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| | issue date = 04/04/2013 | | | issue date = 04/04/2013 |
| | title = 9/13/2012 - Summary of Conference Call with Florida Power & Light Co. Re. the Findings of the Fall 2012 Steam Generator Tube Inspections at Saint Lucie Plant, Unit No. 2 | | | title = 9/13/2012 - Summary of Conference Call with Florida Power & Light Co. Re. the Findings of the Fall 2012 Steam Generator Tube Inspections at Saint Lucie Plant, Unit No. 2 |
| | author name = Orf T J | | | author name = Orf T |
| | author affiliation = NRC/NRR/DORL/LPLII-2 | | | author affiliation = NRC/NRR/DORL/LPLII-2 |
| | addressee name = | | | addressee name = |
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| | docket = 05000389 | | | docket = 05000389 |
| | license number = NPF-016 | | | license number = NPF-016 |
| | contact person = Rodriguez R L NRC/DORL/LPL2-2 415-1558 | | | contact person = Rodriguez R NRC/DORL/LPL2-2 415-1558 |
| | case reference number = TAC ME9534 | | | case reference number = TAC ME9534 |
| | document type = Meeting Summary, Letter | | | document type = Meeting Summary, Letter |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 April 4, 2013 LICENSEE: | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 4, 2013 LICENSEE: Florida Power & Light Co. |
| Florida Power & Light Co. FACILITY: | | FACILITY: Saint Lucie Power Plant, Unit No.2 |
| Saint Lucie Power Plant, Unit No.2 | |
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| ==SUBJECT:== | | ==SUBJECT:== |
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| ==SUMMARY== | | ==SUMMARY== |
| OF SEPTEMBER 13, 2012, CONFERENCE CALL WITH FLORIDA POWER & LIGHT COMPANY REGARDING THE FINDINGS OF THE FALL 2012 STEAM GENERATOR TUBE INSPECTIONS AT SAINT LUCIE PLANT, UNIT NO.2 (TAC NO. ME9534) On September 13, 2012, a Category 1 conference call was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of Florida Power & Light Company at NRC Headquarters, One White Flint North, 11555 Rockville Pike, Rockville, Maryland. | | OF SEPTEMBER 13, 2012, CONFERENCE CALL WITH FLORIDA POWER & LIGHT COMPANY REGARDING THE FINDINGS OF THE FALL 2012 STEAM GENERATOR TUBE INSPECTIONS AT SAINT LUCIE PLANT, UNIT NO.2 (TAC NO. ME9534) |
| The purpose of the call was to discuss the findings of the steam generator tube inspection activities performed at Saint Lucie Plant, Unit No.2 during fall 2012. A list of attendees is provided as Enclosure 1 and a summary of the discussion is provided in Enclosure | | On September 13, 2012, a Category 1 conference call was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of Florida Power & Light Company at NRC Headquarters, One White Flint North, 11555 Rockville Pike, Rockville, Maryland. The purpose of the call was to discuss the findings of the steam generator tube inspection activities performed at Saint Lucie Plant, Unit No.2 during fall 2012. A list of attendees is provided as and a summary of the discussion is provided in Enclosure 2. |
| : 2. Members of the public were not in attendance.
| | Members of the public were not in attendance. Public meeting feedback forms were not received during the conference call. |
| Public meeting feedback forms were not received during the conference call. Please direct any inquiries to me at 301-415-2788, or e-mail me at Tracy.Orf@nrc.gov. | | Please direct any inquiries to me at 301-415-2788, or e-mail me at Tracy.Orf@nrc.gov. |
| Tracy J. Orf, Proj ct Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-389 | | Tracy J. Orf, Proj ct Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-389 |
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| ==Enclosures:== | | ==Enclosures:== |
| | |
| 1 . List of attendees | | 1 . List of attendees |
| : 2. Summary of Conference Call cc w/encls: Distribution via Listserv LIST OF SEPTEMBER | | : 2. Summary of Conference Call cc w/encls: Distribution via Listserv |
| : 13. 2012. CONFERENCE CALL WITH FLORIDA POWER AND LIGHT FALL 2012 STEAM GENERATOR TUBE INSPECTIONS AT ST. LUCIE. UNIT Name Organization Kenneth Karwoski NRC Tracy J. Ort NRC Louis Lake NRC Jack Hoffman FPL Russ Cipolla Intertec Ed Korkowski FPL Allen Brown AREVA Enclosure 1
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| ==SUMMARY==
| | LIST OF ATTENDEES SEPTEMBER 13. 2012. CONFERENCE CALL WITH FLORIDA POWER AND LIGHT CO. |
| OF CONFERENCE CALL WITH ST. LUCIE PLANT UNIT NO.2 REGARDING THE FALL 2012 STEAM GENERATOR TUBE INSPECTION RESULTS DOCKET NO. 50-389 On September 13, 2012, the U.S. Nuclear Regulatory Commission (NRC) staff participated in a conference call with representatives of Florida Power & Light Company (the licensee), regarding their ongoing steam generator tube inspection activities at Saint Lucie Plant (St. Lucie), Unit NO.2. Information provided by the licensee in support of the conference call is located in the Agencywide Documents Access Management System under Accession No. ML 12258A080. | | FALL 2012 STEAM GENERATOR TUBE INSPECTIONS AT ST. LUCIE. UNIT NO.2 Name Organization Kenneth Karwoski NRC Tracy J. Ort NRC Louis Lake NRC Jack Hoffman FPL Russ Cipolla Intertec Ed Korkowski FPL Allen Brown AREVA Enclosure 1 |
| St. Lucie Unit 2 has two Areva-NP Model 86/19TI replacement steam generators (SGs) that were installed in January 2008. Each SG has 8,999 thermally-treated Alloy 690 tubes with a nominal outside diameter of 0.75 inches and a nominal wall thickness of 0.043 inches. During manufacturing, all tubes were hydraulically expanded at both ends over the full depth of the tubesheet.
| |
| The tubesheet was drilled on a triangular pitch with 1-inch spacing, center-to-center.
| |
| The radius of the row 1 U-bends is 4.134 inches. The U-bends in rows 1 through 15 were stress relieved after bending. Seven tube support plates (TSPs), each 1.181 inches thick and made from Type 410 stainless steel, support the vertical section of the tubes. The TSPs have broached trefoil holes. Four sets of anti-vibration bars (AVBs), each 0.112 inches thick and made from Type 405 stainless steel, support the U-bend section of the tubes. Additional clarifying information regarding the licensee-provided document and information not included in the licensee-provided document is summarized below. The licensee indicated that at the time of the call, the bobbin coil inspections were greater than 99 percent complete in both SG A and SG B. There was no correlation found between AVB and TSP wear indications. The total number of indications in the "History of wear indications/affected number of tubes (Cumulative)" table on page 1 of the licensee's informational document is different from the "Wear distribution" histogram on page 2 because they were generated at different times during the outage. However, the general distribution and trend shown in the histogram remains the same when all the data from the table on page 1 is included.
| |
| Regarding the two new indications with depths between 30 and 34 percent reported in the histogram on page 2, one of the two indications is a 34-percent through wall (TW) indication that is located in a tube that had prior wear indications.
| |
| The second indication is a 32-percent TW indication in a tube on the periphery of SG A, in a location where tube wear has already been seen. The licensee indicated that they evaluate whether the growth rate is a function of the beginning-of-cycle (BOC) depth. They indicated in the prior inspections, the growth rates for flaws less than or equal to 13-percent TW were dependent on the BOC depth, but no such correlation existed for flaws greater than 13-percent TW. Enclosure 2
| |
| -2 The licensee indicated that they had implemented modifications to access covers in a prior outage to deal with nuts that loosened during operation, that the modification was working as designed, and that no new loose nuts were noted during this inspection.
| |
| There was no degradation or anomalous conditions identified during the inspection. Profiling of the wear indications had commenced and was being performed to determine if there was any change in the specific type of wear that was occurring in the SG tubes. The licensee indicated that the indications tend to be flat, centered, and no longer than the AVBs causing the wear. The licensee stated that there was no observed primary-to-secondary leakage during the recently completed operating cycle. Also, there were no exceptions taken to the industry guidelines (including the chemistry, inspection, and integrity assessment guidelines). The licensee indicated that the prior operational assessment had predicted that 30-34 tubes would require plugging in SG A during the current inspection, and the actual amount of required plugging was just 7 tubes in SG A. Overall, the licensee indicated that the general trend of the inspection findings was in line with the predicted findings of the prior operational assessment. Seven indications that measured 40-percent TW were detected in 2012. Only one similar indication (40-percent TW) was detected in the last outage. The licensee indicated it was reviewing the increase in the number of new indications in SG B since the number of new indications per cycle increased in the latest inspection. The licensee is scheduled to implement a power uprate during this cycle. At the end of the call, the NRC staff inquired about potentially being briefed on the results of the inspections and the final Condition Monitoring Operational Assessment since they are complicated.
| |
| The representatives from St. Lucie indicated they would work with the NRC project manager in setting up such a meeting. Additional abbreviations used in the licensee-provided document include: Avg. -Average CMOA -Condition Monitoring and Operational Assessment EFPY -Effective Full Power Years FOSAR -Foreign Object Search and Retrieval OA -Operational Assessment POB -Probability of Burst SONGS -San Onofre Nuclear Generating Station April 4, 2013 Florida Power & Light Co.
| |
| Saint Lucie Power Plant, Unit 2
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| ==SUMMARY== | | ==SUMMARY== |
| OF SEPTEMBER 13,2012, CONFERENCE CALL WITH FLORIDA POWER & LIGHT COMPANY REGARDING THE FINDINGS OF THE FALL 2012 STEAM GENERATOR TUBE INSPECTIONS AT SAINT LUCIE PLANT, UNIT NO.2 (TAC NO. ME9534) On September 13, 2012, a Category 1 conference call was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of Florida Power & Light Company at NRC Headquarters, One White Flint North, 11555 Rockville Pike, Rockville, Maryland. | | OF CONFERENCE CALL WITH ST. LUCIE PLANT UNIT NO.2 REGARDING THE FALL 2012 STEAM GENERATOR TUBE INSPECTION RESULTS DOCKET NO. 50-389 On September 13, 2012, the U.S. Nuclear Regulatory Commission (NRC) staff participated in a conference call with representatives of Florida Power & Light Company (the licensee), regarding their ongoing steam generator tube inspection activities at Saint Lucie Plant (St. Lucie), Unit NO.2. Information provided by the licensee in support of the conference call is located in the Agencywide Documents Access Management System under Accession No. ML12258A080. |
| The purpose of the call was to discuss the findings of the steam generator tube inspection activities performed at Saint Lucie Plant, Unit No.2 during fall 2012. A list of attendees is provided as Enclosure 1 and a summary of the discussion is provided in Enclosure
| | St. Lucie Unit 2 has two Areva-NP Model 86/19TI replacement steam generators (SGs) that were installed in January 2008. Each SG has 8,999 thermally-treated Alloy 690 tubes with a nominal outside diameter of 0.75 inches and a nominal wall thickness of 0.043 inches. During manufacturing, all tubes were hydraulically expanded at both ends over the full depth of the tubesheet. The tubesheet was drilled on a triangular pitch with 1-inch spacing, center-to-center. |
| : 2. Members of the public were not in attendance.
| | The radius of the row 1 U-bends is 4.134 inches. The U-bends in rows 1 through 15 were stress relieved after bending. Seven tube support plates (TSPs), each 1.181 inches thick and made from Type 410 stainless steel, support the vertical section of the tubes. The TSPs have broached trefoil holes. Four sets of anti-vibration bars (AVBs), each 0.112 inches thick and made from Type 405 stainless steel, support the U-bend section of the tubes. |
| Public Meeting Feedback forms were not received during the conference call. Please direct any inquiries to me at 301-415-2788, or e-mail me at Tracy.Orf@nrc.gov.
| | Additional clarifying information regarding the licensee-provided document and information not included in the licensee-provided document is summarized below. |
| IRA! Tracy J. Orf, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-389
| | * The licensee indicated that at the time of the call, the bobbin coil inspections were greater than 99 percent complete in both SG A and SG B. |
| | | * There was no correlation found between AVB and TSP wear indications. |
| ==Enclosures:==
| | * The total number of indications in the "History of wear indications/affected number of tubes (Cumulative)" table on page 1 of the licensee's informational document is different from the "Wear distribution" histogram on page 2 because they were generated at different times during the outage. However, the general distribution and trend shown in the histogram remains the same when all the data from the table on page 1 is included. |
| 1 . List of attendees | | Regarding the two new indications with depths between 30 and 34 percent reported in the histogram on page 2, one of the two indications is a 34-percent through wall (TW) indication that is located in a tube that had prior wear indications. The second indication is a 32-percent TW indication in a tube on the periphery of SG A, in a location where tube wear has already been seen. |
| : 2. Summary of Conference Call cc w/encls: Distribution via Listserv DISTRIBUTION:
| | * The licensee indicated that they evaluate whether the growth rate is a function of the beginning-of-cycle (BOC) depth. They indicated in the prior inspections, the growth rates for flaws less than or equal to 13-percent TW were dependent on the BOC depth, but no such correlation existed for flaws greater than 13-percent TW. |
| PUBLIC LPL2-2 R/F RidsAcrsAcnw_MailCTR RidsNrrDorlLpl2-2
| | Enclosure 2 |
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|
| RidsNrrPMStLucie RidsNrrLABClayton RidsRgn2MailCenter
| | -2 |
| | * The licensee indicated that they had implemented modifications to access covers in a prior outage to deal with nuts that loosened during operation, that the modification was working as designed, and that no new loose nuts were noted during this inspection. |
| | There was no degradation or anomalous conditions identified during the inspection. |
| | * Profiling of the wear indications had commenced and was being performed to determine if there was any change in the specific type of wear that was occurring in the SG tubes. |
| | The licensee indicated that the indications tend to be flat, centered, and no longer than the AVBs causing the wear. |
| | * The licensee stated that there was no observed primary-to-secondary leakage during the recently completed operating cycle. Also, there were no exceptions taken to the industry guidelines (including the chemistry, inspection, and integrity assessment guidelines). |
| | * The licensee indicated that the prior operational assessment had predicted that 30-34 tubes would require plugging in SG A during the current inspection, and the actual amount of required plugging was just 7 tubes in SG A. Overall, the licensee indicated that the general trend of the inspection findings was in line with the predicted findings of the prior operational assessment. |
| | * Seven indications that measured 40-percent TW were detected in 2012. Only one similar indication (40-percent TW) was detected in the last outage. |
| | * The licensee indicated it was reviewing the increase in the number of new indications in SG B since the number of new indications per cycle increased in the latest inspection. |
| | * The licensee is scheduled to implement a power uprate during this cycle. |
| | At the end of the call, the NRC staff inquired about potentially being briefed on the results of the inspections and the final Condition Monitoring Operational Assessment since they are complicated. The representatives from St. Lucie indicated they would work with the NRC project manager in setting up such a meeting. |
| | Additional abbreviations used in the licensee-provided document include: |
| | * Avg. - Average |
| | * CMOA - Condition Monitoring and Operational Assessment |
| | * EFPY - Effective Full Power Years |
| | * FOSAR - Foreign Object Search and Retrieval |
| | * OA - Operational Assessment |
| | * POB - Probability of Burst |
| | * SONGS - San Onofre Nuclear Generating Station |
|
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|
| RidsNrrDeEsgb A. Johnson, NRR J. Cassidy, EDO K. Karwoski, NRR R. Rodriguez, NRR T. Wertz, NRR ADAMS Accession No. ML 13084A030 OFFICE LPL2-2/PM LPL2-2/LA ESGB/BC'" LPL2-2/BC LPL2-2/PM NAME TOrt BClayton GKulesa JQuichocho TOrt DATE 04/03/13 04/03/13 08/05/12 04/04/13 04/04/13 *by OFFICIAL RECORD COPY}}
| | ML13084A030 OFFICE LPL2-2/PM LPL2-2/LA ESGB/BC'" LPL2-2/BC LPL2-2/PM NAME TOrt BClayton GKulesa JQuichocho TOrt DATE 04/03/13 04/03/13 08/05/12 04/04/13 04/04/13 |
| | *by memo}} |
Letter Sequence Other |
|---|
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|
MONTHYEARML12258A0802012-09-14014 September 2012
NRC Conference Call St. Lucie Unit 2 Steam Generator Inspection September 13, 2012
Project stage: Request
ML13059A5522013-03-0101 March 2013
3/14/13 - Forthcoming Meeting with Florida Power and Light Company Regarding Steam Generator Performance at St. Lucie Nuclear Plant, Units 1 and 2
Project stage: Request
ML13094A1812013-03-14014 March 2013
Meeting Handout - Operational Assessment for Cycle 20
Project stage: Meeting
ML13094A1932013-03-14014 March 2013
Meeting Handout - Independent Operational Assessment
Project stage: Meeting
ML13094A1912013-03-14014 March 2013
Meeting Handout - Results of Fall 2012 Inspection
Project stage: Meeting
ML13084A0302013-04-0404 April 2013
9/13/2012 - Summary of Conference Call with Florida Power & Light Co. Re. the Findings of the Fall 2012 Steam Generator Tube Inspections at Saint Lucie Plant, Unit No. 2
Project stage: Other
ML13095A3472013-04-11011 April 2013
3/14/2013 - Summary of Meeting with Florida Power & Light Co., to Discuss Insights About the Performance of the Steam Generators at St. Lucie Plant, Unit No. 2 After Three Operating Cycles
Project stage: Meeting
2013-03-14
[Table View] |
|
|---|
Category:Meeting Summary
MONTHYEARML24185A1262024-07-10010 July 2024
Summary of Meeting with Florida Power and Light on License Amendment Requests Regarding the Spent Fuel Criticality Analysis in Support of Planned Transition to 24-Month Fuel Cycles for St. Lucie, Unit 2
ML24128A2102024-05-0707 May 2024
Public Meeting Summary - 2023 Annual Assessment Meeting Regarding Saint Lucie
ML23166A0042023-06-15015 June 2023
Summary of Meeting Concerning 2023 Annual Assessment of the Saint Lucie and the Turkey Point Nuclear Plants
ML23107A2312023-04-18018 April 2023
Summary Meeting with Florida Power and Light/Nextera on Improved Technical Specification Conversion License Amendment Requests
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
ML23069A0282023-03-15015 March 2023
Summary of January 31, 2023, Meeting with Florida Power and Light on St. Lucie and Turkey Point Improved Technical Specifications Conversion License Amendment Requests
ML23066A0872023-03-15015 March 2023
Summary of Meeting with Florida Power and Light on St. Lucie and Turkey Point Improved Technical Specifications Conversion License Amendment Requests
ML23044A4172023-03-0606 March 2023
Summary of January 17, 2023, Meeting with Florida Power and Light on St. Lucie and Turkey Point Improved Technical Specifications Conversion License Amendment Requests
ML22357A0742023-01-19019 January 2023
Summary of December 1, 2022, Meeting with Florida Power and Light on St. Lucie and Turkey Point Improved Technical Specification Conversion License Amendment Requests
ML22350A7082023-01-17017 January 2023
Summary of November 21, 2022, Presubmittal Meeting with Florida Power and Light on St. Lucie License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components
ML22327A2402022-12-0808 December 2022
Summary of October 27, 2022, Meeting with Florida Power and Light on St. Lucie and Turkey Point Improved Technical Specification Conversion License Amendment Requests
ML22263A0122022-09-27027 September 2022
Summary of August 29, 2022, Meeting with Florida Power and Light on St. Lucie and Turkey Point Improved Technical Specification Conversion License Amendment Requests (EPID Nos. L-2021-LLI-0000 and L 2021 Lli 0002)
ML22144A0022022-09-14014 September 2022
Summary of February 16, and May 18, 2022, Meetings with Nextera Energy/Florida Power & Light Company Regarding Planned Submittal of License Amendment Request for a Common Fleet Emergency Plan
ML22229A5252022-08-24024 August 2022
Summary of August 11, 2022, Mtg. with Florida Power & Light/Nextera on St. Lucie and Turkey Point Improved Technical Specification Conversion License Amendment Request (EPIDs L-2021-LLI-0000 & -0002)
ML22145A3932022-05-25025 May 2022
Public Meeting Summary 2021 Annual Assessment Meeting 20220434
ML22020A4032022-02-0707 February 2022
Summary of November 17, 2021, Meeting with Florida Power and Light/Nextera on Improved Technical Specification Conversion License Amendment Requests (EPIDs L-2021-LLI-0000 and L-2021-LLI-0002)
ML22020A4052022-01-24024 January 2022
Summary of January 14, 2022, Teleconference with Florida Power & Light Co. Regarding Verbal Authorization of Request for Alternative to the Requirements of ASME Code for Examination of Closure Head CEDM Housing 27 Canopy Seal Weld
ML21342A3752022-01-0606 January 2022
Summary of Meeting with Florida Power and Light/Nextera on Proposed Improved Technical Specification Conversions
ML21337A1962021-12-16016 December 2021
Public Scoping Meeting Summary for the Environmental Review of the Subsequent License Renewal Application for St. Lucie Plant, Units 1 and 2
ML21337A2062021-11-0303 November 2021
Environmental Scoping Meeting Related to the St. Lucie Plant, Units 1 and 2, Subsequent License Renewal Application
ML21173A2922021-07-0909 July 2021
5-20-21 St. Lucie Plant Units 1 & 2 Subsequent License Renewal Environmental Pre-Application Meeting Summary
ML21176A0552021-06-29029 June 2021
Subsequent License Renewal Application - 2nd Public Meeting Summary of Pre-Submittal Meeting
ML21159A1352021-06-0808 June 2021
Public Meeting Summary Regarding the Saint Lucie Nuclear Plant, Units 1 and 2, Docket No. 50-335 and 389, and the Turkey Point Nuclear Generating Station Units 3 and 4, Docket No. 50-250 and 50-251; Meeting Number 20210505
ML21127A2182021-05-11011 May 2021
Subsequent License Renewal Application - Public Meeting Summary of Pre-Submittal Meeting
ML21092A1022021-04-13013 April 2021
Summary of Pre-Application Meeting to Discuss Planned License Amendments Regarding Conversion to Improved Technical Specifications for the Turkey Point Nuclear Generating, Unit Nos.3 and 4 and St. Lucie Plant, Unit Nos. 1 and 2 Facilities
ML20044E6802020-02-20020 February 2020
Summary of February 10, 2020, Teleconference with Florida Power and Light Company St, Lucie, Unit 2 - Regarding Verbal Authorization of Request to Use ASME Code Case N-513-4 for Alternate Repair of Intake Cooling Water System
ML20034F2862020-02-0303 February 2020
Summary of January 29, 2020, NRC-NMFS Teleconference Regarding St. Lucie Endangered Species Act Consultation
ML19221B6742019-08-13013 August 2019
Summary of Teleconference with Florida Power & Light Company Regarding Verbal Authorization of Request for Alternative Repair of the 2B Boric Acid Makeup Pump
ML19149A5942019-07-0808 July 2019
Summary of March 13, 2019, Meeting with Florida Power & Light Company Regarding a Planned License Amendment Request for St. Lucie Plant, Unit 2
ML19121A6102019-05-0101 May 2019
Public Meeting Summary - St Lucie Nuclear Plant, Docket Nos. 50-389 and 50-335
ML18242A3552018-09-21021 September 2018
Summary of Meeting with Florida Power & Light Company Regarding Planned License Amendment Requests for Turkey Point Nuclear Generating Unit Nos. 3 and 4 and St. Lucie Plant, Unit Nos. 1 and 2
ML18136A9052018-05-31031 May 2018
Summary of April 25, 2017, Meeting with Florida Power & Light Company/Nextera Energy Regarding Planned Submittal of Exemption Requests to Support Closure of NRC Generic Safety Issue 191/NRC Generic Letter 2004-02
ML18135A2462018-05-31031 May 2018
Summary of April 24, 2018, Meeting with Florida Power & Light Company/Nextera Energy Regarding Planned Submittal of License Amendment Request to Adopt Standard Technical Specification 3.0.6
ML18144A1452018-05-24024 May 2018
Public Meeting Summary - St. Lucie Nuclear Plant Docket Nos. 50-335 and 50-389
ML18122A1952018-05-17017 May 2018
Summary of Meeting with Florida Power & Light Company Regarding a Planned License Amendment Request for St. Lucie Nuclear Plant Unit 2
ML17310B2062017-11-20020 November 2017
Summary of September 20, 2017, Meeting with Florida Power & Light Company and NextEra Energy Regarding Closure of NRC Generic Safety Issue 191/NRC Generic Letter 2004-02
ML17291A0452017-11-0606 November 2017
Summary of Meeting with Florida Power and Light Company, Regarding Planned License Amendment Requests for St. Lucie Plants, Units 1 and 2 and Turkey Point Nuclear Generating Unit Nos. 3 and 4
ML17216A1732017-09-0707 September 2017
Notice of Meeting with Florida Power & Light Company and NextEra Energy to Discuss Closing Out Generic Safety Issue-191 and Generic Letter 2004-02
ML16097A1302016-04-0404 April 2016
March 29, 2016 Summary of Public Meeting - 2015 Annual Assessment Regarding Saint Lucie
ML15188A3402015-07-13013 July 2015
Summary of Closed Meeting with Florida Power and Light Company and Areva Regarding Request for Additional Information for the License Amendment and Exemption Requests Re. the Transitioning to Areva Fuel
ML15086A2232015-03-27027 March 2015
Summary of Meeting Concerning the Annual Assessment of St. Lucie Nuclear Plant, Units 1 and 2
ML14163A6522014-06-19019 June 2014
Summary of May 29, 2014, Public Meeting with NextEra Energy, Inc. and Florida Power & Light Company Regarding Proposed Amendment to Transition Fuel Type at St. Lucie Unit 2
ML13225A2932013-08-12012 August 2013
7/23-24/2013, Summary of Meeting 2013 U.S. Nuclear Regulatory Commission (NRC) Initial Exam Writers' Workshop
ML13107B4002013-04-17017 April 2013
Summary of Public Meeting, Florida Power & Light, St. Lucie Nuclear Plant
ML13095A3472013-04-11011 April 2013
3/14/2013 - Summary of Meeting with Florida Power & Light Co., to Discuss Insights About the Performance of the Steam Generators at St. Lucie Plant, Unit No. 2 After Three Operating Cycles
ML13084A0302013-04-0404 April 2013
9/13/2012 - Summary of Conference Call with Florida Power & Light Co. Re. the Findings of the Fall 2012 Steam Generator Tube Inspections at Saint Lucie Plant, Unit No. 2
ML13077A4482013-03-27027 March 2013
7/27/11 Summary of Conference Call with Florida Power and Light Co. Re Findings of the Spring 2011 SG Tube Inspections for St. Lucie Unit 2
ML12326A8162012-11-21021 November 2012
11/9/2012 - Summary of Meeting with the Florida Power and Light Company Regarding the St. Lucie Nuclear Plant
ML12258A0802012-09-14014 September 2012
NRC Conference Call St. Lucie Unit 2 Steam Generator Inspection September 13, 2012
ML12171A3082012-06-18018 June 2012
E-mail Re Draft Summary of 05-31-12 Phone Call
2024-07-10
[Table view]
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
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L-2024-158, Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-25025 September 2024
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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
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2024-09-09
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 4, 2013 LICENSEE: Florida Power & Light Co.
FACILITY: Saint Lucie Power Plant, Unit No.2
SUBJECT:
SUMMARY
OF SEPTEMBER 13, 2012, CONFERENCE CALL WITH FLORIDA POWER & LIGHT COMPANY REGARDING THE FINDINGS OF THE FALL 2012 STEAM GENERATOR TUBE INSPECTIONS AT SAINT LUCIE PLANT, UNIT NO.2 (TAC NO. ME9534)
On September 13, 2012, a Category 1 conference call was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of Florida Power & Light Company at NRC Headquarters, One White Flint North, 11555 Rockville Pike, Rockville, Maryland. The purpose of the call was to discuss the findings of the steam generator tube inspection activities performed at Saint Lucie Plant, Unit No.2 during fall 2012. A list of attendees is provided as and a summary of the discussion is provided in Enclosure 2.
Members of the public were not in attendance. Public meeting feedback forms were not received during the conference call.
Please direct any inquiries to me at 301-415-2788, or e-mail me at Tracy.Orf@nrc.gov.
Tracy J. Orf, Proj ct Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-389
Enclosures:
1 . List of attendees
- 2. Summary of Conference Call cc w/encls: Distribution via Listserv
LIST OF ATTENDEES SEPTEMBER 13. 2012. CONFERENCE CALL WITH FLORIDA POWER AND LIGHT CO.
FALL 2012 STEAM GENERATOR TUBE INSPECTIONS AT ST. LUCIE. UNIT NO.2 Name Organization Kenneth Karwoski NRC Tracy J. Ort NRC Louis Lake NRC Jack Hoffman FPL Russ Cipolla Intertec Ed Korkowski FPL Allen Brown AREVA Enclosure 1
SUMMARY
OF CONFERENCE CALL WITH ST. LUCIE PLANT UNIT NO.2 REGARDING THE FALL 2012 STEAM GENERATOR TUBE INSPECTION RESULTS DOCKET NO. 50-389 On September 13, 2012, the U.S. Nuclear Regulatory Commission (NRC) staff participated in a conference call with representatives of Florida Power & Light Company (the licensee), regarding their ongoing steam generator tube inspection activities at Saint Lucie Plant (St. Lucie), Unit NO.2. Information provided by the licensee in support of the conference call is located in the Agencywide Documents Access Management System under Accession No. ML12258A080.
St. Lucie Unit 2 has two Areva-NP Model 86/19TI replacement steam generators (SGs) that were installed in January 2008. Each SG has 8,999 thermally-treated Alloy 690 tubes with a nominal outside diameter of 0.75 inches and a nominal wall thickness of 0.043 inches. During manufacturing, all tubes were hydraulically expanded at both ends over the full depth of the tubesheet. The tubesheet was drilled on a triangular pitch with 1-inch spacing, center-to-center.
The radius of the row 1 U-bends is 4.134 inches. The U-bends in rows 1 through 15 were stress relieved after bending. Seven tube support plates (TSPs), each 1.181 inches thick and made from Type 410 stainless steel, support the vertical section of the tubes. The TSPs have broached trefoil holes. Four sets of anti-vibration bars (AVBs), each 0.112 inches thick and made from Type 405 stainless steel, support the U-bend section of the tubes.
Additional clarifying information regarding the licensee-provided document and information not included in the licensee-provided document is summarized below.
- The licensee indicated that at the time of the call, the bobbin coil inspections were greater than 99 percent complete in both SG A and SG B.
- There was no correlation found between AVB and TSP wear indications.
- The total number of indications in the "History of wear indications/affected number of tubes (Cumulative)" table on page 1 of the licensee's informational document is different from the "Wear distribution" histogram on page 2 because they were generated at different times during the outage. However, the general distribution and trend shown in the histogram remains the same when all the data from the table on page 1 is included.
Regarding the two new indications with depths between 30 and 34 percent reported in the histogram on page 2, one of the two indications is a 34-percent through wall (TW) indication that is located in a tube that had prior wear indications. The second indication is a 32-percent TW indication in a tube on the periphery of SG A, in a location where tube wear has already been seen.
- The licensee indicated that they evaluate whether the growth rate is a function of the beginning-of-cycle (BOC) depth. They indicated in the prior inspections, the growth rates for flaws less than or equal to 13-percent TW were dependent on the BOC depth, but no such correlation existed for flaws greater than 13-percent TW.
Enclosure 2
-2
- The licensee indicated that they had implemented modifications to access covers in a prior outage to deal with nuts that loosened during operation, that the modification was working as designed, and that no new loose nuts were noted during this inspection.
There was no degradation or anomalous conditions identified during the inspection.
- Profiling of the wear indications had commenced and was being performed to determine if there was any change in the specific type of wear that was occurring in the SG tubes.
The licensee indicated that the indications tend to be flat, centered, and no longer than the AVBs causing the wear.
- The licensee stated that there was no observed primary-to-secondary leakage during the recently completed operating cycle. Also, there were no exceptions taken to the industry guidelines (including the chemistry, inspection, and integrity assessment guidelines).
- The licensee indicated that the prior operational assessment had predicted that 30-34 tubes would require plugging in SG A during the current inspection, and the actual amount of required plugging was just 7 tubes in SG A. Overall, the licensee indicated that the general trend of the inspection findings was in line with the predicted findings of the prior operational assessment.
- Seven indications that measured 40-percent TW were detected in 2012. Only one similar indication (40-percent TW) was detected in the last outage.
- The licensee indicated it was reviewing the increase in the number of new indications in SG B since the number of new indications per cycle increased in the latest inspection.
- The licensee is scheduled to implement a power uprate during this cycle.
At the end of the call, the NRC staff inquired about potentially being briefed on the results of the inspections and the final Condition Monitoring Operational Assessment since they are complicated. The representatives from St. Lucie indicated they would work with the NRC project manager in setting up such a meeting.
Additional abbreviations used in the licensee-provided document include:
- CMOA - Condition Monitoring and Operational Assessment
- EFPY - Effective Full Power Years
- FOSAR - Foreign Object Search and Retrieval
- OA - Operational Assessment
- POB - Probability of Burst
- SONGS - San Onofre Nuclear Generating Station
ML13084A030 OFFICE LPL2-2/PM LPL2-2/LA ESGB/BC'" LPL2-2/BC LPL2-2/PM NAME TOrt BClayton GKulesa JQuichocho TOrt DATE 04/03/13 04/03/13 08/05/12 04/04/13 04/04/13
