the surface of the piping.References:1. St. Lucie Action Request Assignment 01681374-06, NEI 09-014 Revision 3, Asset ManagementPlan, St. Lucie Nuclear Station Underground Piping and Tank Integrity Program (UJPTIP),Revision 0.2. St. Lucie Action Request 02036344, License Renewal Inspection of Condensate Cross Tie C-8-95(a.k.a, 8-C-95).3. St. Lucie Work Order WO 40129353-01, Visual Exam of Buried U1/U2 COND. CROSSTIE8"-C-95. | | L-2015-258AttachmentPage 3 of 3No degradation of the concrete such as cracking, spalling, scaling, pitting, leaching, erosion, settlement,cavitation, abrasion, areas, voids, pop outs or exposed reinforcing steel were identified during theinspection. Debris observed on the concrete duct was from excavated soil and gravel. The concrete ducthas rough edges and surface. It can be concluded that this roughness is due to concrete fornwork removalduring the original construction activities.Based on the observed condition of the concrete, water intrusion is not expected through the concrete tothe surface of the stainless steel crosstie piping.Results of the inspection are located in the Corrective Action program under Action Request (AR)02036344.Buried Piping ProgramSt. Lucie has implemented a buried piping inspection program in accordance with NEI 09-14, "Guidelinefor the Management of Underground Piping and Tank Tntegrity"', Rev. 3. Program review determined thatSt. Lucie Unit 2 design documents are very specific and require concrete encasement of buried piping thatis stainless steel or contains licensed material. Since the Unit 1 design documents did not specificallyrequire this encasement, exploratory digs were conducted. In each of the inspections, the piping wasfound to be encased in concrete and the concrete was solid with no delamination. This piping was thenexempt from piping surface inspection as part of the buried piping inspection program, since it wasdetermined to be encased in concrete.In accordance with NEI 09-14 Rev. 3, the St. Lucie buried piping program scope includes safety- related,licensed material, or environmentally hazardous lines. The 8-C-95 line does not fall into this scopingcondition, but was included and credited in the buried piping program due to the St. Lucie one-timelicense renewal conmmitment. St. Lucie's Buried Piping Asset Management Plan is a living document andis periodically updated with inspection results, risk ranking, and future inspection scope.St. Lucie conducted soil sampling as part of the buried piping inspection program. In general, the soil pHwas approximately 9.0, indicating the soil was alkaline. Based on the EPRI presentation, "WhatConstitutes Corrosive Soil", by Doug Munson, dated July 2013, a pH > 8.5 indicates dissolved salts, lowresistivity, and corrosive to cast iron. The CST crosstie piping at St. Lucie is stainless steel and loss ofmaterial or cracking are not expected to occur with the tested soil condition, due to any migration of waterthrough the concrete to the surface of the piping. |
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| | ==References:== |
| | : 1. St. Lucie Action Request Assignment 01681374-06, NEI 09-014 Revision 3, Asset ManagementPlan, St. Lucie Nuclear Station Underground Piping and Tank Integrity Program (UJPTIP),Revision 0.2. St. Lucie Action Request 02036344, License Renewal Inspection of Condensate Cross Tie C 95(a.k.a, 8-C-95).3. St. Lucie Work Order WO 40129353-01, Visual Exam of Buried U1/U2 COND. CROSSTIE8"-C-95. |
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Category:Letter
MONTHYEARIR 05000335/20240032024-11-0707 November 2024 Integrated Inspection Report 05000335/2024003 and 05000389/2024003 ML24291A2862024-11-0101 November 2024 – Relief Request: 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-2024-176, Annual 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2024-10-30030 October 2024 Annual 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums L-2024-167, Correction to St. Lucie L-2024-132, 2024 Population Update Analysis2024-10-22022 October 2024 Correction to St. Lucie L-2024-132, 2024 Population Update Analysis IR 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-2024-169, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site- Specific Annexes2024-10-15015 October 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site- Specific Annexes 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 ML24228A2962024-09-0606 September 2024 NRC to NMFS, Designation of FPL as the Non-Federal Representative for St. Lucie IR 05000335/20240052024-08-22022 August 2024 Updated Inspection Plan for St. Lucie, Units 1 & 2 - Report 05000335/2024005 and 05000389/2024005 L-2024-133, Snubber Program Plan Submittal2024-08-14014 August 2024 Snubber Program Plan Submittal L-2024-140, Cycle 28 Core Operating Limits Report2024-08-14014 August 2024 Cycle 28 Core Operating Limits Report 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 2024-09-09
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARL-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-2024-104, 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 ML24127A0632024-05-0606 May 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes 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-2023-118, 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-2023-098, 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-2023-059, 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-2023-026, 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 ML23013A2032023-01-13013 January 2023 RAI Set 4 Draft Response 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-2022-156, Correction to Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 1a Response2022-09-19019 September 2022 Correction to Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 1a Response L-2022-143, Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 1A Response2022-09-0808 September 2022 Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 1A Response L-2022-115, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 3 Response and Submittal of Superseded Response for One Set 2 RAI and One Supplement 1 Attachment2022-08-0909 August 2022 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 3 Response and Submittal of Superseded Response for One Set 2 RAI and One Supplement 1 Attachment L-2022-108, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 2 Response2022-07-11011 July 2022 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 2 Response L-2022-075, Subsequent License Renewal Application-Aging Management Requests for Additional Information (RAI) Set 1A Response and Request for Confirmation of Information (RCI) Set 1 Response2022-06-13013 June 2022 Subsequent License Renewal Application-Aging Management Requests for Additional Information (RAI) Set 1A Response and Request for Confirmation of Information (RCI) Set 1 Response L-2022-000, License Amendment Request for the Technical Specifications Conversion to NUREG- 1432 Revision 5 - Request for Supplemental Information (Rsi) Response2022-01-19019 January 2022 License Amendment Request for the Technical Specifications Conversion to NUREG- 1432 Revision 5 - Request for Supplemental Information (Rsi) Response L-2021-105, Response to Request for Additional Information for St. Lucie License Amendment Request to Allow Risk Informed Completion Times (RICT) for the 120-Volt AC Instrument Bus Requirements2021-05-12012 May 2021 Response to Request for Additional Information for St. Lucie License Amendment Request to Allow Risk Informed Completion Times (RICT) for the 120-Volt AC Instrument Bus Requirements L-2021-065, Response to Request for Additional Information. Relief Request Number RR 15, Extension of St. Lucie Unit 2 RPV Welds from 10 to 20 Years2021-04-0101 April 2021 Response to Request for Additional Information. Relief Request Number RR 15, Extension of St. Lucie Unit 2 RPV Welds from 10 to 20 Years L-2020-165, Supplement to Updated Final Response to NRC Generic Letter 2004-022020-12-0404 December 2020 Supplement to Updated Final Response to NRC Generic Letter 2004-02 L-2020-094, Supplemental Response to Request for Additional Information Regarding License Amendment Request to Modify the Reactor Coolant Pump (RCP) Flywheel Inspection Program Requirements2020-06-26026 June 2020 Supplemental Response to Request for Additional Information Regarding License Amendment Request to Modify the Reactor Coolant Pump (RCP) Flywheel Inspection Program Requirements L-2020-061, Response to Request for Additional Information Regarding License Amendment Request to Modify the Reactor Coolant Pump (RCP) Flywheel Inspection Program Requirements2020-04-30030 April 2020 Response to Request for Additional Information Regarding License Amendment Request to Modify the Reactor Coolant Pump (RCP) Flywheel Inspection Program Requirements ML20015A0282020-01-14014 January 2020 NMFS to NRC, Concurrence with Interim Response to Requests for Additional Information for St. Lucie Endangered Species Act Section 7 Consultation L-2019-164, Response to Request for Additional Information Regarding License Amendment Request to Relocate the MOV Thermal Overload Protection Bypass Devices Requirements to Licensee Control2019-09-11011 September 2019 Response to Request for Additional Information Regarding License Amendment Request to Relocate the MOV Thermal Overload Protection Bypass Devices Requirements to Licensee Control L-2019-166, Refueling Outage SL2-24 Steam Generator Tube Inspection Report RAI Response2019-08-21021 August 2019 Refueling Outage SL2-24 Steam Generator Tube Inspection Report RAI Response L-2019-153, Exigent Technical Specification Amendment Request Supplemental RAI Reply One-Time Allowed Outage Time Extension for Inoperable EDG2019-07-25025 July 2019 Exigent Technical Specification Amendment Request Supplemental RAI Reply One-Time Allowed Outage Time Extension for Inoperable EDG L-2019-149, Exigent Technical Specification Amendment Request RAI Reply One-Time Allowed Outage Time Extension for Inoperable EDG2019-07-24024 July 2019 Exigent Technical Specification Amendment Request RAI Reply One-Time Allowed Outage Time Extension for Inoperable EDG L-2019-118, Response to Request for Additional Information Regarding License Amendment Request to Allow Performance of Selected Emergency Diesel Generator (EDG) Surveillance Requirements (Srs) During Power Operation2019-06-28028 June 2019 Response to Request for Additional Information Regarding License Amendment Request to Allow Performance of Selected Emergency Diesel Generator (EDG) Surveillance Requirements (Srs) During Power Operation L-2019-107, License Amendment Request - Iodine Removal System Elimination2019-05-17017 May 2019 License Amendment Request - Iodine Removal System Elimination L-2019-056, Inservice Inspection Plan RAI Reply, Fifth Ten-Year Interval Unit 1 Relief Request2019-03-0707 March 2019 Inservice Inspection Plan RAI Reply, Fifth Ten-Year Interval Unit 1 Relief Request L-2018-205, Response to Request for Additional Information Regarding License Amendment Request to Reduce the Number of Control Element Assemblies2018-11-15015 November 2018 Response to Request for Additional Information Regarding License Amendment Request to Reduce the Number of Control Element Assemblies L-2018-153, Supplemental Information for License Amendment Request to Reduce the Number of Control Element Assemblies2018-08-17017 August 2018 Supplemental Information for License Amendment Request to Reduce the Number of Control Element Assemblies L-16-001, Units. 3 and 4, Response to Request for Supplemental Information Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools.2018-05-24024 May 2018 Units. 3 and 4, Response to Request for Supplemental Information Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools. L-2018-068, Florida Power and Light Co. - Response to Request for Additional Information Re Decommissioning Funding Plan Updates for Independent Spent Fuel Storage Installations2018-04-0303 April 2018 Florida Power and Light Co. - Response to Request for Additional Information Re Decommissioning Funding Plan Updates for Independent Spent Fuel Storage Installations L-77-291, Attachment a to L-77-291 Response to NRC Questions of May 24, 19772018-03-29029 March 2018 Attachment a to L-77-291 Response to NRC Questions of May 24, 1977 L-2018-040, Response to Request for Additional Information Regarding License Amendment Request to Add New Required Actions for an Inoperable Auxiliary Feedwater Pump Steam Supply2018-02-14014 February 2018 Response to Request for Additional Information Regarding License Amendment Request to Add New Required Actions for an Inoperable Auxiliary Feedwater Pump Steam Supply L-2018-006, Third Response to Request for Additional Information Regarding License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Risk Informed Extended Completion Times - RITSTF Initiative 4b2018-02-0101 February 2018 Third Response to Request for Additional Information Regarding License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Risk Informed Extended Completion Times - RITSTF Initiative 4b L-2017-210, Updated Final Response to NRC Generic Letter 2004-022017-12-20020 December 2017 Updated Final Response to NRC Generic Letter 2004-02 L-2017-216, License Renewal Commitments: Reactor Vessel Internals Aging Management Plan, Clarification of Responses to RAI 1 and RAI 62017-12-19019 December 2017 License Renewal Commitments: Reactor Vessel Internals Aging Management Plan, Clarification of Responses to RAI 1 and RAI 6 L-2017-209, Response to Request for Additional Information Regarding Fifth 10-Year Inservice Testing (IST) Program Interval Relief Request PR-012017-11-30030 November 2017 Response to Request for Additional Information Regarding Fifth 10-Year Inservice Testing (IST) Program Interval Relief Request PR-01 L-2017-159, Response to Request for Additional Information Regarding Inservice Inspection Plan, Fifth Ten-Year Interval Unit 1 Relief Request No. 3, Revision 02017-09-13013 September 2017 Response to Request for Additional Information Regarding Inservice Inspection Plan, Fifth Ten-Year Interval Unit 1 Relief Request No. 3, Revision 0 L-2017-116, Response to Request for Additional Information Regarding License Amendment Request to Revise the Technical Specifications (TS) for the Reactor Protection System (RPS) Power Rate-of-Change Instrumentation and Add New TS 3.0.52017-07-0303 July 2017 Response to Request for Additional Information Regarding License Amendment Request to Revise the Technical Specifications (TS) for the Reactor Protection System (RPS) Power Rate-of-Change Instrumentation and Add New TS 3.0.5 L-2016-220, License Amendment Request EDG Day Tank Fuel Volume Change2016-12-0505 December 2016 License Amendment Request EDG Day Tank Fuel Volume Change L-2016-188, Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools, Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f)2016-11-0303 November 2016 Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools, Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) L-2016-153, Response to Request for Additional Information Regarding License Amendment Request for Biological Opinion License Changes2016-08-11011 August 2016 Response to Request for Additional Information Regarding License Amendment Request for Biological Opinion License Changes L-2016-135, Second Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B2016-07-22022 July 2016 Second Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B L-2016-143, Response to Request for Additional Information for the Proposed Technical Specification Change to Remove the 10 Year Sediment Cleaning of the Fuel Oil Storage Tank and Relocate to Licensee-Controlled Documents2016-07-15015 July 2016 Response to Request for Additional Information for the Proposed Technical Specification Change to Remove the 10 Year Sediment Cleaning of the Fuel Oil Storage Tank and Relocate to Licensee-Controlled Documents L-2016-114, Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 48.2016-07-0808 July 2016 Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 48. L-2016-102, RAI Reply - License Amendment Request, Containment Vacuum Gothic Analyses and Conforming Changes2016-05-0606 May 2016 RAI Reply - License Amendment Request, Containment Vacuum Gothic Analyses and Conforming Changes L-2016-104, RAI Reply - Application for Technical Specification Change Regarding Moderator Temperature Coefficient (Mtc) Surveillance Test Elimination at the End of Cycle2016-05-0606 May 2016 RAI Reply - Application for Technical Specification Change Regarding Moderator Temperature Coefficient (Mtc) Surveillance Test Elimination at the End of Cycle 2024-09-16
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0October 6, 2015FPLi L-2015-25810 CFR 50.4U. S. Nuclear Regulatory CommissionAttn: Document Control DeskWashington, DC 20555Re: St. Lucie Unit 1Docket No. 50-335RAI REPLY FOR LICENSE RENEWAL CONDENSATE STORAGE TANKCROSS-CONNECT BURIED PIPING INSPECTION COMMITMENT
References:
- 1. FPL Letter L-2015-135 dated April 29, 2014, "License Renewal Condensate Storage Tank Cross-Connect Buried Piping Inspection (Unit 1 only) Revised Commitment", ADAMS Accession No.ML15 146A055.2. Request for Additional Information License Renewal Condensate Storage Tank Cross-ConnectBuried Piping Inspection Commitment Florida Power and Light Company St. Lucie Unit No. 1(M1F65 18), ADAMS Accession No. ML1 523 7A4 18.Florida Power & Light (FPL) submitted FPL Letter L-20 15-135 dated May 12, 2015, "License RenewalCondensate Storage Tank Cross-Connect Buried Piping Inspection (Unit 1 only) Revised Commitment"in Reference 1. Reference 2 forwarded a NRC request for additional information (RAI) on the submittal.FPL's response to the RAIs is attached to this correspondence.Please contact Lyle Berry at (772) 467-7680 should you have any questions regarding this submittal.VeryEric S. KatzmnanLicensing ManagerSt. Lucie PlantESK/lrbAttachmentcc: USNRC Regional Administrator, Region IIUSNRC Project Manager, St. Lucie Nuclear PlantUSNIRC Senior Resident Inspector, St. Lucie Nuclear PlantFlorida Power & Light Company6501 S. Ocean Drive, Jensen Beach, FL 34957 L-2015-258AttachmentPage 1 of 3REQUEST FOR ADDITIONAL INFORMATIONLICENSE RENEWAL CONDENSATE STORAGE TANKCROSS-CONNECT BURIED PWPNG INSPECTION COMMITMENTFLORIDA POWER AND LIGHT COMPANYST. LUCIE UNIT NO. 1DOCKET NO. 50-335TAG NO. MF6518By letter dated May 12, 2015 (Agency wide Documents Access and Management System Accession No.ML 15 146A055), Florida Power and Light Company provided information regarding the license renewalcommitment for St. Lucie Plant, Unit No. 1 (St. Lucie) to perform a one-time inspection of theCondensate Storage Tank (CST) cross-connect buried piping, prior to the end of the initial operatinglicense term.The U.S. Nuclear Regulatory Commission (NRC) staff has determined that additional information isrequired to complete its review.RAT 1 For the concrete that encases the CST piping, state the extent (i.e., length and depth) of concretethat was exposed and the condition of the concrete.RAI 2 State the basis for why water intrusion is not expected through the concrete to the surface of thestainless steel CST cross-connect piping, or if the potential for water intrusion exists, why lossof material or cracking of the stainless steel piping is not expected.
L-201 5-25 8AttachmentPage 2 of 3NRC RAI# 1For the concrete that encases the CST piping, state the extent (i.e., length and depth) of concrete that was"_- exposed and the condition of the concrete.FPL Response to RAI # 1On March 29, 2015 excavation activities uncovered a concrete structure at the design location ofthe pipe (8-C-95 Condensate Storage Tank cross-connect). A section of concrete was exposedapproximately 11 feet long. The width was 18 inches and the depth of the concrete was determined to be18 inches by partial (semi-circle) excavation at two locations approximately 6 feet apart on the East side.The West side was not disturbed because design drawings indicated a fire protection pipe was in closeproximity on the West side. The drawings identify the lowest section of the pipe run is at elevation13 feet (the nominal site grade elevation is elevation 18 feet) and this is the approximate location wherethe concrete was exposed.There were no indications of any degradation of the concrete such as cracking, spalling, scaling, pitting,leaching, erosion, settlement, cavitation or abrasion areas, voids, pop outs or exposed reinforcing steel.Debris observed on the concrete duct is from excavated soil and gravel. The concrete duct has roughedges and surface. It can be concluded that this roughness is due to concrete formwork removal during theoriginal construction activities and the condition is in accordance with the original constructionspecification for concrete which states, "for surfaces against which backfill or concrete is to be placed notreatment is required except for repair of defective areas."NRC RAI# 2State the basis for why water intrusion is not expected through the concrete to the surface of the stainlesssteel CST cross-connect piping, or if the potential for water intrusion exists, why loss of material orcracking of the stainless steel piping is not expected.FPL Response to RAI # 2The As-Built isometric drawing for the pipe is dated August 7, 1973. Specific records associated with theconcrete placement for the pipe were not located. Plant operating experience obtained from the buriedpiping program and the observed condition of the concrete which was exposed during the inspection willbe used to support the conclusion that water intrusion does not exist and loss of material or cracking ofthe stainless steel piping is not expected.The excavation site was dry which is consistent with the design. Unit 1 FSAR Figure 3-8.41 "Water Tableat EL + 3 'Loading" and Unit 2 FSAR Section 2.4.13.5 "Design Basis for Subsurface HydrostaticLoading" identify "The water table is at elevation plus 3 feet MVLW [sic] for normal conditions...". Withthe design location being approximately 10 feet above the normal water table, the concrete encased pipeis not likely to be submerged for extended periods of time.Summary_ of Inspection Results from excavation of the pipe / concreteAs stated above, on March 29 2015 excavation activities uncovered a concrete structure at the designlocation of the pipe. This supported the conclusion that the pipe is encased in concrete and not directlyburied.
L-2015-258AttachmentPage 3 of 3No degradation of the concrete such as cracking, spalling, scaling, pitting, leaching, erosion, settlement,cavitation, abrasion, areas, voids, pop outs or exposed reinforcing steel were identified during theinspection. Debris observed on the concrete duct was from excavated soil and gravel. The concrete ducthas rough edges and surface. It can be concluded that this roughness is due to concrete fornwork removalduring the original construction activities.Based on the observed condition of the concrete, water intrusion is not expected through the concrete tothe surface of the stainless steel crosstie piping.Results of the inspection are located in the Corrective Action program under Action Request (AR)02036344.Buried Piping ProgramSt. Lucie has implemented a buried piping inspection program in accordance with NEI 09-14, "Guidelinefor the Management of Underground Piping and Tank Tntegrity"', Rev. 3. Program review determined thatSt. Lucie Unit 2 design documents are very specific and require concrete encasement of buried piping thatis stainless steel or contains licensed material. Since the Unit 1 design documents did not specificallyrequire this encasement, exploratory digs were conducted. In each of the inspections, the piping wasfound to be encased in concrete and the concrete was solid with no delamination. This piping was thenexempt from piping surface inspection as part of the buried piping inspection program, since it wasdetermined to be encased in concrete.In accordance with NEI 09-14 Rev. 3, the St. Lucie buried piping program scope includes safety- related,licensed material, or environmentally hazardous lines. The 8-C-95 line does not fall into this scopingcondition, but was included and credited in the buried piping program due to the St. Lucie one-timelicense renewal conmmitment. St. Lucie's Buried Piping Asset Management Plan is a living document andis periodically updated with inspection results, risk ranking, and future inspection scope.St. Lucie conducted soil sampling as part of the buried piping inspection program. In general, the soil pHwas approximately 9.0, indicating the soil was alkaline. Based on the EPRI presentation, "WhatConstitutes Corrosive Soil", by Doug Munson, dated July 2013, a pH > 8.5 indicates dissolved salts, lowresistivity, and corrosive to cast iron. The CST crosstie piping at St. Lucie is stainless steel and loss ofmaterial or cracking are not expected to occur with the tested soil condition, due to any migration of waterthrough the concrete to the surface of the piping.
References:
- 1. St. Lucie Action Request Assignment 01681374-06, NEI 09-014 Revision 3, Asset ManagementPlan, St. Lucie Nuclear Station Underground Piping and Tank Integrity Program (UJPTIP),Revision 0.2. St. Lucie Action Request 02036344, License Renewal Inspection of Condensate Cross Tie C 95(a.k.a, 8-C-95).3. St. Lucie Work Order WO 40129353-01, Visual Exam of Buried U1/U2 COND. CROSSTIE8"-C-95.