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Category:Letter type:L
MONTHYEARL-2024-085, Refueling Outage SL1-32 Low Pressure Turbine Rotor Inspection Results2024-10-15015 October 2024 Refueling Outage SL1-32 Low Pressure Turbine Rotor Inspection Results L-2024-165, Report of 10 CFR 50.59 Plant Changes, Tests and Experiments Made2024-10-14014 October 2024 Report of 10 CFR 50.59 Plant Changes, Tests and Experiments Made L-2024-118, Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1)2024-10-0808 October 2024 Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1) L-2024-155, Subsequent License Renewal Application, Third Annual Update2024-09-27027 September 2024 Subsequent License Renewal Application, Third Annual Update L-2024-158, Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-25025 September 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes 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-2024-071, Cycle 27 Core Operating Limits Report2024-04-29029 April 2024 Cycle 27 Core Operating Limits Report L-2024-070, Cycle 32 Core Operating Limits Report2024-04-29029 April 2024 Cycle 32 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-2024-027, Safety Injection Tank Vent Through Wall Leakage2024-02-29029 February 2024 Safety Injection Tank Vent Through Wall Leakage L-2024-015, 2023 Annual Radioactive Effluent Release Report2024-02-29029 February 2024 2023 Annual Radioactive Effluent Release Report 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 2024-09-09
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U.S. Nuclear Regulatory Commission Document Control Desk JUL 0 3 2017 L-2017-119 10 CFR 54 Washington, D .C. 20555-0001 St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389
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Reactor Vessel Internals Aging Management Plan Reference
- 1. FPL Letter from Christopher Costanzo to U.S. Nuclear Regulatory Commission (L-2015-229) "St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389, License Renewal Commitments- Reactor Vessel Internals Aging Management Plan," Dated September 28, 2015.
- 2. NRC e-Mail from Perry Buckberg to Ken Frehafer, Request for Additional Information, St. Lucie Plant Units 1 and 2, Reactor Vessel Internals Aging Management Plan, Docket Nos. 50-335 and 50-389, TAC Nos. MF6777 and MF6778.
- 3. FPL Letter from Christopher Costanzo to U.S. Nuclear Regulatory Commission (L-2015-040), Reactor Vessel Internals Aging Management Plan, dated February 26, 2016.
- 4. FPL Letter from Daniel DeBoer to U.S. Nuclear Regulatory Commission (L-2017-015), Reactor Vessel Internals Aging Management Plan, dated March 7, 2017.
By letter to the U.S. Nuclear Regulatory Commission (NRC) dated September 28, 2015 (Reference 1), Florida Power & Light Company (FPL) submitted its License Renewal Reactor Internals Inspection Program in accordance with MRP-227A at St. Lucie Nuclear Plants Units 1 and 2, for NRC staff review. The NRC staff reviewed the information provided by FPL in its submittal and requested additional information to complete their review (Reference 2). The responses to RAI-l through RAI-10 were previously submitted to the NRC on February 26, 2016 (Reference 3) and March 7, 2017 (Reference 4).
In References 3 and 4 noted above, FPL noted that PWR Owners Group (PWROG) was developing a Generic Response Report for RAI-9. FPL response to RAI-9 is noted below:
PSLRAI-9:
Applicant/ Licensee Action Item (A/ LAI) 7 requires an applicant or licensee to provide an evaluation demomtrating that mst austenitic stainless steel (Cr:I.SS) RVI components will maintain theirfunctionaliry throughout the period if extmded operation (PEO), considering the potentia/loss iffradure toughness due to both thmnal embrittlement (TE) and irradiation embrittlement (IE). In its response to A/ LAI 7, the licensee identified the R VI components that are fabricated from CASSasSt. Lucie P!ant Unit 1 core suppo1t columns, the CEA shroud tubes for both units, and the St. Lucie P!ant Unit 2 flow l?Jpass itt.rerts.
The licensee ittdimted that all but one if the Unit 1 core supp01t columns m*een in forTE based on the assumption that the columns have fene'te > 20%, since mtified material test reports could not be located for these columns.
The licensee then concluded that the results if this evaluation do not conflict with strategy for aging management ifR VI provided itt MRP-22 7-A. The licensee stated that it is concluded that continued application if the strategies in MRP-2 27-A and the St.
Florida Power & Light Company 6501 S. Ocean Drive, Jensen Beach, FL 34957
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L-2017-119 10 CFR 54 Page 2 of2 Lucie P!ant Units 1 and 2 R VI Inspection Program will meet the requirements for managing age-related degradation of St.
Lucie Plant Units 1 and 2, CASS and mmtensitic stainless steel RVI components. However, the licensee did notprovide any justification for its position that the MRP-22 7A aging management requirements (which require no inspections of the core support columns) are sufficient, considering the potentialfor loss offincture toughness due to two mechanisms, and the susceptibility to cracking of the columns. The staff notes that the core supp011 column welds, which are visible from above the core support plate, are inspected as Primm)' components, butMKP~"""27-A and tbe St. LUcze Plant Onzt IR:Vi ./:fMP.--:n-
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zn expansion to the columns if degradation is detected in the welds.
Since the St. Lucie Plant Unit 1 core supp011 columns (except one) are screened in forTE, and are also susceptible to IE and several cracking mechanisms, the stciff requests the licensee provide an evaluation for St. Lucie Plant Unit 1, demonstrating that the core supp011 columns will remain functional during the PEO considering the potential combined loss ofjiwture toughness due to IE plus IE, along with the potentialfor cracking in the columns.
FPL Response:
The response to RAI-9 described the on-going work by the PWROG for the CASS lower support column welds functionality analysis on a generic basis. Westinghouse, on behalf ofPWROG, has completed the functionality analysis in Report No. PWROG-14048-P, Revision 1 (Proprietary). This report demonstrates the functionality of St. Lucie Unit 1 CASS core support columns (on a generic basis), during the period of extended operation, considering the loss of fracture toughness due to both thermal embrittlement (TE) and irradiation embrittlement (IE).
Report No. PWROG-14048-P, Revision 1 was submitted to the NRC by the Owners Group via OG Letter No. OG-17-62 dated March 1, 2017. This report is currently under NRC review.
This letter is to acknowledge that FPL has reviewed PWROG-14048-P, Revision 1 and concurs that the conclusions noted in the Executive Summary and Section 7 are applicable to St. Lucie Nuclear Plant, Unit 1.
No changes to tl1e PSL RV Internals Aging Management Program as submitted to the NRC in Reference 4 are needed.
By submittal of this letter, FPL has completed responses to all ten NRC RAis on the Reactor Vessel Inspection Program described in reference 2.
Should you have any questions, please contact Mr. Michael Snyder, Licensing Manager, at 772-467-7036.
Very truly yours, Daniel DeBoer Site Director St. Lucie Plant DD/lrb Cc: USNRC Regional Administrator, Region II USNRC Senior Resident Inspector, St. Lucie Units 1 and 2