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| | number = ML15356A650 | | | number = ML15356A650 |
| | issue date = 01/19/2016 | | | issue date = 01/19/2016 |
| | title = St. Lucie Plant, Unit 1 - Review of the License Renewal Condensate Storage Tank Cross-Connect Buried Piping Inspection Commitment (CAC No. MF6518) | | | title = Review of the License Renewal Condensate Storage Tank Cross-Connect Buried Piping Inspection Commitment |
| | author name = Buckberg P H | | | author name = Buckberg P |
| | author affiliation = NRC/NRR/DORL/LPLII-2 | | | author affiliation = NRC/NRR/DORL/LPLII-2 |
| | addressee name = Nazar M | | | addressee name = Nazar M |
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| | docket = 05000335 | | | docket = 05000335 |
| | license number = DPR-067 | | | license number = DPR-067 |
| | contact person = Saba F E, NRR/DORL/LPLII-2 | | | contact person = Saba F, NRR/DORL/LPLII-2 |
| | case reference number = CAC MF6518 | | | case reference number = CAC MF6518 |
| | document type = Letter, Safety Evaluation | | | document type = Letter, Safety Evaluation |
| | page count = 6 | | | page count = 6 |
| | project = CAC:MF6518 | | | project = CAC:MF6518 |
| | stage = Other | | | stage = Approval |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Mano Nazar President and Chief Nuclear Officer Nuclear Division NextEra Energy P.O. Box 14000 Juno Beach, FL 33408-0420 January 19, 2016 | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 19, 2016 Mr. Mano Nazar President and Chief Nuclear Officer Nuclear Division NextEra Energy P.O. Box 14000 Juno Beach, FL 33408-0420 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| ST. LUCIE PLANT, UNIT NO. 1 -REVIEW OF THE LICENSE RENEWAL CONDENSATE STORAGE TANK CROSS-CONNECT BURIED PIPING INSPECTION COMMITMENT (CAC NO. MF6518) | | ST. LUCIE PLANT, UNIT NO. 1 - REVIEW OF THE LICENSE RENEWAL CONDENSATE STORAGE TANK CROSS-CONNECT BURIED PIPING INSPECTION COMMITMENT (CAC NO. MF6518) |
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| ==Dear Mr. Nazar:== | | ==Dear Mr. Nazar:== |
| By letter dated May 12, 2015, as supplemented by letter dated October 6, 2015, Florida Power & Light Company (FPL or the licensee) submitted information summarizing the results of the license renewal condensate storage tank cross-connect buried piping inspection at the St. Lucie Plant, Unit No. 1. This inspection was performed prior to the end of the initial operating license term. The U.S. Nuclear Regulatory Commission (NRC) staff provided a request for additional information dated September 1, 2015. By letter dated October 6, 2015, the licensee provided additional information. The NRC staff has completed its review of FPL's submittals and concludes that the licensee has provided the information required by the St. Lucie Plant, Unit No. 1, Commitment 1 of Table 1 of Appendix D of NUREG-1779, "Safety Evaluation Report Related to the License Renewal of St. Lucie Nuclear Plant, Units 1 and 2," dated September 2003. The NRC staff has determined that no additional follow-up is required at this time. The NRC staff's review of the report is set forth in the enclosed staff evaluation. | | |
| M. Nazar If you have any questions, please contact me at 301-415-1447 or Perry.Buckberg@nrc.gov. Docket No. 50-335 | | By letter dated May 12, 2015, as supplemented by letter dated October 6, 2015, Florida Power & Light Company (FPL or the licensee) submitted information summarizing the results of the license renewal condensate storage tank cross-connect buried piping inspection at the St. Lucie Plant, Unit No. 1. |
| | This inspection was performed prior to the end of the initial operating license term. The U.S. |
| | Nuclear Regulatory Commission (NRC) staff provided a request for additional information dated September 1, 2015. By letter dated October 6, 2015, the licensee provided additional information. |
| | The NRC staff has completed its review of FPL's submittals and concludes that the licensee has provided the information required by the St. Lucie Plant, Unit No. 1, Commitment 1 of Table 1 of Appendix D of NUREG-1779, "Safety Evaluation Report Related to the License Renewal of St. Lucie Nuclear Plant, Units 1 and 2," dated September 2003. |
| | The NRC staff has determined that no additional follow-up is required at this time. |
| | The NRC staff's review of the report is set forth in the enclosed staff evaluation. |
| | |
| | M. Nazar If you have any questions, please contact me at 301-415-1447 or Perry.Buckberg@nrc.gov. |
| | Sincerely, |
| | . Buckberg, Senior Project Manager icensing Branch 11-2 v* ion of Operator Reactor Licensing ice of Nuclear Reactor Regulation Docket No. 50-335 |
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| ==Enclosure:== | | ==Enclosure:== |
| Staff Evaluation cc w/encl: Distribution via Listerv Sincerely, . Buckberg, Senior Project Manager icensing Branch 11-2 v* ion of Operator Reactor Licensing ice of Nuclear Reactor Regulation UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 STAFF EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REVIEW OF THE LICENSE RENEWAL CONDENSATE STORAGE TANK CROSS-CONNECT BURIED PIPING INSPECTION COMMITMENT
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| ==1.0 INTRODUCTION==
| | Staff Evaluation cc w/encl: Distribution via Listerv |
| ST. LUCIE PLANT, UNIT NO. 1 DOCKET NO. 50-335 By letter dated May 12, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 15146A055), as supplemented by letter dated October 6, 2015 (ADAMS Accession No. ML 15301A252), Florida Power & Light Company (FPL or the licensee) submitted information summarizing the results of the license renewal condensate storage tank (CST) cross-connect buried piping inspection at the St. Lucie Plant (St. Lucie), Unit No. 1. This inspection was performed prior to the end of the initial operating license term. The U.S. Nuclear Regulatory Commission (NRC) staff provided a request for additional information dated September 1, 2015 (ADAMS Accession No. ML 15237A418). By letter dated October 6, 2015, the licensee provided additional information. 2.0 BACKGROUND On October 2, 2003 (ADAMS Accession No. ML032870081 ), NRC issued Renewed Facility Operating License No. DPR-67 for the St. Lucie Unit No. 1. The technical basis for issuing the renewed license was set forth in NUREG-1779, "Safety Evaluation Report Related to the License Renewal of St. Lucie Nuclear Plant, Units 1 and 2," dated September 2003 (ADAMS Accession No. ML032940205). The storage capacity of the CST is 250,000 gallons, a sufficient quantity to meet the requirements for decay heat removal and cooldown of the nuclear steam supply system. After a loss of normal feedwater, approximately 130,500 gallons of water are required to permit cooldown to 325 degrees Fahrenheit following a reactor trip. A crosstie is provided between the St. Lucie, Unit No. 1 auxiliary feedwater pumps and the St. Lucie, Unit No. 2 CST solely for the unlikely event that a vertical tornado missile disables the St. Lucie, Unit No. 1 CST. Enclosure | | |
| | UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 STAFF EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REVIEW OF THE LICENSE RENEWAL CONDENSATE STORAGE TANK CROSS-CONNECT BURIED PIPING INSPECTION COMMITMENT ST. LUCIE PLANT, UNIT NO. 1 DOCKET NO. 50-335 |
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| ==3.0 TECHNICAL EVALUATION== | | ==1.0 INTRODUCTION== |
| On March 29, 2015, the licensee performed excavation activities and uncovered a concrete structure at the CST cross-connect. The licensee exposed a section of concrete approximately 11 feet long, the width was 18 inches, and the depth of the concrete was determined to be 18 inches by partial (semi-circle) excavation at two locations approximately 6 feet apart on the East side. The West side was not disturbed by the licensee because the design drawings indicated a fire protection pipe was in close proximity on the West side. The drawings identified the lowest section of the pipe run to be at the 13 feet elevation; the nominal site grade elevation is at the 18 feet elevation. The licensee stated that 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. The licensee observed that the excavation site was dry, which was consistent with the design. The CST cross-connect pipe is approximately 1 O feet above the normal water table. The licensee concluded that the concrete encased CST cross-connect pipe is not likely to be submerged for extended periods of time. St. Lucie has implemented a buried piping inspection program in accordance with Nuclear Energy Institute (NEI) 09-14, "Guideline for the Management of Underground Piping and Tank Integrity," Revision 3 (ADAMS Accession No. ML 13130A302). Since the St. Lucie, Unit No. 1 design documents did not specifically require concrete encasement of the CST cross-connect pipe, the licensee performed exploratory digs. In each of the licensee's inspections, the CST cross-connect piping was found to be encased in concrete, and the concrete was solid with no delamination. St. Lucie conducted soil sampling as part of the buried piping inspection program. In general, the soil pH was approximately 9.0, indicating the soil was alkaline based on the licensee's testing. According to the licensee, a soil pH greater than 8.5 indicates dissolved salts, low resistivity, and corrosive to cast iron. The CST cross-connect piping at St. Lucie is stainless steel and loss of material or cracking are not expected to occur with the tested soil condition, due to any migration of water through the concrete to the surface of the piping according to the licensee. In its letter dated May 12, 2015, the licensee states, in part, that "the applicable aging effecVmechanism for stainless steel piping in soil or concrete is 'loss of material due to pitting and crevice corrosion."' The NRC staff concludes that the CST cross-connect piping was exempt from piping surface inspection as part of the buried piping inspection program, since it was determined to be encased in concrete.
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| In its letter dated May 12, 2015, the licensee proposed the following revised commitment: The Subject pipe for Condensate Storage Tank Cross-Connect Buried Piping Inspection was found encased in a concrete duct and is inaccessible. Corrosion/degradation of embedded metals is not an applicable aging effect. No further inspections are required during the extended period of operation. The Condensate Storage Tank Cross-Connect Buried Piping Inspection (Unit 1 only) is a One Time Inspection Program only. The NRG staff finds that the revised commitment is acceptable.
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| ==4.0 CONCLUSION== | | By letter dated May 12, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15146A055), as supplemented by letter dated October 6, 2015 (ADAMS Accession No. ML15301A252), Florida Power & Light Company (FPL or the licensee) submitted information summarizing the results of the license renewal condensate storage tank (CST) cross-connect buried piping inspection at the St. Lucie Plant (St. Lucie), Unit No. 1. This inspection was performed prior to the end of the initial operating license term. The U.S. Nuclear Regulatory Commission (NRC) staff provided a request for additional information dated September 1, 2015 (ADAMS Accession No. ML15237A418). By letter dated October 6, 2015, the licensee provided additional information. |
| The NRG staff has completed its review of FPL's submittals and concludes that the licensee has provided the information required by the St. Lucie, Unit No. 1, Commitment 1 of Table 1 of Appendix D of NUREG-1779. The NRG staff has determined that no additional followup is required at this time. Principal Contributor: Brian Allik Date: January 19, 201 6 M. Nazar If you have any questions, please contact me at 301-415-1447 or Perrv.Buckberg@nrc.gov. Docket No. 50-335 | | |
| | ==2.0 BACKGROUND== |
| | |
| | On October 2, 2003 (ADAMS Accession No. ML032870081 ), NRC issued Renewed Facility Operating License No. DPR-67 for the St. Lucie Unit No. 1. The technical basis for issuing the renewed license was set forth in NUREG-1779, "Safety Evaluation Report Related to the License Renewal of St. Lucie Nuclear Plant, Units 1 and 2," dated September 2003 (ADAMS Accession No. ML032940205). |
| | The storage capacity of the CST is 250,000 gallons, a sufficient quantity to meet the requirements for decay heat removal and cooldown of the nuclear steam supply system. After a loss of normal feedwater, approximately 130,500 gallons of water are required to permit cooldown to 325 degrees Fahrenheit following a reactor trip. A crosstie is provided between the St. Lucie, Unit No. 1 auxiliary feedwater pumps and the St. Lucie, Unit No. 2 CST solely for the unlikely event that a vertical tornado missile disables the St. Lucie, Unit No. 1 CST. |
| | Enclosure |
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| | ==3.0 TECHNICAL EVALUATION== |
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| | On March 29, 2015, the licensee performed excavation activities and uncovered a concrete structure at the CST cross-connect. The licensee exposed a section of concrete approximately 11 feet long, the width was 18 inches, and the depth of the concrete was determined to be 18 inches by partial (semi-circle) excavation at two locations approximately 6 feet apart on the East side. The West side was not disturbed by the licensee because the design drawings indicated a fire protection pipe was in close proximity on the West side. The drawings identified the lowest section of the pipe run to be at the 13 feet elevation; the nominal site grade elevation is at the 18 feet elevation. |
| | The licensee stated that 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. |
| | The licensee observed that the excavation site was dry, which was consistent with the design. |
| | The CST cross-connect pipe is approximately 1O feet above the normal water table. The licensee concluded that the concrete encased CST cross-connect pipe is not likely to be submerged for extended periods of time. |
| | St. Lucie has implemented a buried piping inspection program in accordance with Nuclear Energy Institute (NEI) 09-14, "Guideline for the Management of Underground Piping and Tank Integrity," Revision 3 (ADAMS Accession No. ML13130A302). Since the St. Lucie, Unit No. 1 design documents did not specifically require concrete encasement of the CST cross-connect pipe, the licensee performed exploratory digs. In each of the licensee's inspections, the CST cross-connect piping was found to be encased in concrete, and the concrete was solid with no delamination. |
| | St. Lucie conducted soil sampling as part of the buried piping inspection program. In general, the soil pH was approximately 9.0, indicating the soil was alkaline based on the licensee's testing. According to the licensee, a soil pH greater than 8.5 indicates dissolved salts, low resistivity, and corrosive to cast iron. The CST cross-connect piping at St. Lucie is stainless steel and loss of material or cracking are not expected to occur with the tested soil condition, due to any migration of water through the concrete to the surface of the piping according to the licensee. |
| | In its letter dated May 12, 2015, the licensee states, in part, that "the applicable aging effecVmechanism for stainless steel piping in soil or concrete is 'loss of material due to pitting and crevice corrosion."' |
| | The NRC staff concludes that the CST cross-connect piping was exempt from piping surface inspection as part of the buried piping inspection program, since it was determined to be encased in concrete. |
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| | In its letter dated May 12, 2015, the licensee proposed the following revised commitment: |
| | The Subject pipe for Condensate Storage Tank Cross-Connect Buried Piping Inspection was found encased in a concrete duct and is inaccessible. |
| | Corrosion/degradation of embedded metals is not an applicable aging effect. No further inspections are required during the extended period of operation. The Condensate Storage Tank Cross-Connect Buried Piping Inspection (Unit 1 only) is a One Time Inspection Program only. |
| | The NRG staff finds that the revised commitment is acceptable. |
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| | ==4.0 CONCLUSION== |
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| | The NRG staff has completed its review of FPL's submittals and concludes that the licensee has provided the information required by the St. Lucie, Unit No. 1, Commitment 1 of Table 1 of Appendix D of NUREG-1779. The NRG staff has determined that no additional followup is required at this time. |
| | Principal Contributor: Brian Allik Date: January 19, 201 6 |
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| | M. Nazar If you have any questions, please contact me at 301-415-1447 or Perrv.Buckberg@nrc.gov. |
| | Sincerely, IRA JLamb for/ |
| | Perry H. Buckberg, Senior Project Manager Plant Licensing Branch 11-2 Division of Operator Reactor Licensing Docket No. 50-335 |
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| ==Enclosure:== | | ==Enclosure:== |
| Staff Evaluation cc w/encl: Distribution via Listerv DISTRIBUTION: PUBLIC LPL2-2 R/F RidsACRS_MailCTR Resource RidsNrrDorlDpr Resource RidsNrrDlrRarb Resource Sincerely, IRA JLamb for/ Perry H. Buckberg, Senior Project Manager Plant Licensing Branch 11-2 Division of Operator Reactor Licensing RidsNrrDorllpl2-2 Resource RidsNrrPMStlucie Resource BAllik, NRR RidsNrrLABClayton Resource RidsRgn2MailCenter Resource ADAMS A ccess1on N o.: ML 15356A650 *b *1 1yema1 OFFICE NRR/DORL/LPL2-2/PM NRR/DORL/LPL2-2/LA NRR/DLR/RARB/BC* NAME Jlamb BClayton DMorey DATE 12/28/2015 1/08/2016 1/06/2016 OFFICE NRR/DORL/LPL2-2/BC NRR/DORL/LPL2-2/PM NAME BBeasley (JLamb for) PBuckberg DATE 1/08/2016 1/19/2016 OFFICIAL RECORD COPY | | |
| }} | | Staff Evaluation cc w/encl: Distribution via Listerv DISTRIBUTION: |
| | PUBLIC RidsNrrDorllpl2-2 Resource RidsRgn2MailCenter Resource LPL2-2 R/F RidsNrrPMStlucie Resource RidsACRS_MailCTR Resource BAllik, NRR RidsNrrDorlDpr Resource RidsNrrLABClayton Resource RidsNrrDlrRarb Resource ADAMS Access1on No.: ML15356A650 *b1yema1*1 OFFICE NRR/DORL/LPL2-2/PM NRR/DORL/LPL2-2/LA NRR/DLR/RARB/BC* |
| | NAME Jlamb BClayton DMorey DATE 12/28/2015 1/08/2016 1/06/2016 OFFICE NRR/DORL/LPL2-2/BC NRR/DORL/LPL2-2/PM NAME BBeasley (JLamb for) PBuckberg DATE 1/08/2016 1/19/2016 OFFICIAL RECORD COPY}} |
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Category:Letter
MONTHYEARIR 05000335/20230102024-01-26026 January 2024 NRC Quadrennial Focused Engineering Inspection (FEI) Commercial Grade Dedication Report 05000335/2023010 and 05000389/2023010 L-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) IR 05000335/20230042024-01-24024 January 2024 Integrated Inspection Report 05000335/2023004 and 05000389/2023004 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, ML23332A1772023-11-28028 November 2023 Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-162, Response to 50.69 2nd Round of Rals2023-11-21021 November 2023 Response to 50.69 2nd Round of Rals IR 05000335/20230032023-11-0606 November 2023 Integrated Inspection Report 05000335/2023003 and 05000389/2023003 ML23270B8882023-10-23023 October 2023 Regulatory Audit Summary Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structure, Systems, and Components for Nuclear Power Reactors EPID L-2022-LLA-0182 ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published ML23275A1102023-10-0202 October 2023 License Amendment Request Revision 2 for the Technical Specifications Conversion to NUREG-1432, Revision 5 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 IR 05000335/20233012023-09-20020 September 2023 NRC Operator License Examination Report 05000335/2023301 and 05000389/2023301 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-2023-108, Report of 10 CFR 50.59 Plant Changes2023-09-11011 September 2023 Report of 10 CFR 50.59 Plant Changes 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-2023-112, 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 ML23219A0042023-09-0101 September 2023 Transmittal Letter - Safety Evaluation Related to the SLRA of St. Lucie Plant, Units 1and 2, Revision 1 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 IR 05000335/20230022023-08-0707 August 2023 Integrated Inspection Report 05000335/2023002 and 05000389/2023002 L-2023-105, Preparation and Scheduling of Operator Licensing Examinations2023-08-0303 August 2023 Preparation and Scheduling of Operator Licensing Examinations ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment ML23212B2652023-07-27027 July 2023 Operator Licensing Written Examination Approval 05000335/2023301 and 05000389/2023301 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 ML23200A1232023-07-21021 July 2023 Transmittal Letter for the St. Lucie SLRA Review 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) ML23184A0352023-06-30030 June 2023 Notification of St. Lucie Units 1 & 2 Focused Engineering Inspection (FEI) 05000335/2023010 and 05000389/2023010 and Initial Information Request 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) IR 05000335/20234032023-06-29029 June 2023 Security Inspection Report 05000335/2023403 and 05000389/2023403 IR 05000335/20234022023-06-20020 June 2023 Security Baseline Inspection Report 05000335/2023402 and 05000389/2023402 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 IR 05000335/20234012023-05-16016 May 2023 Cyber Security Inspection Report 05000335/2023401 and 05000389/2023401 (Cover Letter) IR 05000335/20230012023-05-0909 May 2023 Integrated Inspection Report 05000335/2023001 and 05000389/2023001 ML23109A1132023-04-30030 April 2023 SLRA Change Schedule Letter 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 ML23097A1642023-04-17017 April 2023 Summary of March 23, 2023, Meeting with Florida Power and Light on St. Lucie and Turkey Point Improved Technical Specifications Conversion License Amendment Requests L-2023-055, 2022 Annual Environmental Operating Report2023-04-12012 April 2023 2022 Annual Environmental Operating Report 2024-01-08
[Table view] Category:Safety Evaluation
MONTHYEARML23219A0032023-09-0101 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 ML16210A3742016-08-30030 August 2016 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-422, Revision 2 ML16103A3972016-07-28028 July 2016 Issuance of Amendments Regarding Removal of Technical Specification for Cleaning Fuel Oil Storage Tank Sediment and Relocating Procedures to Licensee Controlled Documents ML16167A4732016-07-0505 July 2016 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML16139A5882016-05-27027 May 2016 Inservice Inspection Plan Fourth 10-Year Interval Relief Request No. 10, Revision 0 ML16124A3832016-05-25025 May 2016 St. Lucie Plant, Unit No. 1 - Issuance of Amendment Regarding Changes to the Snubber Surveillance Requirements (CAC No. MF6490) ML16063A1212016-04-19019 April 2016 Redacted - Issuance of Amendment Regarding License Amendment Request for the Transitioning to Areva Fuel ML15344A3462016-03-31031 March 2016 Issuance of Amendments Regarding Transition to a Risk-Informed, Performance-Based Fire Protection Program in Accordance with Title 10 of the Code of Federal Regulations Section 50.48(c) (CAC Nos. MF1373 & MF1374) 2023-09-01
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 19, 2016 Mr. Mano Nazar President and Chief Nuclear Officer Nuclear Division NextEra Energy P.O. Box 14000 Juno Beach, FL 33408-0420
SUBJECT:
ST. LUCIE PLANT, UNIT NO. 1 - REVIEW OF THE LICENSE RENEWAL CONDENSATE STORAGE TANK CROSS-CONNECT BURIED PIPING INSPECTION COMMITMENT (CAC NO. MF6518)
Dear Mr. Nazar:
By letter dated May 12, 2015, as supplemented by letter dated October 6, 2015, Florida Power & Light Company (FPL or the licensee) submitted information summarizing the results of the license renewal condensate storage tank cross-connect buried piping inspection at the St. Lucie Plant, Unit No. 1.
This inspection was performed prior to the end of the initial operating license term. The U.S.
Nuclear Regulatory Commission (NRC) staff provided a request for additional information dated September 1, 2015. By letter dated October 6, 2015, the licensee provided additional information.
The NRC staff has completed its review of FPL's submittals and concludes that the licensee has provided the information required by the St. Lucie Plant, Unit No. 1, Commitment 1 of Table 1 of Appendix D of NUREG-1779, "Safety Evaluation Report Related to the License Renewal of St. Lucie Nuclear Plant, Units 1 and 2," dated September 2003.
The NRC staff has determined that no additional follow-up is required at this time.
The NRC staff's review of the report is set forth in the enclosed staff evaluation.
M. Nazar If you have any questions, please contact me at 301-415-1447 or Perry.Buckberg@nrc.gov.
Sincerely,
. Buckberg, Senior Project Manager icensing Branch 11-2 v* ion of Operator Reactor Licensing ice of Nuclear Reactor Regulation Docket No. 50-335
Enclosure:
Staff Evaluation cc w/encl: Distribution via Listerv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 STAFF EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REVIEW OF THE LICENSE RENEWAL CONDENSATE STORAGE TANK CROSS-CONNECT BURIED PIPING INSPECTION COMMITMENT ST. LUCIE PLANT, UNIT NO. 1 DOCKET NO. 50-335
1.0 INTRODUCTION
By letter dated May 12, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15146A055), as supplemented by letter dated October 6, 2015 (ADAMS Accession No. ML15301A252), Florida Power & Light Company (FPL or the licensee) submitted information summarizing the results of the license renewal condensate storage tank (CST) cross-connect buried piping inspection at the St. Lucie Plant (St. Lucie), Unit No. 1. This inspection was performed prior to the end of the initial operating license term. The U.S. Nuclear Regulatory Commission (NRC) staff provided a request for additional information dated September 1, 2015 (ADAMS Accession No. ML15237A418). By letter dated October 6, 2015, the licensee provided additional information.
2.0 BACKGROUND
On October 2, 2003 (ADAMS Accession No. ML032870081 ), NRC issued Renewed Facility Operating License No. DPR-67 for the St. Lucie Unit No. 1. The technical basis for issuing the renewed license was set forth in NUREG-1779, "Safety Evaluation Report Related to the License Renewal of St. Lucie Nuclear Plant, Units 1 and 2," dated September 2003 (ADAMS Accession No. ML032940205).
The storage capacity of the CST is 250,000 gallons, a sufficient quantity to meet the requirements for decay heat removal and cooldown of the nuclear steam supply system. After a loss of normal feedwater, approximately 130,500 gallons of water are required to permit cooldown to 325 degrees Fahrenheit following a reactor trip. A crosstie is provided between the St. Lucie, Unit No. 1 auxiliary feedwater pumps and the St. Lucie, Unit No. 2 CST solely for the unlikely event that a vertical tornado missile disables the St. Lucie, Unit No. 1 CST.
Enclosure
3.0 TECHNICAL EVALUATION
On March 29, 2015, the licensee performed excavation activities and uncovered a concrete structure at the CST cross-connect. The licensee exposed a section of concrete approximately 11 feet long, the width was 18 inches, and the depth of the concrete was determined to be 18 inches by partial (semi-circle) excavation at two locations approximately 6 feet apart on the East side. The West side was not disturbed by the licensee because the design drawings indicated a fire protection pipe was in close proximity on the West side. The drawings identified the lowest section of the pipe run to be at the 13 feet elevation; the nominal site grade elevation is at the 18 feet elevation.
The licensee stated that 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.
The licensee observed that the excavation site was dry, which was consistent with the design.
The CST cross-connect pipe is approximately 1O feet above the normal water table. The licensee concluded that the concrete encased CST cross-connect pipe is not likely to be submerged for extended periods of time.
St. Lucie has implemented a buried piping inspection program in accordance with Nuclear Energy Institute (NEI) 09-14, "Guideline for the Management of Underground Piping and Tank Integrity," Revision 3 (ADAMS Accession No. ML13130A302). Since the St. Lucie, Unit No. 1 design documents did not specifically require concrete encasement of the CST cross-connect pipe, the licensee performed exploratory digs. In each of the licensee's inspections, the CST cross-connect piping was found to be encased in concrete, and the concrete was solid with no delamination.
St. Lucie conducted soil sampling as part of the buried piping inspection program. In general, the soil pH was approximately 9.0, indicating the soil was alkaline based on the licensee's testing. According to the licensee, a soil pH greater than 8.5 indicates dissolved salts, low resistivity, and corrosive to cast iron. The CST cross-connect piping at St. Lucie is stainless steel and loss of material or cracking are not expected to occur with the tested soil condition, due to any migration of water through the concrete to the surface of the piping according to the licensee.
In its letter dated May 12, 2015, the licensee states, in part, that "the applicable aging effecVmechanism for stainless steel piping in soil or concrete is 'loss of material due to pitting and crevice corrosion."'
The NRC staff concludes that the CST cross-connect piping was exempt from piping surface inspection as part of the buried piping inspection program, since it was determined to be encased in concrete.
In its letter dated May 12, 2015, the licensee proposed the following revised commitment:
The Subject pipe for Condensate Storage Tank Cross-Connect Buried Piping Inspection was found encased in a concrete duct and is inaccessible.
Corrosion/degradation of embedded metals is not an applicable aging effect. No further inspections are required during the extended period of operation. The Condensate Storage Tank Cross-Connect Buried Piping Inspection (Unit 1 only) is a One Time Inspection Program only.
The NRG staff finds that the revised commitment is acceptable.
4.0 CONCLUSION
The NRG staff has completed its review of FPL's submittals and concludes that the licensee has provided the information required by the St. Lucie, Unit No. 1, Commitment 1 of Table 1 of Appendix D of NUREG-1779. The NRG staff has determined that no additional followup is required at this time.
Principal Contributor: Brian Allik Date: January 19, 201 6
M. Nazar If you have any questions, please contact me at 301-415-1447 or Perrv.Buckberg@nrc.gov.
Sincerely, IRA JLamb for/
Perry H. Buckberg, Senior Project Manager Plant Licensing Branch 11-2 Division of Operator Reactor Licensing Docket No. 50-335
Enclosure:
Staff Evaluation cc w/encl: Distribution via Listerv DISTRIBUTION:
PUBLIC RidsNrrDorllpl2-2 Resource RidsRgn2MailCenter Resource LPL2-2 R/F RidsNrrPMStlucie Resource RidsACRS_MailCTR Resource BAllik, NRR RidsNrrDorlDpr Resource RidsNrrLABClayton Resource RidsNrrDlrRarb Resource ADAMS Access1on No.: ML15356A650 *b1yema1*1 OFFICE NRR/DORL/LPL2-2/PM NRR/DORL/LPL2-2/LA NRR/DLR/RARB/BC*
NAME Jlamb BClayton DMorey DATE 12/28/2015 1/08/2016 1/06/2016 OFFICE NRR/DORL/LPL2-2/BC NRR/DORL/LPL2-2/PM NAME BBeasley (JLamb for) PBuckberg DATE 1/08/2016 1/19/2016 OFFICIAL RECORD COPY