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Category:Letter type:L
MONTHYEARL-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-2024-007, Inservice Inspection Program Owner'S Activity Report (OAR-1)2024-01-18018 January 2024 Inservice Inspection Program Owner'S Activity Report (OAR-1) 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-2023-166, Turkey Points Units 3 and 4, Correction to the 2022 Annual Radioactive Effluent Release Report2023-12-0606 December 2023 Turkey Points Units 3 and 4, Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-172, Supplement to Exemption Request Regarding Enhanced Weapons. 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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-2023-069, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-05-31031 May 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2023-072, Preparation and Scheduling of Operator Licensing Examinations2023-05-22022 May 2023 Preparation and Scheduling of Operator Licensing Examinations 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 L-2023-061, 2022 Annual Radiological Environmental Operating Report2023-05-12012 May 2023 2022 Annual Radiological Environmental Operating Report L-2023-062, Cycle 33 Core Operating Limits Report2023-04-27027 April 2023 Cycle 33 Core Operating Limits Report L-2023-060, Radiological Emergency Plan, Revision 752023-04-26026 April 2023 Radiological Emergency Plan, Revision 75 L-2023-054, Submittal of Periodic Reports2023-04-12012 April 2023 Submittal of Periodic Reports L-2023-049, Correction to U4R33 Steam Generator Tube Inspection Report2023-03-30030 March 2023 Correction to U4R33 Steam Generator Tube Inspection Report L-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023 Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update L-2023-028, 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 Applications2023-03-27027 March 2023 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-2023-025, Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-12023-03-15015 March 2023 Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-1 L-2023-029, and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3)2023-03-10010 March 2023 and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2023-040, Response to Requests for Additional Information (Rals) and Requests for Confirmation of Information (Rc Ls) Following Regulatory Audit of Subsequent License Renewal Application2023-03-0303 March 2023 Response to Requests for Additional Information (Rals) and Requests for Confirmation of Information (Rc Ls) Following Regulatory Audit of Subsequent License Renewal Application L-2023-037, Annual Radioactive Effluent Release Report2023-03-0101 March 2023 Annual Radioactive Effluent Release Report L-2023-017, Radiological Emergency Plan Revision 73 and Revision 7 42023-02-17017 February 2023 Radiological Emergency Plan Revision 73 and Revision 7 4 L-2023-010, Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of RPS / ESFAS / Nis2023-02-10010 February 2023 Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of RPS / ESFAS / Nis L-2023-004, Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of Huma Factors Results2023-01-17017 January 2023 Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of Huma Factors Results L-2022-185, Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-12-0909 December 2022 Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2022-181, Response to Request for Additional Information Regarding License Amendment Request for the Technical Specifications Conversion to NUREG-1431, Revision 52022-12-0101 December 2022 Response to Request for Additional Information Regarding License Amendment Request for the Technical Specifications Conversion to NUREG-1431, Revision 5 L-2022-182, Emergency Response Data System (Eros) Changes2022-11-17017 November 2022 Emergency Response Data System (Eros) Changes L-2022-180, CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2022-11-0909 November 2022 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums L-2022-168, and Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report2022-10-26026 October 2022 and Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report L-2022-171, 10 CFR 50.59(d)(2) Summary Report2022-10-20020 October 2022 10 CFR 50.59(d)(2) Summary Report L-2022-167, Submittal of Periodic Reports2022-10-13013 October 2022 Submittal of Periodic Reports L-2022-166, Response to Request for Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement2022-10-0505 October 2022 Response to Request for Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement L-2022-149, U4R33 Steam Generator Tube Inspection Report2022-10-0404 October 2022 U4R33 Steam Generator Tube Inspection Report L-2022-160, Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-10-0404 October 2022 Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2022-148, Florida Power & Light Company, Comments on NRC Inspection Procedure (IP) 71111.21 N.03, Commercial Grade Dedication2022-09-16016 September 2022 Florida Power & Light Company, Comments on NRC Inspection Procedure (IP) 71111.21 N.03, Commercial Grade Dedication L-2022-151, Evacuation Time Estimate Study2022-09-15015 September 2022 Evacuation Time Estimate Study L-2022-142, Revised Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-0042022-08-19019 August 2022 Revised Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-004 L-2022-136, Response to Request for Additional Information Regarding Turkey Point Unit 3 Cycle 32 Steam Generator Tube Inspection Report2022-08-12012 August 2022 Response to Request for Additional Information Regarding Turkey Point Unit 3 Cycle 32 Steam Generator Tube Inspection Report L-2022-109, Inservice Inspection Program - Owner'S Activity Report (OAR-1)2022-06-27027 June 2022 Inservice Inspection Program - Owner'S Activity Report (OAR-1) L-2022-076, Subsequent License Renewal Application - Appendix E Environmental Report Supplement 22022-06-0909 June 2022 Subsequent License Renewal Application - Appendix E Environmental Report Supplement 2 2024-01-25
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FPL MAY 2 7 2DO3 L-2003-122 10 CFR 50.4 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington D. C. 20555 Re: Turkey Point Unit 3 Docket No. 50-250 NRC Order EA-03-009 - Reactor Pressure Vessel Head And Vessel Head Penetration Nozzle Inspection Results NRC Order EA-03-009, issued on Februay 11, 2003 established interim inspection requirements for reactor pressure vessel heads of pressurized water reactors.Section IV. E. of the NRC Order requires that the results of the inspection be provided within 60 days of the plant being returned to operation. In accordance with section IV. E. of the NRC Order, the attachment to this letter submits the Florida Power and Light Company (FPL) inspection results for Turkey Point Unit 3 for the March 2003 refueling outage.
Based on the results of the reactor pressure vessel head visual examination, reactor pressure vessel head penetration nozzles ultrasonic examinations and leak path assessments (including liquid penetrant of the vent), FPL concludes that the alloy 600 reactor pressure vessel head penetration nozzles are not degraded, and no wastage has occurred of the reactor pressure vessel head.
Should there be any questions on this letter, please contact Walter Parker at (305) 246-6632.
Very truly yours, Terry 0. Jones Vice President Turkey Point Plant OH Attachment cc: Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point an FPL Group company
Attachment to L-2003-122 Page 1 of 4 NRC ORDER EA-03-009 60 DAY REPORT: REACTOR PRESSURE VESSEL HEAD AND VESSEL HEAD PENETRATION NOZZLE POST OUTAGE INSPECTION RESULTS FOR TURKEY POINT UNIT 3 The NRC issued an Order' on Februay 11, 2003 establishing interim inspection requirements for reactor pressure vessel heads of pressurized water reactors. In section IV.E. of the NRC Order, the NRC required that the results of the inspection be provided within 60 days of the plant being returned to operation. Florida Power and Light Company (FPL) hereby submits the inspection results for Turkey Point Unit 3 for the March 2003 refueling outage.
Turkey Point Unit 3 March 2003 Post Outage Inspection Results:
- 1. Plant Susceptibility Category: The Turkey Point Unit 3 reactor pressure vessel (RPV) closure head had approximately 18.3 effective degradation years at the start of the March 2003 refueling outage, as identified in the FPL response to NRC Bulletin 2002-022. The inspection category identified in the Order is High. The corresponding inspection method specified in Section IV.C.(1). is as follows:
IV.C.(1) For those plants in the High category, RPV head and headpenetration nozzle inspections shall be performed using the following techniques every refueling outage.
(a) Bare metal visual examination of 100% of the RPV head surface (including 3600 around each RPV head penetration nozzle), AND (b) Either:
(i) Ultrasonic testing of each RPV head penetration nozzle (i.e., nozzle base material) from two (2) inches above the J-groove weld to the bottom of the nozzle and an assessment to determine if leakage has occurred into the interference fit zone, OR (ii) Eddy current testing or dye penetrant testing of the wetted surface of each J-Groove weld and RPV head penetration nozzle base material to at least two (2) inches above the J-groove weld.
- 2. Inspection Scone and Method:
2.a. RPV Bare Metal Head Surface Visual: A bare metal visual inspection of 100% of the RPV head top surface, including 3600 around each RPV head penetration nozzle, was performed as identified in section IV.C.(1)(a) of the NRC Order. The VT was performed with the head shroud raised and all of the RPV head insulation removed, providing unrestricted visual access using both direct and remote visual examination techniques.
The scope of the inspection did not include the inside surface of the 58 RPV stud holes as clarified in the summary of the February 24, 2003 NRC meeting 3 conducted to discuss the NRC Order.
A limitation was noted where the /2"thick shroud support ring comes in close contact with the sloping RPV head outside of the RVHP nozzles. The square cut edge of the shroud support ring comes in close contact with the sloping RPV head for approximately half of the
Attachment to L-2003-122 Page 2 of 4 circumference of this 120" diameter ring. The adjacent areas uphill and downhill of the shroud ring and the areas under the shroud ring where a gap existed were visually examined. These areas were found to be free of any boric acid accumulation or staining.
The shroud ring metal edge to vessel contact, and lack of staining indicated that no wastage could have occurred. The limited area under the shroud ring was not considered relevant because there was no source of external boric acid leakage at or under the shroud ring that could result in wastage (Reference 3, NRC response to NEI question # 2). The limited area under the shroud ring is less than 0.3% of the vessel surface (<100 in2 / 31,700 in2), since only the edge of the shroud ring was in contact with the RPV head instead of the entire 1/2" thickness.
2.b. RPV Head Penetration Inspection: The ultrasonic (UT) examination technique option, identified in section IV.C.(1 )(b)(i) of the NRC Order, was performed of all of the 66 reactor vessel head penetration (RVHP) nozzles, including the vent line. The inspection included the nozzle base material 2" above the J-groove weld, down to the bottom end of all of the penetrations, with minor limitations for nine penetrations. These nine penetrations were inspected from 2" above the J-groove weld, down to a minimum of 1" below the weld.
This limitation was the subject of a relaxation request 4 5that was approved by the NRC 6.
As part of the UT examinations, the 65 RVHPs with interference fits were assessed to determine if leakage had occurred into the interference fit zone (annulus between the RPV head and the penetration above the pressure boundary weld). This assessment used the Framatome-ANP proprietary "leak path" technique, which was described in the post outage inspection report for the previous FPL St. Lucie Unit 1 RPV head inspection 7 The UT examinations of the 65 RVHPs (excluding the vent), were performed utilizing a circumferential "blade probe" consisting of two elements in a pitch/catch configuration in accordance with Framatome-ANP procedure 54-ISI-100-09. The vent inspection was performed using a rotating transducer in accordance with Framatome-ANP procedure 54-lSI-1 37-01.
The UT procedures utilized for the examination of the vent and the 65 RVHPs have been previously submitted to the NRC by the inspection vendore 9. Since the submittal to the NRC, the UT procedure used for the vent line was revised to include the change authorizations identified in Reference 9 from the Fall 2002 inspections. After the issuance of the NRC Order, one non technical change authorization for each procedure, FRA-03-004 Rev. 1 and FRA-03-005 Rev. 1, was also processed for the UT procedures to match the examination area wording with the area defined in the NRC Order. The inspection essential variables, procedure demonstrations, and personnel qualifications that were described in Reference 7 remain unchanged.
- 3. Inspection Results Summary:
3.a. RPV Head Visual Results: The overall condition of the Turkey Point Unit 3 RPV head was clean with no evidence of leakage from the 66 RVHPs or wastage of the RPV head surface.
3.b. RPV Head Penetration Inspection Results: In accordance with UT procedures 54-ISI-100-09 and 54-ISI-137-01 (vent line), there were no indications identified in any of the 66 RVHPs in the Turkey Point Unit 3 RPV head. There was also no evidence of a "leak path" signature for any of the 65 interference fit RVHPs (excluding the vent) examined,
Attachment to L-2003-122 Page 3 of 4 which is the Framatome-ANP assessment to determine if leakage has occurred into the interference fit zone.
Since the vent line is a clearance fit nozzle, a clean visual inspection provides a direct determination that no leakage has occurred into the annulus. In addition, the flush pressure boundary surface inside of the RPV head associated with the vent line (the head vent line, alloy 600 attachment weld, and a portion of the adjacent stainless steel clad weld) was examined using the liquid penetrant (PT) examination method. The acceptance criteria utilized for the PT examination was "PT white." There were no PT indications identified in the inspected area associated with the head vent line, which provides additional confirmation for the assessment that the vent line has no leakage into the annulus.
4.
Conclusion:
FPL has complied with the requirements of the NRC Order (EA-03-009) for the Turkey Point Unit 3 Cycle 20 refueling outage, based upon the performance of the RPV head inspection and the NRC conditional approval of the relaxation request for the non-pressure boundary portion of nine RVHPs 6, Based on the results of the visual examinations, UT examinations, and leak path assessments (including PT of the vent), FPL concludes that the alloy 600 RVHP nozzles are not degraded, and no wastage has occurred of the RPV head.
'US NRC Letter EA-03-009, Issuance of Order Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors," from Samuel J. Collins (NRC) to all Pressurized Water Reactor Licensees, February 11, 2003.
2 FPL letter L-2002-185, St. Lucie Units 1 and 2, Docket Nos. 50-335, 50-389, Turkey Point Units 3 and 4, Docket Nos. 50-250 and 50-251, Response to NRC Bulletin 2002-02, Reactor Pressure Vessel Head Penetration Nozzle Inspection Programs " R. S. Kundalkar to NRC, September 11, 2002.
3 US NRC Letter (ADAMS Accession No. ML030780413), Summary of Meeting Held on February 24, 2003, with Nuclear Energy Institute and EPRI MRP to Discuss the Order Issued on Reactor Vessel Head Inspections," S.D. Bloom to A.J. Mendiola, March 21, 2003.
4 FPL letter L-2003-067, 'Turkey Point Units 3, Docket No. 50-250, Order (EA-03-009) Relaxation Request, Examination Coverage of Reactor Pressure Vessel Head Penetration Nozzles," W.
Jefferson to NRC, March 11, 2003.
5 FPL letter L-2003-068, 'Turkey Point Units 3, Docket No. 50-250, Order (EA-03-009) Relaxation Request, Examination Coverage of Reactor Pressure Vessel Head Penetration Nozzles -
Supplemental Data," W. Jefferson to NRC, March 14, 2003.
6 US NRC Memo (ADAMS Accession No. ML030790501), Turkey Point Unit 3 - Relaxation of the Requirements of Order (EA-03-009) Regarding Reactor Pressure Vessel Head Inspections (TAC No.
MB7990) and attached Safety Evaluation by the Office of Nuclear Reactor Regulation' S.W. Moore to J.A. Stall, March 20, 2003.
Attachment to L-2003-122 Page 4 of 4 7 FPL letter L-2002-233, St. Lucie Units 1 and 2, Docket Nos. 50-335, 50-389, Reactor Pressure Vessel Head (RPVH) Inspection, NRC Bulletin 2002-02 Supplemental Response, D. E. Jemigan to NRC, November 21, 2002.
8 Framatome ANP Letter NRC:02:056, "Procedures for the Conduct of Ultrasonic Examinations of Reactor Vessel Head Penetrations," James F. Mallay (FRA-ANP) to NRC Document Control Desk, November 11, 2002.
9 Framatome ANP Letter NRC:02:057, Change Authorizations to Procedures for the Conduct of Ultrasonic Examinations of Reactor Vessel Head Penetrations," James F. Mallay (FRA-ANP) to NRC Document Control Desk, November 15, 2002.