Letter Sequence Response to RAI |
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Category:Letter type:NG
MONTHYEARNG-24-0004, 2023 Annual Radiological Environmental Operating Report2024-05-0808 May 2024 2023 Annual Radiological Environmental Operating Report NG-24-0003, Submittal of 2023 Annual Radioactive Material Release Report2024-04-24024 April 2024 Submittal of 2023 Annual Radioactive Material Release Report NG-24-0001, 2024 Annual Decommissioning and Spent Fuel Management Funding Status Report and Independent Spent Fuel Storage Installation (ISFSI) Decommissioning Financial Assurance Update2024-03-0606 March 2024 2024 Annual Decommissioning and Spent Fuel Management Funding Status Report and Independent Spent Fuel Storage Installation (ISFSI) Decommissioning Financial Assurance Update NG-24-0002, 2023 Annual Exposure Report - Form 5s2024-03-0606 March 2024 2023 Annual Exposure Report - Form 5s NG-23-0010, Supplement to Duane Arnold Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-12-0606 December 2023 Supplement to Duane Arnold Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule NG-23-0009, Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule NG-23-0006, Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-05-23023 May 2023 Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update NG-23-0004, 2022 Annual Radioactive Material Release Report2023-04-25025 April 2023 2022 Annual Radioactive Material Release Report NG-23-0003, 2022 Annual Exposure Report - Form 5s2023-04-21021 April 2023 2022 Annual Exposure Report - Form 5s NG-23-0002, 10 CFR 50.59 Report, Commitment Changes, 10 CFR 72.48 Report, Quality Assurance Program Changes, Technical Specification Basis Changes, and Revision of the DAEC Defueled Safety Analysis Report2023-03-27027 March 2023 10 CFR 50.59 Report, Commitment Changes, 10 CFR 72.48 Report, Quality Assurance Program Changes, Technical Specification Basis Changes, and Revision of the DAEC Defueled Safety Analysis Report NG-23-0001, 2023 Annual Decommissioning and Spent Fuel Management Funding Status Report2023-03-27027 March 2023 2023 Annual Decommissioning and Spent Fuel Management Funding Status Report NG-22-0055, Revision to Duane Arnold Energy Center (DAEC) ISFSI-Only Emergency Plan2022-05-20020 May 2022 Revision to Duane Arnold Energy Center (DAEC) ISFSI-Only Emergency Plan NG-22-0053, 2021 Annual Radiological Environmental Operating Report2022-05-0606 May 2022 2021 Annual Radiological Environmental Operating Report NG-22-0052, Regulatory Issue Summary 2000-11. 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Revision 0 NG-22-0047, Registration of Independent Spent Fuel Installation Storage Cask and Notification of Permanent Removal of All Spent Fuel Assemblies from the Spent Fuel Pool2022-04-11011 April 2022 Registration of Independent Spent Fuel Installation Storage Cask and Notification of Permanent Removal of All Spent Fuel Assemblies from the Spent Fuel Pool NG-22-0042, Registration of Independent Spent Fuel Installation Storage Casks2022-04-0808 April 2022 Registration of Independent Spent Fuel Installation Storage Casks NG-22-0041, And Independent Spent Fuel Storage Installation, 2022 Annual Decommissioning and Spent Fuel Management Funding Status Report2022-03-31031 March 2022 And Independent Spent Fuel Storage Installation, 2022 Annual Decommissioning and Spent Fuel Management Funding Status Report NG-22-0030, Registration of Independent Spent Fuel Installation Storage Casks2022-03-23023 March 2022 Registration of Independent Spent Fuel Installation Storage Casks NG-22-0031, 2021 Annual Exposure Report - Form 5s2022-03-23023 March 2022 2021 Annual Exposure Report - Form 5s NG-22-0025, Registration of Independent Spent Fuel Installation Storage Casks2022-03-0808 March 2022 Registration of Independent Spent Fuel Installation Storage Casks NG-22-0021, Registration of Independent Spent Fuel Installation Storage Casks2022-02-24024 February 2022 Registration of Independent Spent Fuel Installation Storage Casks NG-22-0014, Registration of Independent Spent Fuel Installation Storage Casks2022-02-10010 February 2022 Registration of Independent Spent Fuel Installation Storage Casks NG-22-0009, Registration of Independent Spent Fuel Installation Storage Casks2022-01-20020 January 2022 Registration of Independent Spent Fuel Installation Storage Casks NG-22-0001, Supplement to Exemption Request for Failed Fuel Can Weight in a Certificate of Compliance 1004 Renewed Amendment 17 61BTH Type 2 Dry Shielded Canister2022-01-0606 January 2022 Supplement to Exemption Request for Failed Fuel Can Weight in a Certificate of Compliance 1004 Renewed Amendment 17 61BTH Type 2 Dry Shielded Canister NG-21-0038, Registration of Independent Spent Fuel Installation Storage Casks2021-12-22022 December 2021 Registration of Independent Spent Fuel Installation Storage Casks NG-21-0035, Supplement to Exemption Request for Failed Fuel Can Weight in a Certificate of Compliance 1004 Renewed Amendment 17 61 Bth Type 2 Dry Shielded Canister2021-12-10010 December 2021 Supplement to Exemption Request for Failed Fuel Can Weight in a Certificate of Compliance 1004 Renewed Amendment 17 61 Bth Type 2 Dry Shielded Canister NG-21-0030, Exemption Request for Failed Fuel Can Weight in a Certificate of Compliance 1004 Renewed Amendment 17 61 Bth Type 2 Dry Shielded Canister2021-10-21021 October 2021 Exemption Request for Failed Fuel Can Weight in a Certificate of Compliance 1004 Renewed Amendment 17 61 Bth Type 2 Dry Shielded Canister NG-21-0028, Request for Approval of NextEra Energy Duane Arnold, Llc'S Decommissioning Quality Assurance Program Revision 02021-07-30030 July 2021 Request for Approval of NextEra Energy Duane Arnold, Llc'S Decommissioning Quality Assurance Program Revision 0 NG-21-0010, License Amendment Request (TSCR-192): Independent Spent Fuel Storage Installation (ISFSI) Emergency Plan and Emergency Action Level Scheme2021-06-28028 June 2021 License Amendment Request (TSCR-192): Independent Spent Fuel Storage Installation (ISFSI) Emergency Plan and Emergency Action Level Scheme NG-21-0026, CFR 72.48 Report of Changes. Tests. and Experiments2021-06-16016 June 2021 CFR 72.48 Report of Changes. Tests. and Experiments NG-21-0011, Submittal of 2020 Annual Radiological Environmental Operating Report2021-05-0404 May 2021 Submittal of 2020 Annual Radiological Environmental Operating Report NG-21-0009, Report of Facility Changes. Tests and Experiments. and Commitment Changes2021-04-27027 April 2021 Report of Facility Changes. Tests and Experiments. and Commitment Changes NG-21-0021, Supplement to License Amendment Request (TSCR-185): Application to Revise Operating License to Remove Cyber Security Plan Requirements2021-04-22022 April 2021 Supplement to License Amendment Request (TSCR-185): Application to Revise Operating License to Remove Cyber Security Plan Requirements NG-21-0006, 2021 Annual Decommissioning and Spent Fuel Management Funding Status Report2021-03-31031 March 2021 2021 Annual Decommissioning and Spent Fuel Management Funding Status Report NG-21-0005, NextEra Energy Duane Arnold, LLC - Transmittal of the DAEC Defueled Safety Analysis Report Revision 02021-03-29029 March 2021 NextEra Energy Duane Arnold, LLC - Transmittal of the DAEC Defueled Safety Analysis Report Revision 0 NG-20-0094, License Amendment Request (TSCR-189): Revision to Facility License and Technical Specifications to Reflect Permanent Removal of Spent Fuel from the Spent Fuel Pool2021-02-19019 February 2021 License Amendment Request (TSCR-189): Revision to Facility License and Technical Specifications to Reflect Permanent Removal of Spent Fuel from the Spent Fuel Pool NG-21-0004, Response to Request for Additional Information Related to Post Shutdown Decommissioning Activities Report2021-02-0505 February 2021 Response to Request for Additional Information Related to Post Shutdown Decommissioning Activities Report NG-20-0078, Update to Spent Fuel Management Plan Pursuant to 10 CFR 50.54(bb)2021-01-13013 January 2021 Update to Spent Fuel Management Plan Pursuant to 10 CFR 50.54(bb) NG-20-0101, Request for a One-Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(1)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to COVID-19 Pandemic2020-12-29029 December 2020 Request for a One-Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(1)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to COVID-19 Pandemic NG-20-0099, Response to Request for Additional Information Relating to License Amendment Request (TSCR-187): Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme2020-12-0101 December 2020 Response to Request for Additional Information Relating to License Amendment Request (TSCR-187): Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme NG-20-0093, Supplement to License Amendment Request (TSCR-187): Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme2020-10-29029 October 2020 Supplement to License Amendment Request (TSCR-187): Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme NG-20-0090, Certification of Permanent Removal of Fuel from the Reactor Vessel for Duane Arnold Energy Center2020-10-12012 October 2020 Certification of Permanent Removal of Fuel from the Reactor Vessel for Duane Arnold Energy Center NG-20-0083, Registration of Independent Spent Fuel Installation Storage Casks2020-10-12012 October 2020 Registration of Independent Spent Fuel Installation Storage Casks NG-20-0069, Response to Request for Additional Information Relating to Request for Exemption from Portions of 10 CFR 50.47 and 10 CFR 50, Appendix E2020-10-0707 October 2020 Response to Request for Additional Information Relating to Request for Exemption from Portions of 10 CFR 50.47 and 10 CFR 50, Appendix E NG-20-0082, Registration of Independent Spent Fuel Installation Storage Casks2020-09-28028 September 2020 Registration of Independent Spent Fuel Installation Storage Casks NG-20-0071, Request for One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Evaluated Exercise Requirements Due to COVID-19 Pandemic2020-09-22022 September 2020 Request for One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Evaluated Exercise Requirements Due to COVID-19 Pandemic NG-20-0077, Registration of Independent Spent Fuel Installation Storage Casks2020-09-10010 September 2020 Registration of Independent Spent Fuel Installation Storage Casks 2024-05-08
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FPL Energy Duane Arnold, LLC 3277 DAEC Road Palo, Iowa 52324 FPL Dun Arroddf Eone~g Cent1er February 26, 2007 NG-07-0188 10 CFR 50.55a(a)(3)(i)
U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Duane Arnold Energy Center Docket No: 50-331 Op. License No: DPR-49 Response to Requests for Additional Information on Alternative to ASME Section Xl Requirements to use Code Cases N-504-2 and N-638-1 for Weld Overlay Repairs at the Duane Arnold Energqy Center
Reference:
- 1) Letter, Gary Van Middlesworth (FPL Energy Duane Arnold) to Document Control Desk (USNRC) - Alternative to ASME Section XI Requirements to use Code Cases N-504-2 and N-638-1 for Weld Overlay Repairs at the Duane Arnold Energy Center, dated February 24, 2006 Reference 1 forwarded the FPL Energy Duane Arnold request for relief to allow use of an alternative to ASME Section XI Requirements to use Code Cases N-504-2 and N-638-1 for weld overlay repairs at the Duane Arnoid Energy Center (DAEC). in an email dated February 26, 2007, the NRC provided a request for additional information concerning Reference 1. This submittal provides the responses to the requests.
FPL Energy Duane Arnold requests approval of Reference 1 prior to beginning the weld overlay repair of safe-end-to-nozzle welds RRC-F002 and RRF-F002, currently scheduled for February 27, 2007.
This letter contains no new commitments and no revisions to existing co0mmitments.
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NG-07-0188 February 26, 2007 Page 2 of 2 Questions regarding this matter should be directed to Steve Catron, Licensing Manager, 19) 51-7234.
G an Middlesworth Site Vice President, Duane Arnold Energy Center FPL Energy Duane Arnold Enclosure cc: Administrator, Region III, USNRC Project Manager, DAEC, USNRC Resident Inspector, DAEC, USNRC
Enclosure to NG-07-0188 Response to Requests for Additional Information on Alternative to ASME Section XI Requirements to use Code Cases N-504-2 and N-638-1 for Weld Overlay Repairs at the Duane Arnold Energy Center Request #1 How has the licensee addressed the rapid cooling rates which are possible from water-backed welding on the SA-508 Class 2 base metal? Has a mockup or procedure qualification record (PQR) of a water-backed weld overlay been performed? What overlay thickness was used on the mockup or PQR? What is the thickness of the nozzle under the weld overlay? Has any testing (metallurgical, destructive, non-destructive, etc.) been performed on any weld overlays fabricated on water-backed SA-508 Class 2 base metal?
FPL Energy Duane Arnold Response:
The welding procedure was qualified for water-backed welding. The procedure was qualified using PQR 0303T803 Rev. 0 which is a water-backed PQR. The overlay thickness used for the PQR was 1.5 inch deep cavity on a 3 inch coupon.
The nozzle thickness in the area of the overlay is 1.06 inch. FPL Energy Duane Arnold has performed pre-service and inservice examinations of the two overlays that were completed using Code Cases N-504-1 and N-606 in 1999.
Request #2 What is the maximum area of the P-3 material that will be welded on? This should be stated in the relief request. The relief request mentions 500 sq. in., but not as the maximum area that is to be welded on during this specific repair.
FPL Enerqy Duane Arnold Response:
The weld overlay will cover approximately 180 square inches of the low alloy nozzle (ref. page 11 of 14 of the relief request (Reference 1)).
Request #3 How often will contact pyrometers be used to measure weld preheat and interpass temperatures? Every pass? Every layer? Once during welding?
FPL Energy Duane Arnold Response:
The contact pyrometers will be used to verify pre-heat prior to welding and every three to five beads on the first three layers.
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Enclosure to NG-07-0188 Request #4 On page 12 of 14 [of Reference 1], under "Exception to Code Case N-638-1, Paragraph 4.0(b)," how far will the surface examination be continued past the toe of the weld overlay on the SA-508 Class 2 base metal?
FPL Energy Duane Arnold Response:
The surface examination will extend to 1.5" up on the nozzle.
Request #5 On page 12 of 14 [of Reference 1], under "Exception to Code Case N-638-1, Paragraph 4.0(b)," will the ultrasonic examination extend up to the very edge of the overlay?
FPL Energy Duane Arnold Response:
The ultrasonic examination will be performed in accordance with PDI-UT-8 Revision F which states: "Pre-service examinations shall be performed across the entire overlay surface. Inservice examinations shall be performed to the extent necessary to cover the required examination volume." The examination volume is depicted in Figure 4300-1 of Appendix Q.
Request #6 On Page 12 of 14 [of Reference 1], under "Exception to Code Case N-638-1 Paragraph 4.0(b), the licensee states that "...Any laminar flaws in the weld overlay will be evaluated in accordance with ASME Section XI Non-mandatory Appendix Q, Paragraph Q-4100, except, as allowed by IWB-3132.2, any flaws that exceed the acceptance standards of Table IWB-341 0-1 are acceptable for continued service, without repair, if an analytical evaluation, performed in accordance with IWB-3600, meets the acceptance criteria of IWB-3600."
The staff does not agree with the licensee's exception to Appendix Q, Paragraph Q-4100. Paragraph Q-4100(1) does not allow laminar flaws to be accepted by IWB-3600. In addition, Code Case N-504-2, Paragraph (i) does not allow flaw acceptance by IWB- 3600 for the preservice examination. The NRC staffs position is that any flaw detected in the weld overlay during the preservice examination that does not satisfy the acceptance standards of Table IWB-3514-2 must to be removed or repaired. Therefore, the licensee should modify its relief request to be consistent with the NRC staffs position or provide a detailed, technical basis to support its exception to paragraph Q-4100 of Appendix Q of the ASME Code,Section XI.
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Enclosure to NG-07-0188 FPL Energy Duane Arnold Response:
The exception as noted in the original relief request will be removed. The DAEC will comply with the requirements contained in Non-mandatory Appendix Q Paragraph Q-4100(1). The exception on page 12 of 14 from Reference 1 is hereby revised as follows:
"Code Case N-638-1 Paragraph 4.0(b) specifies that the final weld surface and band area (1.5T width or 5 inches, whichever is less) shall be examined using surface and ultrasonic methods when the completed weld has been at ambient temperature for at least 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. The UT shall be in accordance with ASME Section XI, Appendix I. Surface exams will be performed. IWA-4634 requires UT of the weld only. ARy laminar flaws in the weld overlay will be evaluated iR acco.rdance with ASME Se*ction l No man ,*+dato,- Appendix Q, Paragraph Q 4100, except, as allowed by IWVB 3132.3, any flaws that exceed the acceptanc standards of Table 1 10_1 are acceptable for
,-- *oGntinued serpvifce, without repair, if an anal.cal evaluation, performed in accor dance with IWB 3600, meets the acceptance criteria of I,,,-B 3600. Full UT of the 1.5T band will not be performed. The weld overlay will extend into the blend radius of the nozzle beyond the length required by Code case N-504-2 for structural reinforcement.
This extension onto the blend radius eliminates a stress riser on the nozzle and provides additional OD surface area for UT examination of the defect area. UT examination on the nozzle beyond the overlay will not provide any information regarding the area of the defect that required repair. Additionally, such UT would likely be unsatisfactory when applied to the nozzle blend radius, where the toe of the weld overlay resides. The UT return signal would be difficult to obtain and to interpret. Alternatively, surface examination will assure that no defects have been created at the toe of the weld overlay. Therefore, this alternative provides an acceptable level of quality and safety."
Request #7 Clarify whether the weld overlay will be applied multiple times to a specific weld.
FPL Energy Duane Arnold Response:
The DAEC will only apply one overlay to each weld RRF-F002 and RRC-F002.
Reference:
- 1) Letter, Gary Van Middlesworth (FPL Energy Duane Arnold) to Document Control Desk (USNRC) - Alternative to ASME Section XI Requirements to use Code Cases N-504-2 and N-638-1 for Weld Overlay Repairs at the Duane Arnold Energy Center, dated February 24, 2006 3 of 3