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Category:Letter type:L
MONTHYEARL-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 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 L-2024-140, Cycle 28 Core Operating Limits Report2024-08-14014 August 2024 Cycle 28 Core Operating Limits Report L-2024-133, Snubber Program Plan Submittal2024-08-14014 August 2024 Snubber Program Plan Submittal L-2024-132, 2024 Population Update Analysis2024-08-13013 August 2024 2024 Population Update Analysis 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 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 L-2024-117, Safety Injection Tank Vent Through Wall Leakage2024-07-11011 July 2024 Safety Injection Tank Vent Through Wall Leakage 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-2024-110, 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-2024-109, Schedule for Subsequent License Renewal Environmental Review2024-07-0303 July 2024 Schedule for Subsequent License Renewal Environmental Review 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 L-2024-090, Revised Steam Generator Tube Inspection Reports2024-06-0404 June 2024 Revised Steam Generator Tube Inspection Reports L-2024-075, Notification of Improved Standard Technical Specifications (ITS) Implementation2024-05-13013 May 2024 Notification of Improved Standard Technical Specifications (ITS) Implementation 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 L-2024-064, Florida Power & Light Company - 10 CFR 50.46 - Emergency Core Cooling System SBLOCA 30-Day Report2024-04-17017 April 2024 Florida Power & Light Company - 10 CFR 50.46 - Emergency Core Cooling System SBLOCA 30-Day Report L-2024-056, Annual Radiological Environmental Operating Report for Calendar Year 20232024-04-17017 April 2024 Annual Radiological Environmental Operating Report for Calendar Year 2023 L-2024-054, 2023 Annual Environmental Operating Report2024-04-0909 April 2024 2023 Annual Environmental Operating Report L-2024-047, Proposed Use of a Subsequent ASME Code Edition and Addenda2024-03-28028 March 2024 Proposed Use of a Subsequent ASME Code Edition and Addenda L-2024-045, Report of 10 CFR 72.48 Plant Changes2024-03-27027 March 2024 Report of 10 CFR 72.48 Plant Changes L-2024-011, and Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2024-03-13013 March 2024 and Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications L-2024-023, Unusual or Important Environmental Event - Turtle Mortality2024-03-0606 March 2024 Unusual or Important Environmental Event - Turtle Mortality L-2024-015, 2023 Annual Radioactive Effluent Release Report2024-02-29029 February 2024 2023 Annual Radioactive Effluent Release Report L-2024-027, Safety Injection Tank Vent Through Wall Leakage2024-02-29029 February 2024 Safety Injection Tank Vent Through Wall Leakage L-2024-029, 2023 Annual Operating Report2024-02-28028 February 2024 2023 Annual Operating Report L-2024-026, Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules2024-02-27027 February 2024 Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules 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) 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-2023-175, Supplement to Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-2023-162, Response to 50.69 2nd Round of Rals2023-11-21021 November 2023 Response to 50.69 2nd Round of Rals L-2023-131, Subsequent License Renewal Application - Second Annual Update2023-09-28028 September 2023 Subsequent License Renewal Application - Second Annual Update L-2023-136, Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-26026 September 2023 Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-122, Corrections to the 2022 Annual Radiological Environmental Operating Report2023-09-20020 September 2023 Corrections to the 2022 Annual Radiological Environmental Operating Report L-2023-127, Correction to the 2022 Annual Radioactive Effluent Release Report2023-09-18018 September 2023 Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-113, Correction to the 2020 Annual Radiological Environmental Operating Report2023-09-14014 September 2023 Correction to the 2020 Annual Radiological Environmental Operating Report L-2023-118, Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-11011 September 2023 Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-108, Report of 10 CFR 50.59 Plant Changes2023-09-11011 September 2023 Report of 10 CFR 50.59 Plant Changes 2024-09-09
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0 Florida Power& Light Company, 6501 S Ocean Drive, Jensen Beach, FL 34957 FPL March 31, 2003 L-2003-085 10 CFR 50.4 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 RE: St. Lucie Unit 2 Docket No. 50-389 NRC Information Request Steam Generator Tubesheet Inspection Practices Based on discussions and conference calls among the NRC, Nuclear Energy Institute (NEI), and the industry on steam generator (SG) tubesheet inspections for plants with mill annealed Alloy 600 SG tubes, St. Lucie Unit 2 was among the plants requested by NEI letter dated February 28, 2003, to submit the attached information by the end of March 2003.
Last spring, the NRC questioned two PWR licensees on the inspection methods used for steam generator tubes at locations within the tubesheet. The NRC challenged inspection practices that do not expand tube sample selections deeper within the tubesheet when degradation is found or expected below a specific depth. Instead of expanding the inspection within the tubesheet under these circumstances, some licensees justify limiting the depth inspected with rotating probes on the basis that degradation below the specified depth is not an operational or safety concern. The NRC believes that technical specifications require each licensee to apply inspection methods capable of detecting the type of flaws, which may potentially exist at each tube location where a tube inspection is required. The industry is in general agreement with the staffs position regarding the need to ensure tube integrity, but holds that the technical specifications do not specify the type of eddy current probe that should be used. The industry believes the adequacy of inspections, and therefore the type of eddy current probe used, is dictated by 10CFR50 Appendix B considerations. The industry and NRC have met numerous times in an attempt to reach a common understanding on this issue.
The NRC has been working on a generic communication on this subject since last summer. In the early part of this year the NRC staff started contacting licensees who they believed were most susceptible to tube cracking within the tubesheet (i.e., plants with mill annealed Alloy 600 tubing.) By letter dated February 28, 2003, NEI requested
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an FPL Group company
St. Lucie Unit 2 Docket No. 50-389 L-2003-085 Page 2 the applicable utilities to provide the requested information using the format in of the NEI letter.
On January 23, 2003 by letter L-2003-002, Florida Power & Light Company FPL) submitted a contingency license amendment request to change the Technical Specification definition of steam generator tube inspection. The proposed amendment addresses the extent of planned hot leg tubesheet inspections, and their bases, for the SL2-14 inspection in April/May 2003. FPL's planned inspection scope for SL2-14, has been modified to exceed the scope described in the subject PLA as follows:
- The depth of the inspection with Plus Point probes inside the tubesheet will be a minimum of 7 inches, as referenced from the bottom of the tube expansion transition for all active hot leg tubes.
- Any detected degradation within or below this inspection zone will be plugged.
This revised scope is reflected in the attached information. Please contact George Madden at 772-467-7155 if there are any questions about this submittal.
V t uf u s,Jr St. Lucie Plant Attachment WJ/GRM
St. Lucie Unit 2 Docket No. 50-389 L-2003-085 Page 3 Industry Template For Submittal of Information on Steam Generator Inspection within the Tubesheet
REFERENCE:
NEI Letter to Administrative Points of Contact, "Steam Generator Tubesheet Inspections," February 28, 2003, Enclosure 2
St. Lucie Unit 2 Docket No. 50-389 L-2003-085 Page 4 Florida Power & Light Company St. Lucie Unit 2 Tubesheet Inspection Practices Plant Information Plant Name: Florida Power & Light, St. Lucie Unit 2 ThOt: 5990F Normal Steady State Full Power DP: 1435 psid (2250 psia - 815 psia)
Model of Steam Generator: CE 3410 Tube Material: High Temperature Mill Annealed Alloy 600 (Inconel)
Tube Diameter: 0.750" Tube Wall Thickness: 0.048" Nominal Expansion Process and Extent: Full depth explosive Tubesheet Thickness: 21.5" (plus 0.25" cladding)
Susceptible to degradation below expansion transition region:
Yes X No If no, provide basis for non-susceptibility determination:
Historical Inspection Practices and Results Most recent outage: Cycle #: SL2-13, Nov. 2001 Inspection techniques used: Bobbin and Plus Point Probes Extent of inspections (be specific on landmarks used to determine inspection extent):
Bobbin extent is full depth of all active tubes (hot leg and cold leg tubesheet)
Plus Point extent is +3"I-5" minimum from the top of the hot leg tubesheet Results (degradation mechanisms identified and orientation):
Note: Reference FPL PowerPoint presentation to NRR on 2-20-03 for further details No circumferential indications below the hot leg tube expansion transition 2 Axial IDSCC indications up to 2.1" below the hot leg top of tubesheet Bases for inspection technique and inspection extent:
EPRI Qualified & Site Validated Techniques. CEOG Task 1154 WCAP-15720, Rev. 0
'NDE Inspection strategy for the Tubesheet Region in CE Designed Units."
Technical Document reference (Generic or Plant Specific?):
Generic CEOG Task 1154 WCAP-15720, Rev. 0, NDE Inspection strategy for the Tubesheet Region in CE Designed Units.
If generic, provide statement that plant conditions and design are bounded by Technical Document inputs and assumptions: Generic CEOG Task 1154 WCAP-15720, Rev. 0 bounds St. Lucie Unit 2 operating conditions and inspection experience.
St. Lucie Unit 2 Docket No. 50-389 L-2003-085 Page 5 Florida Power & Light Company St. Lucie Unit 2 Tubesheet Inspection Practices Historical Inspection Practices and Results (Continued)
Previous outages:
Cycle #: SL2-12, April 2000 Inspection techniques used: Bobbin and Plus Point Probes Extent of inspections (be specific on landmarks used to determine inspection extent):
Bobbin extent is full depth of all active tubes (hot leg and cold leg tubesheet)
Plus Point extent is +3"/-2" minimum from the top of the hot leg tubesheet Results (degradation mechanisms identified and orientation):
Note: Reference FPL presentation materials to NRR on 2-20-03 for further details No circumferential indications below the hot leg expansion transition 1 Axial IDSCC indication 0.17" below the hot leg top of tubesheet Bases for inspection technique and inspection extent:
EPRI Qualified & Site Validated Techniques and accepted Industry practice regarding extent of rotating probe inspection within the tubesheet. Pending Generic CEOG Task 1154 Report.
Previous outages:
Cycle #: SL2-1 1, Nov. 1998 Inspection techniques used: Bobbin and Plus Point Probes Extent of inspections (be specific on landmarks used to determine inspection extent):
Bobbin extent isfull depth of all active tubes (hot leg and cold leg tubesheet)
Plus Point extent is +3"/-1" minimum from the top of the hot leg tubesheet Results (degradation mechanisms identified and orientation):
No circumferential indications below the hot leg expansion transition No axial indications below the hot leg top of tubesheet Bases for inspection technique and inspection extent:
EPRI Qualified & Site Validated Techniques and accepted Industry practice regarding extent of rotating probe inspection within the tubesheet.
Previous outages-Cycle #: SL2-10, April 1997 Inspection techniques used: Bobbin and Plus Point Probes Extent of inspections (be specific on landmarks used to determine inspection extent):
Bobbin extent is full depth of all active tubes (hot leg and cold leg tubesheet)
Plus Point extent is +2"I-1" minimum from the top of the hot leg tubesheet Results (degradation mechanisms identified and orientation):
No circumferential indications below the hot leg expansion transition 1 Axial indication 1.1" below the hot leg top of tubesheet Bases for inspection technique and inspection extent:
EPRI Qualified Techniques and accepted Industry practice regarding extent of rotating probe inspection within the tubesheet.
St. Lucie Unit 2 Docket No. 50-389 L-2003-085 Page 6 Florida Power & Light Company St. Lucie Unit 2 Tubesheet Inspection Practices Planned Inspection for Next Outage Anticipated date of outage SL2-14, April 21, 2003 Techniques to be used: Bobbin and Plus Point Probes Extent of inspections (be specific on landmarks used to determine inspection extent):
Bobbin extent is full depth of all active tubes (hot leg and cold leg tubesheet)
Plus Point extent is +3/-7" minimum from the bottom of the expansion transition for all active hot leg tubes. Any detected degradation within or below the inspection zone will be plugged. This inspection plan exceeds the recommendations of WCAP-15975-P, Rev. 0, and the commitment made by FPL in our recent proposed license amendment (see Bases for inspection below)
Bases for inspection technique and inspection extent:
- WCAP-15975-P, Rev. 0, NDE Inspection Strategy for the Tubesheet Region in St. Lucie Unit 2.
- Florida Power & Light, St. Lucie Unit 2 Proposed License Amendment, 'Contingency Change to the Definition of Steam Generator Tube Inspection," FPL letter L-2003-002, January 23, 2003.